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| {{#Wiki_filter:RFGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: OREILLY J P ORG: SCHMIDT A D NRC FL PNR 8.LIGHT DOCDATE: 07/07/78 DATE RCVD: 07/31/78 DOCTYPE: LETTER NOTARIZED: | | {{#Wiki_filter:RFGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO COPIES RECEIVED | | DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: OREILLY J P ORG: SCHMIDT A D DOCDATE: 07/07/78 NRC FL PNR 8. LIGHT DATE RCVD: 07/31/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LTR 1 ENCL 1 FORNARDING LICENSEE EVENT REPT (RO 50-335f78-021) | | LTR 1 ENCL 1 FORNARDING LICENSEE EVENT REPT (RO 50-335f78-021) ON 06/08/78 CONCERNING DURING PWR ASCENSXON TESTING FOLLOWlNG REFUELING OUTAGE'EA 865 DROPPED FOUR TIMES DUF TO FAILURE OF ONE OR MORE OF ITS COIL PNR PROGRAMMER TIMING MODULE, INTEGRAL TIMER > OR 15 VO PLANT NAME: ST LUCIE 51 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:DL. |
| ON 06/08/78 CONCERNING DURING PWR ASCENSXON TESTING FOLLOWlNG REFUELING OUTAGE'EA 865 DROPPED FOUR TIMES DUF TO FAILURE OF ONE OR MORE OF ITS COIL PNR PROGRAMMER TIMING MODULE, INTEGRAL TIMER>OR 15 VO PLANT NAME: ST LUCIE 51 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: DL.~444H~+++~~4+4+++4+ | | ~444H~+++~~4+4+++4+ DXSTRIBUT10N OF THI MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002). |
| DXSTRIBUT10N OF THI MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002).FOR ACTION INTERNAL: EXTERNAL: ORB94 BC++W/4 ENCL REG FILE W/ENCL h E~~2 ENCL 1 SYSTEMS BR++W/ENCL NOVAK/CHECK+4W/ENCL AD FOR ENG>~~N/ENCL I.IANAUER4 | | FOR ACTION ORB94 BC++W/4 ENCL INTERNAL: REG FILE W/ENCL NRC PDR>+W/ENCL h E~~ 2 ENCL MIPC4~W/3 ENCL 1 SYSTEMS BR++W/ENCL EMERGENCY PLAN BR>+W/ENCL NOVAK/CHECK+4W/ ENCL EEB~~W/ENCL AD FOR ENG>~~N/ENCL PLANT SYSTEMS BR+>N/ENCL I.IANAUER4~W/ ENCL AD FOR PLANT SYSTEMS+4W/ENCL AD FOR SYS 5 PROJ+~~N/ENCL REACTOR SAFETY BR>>W/ENCL ENGINEERING BR++WfENCL VOLLMER/BUNCH+wW/ENCL KREGER/J. COLLINS+4W/ENCL POWER SYS BR>4N/ENCL K SEYFRIT/ IE+4l J/ENCL EXTERNAL: LPDR S FT PIERCE) FL++N/ENCL TICi LIZ CARTER++W/ENCL NSIC+4IN/ENCL ACRS CAT B%4W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7821400 5 SI ZE: iP+iP+iP jlà THE END |
| ~W/ENCL AD FOR SYS 5 PROJ+~~N/ENCL ENGINEERING BR++Wf ENCL KREGER/J.COLLINS+4W/ENCL K SEYFRIT/IE+4l J/ENCL LPDR S FT PIERCE)FL++N/ENCL TICi LIZ CARTER++W/ENCL NSIC+4IN/ENCL ACRS CAT B%4W/16 ENCL NRC PDR>+W/ENCL MIPC4~W/3 ENCL EMERGENCY PLAN BR>+W/ENCL EEB~~W/ENCL PLANT SYSTEMS BR+>N/ENCL AD FOR PLANT SYSTEMS+4W/ENCL REACTOR SAFETY BR>>W/ENCL VOLLMER/BUNCH+wW/ENCL POWER SYS BR>4N/ENCL DISTRIBUTION: | |
| LTR 45 ENCL 45 SI ZE: iP+iP+iP CONTROL NBR: 7821400 5 jlÃTHE END H 1 p~E y~E I E a'E I I r* | |
| FLORIDA POWER 5 LIGHT COMPANY July 7, 1978 PRN-LI-78-182 Mr'.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.H., Suite 1217 Atlanta, Georgia 30303
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| ==Dear Mr.O'Reilly:== | | 1 H |
