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| | issue date = 06/11/1987 | | | issue date = 06/11/1987 |
| | title = LER 87-030-00:on 870512,Maint Surveillance Tests I0140, I0141 & I0142 for P-12 Interlock Missed Thus Violating Tech Specs Requirements.Caused by Personnel Error.Procedures revised.W/870611 Ltr | | | title = LER 87-030-00:on 870512,Maint Surveillance Tests I0140, I0141 & I0142 for P-12 Interlock Missed Thus Violating Tech Specs Requirements.Caused by Personnel Error.Procedures revised.W/870611 Ltr |
| | author name = SCHWABENBAUER, WATSON R A | | | author name = Schwabenbauer, Watson R |
| | author affiliation = CAROLINA POWER & LIGHT CO. | | | author affiliation = CAROLINA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:RF Y INFORMATION DISTRI"I SYSTEM (RIDS)ACCESSION NBR: 8706160546 DOC DATE: 87/06/1 1.NOTARIZED: | | {{#Wiki_filter:RF Y INFORMATION DISTRI "I SYSTEM (RIDS) |
| NO FACIL: 50-400 Shearon Harris Nuclear Poeer Plant>Unit 1>Carolina AUTH.'AME AUTHOR AFFILIATION SCHWABENBAUER Caro l ina P over 8<L i g h t Co.WATSON>R.A.~Car o l ina P oeer 8c Li g h t Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400 | | ACCESSION NBR: 8706160546 DOC DATE: 87/06/1 1 . NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Poeer Plant> Unit 1> Carolina 05000400 AUTH.'AME AUTHOR AFFILIATION SCHWABENBAUER Caro l ina P over 8< Li g h t Co. |
| | WATSON> R. A. ~ Car o l ina P oeer 8c Lig h t Co. |
| | RECIP. NAME RECIPIENT AFFILIATION |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-030-00: | | LER 87-030-00: on $ 70512> Maint Surveillance Tests I0140> |
| on$70512>Maint Surveillance Tests I0140>I0141 9~l0142 for P-12 interlock missed thus violating Tech Specs requirements. | | I0141 9~ l0142 for P-12 interlock missed thus violating Tech Specs requirements. Caused bg personnel error. Procedures revised. W/870611 ltr. |
| Caused bg personnel error.Procedures revised.W/870611 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.73 Licensee Event Report (I ER)>Incident Rpt>etc.NOTES: Application f or permit renewal f iled.05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY>B COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1 INTERNAL: ACRS M I CHELSON AEOD/DOA AEOD/DSP/TPAB NRR/DEST/ADE NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEBT/RSB NRR/DLPG/HFB NRR/DOEA/EAB | | DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE: |
| ~NRR/DREP/RPB NRR/PMAS/PTSB RES DEPY GI EXTERNAL: EG5G GROH>M LPDR NSIC HARRIS>J 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 ACRS MOELLER AEOD/DSP/ROAB DEDRO NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB-PWA RB REG FILE 02 2 FILE 01 H ST LOBBY WARD NRC PDR NSIC MAYS>G'1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL 40 NRC Form 386 (9.83)LICENSEE EVENT REPORT (LER)U.S, NUCLEAR REOULATORY COMMISSION APPROVED OM 5 NO.3(504(04 EXPIRES: Sl31l88 FACILITY NAME nl SHEARON HARRIS PLANT UNIT 1 TITLE (4)MISSED MONTHLY SURVEILLANCE TESTS FOR P-12 INTERL C DOCKET NUMBER (2)PAOE 3 0 5 0 0 0 4 P O 1 OF 3 EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)IAONTH OAY YEAR YEAR SkM'EQUENTIAL
| | TITLE: 50. 73 Licensee Event Report (I ER) Incident Rpt> > etc. |
| :rr'srS N V MS 6 R REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI 0 5 0 0 0 8 7 8 7 0 3 0 0 5 0 0 0 OPERATINO MODE (9)POWER LEYEL O O k..'ss~v rr3+,,~g 20A02(b)20.406(~l(1)(i)20A05(~)(I)(iil 20A06(el(1 l(iii)20A05 (4)(1)(iv)20,406(e)11)(vl 20.40S(el 50.38(cl(1) 50.35(cl(2) 50.7 3(e I (2)Ill 50.73(~l(2)(ii)50.73(el(2)(i(i l LICENSEE CONTACT FOR THIS LER (12(50.73(el(2((iv) 60,73(~)(2)(vl 50.73(e)(2((vB) 50,73(e)(2)(vill)(Al 60.73(el(2)(vliil(BI 60.73(~)(2)(x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R ((: fCheck one or more of the follorylnp)
| | NOTES: Application f or permit renewal f iled. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 BUCKLEY> B 1 1 INTERNAL: ACRS M I CHELSON 1 1 ACRS MOELLER AEOD/DOA 1 AEOD/DSP/ROAB AEOD/DSP/TPAB 1 1 DEDRO 1 NRR/DEST/ADE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 NRR/DEST/PSB 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 |
| (11)73.71(ir)73.71(c)OTHER fSpecify in Ahstrect trefow end ln Text, NRC Form JSSAJ NAME R.SCHWABENBAUER
| | ~ |
| -REGULATORY COMPLIANCE AREA CODE TELFPHONE NUMBER COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER vsyr AM v'PORTABLE TO NPRDS'.'x:.o,.n.:.'..
