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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)A'CCESSION NBR:8909200244 DOC.DATE: 89/09/13 NOTARIZED: | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH.NAME AUTHOR AFFILIATION LYONS,E.Florida Power&Light Co.WOODY,C.O. | | A'CCESSION NBR:8909200244 DOC.DATE: 89/09/13 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION LYONS,E. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | WOODY,C.O. Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 89-012-00:on 890707,source surveillances required by Tech Spec missed due to inadequate administrative controls.W/8 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL i SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc NOTES RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO.NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DS IR/EI B EXTERNAL: EG&G WILLIAMS,S LPDR NSIC MAYS,G NUDOCS FULL TXT 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 1 1 1 4 4 1 1 1 1.1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DS P IRM/DCTS/DAB NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRR RPB 10 RGN2 FILE 01 L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1'1 1 1 1 NOIR'ZO ALL'KIDS" R1XXPI1MS: | | LER 89-012-00:on 890707,source surveillances required by Tech Spec missed due to inadequate administrative controls. |
| PZZRSE HELP US KO REDUCE%MDDE!CONZMT'IHE DOCUMEÃI'ONTROL DESK, RXM P1-37 (EXT.20079)%0 XZiXMQQZB YOGR NAME PKN DISTRIBUTION LTSTS KK DOCUMEÃIS VXJ DON~T NEZD!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40 | | W/8 ltr. |
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL i SIZE: |
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1' IRM/DCTS/DAB 1 1 |
| | . NRR/DEST/CEB 8H 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR RPB 10 2 2 NUDOCS-ABSTRACT 1 1 1 1 RES/DS IR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 L ST LOBBY WARD 1' LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1. NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOIR 'ZO ALL 'KIDS" R1XXPI1MS: |
| | PZZRSE HELP US KO REDUCE %MDDE! CONZMT 'IHE DOCUMEÃI'ONTROL DESK, RXM P1-37 (EXT. 20079) %0 XZiXMQQZB YOGR NAME PKN DISTRIBUTION LTSTS KK DOCUMEÃIS VXJ DON~T NEZD! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40 |
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| P.x14000, Juno Beach, FL 33408.0420 SEPTEMBER 1 3 1989 L-89-336 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | | P. x14000, Juno Beach, FL 33408.0420 SEPTEMBER 1 3 1989 L-89-336 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| Re: Turkey Point Units 3 and 4 Docket No.50-250 and 50-251 Reportable Event: 89-12 Date of Event: July 7, 1989 Source Surveillances Required by Technical Specification 3.11 and 4.13 Missed Due to Inade ate Administrative Controls The attached Licensee Event Report (LER)is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.Very truly yours, C.0.Woody Acting Senior Vice President-Nuclear COW/JRH/cm cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC~Senior Resident Inspector, USNRC, Turkey Po'int Plant 89%200244 8)0913 PDR ADOCK 05000250 S PDC an FPL Group company NRC Form 344 (9)U.S.NUCLEAR AEOULATORY COMMISSION APPROVED OM()NO.31500)04 LICENSEE EVENT REPORT (LER)EXPIAES: 4/31/SS FACILITY NAMK (II DOCKET NUMBER l2)PA E 3 Turkey Point Unit 3 0 5 0 0 0 250 1 OFO 3 source Surveillances Required by Technical Specifications 3.11 and 4.13 EVENT OATK (5)MONTH DAY YEAR YEAR ER NUMBER (4)REPORT DATE (7)+~Sr ESOVSNTIAL