| REPORTABLE OCCURRENCE 335-78-21 ST.LUCIE UNIT 1 DATE OF OCCURRENCE'UNE 8 1978 C7 f Pl CI)C)L.~mph CA n ca~'>tg~-C7 PJ)p CA~CZl TECHNICAL SPECIFICATION 3.1.3.l.e CEA 68 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide notification of the subject occurrence. | | ~ |
| 'ery truly yours, A.D.Schmidt Vice President Power Resources MAS/cpc Attachment cc: Harold F.Reis, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)782 f g{)p9g t E, p,'I I 4 U 1 4 I't NAC FOAM 368 l1 TTl LICEIVSEE EVEIVT REPORT I U.S.NUCLEAR REGULATORY COMMISSION I I 1 CON'T~0 1 0 2 I l I I lQI (FI.EASE PAINT OR TYPe ALL AECUIRED INFOARaaIATIONI UCKNSKc CQQK Ic Q,.Q Q iS LiCSNSK, YSc JO 51 CAT Q LICSNSK NUMSKR 0 0171 aiLBOTI 171 I Jaa"'.il ZQQ I I'Q~SO St 0 CCK K~GAUM 8 6 R 58 FVENT OESCAIPTION ANO PROSAELE CONSECUEBVCES QIO Durin ower ascension testin f 1 wi 4VKNT QATc I4 1$Af PORT QAT'f C A 6 r fu FILI 7 iii I I 1-101010101 I-I I~ill I~IQL~03~04 each of the first three dro s CEA 868 was restored to its normal osition~0$i hin the time limit re uired b the a licable Technical S ecification | | p E |
| ~08 3.1.3.l.e action statement. | | y E |
| After the four h dro CEA 68 was declared re re laced after which CEA 868 was~oa[009)CE3 imin module inte ral timer or 15 volt ower su lier.Since all three SYSTEM CAVSK CAVSK CQMI.VALVE C 08 CQQE SUSCQQK CCMPONKNT CQQK SUSCQCS SUSCQQS LRRIIQ LEJQLL LHC~eR 4-'7 I FIB LAC 1 8 9 III II I2 IS'19 9$4CVKNTIAL" OCCURAEiICK AKPQAT RKVISIQN LcRIRO%VKNT YKAA Af PORT NO.CQQK TYPS NO.OZB 06 a NZ[77'8J~~02 I 1~m~03~L~~0 2 I 32 24 28 21 30 31 32 ACTION SVTVAK KPScC.SNUT001NN AT~ACIaMSNT ISA'RIMKC Mi.CQMPCNKNT TAKEN ACTION CN PLANT MKTIaCO MCVR$22 SV8MITTKO SCRMSUS.SVPSUKR MAaIVSACTURSR LAJQLzJQ LBJaa LRJQ~00 0 II LYJQ MNQ~NIQ LOOOR NC 34 i6 31 40 41~2 43 44 41 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS Q21 0 CEA 868 dro ed due to failure of one or more'of its coil ower ro raomer A weeks.8 9 S 4CILI~Y%0 5~ATVS~i PQ'rVKR OTNKil STATVS i~8QZN~018 10 Qc NA 1 8 10 12 13 44 ACTIVITY CON TKNT aIKLKASSO CS AKI.SASK AMOUlcr QS ACTIVITY Q38~II 9~Z Q3~ZQ34 NA 1 10 44 Pf ASCNNKL f XFaQSUA 6 3~00 0 QOZ~ZQLB 9 It SSASCNNKL IN4VAIK3 a~OO 10 IQO LCSSOS CaI QAMACK TO S4CIUTY Q43 0 6 SCRI PTI CN~i9~ZQ2 1 8 i I0 FaUSLIC:TY.SSLK0 QK SCRIPT.N Q KK ULO 2 8 3:0 PIAME OF PREPARER M6THCO CS CISCQVKR Y~AQQI'5 46 45 NA NA QISCQVKAY KSCRIPTICN 82 Operator Obser vatWon LccATIONg Af LKAsc Q36 30 NRC USc CNI.Y I'I'I lli Ill II 68 59 50 rvcNE: 305 552 3802 REPORTABLE OCCURRENCE 335-78-21 LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion The coil power programer timing module, the integral timer, and the 15 volt power supplier for CEA 868 were replaced, after which CEA 868 operated satisfactorily. | | ~ |
| CEA>68 was aligned to its normal position and power ascension testing continued. | | I E a |
| As a result of the reactivity insertions of the dropped CEA s, azimuthal power tilt (Tq)increased and twice exceeded the limit requiring action in accordance nit(Technical Specification 3.2.4.Also, the total planar radial peaking factor (Fxy)increased and exceeded the limit requiring action in accordance with Technical Specification 3.2.2 severalTtimes.