| | NRR/DREP/RPB -PWA RB 1 1 NRR/PMAS/PTSB 1 1 REG FILE 02 1 1 RES DEPY GI 1 1 2 FILE 01 1 EXTERNAL: EG5G GROH> M 5 5 H ST LOBBY WARD 1 1 LPDR NRC PDR 1 1 NSIC HARRIS> J 1 NSIC MAYS> G' 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL 40 |
| p''o6 wc''SYSTEM COMPONENT MANUFAC-TURER EPORTABLE TO NPRDS SNK4'Sr!m.'CICO.x xN:cl.i~x.P(SUPPLEMENTAL REPORT EXPECTED (14(I YES flf yes, complere EXPECTED SifSMISSIOhf DATE/NO ABSTRACT (Llmlt to 1400 speces, f e., epproxlmetely fifteen slnpleepece typewrlnen llnesl (ISI EXPECTED SUBMISSION DATE I'(6)MONTH OAY YEAR The plant was operating in Mode 1 at 100 percent Reactor power.At 1255 hours on May 12, 1987, it was discovered that Maintenance Surveillance Tests (MST)I0140, I0141, and I0142, the Operational Test procedures for the three Reactor Coolant System (RCS)delta T/Tavg protection loops, do not test the P-12 interlock. | | |
| The plant had mistakenly taken credit for these procedures meeting the monthly Analog Operational Test requirements of Technical Specifications 4.3.2.1, Table 4.3-2, Item 10b.Upon discovery, it was immediately verified that the surveillance requirements for these channels were current using the calibration procedures for the three delta T/Tavg protection loops.However, it was also determined that the monthly surveillance testing requirements had been missed in the past.8706160546 870611 PDR ADOCK 05000400 PDR gGW>(/(NRC Form 358 (94)3) | | NRC Form 386 U.S, NUCLEAR REOULATORY COMMISSION (9.83) APPROVED OM 5 NO. 3(504(04 EXPIRES: Sl31l88 LICENSEE EVENT REPORT (LER) |
| NRC Form BEBA (BA)3)LICE EE NT REPORT (LER)TEXT CON IU N U.S.NUCLEAR REGULATORY COMMISSION APPROVE'O OMB NO.3150M)04 EXPIRES: 8/31/88 FACILITY NAME (1)SHEARON HARRIS PLANT UNIT 1 TEXT//F'moro E/toco/t nrtu/ror/uw a/f//Ooto/ | | DOCKET NUMBER (2) PAOE 3 FACILITY NAME nl SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 P O 1 OF 3 TITLE (4) |
| ///IC Form 3EBAB/(13)DOCKET NUMBER (2)o 6 o o o 400 LER NUMBER (6)YEAR 9".R BEQUEIITIAL
| | MISSED MONTHLY SURVEILLANCE TESTS FOR P-12 INTERL C EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| .~REvtstoN NUMBER>Sot NUMBER 87-03 0-0 0 PAGE (3)0 20F DESCRIPTION On May 12, 1987, while the plant was operating at 100 percent power in Mode 1, it was discovered that Maintenance Surveillance Tests (MST)I0140, I0141, and I0142,, the Analog Operational Test procedures for the three Reactor Coolant System (RCS)delta T/Tavg protection loops, do not test the P-12 interlock. | | SkM'EQUENTIAL REVISION DAY YEAR FACILITYNAMES DOCKET NUMBER(SI IAONTH OAY YEAR YEAR :rr'srS N V MS 6 R MONTH 0 5 0 0 0 0 5 0 0 0 8 7 8 7 0 3 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CF R ((: fCheck one or more of the follorylnp) (11) |
| The P-12 interlock provides protection against an uncontrolled cooldown from the steam dump system.On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the plant steam dump system.The discovery was made by an Instrument and Control (I&C)technician as he was preparing to run MST-I0142. | | OPERATINO MODE (9) 20A02(b) 20.40S(el 50.73(el(2((iv) 73.71(ir) |
| He discovered the discrepancy while reviewing Technical Specifications and the procedure. | | POWER 20.406( ~ l(1)(i) 50.38(cl(1) 60,73( ~ ) (2) (vl 73.71(c) |
| It was then determined that the only test of the P-12 interlock took place during the running of the loop calibration procedures (MST-I0037, MST-I0038, and MST-I0039). | | LEYEL OTHER fSpecify in Ahstrect O O 20A05( ~ ) (I) (iil 50.35(cl(2) 50.73(e)(2((vB) trefow end ln Text, NRC Form k..' 20A06(el(1 l(iii) 50.7 3(e I (2) Ill 50,73(e) (2) (vill)(Al JSSAJ ss ~ |