NVMSKR OAY YEAR RIW~REVISION MONTH kcrer NVMSSR OTHER FACILITIES INVOLVED (4)DOCKET NUMBER(SI FACILITY NAMES Turkey Point Unit 4 0 5 0 0 0 2 5 0 7 7 8 9 8)(9 0 1 2 000 9 13 89 0 5 0 0 0 OPS RAT I NO MOCK (1)POWER LEVEL 1 P P 110)<44~IS:,.20.402 I 4 I 20AOS(~l(1)(il 20AOS(~(Ill(4 I 20,405(~)(I)(iii)20AOS(c)(I l(lrl 20.405 (c I (I I (r)20.405(c)SODS(e)(l) 50.34(e)(2)X 50.73(el(2)lil 50.73(cl(2)(4) 50.734)(2)(i(i I LICENSEE CONTACT FOR THIS LER (12I 50.73(e)(2((irl 50.73(c I (2 l(r)50.73(el(2)(rill 50.73(e l(2)(riii)(Al 50.73(el(2)(riii)(BI 50.73(c I (2)(e I THIS REPORT IS SUSMITTKD PURSUANT TO THE REQUIREMENTS OF 10 CFR g: ICnece one or more ol tne lorlortlnPI (11)73.71(bl 73.71(c)OTHER ISpeclry In Abttrcct below enrt In Teer.HRC Form 3EEAI NAME Ed Lyons-Regulation and Compliance Engineer TELEPHONE NVIIBEA AREA CODE 3 052 46-73 COMPLETE ONE LINE FOR EACH COMPONENT FAILUAE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC TUREA 5 3)CAUSE SYSTEM COMPONENT y'......r...3 r R: MANUFAC.TVRER er EPOATABLE TO NPRDS 5¹W SUPPLEMENTAL REPORT EXPECTED (14)YES III yer, complete EIIPECTED SUEMISSIDH DATE)NO ABSTRACT ILlmlt to 1400 rpecet, I.e., epproelmetery llltecn slnole u>>ce typewritten tined (14(EXPECTED SUBMISSION OATS (IS)MONTH DAY YEAR On July 7, 1989, with Unit 3 and Unit 4 in Mode 1 at 100%, Health Physias personnel (non-licensed utility personnel) disoovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Teohniaal Specifications (TS)3.11 and 4.13.The sub)eat Cesium-137 calibration sourae has an activity of 30 miaroauries. | | Re: Turkey Point Units 3 and 4 Docket No. 50-250 and 50-251 Reportable Event: 89-12 Date of Event: July 7, 1989 Source Surveillances Required by Technical Specification 3.11 and 4.13 Missed Due to Inade ate Administrative Controls The attached Licensee Event Report (LER) is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
| TS 3.11 requires those quantities of by-product material that exceed the quantities listed in 10CPR30.71 are to be leak tested in aeeordanae with the sohedule described in TS 4.13.The required leakage tests have not been performed, sinae receipt of the subject liquid Sointillation Counter in June, 1987.This.LER is being submitted late, sinae the appropriate personnel were not notified of the incident until August 16, 1989.The sub5eot Cesium-137 aalibration source passed a leak test conducted on July 9, 1989.On June 30, 1989, Administrative Proaedure, O-ADM-022,"Proauring Radioaative Souraes," was issued.This procedure administratively controls the procuring of all radioactive souraes (except fuel), and requires all shippers to indicate on the outside of the package if the package contains radioaative material.The individual responsible for the tardiness of this LER has been aounseled. | | Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/JRH/cm cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC |
| NRC Form 344 (9.43 I 4 | | ~ |
| NRC form 344A ps')LICENSEE E T REPORT (LER)TEXT CONTINUA U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3)eAM)04 EXPIRES: S)31188 f Se,ILITY NAME (1)OOCKET NUMSER (1)LER NUMBER (Sl PAGE (3)Turkey Point Unit 3 TEXT lll more spece hs rryked, Ihse afChCoresi NRC femr JSSA'sl (17)YEAR o s o o o 250 89)hIP SEGVENTIAL | | Senior Resident Inspector, USNRC, Turkey Po'int Plant 89%200244 8)0913 PDR ADOCK 05000250 S PDC an FPL Group company |