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| In all of the above cases, reactor power was reduced, and both Tq and Fxy were returned to normal within the time limits described in their respective Specifications.}} | | |
| | FLORIDA POWER 5 LIGHT COMPANY July 7, 1978 PRN-LI-78-182 Mr'. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement C7 U. S. Nuclear Regulatory Commission n Plf 230 Peachtree Street, N. H., Suite 1217 CI) ca~'> |
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| | Atlanta, Georgia 30303 C)L .~ PJ) |
| | C7 |
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| | ==Dear Mr. O'Reilly:== |
| | mph CA p |
| | ~ CZl REPORTABLE OCCURRENCE 335-78-21 ST. LUCIE UNIT 1 CA DATE OF OCCURRENCE'UNE 8 1978 TECHNICAL SPECIFICATION 3.1.3.l.e CEA 68 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide notification of the subject occurrence. |
| | 'ery truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (30) |
| | Director, Office of Management Information and Program Control (3) 782 f g{)p9g t |
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| | I NAC FOAM 368 U. S. NUCLEAR REGULATORY COMMISSION l1 TTl I LICEIVSEE EVEIVT REPORT I l I lQI (FI.EASE PAINT OR TYPe ALL AECUIRED INFOARaaIATIONI Q~ |
| | I I 1 |
| | CON'T FILI 7 UCKNSKc CQQK iii Ic I |
| | Q, I 1-101010101 GAUM LICSNSK NUMSKR I- I I |
| | .Q ~ill I iS LiCSNSK, YSc JO Q ~IQL 51 CAT Q |
| | ~0 1 |
| | "'.il ZQQ SO St I I 0 CCK K ~ |
| | 86R 58 0 |
| | 4VKNT QATc 0171 I4 aiLBOTI 1$ |
| | 171 AfPORT QAT'f I |
| | Jaa FVENT OESCAIPTION ANO PROSAELE CONSECUEBVCES QIO 0 2 Durin ower ascension testin f 1 wi r fu C A 6 |
| | ~03 |
| | ~04 each of the first three dro s CEA 868 was restored to its normal osition |
| | ~0$ i hin the time limit re uired b the a licable Technical S ecification |
| | ~08 3.1.3.l.e action statement. After the four h dro CEA 68 was declared re re laced after which CEA 868 was |
| | ~oa |
| | [009) 1 8 9 SYSTEM C |
| | LRRIIQ 08 III CAVSK CQQE LEJQLL II CAVSK SUSCQQK LHC I2 |
| | $ 4CVKNTIAL |
| | ~eR CCMPONKNT CQQK IS OCCURAEiICK 4-'7 CQMI. |
| | SUSCQCS I |
| | '19 FIB LAC AKPQAT VALVE SUSCQQS 9 |
| | RKVISIQN OZB LcRIRO 06 a NZ ACTION SVTVAK |
| | %VKNT YKAA |
| | [77'8J 2I 32 KPScC. |
| | ~ SNUT001NN |
| | ~02 24 AfPORT NO. |
| | I 1 28 |
| | ~m 21 |
| | ~03 CQQK AT ~ ACIaMSNT ISA'RIMKC TYPS |
| | ~L 30 |
| | ~31 Mi. |
| | NO. |
| | ~0 32 CQMPCNKNT TAKEN ACTION CN PLANT MKTIaCO MCVR$ 22 SV8MITTKO SCRMSUS. SVPSUKR MAaIVSACTURSR LAJQLzJQ 34 LBJaa LRJQ i6 |
| | ~00 31 0 II 40 LYJQ 41 MNQ ~NIQ 43 LOOOR 44 NC |
| | ~ 2 41 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS Q21 CE3 0 CEA 868 dro ed due to failure of one or more 'of its coil ower ro raomer imin module inte ral timer or 15 volt ower su lier. Since all three A |
| | weeks. |
| | 8 9 S 4CILI Y~ |
| | %0 M6THCO CS 5 ~ ATVS ~i PQ'rVKR OTNKil STATVS CISCQVKR Y QISCQVKAY KSCRIPTICN 82 i ~8QZN ~018 10 Qc NA ~AQQI Operator Obser vatWon 1 8 10 12 13 44 '5 46 ACTIVITY CON TKNT aIKLKASSO CS AKI.SASK AMOUlcrQS ACTIVITYQ38 LccATIONg AfLKAsc Q36 |
| | ~II 9 ~Z Q3 ~ZQ34 NA 1 10 44 45 Pf ASCNNKL fXFaQSUA 6 3 |
| | ~00 9 |
| | 0 It QOZ~ZQLB SSASCNNKL IN4VAIK3 30 a ~OO 10 IQO NA LCSSOS CaI QAMACK TO S4CIUTY 0 6 SCRI PTI CN Q43 |
| | ~i9 1 8 |
| | ~ZQ2 i I0 NA FaUSLIC:TY |
| | .SSLK0 QK SCRIPT.N Q 'I 'I lliIll II NRC USc CNI.Y KK ULO 2 8 3:0 I 68 59 50 PIAME OF PREPARER rvcNE: 305 552 3802 |
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| | REPORTABLE OCCURRENCE 335-78-21 LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion The coil power programer timing module, the integral timer, and the 15 volt power supplier for CEA 868 were replaced, after which CEA 868 operated satisfactorily. CEA >68 was aligned to its normal position and power ascension testing continued. |
