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| =Text= | | =Text= |
| {{#Wiki_filter:Dro one'EGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DI TRIBUTION FOR INCONING NATERIAL 0-33 REC: QREILLY J P NRC ORG: SCHMIDT A D FL PWR 5 LIGHT DOCD ATE: 09/22/78 DATE RCVD: 10/02l78 DOCTYPE: LETTER NOTARIZED: | | {{#Wiki_filter:Dro one'EGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS) |
| NO COPIES RECEIVED | | DI TRIBUTION FOR INCONING NATERIAL 0-33 REC: QREILLY J P ORG: SCHMIDT A D DOCD ATE: 09/22/78 NRC FL PWR 5 LIGHT DATE RCVD: 10/02l78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-032) | | LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-032) ON 08/30/78 CONCERNING DAILY CALIBRATION OF NUC AND T PWR (TECH SPEC 4. 3. i. Ai. SHORT 1) WAS INADVERTENTLY MAINTENANCE NIS ED DURING ONE SURVEILLANCE INTERVAL ENCOMPASSING OUTAGE AND SUB EGUENT STARTUP. |
| ON 08/30/78 CONCERNING DAILY CALIBRATION OF NUC AND T PWR (TECH SPEC 4.3.i.i.1)WAS INADVERTENTLY NIS ED DURING ONE SURVEILLANCE INTERVAL ENCOMPASSING A SHORT MAINTENANCE OUTAGE AND SUB EGUENT STARTUP.PLANT NAME: ST LUCIE ei REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: PL.>><<<<<<>(re<><>w>s>au<<nx DISTRIBUTlQN Qf THlS NATERIAL IS AS FQLLPWS<<<<<<v<<w+<<<<<<<<<<<<<<<<<<<<<< | | PLANT NAME: ST LUCIE ei REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:PL. |
| INCIDENT REPORTS (DISTRIBUTION CODE A002)FOR ACTlON: INTERNAL: BR CHIEI N4 BC<<<<W/4 ENCL ENCL I 5 E<<<:W/2 ENCL C SYSTENS BR<<<<l)/ENCL NGVAK/CHECK<+W/ENCL AD FOR ENG%<<W/ENCL HANAUER~<W/ENCL AD FGR SYS Sc PROJ<<<<W/ENCL ENGINEERING BRN<<W/ENCL KREGER/J.COLL INS<<<<W/ENCL K SEYFRIT/IE<<<<W/ENCL NRC PDR<<<<l)/ENCI | | >><<<<<<>(re<><>w>s>au<<nx DISTRIBUTlQN Qf THlS NATERIAL IS AS FQLLPWS <<<<<<v<<w+<<<<<<<<<<<<<<<<<<<<<< |
| 'NIPC<<<<W/3 ENCL EMERGENCY PLAN BR++W/ENCL EEB<<.<<L I/ENCL PLANT SYSTEMS BR++W/EhlCL AD FOR PLANT SYSTEMS<<<<W/ENCL REACTOR SAFETY BR++W/EhlCL VGLLMER/BUNCH<<'<<'W/ENCL POWER SYS BR<<<W/ENCL EXTERNAL: LPDR'S FT PIERCEi FL<<'.~W/ENCL NS I C<<<<W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUTION: | | INCIDENT REPORTS (DISTRIBUTION CODE A002) |
| LTR 44 ENCL 44 SIZE: 1P+1P r<<<<<<<<<<<<<<<<%%<<%<<45<<%<<<<<<<<<<<<<<<<<<<<<<%<<<<e><<<<<<<< | | FOR ACTlON: BR CHIEI N4 BC<<<<W/4 ENCL INTERNAL: ENCL NRC PDR<<<<l)/ENCI I 5 E<<<:W/2 ENCL 'NIPC<<<<W/3 ENCL C SYSTENS BR<<<<l)/ENCL EMERGENCY PLAN BR++W/ENCL NGVAK/CHECK<+W/ENCL EEB<<.<<L I/ENCL AD FOR ENG%<<W/ENCL PLANT SYSTEMS BR++W/EhlCL HANAUER~<W/ENCL AD FOR PLANT SYSTEMS<<<<W/ENCL AD FGR SYS Sc PROJ<<<<W/ENCL REACTOR SAFETY BR++W/EhlCL ENGINEERING BRN<<W/ENCL VGLLMER/BUNCH<<'<<'W/ENCL KREGER/ J. COLL INS<<<<W/ENCL POWER SYS BR<<<W/ENCL K SEYFRIT/IE<<<<W/ENCL EXTERNAL: LPDR'S FT PIERCEi FL<<'.~W/ENCL NS I C<<<<W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 7806801 6 SIZE: 1P+1P r |
| CONTROL NBR: 7806801 6 THE END
| | <<<<<<<<<<<<<<<<%%<<%<<45<<%<<<<<<<<<<<<<<<<<<<<<<%<<<<e><<<<<<<< THE END |