| :...'h NVMEER-0 1 2>~Ah(REVISION NVMSER 0 0 0 2 0 3 Event On July 7, 1989)Health Physics (non-licensed utility personnel) discovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Technical Specifications 3.11,"Miscellaneous Radioactive Materials Sources," and 4.13,"Radioactive Materials Sources Surveillance | | |
| ." The Cesium-137 internal calibration source has an activity of 30 microcuries | | NRC Form 344 U.S. NUCLEAR AEOULATORY COMMISSION (9 ) |
| .Technical Specification 3.11 requires those quantitites of by-product material that exceed the quantities listed in 10CFR30.71 (Schedule B)be leak tested in accordance with the schedule described in Technical Specification 4.13.Since receipt of the subject liquid Scintillation Counter in June, 1987, the required tests for leakage have not been performed. | | APPROVED OM() NO. 31500)04 EXPIAES: 4/31/SS LICENSEE EVENT REPORT (LER) |
| This report was not submitted within 30 days as required by 10CFR50.73(a) due to non-cognitive personnel error (non-licensed utility personnel) in that the appropriate personnel were not made aware of the incident until August 16, 1989.Cause of the Event The source delineated above fell under the Department of Transportation category of"Excepted Radioactive Materials," more specifically 49CFR173.422,"Exceptions for Instruments and Articles." This regulation indicates that shipments containing less than 100,000 microcuries of Cesium-137 as a component part of the instrument or article do not require any labeling on the outside of the package.For cases such as this, appropriate administrative controls to ensure that Health Physics personnel were notified upon receipt of the source did not exist.Therefore, Health Physics did not know the Cesium-137 internal calibration source existed on site.Anal sis of the Event Although Technical Specifications 3.11 and 4.13 require the subject source to be tested for leakage, 10CFR31.5(c)(2)(ii) states that devices containing not more than 100 microcuries of other beta and/or gamma emitting material need not be tested for any purpose.In addition;the subject Cesium-137 calibration source passed a leak test conducted on July 9, 1989.Based on the above, this event had no effect on the health and safety of the public.Corrective Actions 1)The Cesium-137 calibration source contained within the subject liquid Scintillation Counter passed a leak test conducted. | | DOCKET NUMBER l2) PA E 3 FACILITY NAMK (II Turkey Point Unit 3 0 5 0 0 0 250 1 OFO 3 source Surveillances Required by Technical Specifications 3. 11 and 4. 13 EVENT OATK (5) ER NUMBER (4) REPORT DATE (7) OTHER FACILITIES INVOLVED (4) |
| on July 9, 1989.NRC POEM 344A (083) | | YEAR +~Sr ESOVSNTIAL RIW~ REVISION OAY YEAR FACILITYNAMES DOCKET NUMBER(SI MONTH DAY YEAR NVMSKR kcrer NVMSSR MONTH Turkey Point Unit 4 0 5 0 0 0 2 5 0 7 7 8 9 8) (9 0 1 2 000 9 13 89 0 5 0 0 0 THIS REPORT IS SUSMITTKD PURSUANT TO THE REQUIREMENTS OF 10 CFR g: ICnece one or more ol tne lorlortlnPI (11) |
| NRC eorm 3BBA (94L('ICENSEE EV REPORT (LERI TEXT CONTINUAT V.S.NUCLEAR REOULATORY COMMISSION APPROYEO OMS NO.3(BOW(0+EXPIRES: B/31/ES PAL.ITY NAME (1)Turkey Point Unit 3 DOCKET NUMBER (21 o s o o o 2 5 0 LER NUMBER (Bl YEAR N(SBCUBNTIAL r@d'EVISION NUMBER'.NUMBER 013-0 PAGE (3)OF 0 3 TEXT///more eoece/e mrtu/red, uee eddidone/HRC/orIII 35SA 3/(17(2)Prior to the identification of this event, Administrative Procedure O-ADM-022,"Procuring Radioactive Sources," was issued on June 30, 1989.Except for fuel,, this procedure administratively controls the procurement of all radioactive sources.3)The individual responsible for the tardiness of this Licensee Event Report has been counseled on the requirements of plant procedures on event reporting and instructed on the appropriate mechanism to obtain an evaluation of the reportability of an event.4)A memorandum will be issued to appropriate Health Physics personnel discussing