| | of the reactivity insertions of the dropped tilt result s, azimuthal power As a CEA (Tq) increased and twice exceeded the limit requiring action in accordance nit( Technical Specification 3.2.4. Also, the total planar radial peaking factor (Fxy) increased and exceeded the limit requiring action in accordance with Technical Specification 3.2.2 severalTtimes. In all of the above cases, reactor power was reduced, and both Tq and Fxy were returned to normal within the time limits described in their respective Specifications.}} |
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000335/LER-2016-0032017-08-15015 August 2017 Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip, LER 16-003-01 for St. Lucie, Unit 1, Regarding Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip 05000389/LER-2017-0012017-04-27027 April 2017 Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements, LER 17-001-00 for St. Lucie, Unit 2 Regarding Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements 05000335/LER-2016-0012016-07-29029 July 2016 Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical.... L-2016-152, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Te2016-07-29029 July 2016 LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Tech L-2010-255, Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed2010-11-0101 November 2010 Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed ML0414104442004-05-18018 May 2004 Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel ML18127A6421978-09-22022 September 1978 LER 1978-032-00 for St. Lucie Unit 1, on 08/30/78 Concerning Daily Calibration of Nuc & ^T PWR (Technical Specification 4.3.1.1.1) Was Inadvertently Missed During One Surveillance Interval Encompassing Short Maintenance Outage & Subsequent ML18127A6431978-09-18018 September 1978 LER 1978-031-00 for St. Lucie Unit 1, on 08/16/78 Concerning the Ginca Code Operator Used Incorrect Flux Inputs in Arriving at the Incore Setpoints ML18127A6461978-09-0808 September 1978 LER 1978-030-00 for St. Lucie Unit 1, on 08/10/78 Concerning. the Surveillance Requirement of Specification 4.4.8 Which Requires an Isotopic Analysis for Iodine in the Primary Coolant, Was Inadvertently Missed ML18127A6471978-08-30030 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/31/78 Concerning Containment Vacuum Relief Valve (FCV-25-8) Instrument Air Supply Low Pressure Alarm Was Received. Cause Was Diaphragm Leak in Solenoid Valve Which Controls Instrument Air Supply ML18127A6481978-08-28028 August 1978 LER 1978-026-00 for St. Lucie Unit 1, on 07/30/78 Concerning During PWR Operation Digital Data Processing System Malfunctioned Resulting in Loss of CEA Backup Position Indication & Incore Flux Detector System Used to Monitor Flux D ML18127A6491978-08-25025 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/28/78 Concerning Notification by Applicant'S Vendor of Potential Problem with Certain Motor Operated Valves ML18127A6501978-08-0808 August 1978 LER 1978-011-01 for St. Lucie Unit 1, Update Concerning When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6511978-08-0707 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/24/78 Concerning an Error in the Analysis for the Cask Drop Accident Which Makes the Technical Specification 3.9.14 Non-Conservative ML18127A6521978-07-24024 July 1978 LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent ML18127A6531978-07-14014 July 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3. 3. 