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| 0 Qo.'--1 FLORIDA POWEII 5 LIGHT COMPANY September 22, 1978 P RN-L I-78-267 Hr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S=.Nuclear Regulatory Commission 101 Harietta Street, Suite 3100 Atlanta, Georgia 30303 CQ 4 4 Cf.CJ REPORTABLE OCCURRENCE 335-78-32 m ST.LUCIE UNIT 1 DATE OF OCCURRENCE: | | 0 Qo.'-- |
| AUGUST"30 1978 g TECHNICAL SPECIFICATION 4.3.1.1.1 NUCLEAR POWER 5 AT POWER CALIBRATIONS
| | 1 FLORIDA POWEII 5 LIGHT COMPANY September 22, 1978 P RN-L I-78-267 Hr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S=. Nuclear Regulatory Commission 101 Harietta Street, Suite 3100 CQ Atlanta, Georgia 30303 4 4 Cf. |
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| ==Dear Hr.O'Reilly:== | | ==Dear Hr. O'Reilly:== |
| Very truly yours, hMIJLNIIN Mm HE tmpy A.D.chmidt Vice President Power Resources HAS/cpc Attachment cc: Harold F.Reis, Esquire Director, Office of Inspection and Enforcement (30)-/director, Office of Hanagement Information and Program Control (3)806S0166 PEOPLE...SERVING I'EOPLE ,The attached Licensee Event Report is being submitted in accordance with Technical Speci fication 6.9 to provi de 30-day notification of the subject occurrence. | | |
| NRC FOAM 366 I7 77)LlCENSEE EVENT REPORT U.S NUCLEAR REGULATORY COiLIMISSION 7 S CON'T I Fl LlS LIS ll IQ20 Ol-LICEiNSc f COOK 14 i5 QI", IPLEASE PRINT OA TYPE AI L AEQIJIAKE7 INFORMATIONI 0 I0I 0)0I01-0I0 Qi4I1 1'Il 1Qz~lQi LIC.i'ISE'IU(49'ER 26 IJCcNSK TYPE'0 5 I A~La 0 2 i,"o'cf~LJQS 0 510 0 0 3 3 SlQ7 01 8 3 0 60 Bl OOCI4KT NVMBcR 69 67 c VENT OATE EVENT OESCAIPTION ANO PROSABI E CONSFQUEiNCES QIO The dail calibration of Nuclear and AT Power T.S.74 75~OAT OATc ao QB.3..1 1 was i dver-entl miss d d ri r 1 t nan e outa~O4 a d subs I nt s~OS.-ll dn 1h i~QB'rformed'zon the da before the r 1 r 1 I u ch dl e.h-a ibrati n had been occurrence.. | | REPORTABLE OCCURRENCE 335-78-32 m CJ ST. LUCIE UNIT 1 DATE OF OCCURRENCE: AUGUST "30 1978 g TECHNICAL SPECIFICATION 4. 3.1.1.1 NUCLEAR POWER 5 AT POWER CALIBRATIONS |
| 'Reactor ower did not exceed a~OS 7 a 9~ao SYSTEAI CAUSE CAUSE COIIJP.VAI.VE CCOE COOK SUBCQQB COMPONENT CQOE sUBcoDK sUacocf ZZZZZZO MZO LaJC~zz O L>JC Lii.O 7 5 9 10 I I 12 17'IS 19 SEQUENTIAL OCCURRENCE REPORT REVISION Lf R(AQ EVENT YcAR REPOATNQ.COOE, 7'YPE NO.Qiz izczzzzz-. | | ,The attached Licensee Event Report is being submitted in accordance with Technical Speci fication 6.9 to provi de 30-day notification of the subject occurrence. |
| ~78~~03 2~~IILLLI'J~~0 21 22 3 24 26 2(29 79 30 ACTION FVTUPE EFFfC SIIUTOOWVN Al*CIIMENT NPRO~PRIMcCOUP. | | Very truly yours, A. D. chmidt Vice President Power Resources hMIJLNIIN Mm HE tmpy HAS/cpc Attachment cc: Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (30) |