| A review of previous calibrations was performed to determine if the plant was in current compliance with Technical Specifications and if any Surveillance Testing had, indeed, been missed.It was immediately verified that the Surveillance requirements on these channels were current due to all three being recalibrated within the previous 6 days.A review of previous calibration dates and plant modes was conducted to determine if the Technical Specification requirements had been violated.Technical Specifications require the P-12 interlock be tested every 31 days plus 25 percent (7 days).The plant entered Mode 3 for the first time at approximately 2000 hours on December 24, 1986.The temperature loops were calibrated on several occasions as part of the Power Ascension Test Program.The review for Loop T-412 shows the monthly Operational Test was missed once by ll days between the February 20, 1987 and April 10, 1987.The review for Loop T-422 shows the allowance for the monthly Operational Test was missed once by 13 days between January 15, 1987 and March 7, 1987.The review for Loop T-432 shows the allowance for the monthly Operational Test was never missed on this channel and has been in compliance with Technical Specification requirements. | | 20A05 (4) (1)(iv) 50.73( ~ l(2)(ii) 60.73(el(2)(vliil(BI v rr3+,, ~g 20,406(e)11)(vl 50.73(el(2)(i(i l 60.73( ~ )(2)(x) |
| CAUSE The cause of the event was personnel error through inadequate review of changes to the purpose section of the procedures. | | LICENSEE CONTACT FOR THIS LER (12( |
| In July, 1986, Maintenance personnel identified 56 surveillance procedures in which the purpose section of the procedure did not match the requirements for the procedure as specified in the Technical Specification cross-reference index.As a result, changes to these procedures then were made.At that time, an error was made on MST-I0140, MST-I0141, and MST-I0142. | | NAME TELFPHONE NUMBER AREA CODE R. SCHWABENBAUER REGULATORY COMPLIANCE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) vsyr AM v MANUFAC. 'PORTABLE MANUFAC- EPORTABLE CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TURER TO NPRDS TURER TO NPRDS |
| These procedures did not check the P-12 interlock, as required by the cross-reference. | | '.'x:.o,.n.:.'.. |
| While the purpose statement of the procedures were revised, the procedure steps were not.This resulted in the procedures normally relied on to test the P-12 interlock not performing this function.NRC'FORM 3BBA ((F83)*U.S.GPO;1985 0.52E 538/455 | | p'' o6 wc'' |
| ~~~0 NRC Form 356A (983)LICE EE ENT REPORT HLER)TEXT CON IVU N U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)SHEARON HARRIS PLANT UNIT 1 TEXT//P more 4/>>ce/4 BEE/rerL l>>e////WORE/I HRC Form 35549/(0)YEAR o s o o o 40 087 SEQUENTIAL NUMBER 0 3 0 REVISION NUMBER 0 003 QF0 3 ANALYSIS There was no impact on safety, as P-12 interlock does not perform a safety function per accident analysis, and when checked was found to be in tolerance. | | SNK4 |
| This event is being reported in'accordance with lOCFRS0.73(a)(2)(i)(B), as Technical Specification 4.3.2.1, Table 4.3-2, Item 10b was violated.CORRECTIVE ACTION 1.The P-12 interlock surveillance requirement has been incorporated into applicable procedures. | | 'Sr!m :cl |
| 2.MST-I0140, MST-I0141, and MST-I0142 have been revised to correct their purpose section.3.'review was conducted of the other 53 MST's changed at the time, and no other discrepancies were found.4.A training session was held with the Maintenance procedure writers as a result of this event.NRC FORM BBBA (94)3)*U,S.GPO:(9884).524 538/455 | | .'CICO.. i~x x.xN P( |
| ~0 l | | SUPPLEMENTAL REPORT EXPECTED (14( MONTH OAY YEAR EXPECTED SUBMISSION I DATE I'(6) |