| | OPS RAT I NO MOCK (1) 20.402 I 4 I 20.405(c) 50.73(e) (2((irl 73.71(bl POWER 20AOS( ~ l(1)(il SODS(e)(l) 50.73(c I (2 l(r) 73.71(c) |
| .the importance of obtaining an evaluation of the reportability of an event.Additional Information:
| | LEVEL 110) 1 P P 20AOS( ~ (Ill(4I 50.34(e) (2) 50.73(el(2) (rill OTHER ISpeclry In Abttrcct below enrt In Teer. HRC Form 20,405( ~ ) (I ) (iii) X 50.73(el(2)lil 50.73(e l(2) (riii)(Al 3EEAI 20AOS(c) (I l(lrl 50.73(cl(2)(4) 50.73(el(2)(riii) (BI |
| No similar Licensee Event Reports were identified. | | <44 ~IS:,. 20.405 (c I (I I (r) 50.734) (2) (i(iI 50.73(c I (2)(e I LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NVIIBEA AREA CODE Ed Lyons - Regulation and Compliance Engineer 3 052 46- 73 COMPLETE ONE LINE FOR EACH COMPONENT FAILUAE DESCRIBED IN THIS REPORT (13) er MANUFAC 5 MANUFAC. EPOATABLE CAUSE SYSTEM COMPONENT TUREA ) CAUSE SYSTEM COMPONENT TVRER TO NPRDS y'...... r ... 33 r R: |
| | 5¹W SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION OATS (IS) |
| | YES IIIyer, complete EIIPECTED SUEMISSIDH DATE) NO ABSTRACT ILlmlt to 1400 rpecet, I.e., epproelmetery llltecn slnole u>>ce typewritten tined (14( |
| | On July 7, 1989, with Unit 3 and Unit 4 in Mode 1 at 100%, Health Physias personnel (non-licensed utility personnel) disoovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Teohniaal Specifications (TS) 3.11 and 4.13. The sub)eat Cesium-137 calibration sourae has an activity of 30 miaroauries. TS 3.11 requires those quantities of by-product material that exceed the quantities listed in 10CPR30.71 are to be leak tested in aeeordanae with the sohedule described in TS 4.13. The required leakage tests have not been performed, sinae receipt of the subject liquid Sointillation Counter in June, 1987. This. LER is being submitted late, sinae the appropriate personnel were not notified of the incident until August 16, 1989. The sub5eot Cesium-137 aalibration source passed a leak test conducted on July 9, 1989. On June 30, 1989, Administrative Proaedure, O-ADM-022, "Proauring Radioaative Souraes," was issued . This procedure administratively controls the procuring of all radioactive souraes (except fuel), and requires all shippers to indicate on the outside of the package if the package contains radioaative material. The individual responsible for the tardiness of this LER has been aounseled. |
| | NRC Form 344 (9.43 I |
| | |
| | 4 NRC form 344A U.S. NUCLEAR REGULATORY COMMISSION ps') LICENSEE E T REPORT (LER) TEXT CONTINUA APPROVEO OMS NO. 3)eAM)04 EXPIRES: S)31188 fSe,ILITY NAME (1) OOCKET NUMSER (1) LER NUMBER (Sl PAGE (3) |
| | YEAR )hIP SEGVENTIAL >~Ah( REVISION |
| | :...'h NVMEER NVMSER Turkey Point Unit 3 o s o o o 250 89 0 1 2 0 0 0 2 0 3 TEXT lllmore spece hs rryked, Ihse afChCoresi NRC femr JSSA'sl (17) |
| | Event On July 7, 1989) Health Physics (non-licensed utility personnel) discovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Technical Specifications 3.11, "Miscellaneous Radioactive Materials Sources," and 4.13, "Radioactive Materials Sources Surveillance ." The Cesium-137 internal calibration source has an activity of 30 microcuries . Technical Specification 3.11 requires those quantitites of by-product material that exceed the quantities listed in 10CFR30.71 (Schedule B) be leak tested in accordance with the schedule described in Technical Specification 4.13. Since receipt of the subject liquid Scintillation Counter in June, 1987, the required tests for leakage have not been performed. |