2. I. B ML18127A6551978-07-13013 July 1978 LER 1978-022-00 for St. Lucie Unit 1, on 06/15/78 Concerning During PWR Operation, the Digital Data Processing System Malfunctioned Due to Malfunctioning Multiplexer Card ML18127A6541978-07-13013 July 1978 LER 1978-023-00 for St. Lucie Unit 1, on 05/15/78 Concerning During Testing Humidity Control Heaters on the Shield Bldg Ventilation System (B Train) Tripped on High Temperatures Due to High Temperature Caused by Low Flow ML18127A6561978-07-0808 July 1978 LER 1978-021-00 for St. Lucie Unit 1, on 06/08/78 Concerning During PWR Ascension Testing Following Refueling Outage CEA #65 Dropped Four Times Due to Failure of One or More of Its Coil PWR Programmer Timing Module, Integral Timer ML18127A6581978-07-0707 July 1978 LER 1978-020-00 for St. Lucie Unit 1, on 06/07/78 Concerning Pwer Ascension Physics Testing Following a Refueling Outage, CEA #65 Dropped ML18127A6601978-06-28028 June 1978 LER 1978-019-00 for St. Lucie Unit 1, on 05/30/78 Concerning During Special Low Pier Feedwater Control System Test a 15% Feedwater Bypass Control Valve Inadvertently Opened Fully Causing Excessive Cooling of 1A Steam Generator ML18127A6611978-06-26026 June 1978 LER 1978-018-00 for St. Lucie Unit 1, on 05/26/78 Concerning CEA #19 Dropped for No Apparent Reason ML18127A6621978-06-13013 June 1978 LER 1978-017-00 for St. Lucie Unit 1, on 05/14/78 Concerning Improper Switching at Pratt & Whitney Substation Combined with Incorrect Wiring of Protective Relays at Midway Substation Led to Deenergization of Midway Substation Resulting in L ML18127A6641978-06-0909 June 1978 LER 1978-016-00 for St. Lucie Unit 1, on 05/26/78 Concerning Containment Pressure-High Trip Setpoint (Table 2.2-1) Appeared to Be in Error During the Refueling Outage ML18127A6651978-05-23023 May 1978 LER 1978-015-00 for St. Lucie Unit 1, on 04/23/78 Concerning Operator Blew Down 1B Bamt Level Instrument to Prevent Sensing Line Blockage, Causing Instrument to Fail High ML18127A6691978-04-28028 April 1978 LER 1978-011-00 for St. Lucie Unit 1, When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6681978-04-28028 April 1978 LER 1978-012-00 for St. Lucie Unit 1, on 04/16/78 Concerning Eddy Current Testing Performed on Fuel Assembly CEA Guide Tubes at Unit 1 Showed Near in Guide Tubes Where Tips of Fully Withdrawn CEAs Were Located ML18127A6701978-04-27027 April 1978 LER 1978-013-00 for St. Lucie Unit 1, on 03/28/78 Concerning During Shutdown for Refueling, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8 ML18127A6711978-04-25025 April 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for the Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3.3.2.1.B ML18127A6731978-03-30030 March 1978 LER 1978-009-00 for St. Lucie Unit 1, During PWR Operation Digital Data Processing System Malfunctioned. Apparent Momentary Memory Failure Caused Ddps to Halt ML18127A6741978-03-24024 March 1978 LER 1978-008-00 for St. Lucie Unit 1, Due to an Administrative Error During a Procedure Revision Instructions for Documenting Surveillance of Volume in Diesel Generator Engine Mounted Fuel Tanks Were Omitted ML18127A6781978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18127A6791978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18144A8051977-12-15015 December 1977 12/15/1977 Memo Reportable Occurrence 335-77-50 ML18110A8681977-10-24024 October 1977 LER 1977-335-39 for St. Lucie, Unit 1 on Refueling Water Tank Piping ML18110A8691977-09-26026 September 1977 LER 1977-335-35 for St. Lucie, Unit 1 on Intake Cooling Water Pump ML18110A8711977-09-15015 September 1977 LER 1977-335-34 for St. Lucie, Unit 1 on Containment Spray Header Valve ML18110A8731977-09-13013 September 1977 LER 1977-335-31 for St. Lucie, Unit 1 on Repair of Leaking Shaft Mechanical Seal of Component Cooling Water Pump ML18110A8741977-09-0909 September 1977 LER 1977-335-33 for St. Lucie, Unit 1 on Steam Driven Auxiliary Feedwater Pump ML18110A8751977-08-31031 August 1977 LER 1977-335-32 for St. Lucie, Unit 1 on Refueling Water Tank Level Setpoint Drift ML18110A8761977-07-14014 July 1977 LER 1977-335-30 for St. Lucie, Unit 1 on Detector Calibration ML18110A8781977-07-0808 