| ~~~II, 0~Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 Jun>>>987 File Number: SHF/10-13510C Letter Number: HO-870450 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-030-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. | | YES flfyes, complere EXPECTED SifSMISSIOhf DATE/ NO ABSTRACT (Llmlt to 1400 speces, f e., epproxlmetely fifteen slnpleepece typewrlnen llnesl (ISI The plant was operating in Mode 1 at 100 percent Reactor power. At 1255 hours on May 12, 1987, it was discovered that Maintenance Surveillance Tests (MST) |
| This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, RAW:lmj Enclosure R.A.Watson Vice President Harris Nuclear Project cc: Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/LER/PAGE 1/Osl}} | | I0140, I0141, and I0142, the Operational Test procedures for the three Reactor Coolant System (RCS) delta T/Tavg protection loops, do not test the P-12 interlock. The plant had mistakenly taken credit for these procedures meeting the monthly Analog Operational Test requirements of Technical Specifications 4.3.2.1, Table 4.3-2, Item 10b. |
| | Upon discovery, it was immediately verified that the surveillance requirements for these channels were current using the calibration procedures for the three delta T/Tavg protection loops. However, it was also determined that the monthly surveillance testing requirements had been missed in the past. |
| | 8706160546 870611 PDR ADOCK 05000400 PDR gGW> |
| | (/( |
| | NRC Form 358 (94)3) |
| | |
| | NRC Form BEBA U.S. NUCLEAR REGULATORY COMMISSION (BA)3) |
| | LICE EE NT REPORT (LER) TEXT CON IU N APPROVE'O OMB NO. 3150M)04 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR 9".R BEQUEIITIAL NUMBER |
| | .~ REvtstoN |
| | >Sot NUMBER SHEARON HARRIS PLANT UNIT 1 o 6 o o o 400 87 03 0 0 0 0 20F TEXT //F'moro E/toco /t nrtu/ror/ uw a/f//Ooto/ ///IC Form 3EBAB/ (13) |
| | DESCRIPTION On May 12, 1987, while the plant was operating at 100 percent power in Mode 1, it was discovered that Maintenance Surveillance Tests (MST) I0140, I0141, and I0142,, the Analog Operational Test procedures for the three Reactor Coolant System (RCS) delta T/Tavg protection loops, do not test the P-12 interlock. |
| | The P-12 interlock provides protection against an uncontrolled cooldown from the steam dump system. On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the plant steam dump system. |
| | The discovery was made by an Instrument and Control (I&C) technician as he was preparing to run MST-I0142. He discovered the discrepancy while reviewing Technical Specifications and the procedure. It was then determined that the only test of the P-12 interlock took place during the running of the loop calibration procedures (MST-I0037, MST-I0038, and MST-I0039). |
| | A review of previous calibrations was performed to determine if the plant was in current compliance with Technical Specifications and if any Surveillance Testing had, indeed, been missed. It was immediately verified that the Surveillance requirements on these channels were current due to all three being recalibrated within the previous 6 days. |
| | A review of previous calibration dates and plant modes was conducted to determine if the Technical Specification requirements had been violated. |
| | Technical Specifications require the P-12 interlock be tested every 31 days plus 25 percent (7 days). The plant entered Mode 3 for the first time at approximately 2000 hours on December 24, 1986. The temperature loops were calibrated on several occasions as part of the Power Ascension Test Program. |