| | This report was not submitted within 30 days as required by 10CFR50.73(a) due to non-cognitive personnel error (non-licensed utility personnel) in that the appropriate personnel were not made aware of the incident until August 16, 1989. |
| | Cause of the Event The source delineated above fell under the Department of Transportation category of "Excepted Radioactive Materials," more specifically 49CFR173 .422, "Exceptions for Instruments and Articles ." This regulation indicates that shipments containing less than 100,000 microcuries of Cesium-137 as a component part of the instrument or article do not require any labeling on the outside of the package . For cases such as this, appropriate administrative controls to ensure that Health Physics personnel were notified upon receipt of the source did not exist. Therefore, Health Physics did not know the Cesium-137 internal calibration source existed on site. |
| | Anal sis of the Event Although Technical Specifications 3.11 and 4.13 require the subject source to be tested for leakage, 10CFR31.5(c)(2)(ii) states that devices containing not more than 100 microcuries of other beta and/or gamma emitting material need not be tested for any purpose. In addition; the subject Cesium-137 calibration source passed a leak test conducted on July 9, 1989. Based on the above, this event had no effect on the health and safety of the public. |
| | Corrective Actions |
| | : 1) The Cesium-137 calibration source contained within the subject liquid Scintillation Counter passed a leak test conducted. on July 9, 1989. |
| | NRC POEM 344A (083) |
| | |
| | V.S. NUCLEAR REOULATORY COMMISSION (94L('ICENSEE EV NRC eorm 3BBA REPORT (LERI TEXT CONTINUAT APPROYEO OMS NO. 3(BOW(0+ |
| | EXPIRES: B/31/ES PAL. ITY NAME (1) DOCKET NUMBER (21 LER NUMBER (Bl PAGE (3) |
| | YEAR N( NUMBER '. |
| | SBCUBNTIAL r@d'EVISION NUMBER Turkey Point Unit 3 o s o o o 2 5 0 013 0 OF 0 3 TEXT /// more eoece /e mrtu/red, uee eddidone/ HRC /orIII35SA 3/ (17( |
| | : 2) Prior to the identification of this event, Administrative Procedure O-ADM-022, "Procuring Radioactive Sources," was issued on June 30, 1989. |
| | Except for fuel,, this procedure administratively controls the procurement of all radioactive sources . |
| | : 3) The individual responsible for the tardiness of this Licensee Event Report has been counseled on the requirements of plant procedures on event reporting and instructed on the appropriate mechanism to obtain an evaluation of the reportability of an event. |
| | : 4) A memorandum will be issued to appropriate Health Physics personnel discussing |
| | . the importance of obtaining an evaluation of the reportability of an event . |
| | Additional Information: |
| | No similar Licensee Event Reports were identified. |
| NRC FORM 3BBA (9831}} | | NRC FORM 3BBA (9831}} |
|
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:RO)
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
A'CCESSION NBR:8909200244 DOC.DATE: 89/09/13 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION LYONS,E. Florida Power & Light Co.
WOODY,C.O. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 89-012-00:on 890707,source surveillances required by Tech Spec missed due to inadequate administrative controls.