July 1977 LER 1977-335-28 for St. Lucie, Unit 1 on Containment Isolation Valve ML18110A8771977-07-0808 July 1977 LER 1977-335-03 for St. Lucie, Unit 1 on Diesel Generator 1A, Update Report No. 1 ML18110A8791977-06-27027 June 1977 LER 1977-335-27 for St. Lucie, Unit 1 on Dropped Control Element Assembly No. 39 Initiating a Turbine Runback ML18110A8801977-06-16016 June 1977 LER 1977-335-26 for St. Lucie, Unit 1 on Off-Site Power ML18110A8821977-06-0303 June 1977 LER 1977-335-25 for St. Lucie, Unit 1 Setpoint of Bistable Trip Unit for Steam Generator Pressure Found Inadequately Conservative ML18110A8831977-05-24024 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Safety Injection Line Weld ML18110A8841977-05-19019 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Pressure Boundary Leakage ML18110A8851977-05-15015 May 1977 LER 1977-335-20 for St. Lucie, Unit 1 Ginca Code ML18110A8811977-05-13013 May 1977 LER 1977-335-23 for St. Lucie, Unit 1 on RCS Flow 2017-08-15
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RFGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: OREILLY J P ORG: SCHMIDT A D DOCDATE: 07/07/78 NRC FL PNR 8. LIGHT DATE RCVD: 07/31/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORNARDING LICENSEE EVENT REPT (RO 50-335f78-021) ON 06/08/78 CONCERNING DURING PWR ASCENSXON TESTING FOLLOWlNG REFUELING OUTAGE'EA 865 DROPPED FOUR TIMES DUF TO FAILURE OF ONE OR MORE OF ITS COIL PNR PROGRAMMER TIMING MODULE, INTEGRAL TIMER > OR 15 VO PLANT NAME: ST LUCIE 51 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:DL.
~444H~+++~~4+4+++4+ DXSTRIBUT10N OF THI MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002).
FOR ACTION ORB94 BC++W/4 ENCL INTERNAL: REG FILE W/ENCL NRC PDR>+W/ENCL h E~~ 2 ENCL MIPC4~W/3 ENCL 1 SYSTEMS BR++W/ENCL EMERGENCY PLAN BR>+W/ENCL NOVAK/CHECK+4W/ ENCL EEB~~W/ENCL AD FOR ENG>~~N/ENCL PLANT SYSTEMS BR+>N/ENCL I.IANAUER4~W/ ENCL AD FOR PLANT SYSTEMS+4W/ENCL AD FOR SYS 5 PROJ+~~N/ENCL REACTOR SAFETY BR>>W/ENCL ENGINEERING BR++WfENCL VOLLMER/BUNCH+wW/ENCL KREGER/J. COLLINS+4W/ENCL POWER SYS BR>4N/ENCL K SEYFRIT/ IE+4l J/ENCL EXTERNAL: LPDR S FT PIERCE) FL++N/ENCL TICi LIZ CARTER++W/ENCL NSIC+4IN/ENCL ACRS CAT B%4W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7821400 5 SI ZE: iP+iP+iP jlà THE END
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FLORIDA POWER 5 LIGHT COMPANY July 7, 1978 PRN-LI-78-182 Mr'. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement C7 U. S. Nuclear Regulatory Commission n Plf 230 Peachtree Street, N. H., Suite 1217 CI) ca~'>
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~ CZl REPORTABLE OCCURRENCE 335-78-21 ST. LUCIE UNIT 1 CA DATE OF OCCURRENCE'UNE 8 1978 TECHNICAL SPECIFICATION 3.1.3.l.e CEA 68 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide notification of the subject occurrence.
'ery truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (30)
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REPORTABLE OCCURRENCE 335-78-21 LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion The coil power programer timing module, the integral timer, and the 15 volt power supplier for CEA 868 were replaced, after which CEA 868 operated satisfactorily. CEA >68 was aligned to its normal position and power ascension testing continued.
of the reactivity insertions of the dropped tilt result s, azimuthal power As a CEA (Tq) increased and twice exceeded the limit requiring action in accordance nit( Technical Specification 3.2.4. Also, the total planar radial peaking factor (Fxy) increased and exceeded the limit requiring action in accordance with Technical Specification 3.2.2 severalTtimes. In all of the above cases, reactor power was reduced, and both Tq and Fxy were returned to normal within the time limits described in their respective Specifications.