| | The review for Loop T-412 shows the monthly Operational Test was missed once by ll days between the February 20, 1987 and April 10, 1987. The review for Loop T-422 shows the allowance for the monthly Operational Test was missed once by 13 days between January 15, 1987 and March 7, 1987. The review for Loop T-432 shows the allowance for the monthly Operational Test was never missed on this channel and has been in compliance with Technical Specification requirements. |
| | CAUSE The cause of the event was personnel error through inadequate review of changes to the purpose section of the procedures. In July, 1986, Maintenance personnel identified 56 surveillance procedures in which the purpose section of the procedure did not match the requirements for the procedure as specified in the Technical Specification cross-reference index. As a result, changes to these procedures then were made. At that time, an error was made on MST-I0140, MST-I0141, and MST-I0142. These procedures did not check the P-12 interlock, as required by the cross-reference. While the purpose statement of the procedures were revised, the procedure steps were not. This resulted in the procedures normally relied on to test the P-12 interlock not performing this function. |
| | NRC'FORM 3BBA *U.S.GPO;1985 0.52E 538/455 |
| | ((F83) |
| | |
| | ~ ~ ~ 0 U.S. NUCLEAR REGULATORY COMMISSION NRC Form 356A (983) |
| | LICE EE ENT REPORT HLER) TEXT CON IVU N APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | SEQUENTIAL REVISION YEAR NUMBER NUMBER SHEARON HARRIS PLANT UNIT 1 o s o o o 40 087 0 3 0 0 003 QF0 3 TEXT //P more 4/>>ce /4 BEE/rerL l>>e ////WORE/I HRC Form 35549/ (0) |
| | ANALYSIS There was no impact on safety, as P-12 interlock does not perform a safety function per accident analysis, and when checked was found to be in tolerance. |
| | This event is being reported in 'accordance with 10CFRS0.73(a)(2)(i)(B), as Technical Specification 4.3.2.1, Table 4.3-2, Item 10b was violated. |
| | CORRECTIVE ACTION |
| | : 1. The P-12 interlock surveillance requirement has been incorporated into applicable procedures. |
| | : 2. MST-I0140, MST-I0141, and MST-I0142 have been revised to correct their purpose section. |
| | 3.' review was conducted of the other 53 MST's changed at the time, and no other discrepancies were found. |
| | : 4. A training session was held with the Maintenance procedure writers as a result of this event. |
| | NRC FORM BBBA *U,S.GPO:(9884).524 538/455 (94)3) |
| | |
| | ~ 0 l |
| | |
| | ~ ~ 0 ~ |
| | ~II, Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 Jun > > >987 File Number: SHF/10-13510C Letter Number: HO-870450 (0) |
| | U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-030-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983. |
| | Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:lmj Enclosure cc: Dr. J. Nelson Grace (NRC RII) |
| | Mr. B. Buckley (NRR) |
| | Mr. G. Maxwell (NRC SHNPP) |
| | MEM/LER/PAGE 1/Osl}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
[Table view] |
Text
RF Y INFORMATION DISTRI "I SYSTEM (RIDS)
ACCESSION NBR: 8706160546 DOC DATE: 87/06/1 1 . NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Poeer Plant> Unit 1> Carolina 05000400 AUTH.'AME AUTHOR AFFILIATION SCHWABENBAUER Caro l ina P over 8< Li g h t Co.
WATSON> R. A. ~ Car o l ina P oeer 8c Lig h t Co.
RECIP. NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-030-00: on $ 70512> Maint Surveillance Tests I0140>
I0141 9~ l0142 for P-12 interlock missed thus violating Tech Specs requirements. Caused bg personnel error. Procedures revised. W/870611 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: 50. 73 Licensee Event Report (I ER) Incident Rpt> > etc.