W/8 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL i SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1' IRM/DCTS/DAB 1 1
. NRR/DEST/CEB 8H 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR RPB 10 2 2 NUDOCS-ABSTRACT 1 1 1 1 RES/DS IR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 L ST LOBBY WARD 1' LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1. NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOIR 'ZO ALL 'KIDS" R1XXPI1MS:
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FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40
P. x14000, Juno Beach, FL 33408.0420 SEPTEMBER 1 3 1989 L-89-336 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket No. 50-250 and 50-251 Reportable Event: 89-12 Date of Event: July 7, 1989 Source Surveillances Required by Technical Specification 3.11 and 4.13 Missed Due to Inade ate Administrative Controls The attached Licensee Event Report (LER) is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/JRH/cm cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC
~
Senior Resident Inspector, USNRC, Turkey Po'int Plant 89%200244 8)0913 PDR ADOCK 05000250 S PDC an FPL Group company
NRC Form 344 U.S. NUCLEAR AEOULATORY COMMISSION (9 )
APPROVED OM() NO. 31500)04 EXPIAES: 4/31/SS LICENSEE EVENT REPORT (LER)
DOCKET NUMBER l2) PA E 3 FACILITY NAMK (II Turkey Point Unit 3 0 5 0 0 0 250 1 OFO 3 source Surveillances Required by Technical Specifications 3. 11 and 4. 13 EVENT OATK (5) ER NUMBER (4) REPORT DATE (7) OTHER FACILITIES INVOLVED (4)
YEAR +~Sr ESOVSNTIAL RIW~ REVISION OAY YEAR FACILITYNAMES DOCKET NUMBER(SI MONTH DAY YEAR NVMSKR kcrer NVMSSR MONTH Turkey Point Unit 4 0 5 0 0 0 2 5 0 7 7 8 9 8) (9 0 1 2 000 9 13 89 0 5 0 0 0 THIS REPORT IS SUSMITTKD PURSUANT TO THE REQUIREMENTS OF 10 CFR g: ICnece one or more ol tne lorlortlnPI (11)
OPS RAT I NO MOCK (1) 20.402 I 4 I 20.405(c) 50.73(e) (2((irl 73.71(bl POWER 20AOS( ~ l(1)(il SODS(e)(l) 50.73(c I (2 l(r) 73.71(c)
LEVEL 110) 1 P P 20AOS( ~ (Ill(4I 50.34(e) (2) 50.73(el(2) (rill OTHER ISpeclry In Abttrcct below enrt In Teer. HRC Form 20,405( ~ ) (I ) (iii) X 50.73(el(2)lil 50.73(e l(2) (riii)(Al 3EEAI 20AOS(c) (I l(lrl 50.73(cl(2)(4) 50.73(el(2)(riii) (BI
<44 ~IS:,. 20.405 (c I (I I (r) 50.734) (2) (i(iI 50.73(c I (2)(e I LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NVIIBEA AREA CODE Ed Lyons - Regulation and Compliance Engineer 3 052 46- 73 COMPLETE ONE LINE FOR EACH COMPONENT FAILUAE DESCRIBED IN THIS REPORT (13) er MANUFAC 5 MANUFAC. EPOATABLE CAUSE SYSTEM COMPONENT TUREA ) CAUSE SYSTEM COMPONENT TVRER TO NPRDS y'...... r ... 33 r R:
5¹W SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION OATS (IS)
YES IIIyer, complete EIIPECTED SUEMISSIDH DATE) NO ABSTRACT ILlmlt to 1400 rpecet, I.e., epproelmetery llltecn slnole u>>ce typewritten tined (14(
On July 7, 1989, with Unit 3 and Unit 4 in Mode 1 at 100%, Health Physias personnel (non-licensed utility personnel) disoovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Teohniaal Specifications (TS) 3.11 and 4.13. The sub)eat Cesium-137 calibration sourae has an activity of 30 miaroauries. TS 3.11 requires those quantities of by-product material that exceed the quantities listed in 10CPR30.71 are to be leak tested in aeeordanae with the sohedule described in TS 4.13. The required leakage tests have not been performed, sinae receipt of the subject liquid Sointillation Counter in June, 1987. This. LER is being submitted late, sinae the appropriate personnel were not notified of the incident until August 16, 1989. The sub5eot Cesium-137 aalibration source passed a leak test conducted on July 9, 1989. On June 30, 1989, Administrative Proaedure, O-ADM-022, "Proauring Radioaative Souraes," was issued . This procedure administratively controls the procuring of all radioactive souraes (except fuel), and requires all shippers to indicate on the outside of the package if the package contains radioaative material. The individual responsible for the tardiness of this LER has been aounseled.
NRC Form 344 (9.43 I
4 NRC form 344A U.S. NUCLEAR REGULATORY COMMISSION ps') LICENSEE E T REPORT (LER) TEXT CONTINUA APPROVEO OMS NO. 3)eAM)04 EXPIRES: S)31188 fSe,ILITY NAME (1) OOCKET NUMSER (1) LER NUMBER (Sl PAGE (3)
YEAR )hIP SEGVENTIAL >~Ah( REVISION
- ...'h NVMEER NVMSER Turkey Point Unit 3 o s o o o 250 89 0 1 2 0 0 0 2 0 3 TEXT lllmore spece hs rryked, Ihse afChCoresi NRC femr JSSA'sl (17)
Event On July 7, 1989) Health Physics (non-licensed utility personnel) discovered a liquid Scintillation Counter with an internal calibration source that had not been leak tested as required by Technical Specifications 3.11, "Miscellaneous Radioactive Materials Sources," and 4.13, "Radioactive Materials Sources Surveillance ." The Cesium-137 internal calibration source has an activity of 30 microcuries . Technical Specification 3.11 requires those quantitites of by-product material that exceed the quantities listed in 10CFR30.71 (Schedule B) be leak tested in accordance with the schedule described in Technical Specification 4.13. Since receipt of the subject liquid Scintillation Counter in June, 1987, the required tests for leakage have not been performed.
This report was not submitted within 30 days as required by 10CFR50.73(a) due to non-cognitive personnel error (non-licensed utility personnel) in that the appropriate personnel were not made aware of the incident until August 16, 1989.
Cause of the Event The source delineated above fell under the Department of Transportation category of "Excepted Radioactive Materials," more specifically 49CFR173 .422, "Exceptions for Instruments and Articles ." This regulation indicates that shipments containing less than 100,000 microcuries of Cesium-137 as a component part of the instrument or article do not require any labeling on the outside of the package . For cases such as this, appropriate administrative controls to ensure that Health Physics personnel were notified upon receipt of the source did not exist. Therefore, Health Physics did not know the Cesium-137 internal calibration source existed on site.
Anal sis of the Event Although Technical Specifications 3.11 and 4.13 require the subject source to be tested for leakage, 10CFR31.5(c)(2)(ii) states that devices containing not more than 100 microcuries of other beta and/or gamma emitting material need not be tested for any purpose. In addition; the subject Cesium-137 calibration source passed a leak test conducted on July 9, 1989. Based on the above, this event had no effect on the health and safety of the public.
Corrective Actions
- 1) The Cesium-137 calibration source contained within the subject liquid Scintillation Counter passed a leak test conducted. on July 9, 1989.
NRC POEM 344A (083)
V.S. NUCLEAR REOULATORY COMMISSION (94L('ICENSEE EV NRC eorm 3BBA REPORT (LERI TEXT CONTINUAT APPROYEO OMS NO. 3(BOW(0+
EXPIRES: B/31/ES PAL. ITY NAME (1) DOCKET NUMBER (21 LER NUMBER (Bl PAGE (3)
YEAR N( NUMBER '.
SBCUBNTIAL r@d'EVISION NUMBER Turkey Point Unit 3 o s o o o 2 5 0 013 0 OF 0 3 TEXT /// more eoece /e mrtu/red, uee eddidone/ HRC /orIII35SA 3/ (17(
- 2) Prior to the identification of this event, Administrative Procedure O-ADM-022, "Procuring Radioactive Sources," was issued on June 30, 1989.
Except for fuel,, this procedure administratively controls the procurement of all radioactive sources .
- 3) The individual responsible for the tardiness of this Licensee Event Report has been counseled on the requirements of plant procedures on event reporting and instructed on the appropriate mechanism to obtain an evaluation of the reportability of an event.
- 4) A memorandum will be issued to appropriate Health Physics personnel discussing
. the importance of obtaining an evaluation of the reportability of an event .
Additional Information:
No similar Licensee Event Reports were identified.
NRC FORM 3BBA (9831