NOTES: Application f or permit renewal f iled. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 BUCKLEY> B 1 1 INTERNAL: ACRS M I CHELSON 1 1 ACRS MOELLER AEOD/DOA 1 AEOD/DSP/ROAB AEOD/DSP/TPAB 1 1 DEDRO 1 NRR/DEST/ADE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 NRR/DEST/PSB 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1
~
NRR/DREP/RPB -PWA RB 1 1 NRR/PMAS/PTSB 1 1 REG FILE 02 1 1 RES DEPY GI 1 1 2 FILE 01 1 EXTERNAL: EG5G GROH> M 5 5 H ST LOBBY WARD 1 1 LPDR NRC PDR 1 1 NSIC HARRIS> J 1 NSIC MAYS> G' 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL 40
NRC Form 386 U.S, NUCLEAR REOULATORY COMMISSION (9.83) APPROVED OM 5 NO. 3(504(04 EXPIRES: Sl31l88 LICENSEE EVENT REPORT (LER)
DOCKET NUMBER (2) PAOE 3 FACILITY NAME nl SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 P O 1 OF 3 TITLE (4)
MISSED MONTHLY SURVEILLANCE TESTS FOR P-12 INTERL C EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
SkM'EQUENTIAL REVISION DAY YEAR FACILITYNAMES DOCKET NUMBER(SI IAONTH OAY YEAR YEAR :rr'srS N V MS 6 R MONTH 0 5 0 0 0 0 5 0 0 0 8 7 8 7 0 3 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CF R ((: fCheck one or more of the follorylnp) (11)
OPERATINO MODE (9) 20A02(b) 20.40S(el 50.73(el(2((iv) 73.71(ir)
POWER 20.406( ~ l(1)(i) 50.38(cl(1) 60,73( ~ ) (2) (vl 73.71(c)
LEYEL OTHER fSpecify in Ahstrect O O 20A05( ~ ) (I) (iil 50.35(cl(2) 50.73(e)(2((vB) trefow end ln Text, NRC Form k..' 20A06(el(1 l(iii) 50.7 3(e I (2) Ill 50,73(e) (2) (vill)(Al JSSAJ ss ~
20A05 (4) (1)(iv) 50.73( ~ l(2)(ii) 60.73(el(2)(vliil(BI v rr3+,, ~g 20,406(e)11)(vl 50.73(el(2)(i(i l 60.73( ~ )(2)(x)
LICENSEE CONTACT FOR THIS LER (12(
NAME TELFPHONE NUMBER AREA CODE R. SCHWABENBAUER REGULATORY COMPLIANCE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) vsyr AM v MANUFAC. 'PORTABLE MANUFAC- EPORTABLE CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TURER TO NPRDS TURER TO NPRDS
'.'x:.o,.n.:.'..
p o6 wc
SNK4
'Sr!m :cl
.'CICO.. i~x x.xN P(
SUPPLEMENTAL REPORT EXPECTED (14( MONTH OAY YEAR EXPECTED SUBMISSION I DATE I'(6)
YES flfyes, complere EXPECTED SifSMISSIOhf DATE/ NO ABSTRACT (Llmlt to 1400 speces, f e., epproxlmetely fifteen slnpleepece typewrlnen llnesl (ISI The plant was operating in Mode 1 at 100 percent Reactor power. At 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br /> on May 12, 1987, it was discovered that Maintenance Surveillance Tests (MST)
I0140, I0141, and I0142, the Operational Test procedures for the three Reactor Coolant System (RCS) delta T/Tavg protection loops, do not test the P-12 interlock. The plant had mistakenly taken credit for these procedures meeting the monthly Analog Operational Test requirements of Technical Specifications 4.3.2.1, Table 4.3-2, Item 10b.
Upon discovery, it was immediately verified that the surveillance requirements for these channels were current using the calibration procedures for the three delta T/Tavg protection loops. However, it was also determined that the monthly surveillance testing requirements had been missed in the past.
8706160546 870611 PDR ADOCK 05000400 PDR gGW>
(/(
NRC Form 358 (94)3)
NRC Form BEBA U.S. NUCLEAR REGULATORY COMMISSION (BA)3)
LICE EE NT REPORT (LER) TEXT CON IU N APPROVE'O OMB NO. 3150M)04 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR 9".R BEQUEIITIAL NUMBER
.~ REvtstoN
>Sot NUMBER SHEARON HARRIS PLANT UNIT 1 o 6 o o o 400 87 03 0 0 0 0 20F TEXT //F'moro E/toco /t nrtu/ror/ uw a/f//Ooto/ ///IC Form 3EBAB/ (13)
DESCRIPTION On May 12, 1987, while the plant was operating at 100 percent power in Mode 1, it was discovered that Maintenance Surveillance Tests (MST) I0140, I0141, and I0142,, the Analog Operational Test procedures for the three Reactor Coolant System (RCS) delta T/Tavg protection loops, do not test the P-12 interlock.
The P-12 interlock provides protection against an uncontrolled cooldown from the steam dump system. On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the plant steam dump system.
The discovery was made by an Instrument and Control (I&C) technician as he was preparing to run MST-I0142. He discovered the discrepancy while reviewing Technical Specifications and the procedure. It was then determined that the only test of the P-12 interlock took place during the running of the loop calibration procedures (MST-I0037, MST-I0038, and MST-I0039).
A review of previous calibrations was performed to determine if the plant was in current compliance with Technical Specifications and if any Surveillance Testing had, indeed, been missed. It was immediately verified that the Surveillance requirements on these channels were current due to all three being recalibrated within the previous 6 days.
A review of previous calibration dates and plant modes was conducted to determine if the Technical Specification requirements had been violated.
Technical Specifications require the P-12 interlock be tested every 31 days plus 25 percent (7 days). The plant entered Mode 3 for the first time at approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on December 24, 1986. The temperature loops were calibrated on several occasions as part of the Power Ascension Test Program.
The review for Loop T-412 shows the monthly Operational Test was missed once by ll days between the February 20, 1987 and April 10, 1987. The review for Loop T-422 shows the allowance for the monthly Operational Test was missed once by 13 days between January 15, 1987 and March 7, 1987. The review for Loop T-432 shows the allowance for the monthly Operational Test was never missed on this channel and has been in compliance with Technical Specification requirements.
CAUSE The cause of the event was personnel error through inadequate review of changes to the purpose section of the procedures. In July, 1986, Maintenance personnel identified 56 surveillance procedures in which the purpose section of the procedure did not match the requirements for the procedure as specified in the Technical Specification cross-reference index. As a result, changes to these procedures then were made. At that time, an error was made on MST-I0140, MST-I0141, and MST-I0142. These procedures did not check the P-12 interlock, as required by the cross-reference. While the purpose statement of the procedures were revised, the procedure steps were not. This resulted in the procedures normally relied on to test the P-12 interlock not performing this function.
NRC'FORM 3BBA *U.S.GPO;1985 0.52E 538/455
((F83)
~ ~ ~ 0 U.S. NUCLEAR REGULATORY COMMISSION NRC Form 356A (983)
LICE EE ENT REPORT HLER) TEXT CON IVU N APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
SEQUENTIAL REVISION YEAR NUMBER NUMBER SHEARON HARRIS PLANT UNIT 1 o s o o o 40 087 0 3 0 0 003 QF0 3 TEXT //P more 4/>>ce /4 BEE/rerL l>>e ////WORE/I HRC Form 35549/ (0)
ANALYSIS There was no impact on safety, as P-12 interlock does not perform a safety function per accident analysis, and when checked was found to be in tolerance.
This event is being reported in 'accordance with 10CFRS0.73(a)(2)(i)(B), as Technical Specification 4.3.2.1, Table 4.3-2, Item 10b was violated.
CORRECTIVE ACTION
- 1. The P-12 interlock surveillance requirement has been incorporated into applicable procedures.
- 2. MST-I0140, MST-I0141, and MST-I0142 have been revised to correct their purpose section.
3.' review was conducted of the other 53 MST's changed at the time, and no other discrepancies were found.
- 4. A training session was held with the Maintenance procedure writers as a result of this event.
NRC FORM BBBA *U,S.GPO:(9884).524 538/455 (94)3)
~ 0 l
~ ~ 0 ~
~II, Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 Jun > > >987 File Number: SHF/10-13510C Letter Number: HO-870450 (0)
U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-030-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.
Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:lmj Enclosure cc: Dr. J. Nelson Grace (NRC RII)
Mr. B. Buckley (NRR)
Mr. G. Maxwell (NRC SHNPP)
MEM/LER/PAGE 1/Osl