| COAIPONKNT TAICKN ACTION QVPLANT MKTII Q IIOURS+22 SUBMITTKO FoilMSUB.SUPPUKA, MANUFACTURER zczclczc zz-c LUS lozoQl LIUo L~Jo Mzo'zzzzzzzc CAUSc OESCRIPTION ANO CORRECTIVE ACTIONS Q27 o f the ut and subs u nt startu the o eratin shi ft that nor-mall erforms'the surveillance turned it over to the relievin shift.-: The relievin o erat rs h w v r w r n t aware h the were re uired to er form it.Personnel involved were instructed NA.re uired surveillances as scheduled and in en B 9 FACILITY~3O METIIOO OF STATUS N POYIER OTIIER STATUS Q OISCOVEA Y cic zzzc IILllolo~zz L~io 7 a 9 10 I'2 12 43 ACTIVITY CQN i KNT RELEASED OF REI.EASE AMOUNT OF ACTIVITY Q35~16~ZQ33~Z08 ZA 7 10 11 44 45 PKRSONNK!. | | - /director, Office of Hanagement Information and Program Control (3) 806S0166 PEOPLE... SERVING I'EOPLE |
| EXPOSURES NUMSKR TYPE OESCRIPTION Q39,~oo o Qz'zQLc 7 6 9'1 12 13 PPASONNEL INJURI K>~is~OO 0 Qic'NA a ll 12 I.CSS OF CA DAMAGE~0 FACI LIT<Q43 TYPE CESCAIP TION EK LZlQ2 NA 7 a 7 10 PUBLICITY ISSUco OKSCRIPT I40 K&8~O NA a>10 NAME oF PREPARER H.A.Sebo man OISCOV AY OKSCAIPTICN Q42 Routine Ins ection I.oCAT jgoF RasAsf Q36 ao i 50 NRC USE ONLY I I I I I P'IONEI on the im ortance of erformin surin a thorou h shift turnov r.}} | | |
| | NRC FOAM 366 U. S NUCLEAR REGULATORY COiLIMISSION I7 77) |
| | LlCENSEE EVENT REPORT I |
| | QI ", IPLEASE PRINT OA TYPE AI L AEQIJIAKE7 INFORMATIONI 7 S Fl LlS LICEiNSc LIS f COOK ll IQ20 14 i5 Ol- 0 I0I 0)0I01 LIC .i'ISE 'IU(49'ER 0I0 Qi4I1 26 1 |
| | IJCcNSK TYPE |
| | 'Il 1Qz~lQi |
| | '0 5 I A ~ La CON'T i,"o'cf ~LJQS 0 510 0 0 3 3 SlQ7 01 8 3 0 QB 60 Bl OOCI4KT NVMBcR 69 67 c VENT OATE 74 75 ~OAT OATc ao EVENT OESCAIPTION ANO PROSABI E CONSFQUEiNCES QIO 0 2 The dail calibration of Nuclear and AT Power T.S. .3..1 1 was i dver-entl miss d d ri r 1 |
| | ~O4 t nan e outa a d subs I nt s r 1 r 1 I |
| | ~OS. - |
| | ll dn 1h i |
| | u ch dl e. h - |
| | a ibrati n had been |
| | ~QB 'rformed'zon the da before the occurrence.. 'Reactor ower did not exceed a |
| | 7 |
| | ~OS a 9 SYSTEAI CCOE ZZZZZZO CAUSE COOK MZO CAUSE SUBCQQB LaJC |
| | ~ |
| | ~zz COMPONENT CQOE COIIJP. |
| | sUBcoDK O L>JC Lii.O VAI.VE sUacocf ao 7 5 Qiz LfR(AQ izczzzzz-. |
| | ACTION FVTUPE TAICKN ACTION 9 |
| | EVENT YcAR |
| | ~78 21 10 22 EFFfC QVPLANT II |
| | ~ 3 SIIUTOOWVN MKTII Q 12 |
| | ~03 24 SEQUENTIAL REPOATNQ. |
| | 2 17 26 IIOURS +22 |
| | ~~ |
| | 2( 29 Al *CIIMENT |
| | 'IS OCCURRENCE COOE, IILLLI 79 |
| | 'J NPRO~ |
| | FoilMSUB. |
| | 19 REPORT 7'YPE 30 |
| | ~ |
| | PRIMcCOUP. |
| | SUPPUKA, REVISION NO. |
| | ~0 COAIPONKNT lozoQl SUBMITTKO MANUFACTURER zczclczc zz-c LUS LIUo L~Jo Mzo 'zzzzzzzc CAUSc OESCRIPTION ANO CORRECTIVE ACTIONS Q27 o f the ut and subs u nt startu the o eratin shi ft that nor-mall erforms'the surveillance turned it over to the relievin shift.-: The relievin o erat rs h w v r w r n t aware h the were re uired to er form it. Personnel involved were instructed on the im ortance of erformin re uired surveillances as scheduled and in en surin a thorou h shift turnov r. |
| | B 9 ao FACILITY Q |
| | ~3O METIIOO OF i cic 7 a STATUS zzzc 9 |
| | ACTIVITY IILllolo~zz 10 N POYIER CQN i KNT I'2 12 OTIIER STATUS OISCOVEA Y L~io 43 OISCOV AY OKSCAIPTICN Q42 Routine Ins ection AMOUNTOF ACTIVITYQ35 RELEASED OF REI.EASE I.oCAT jgoF RasAsf Q36 |
| | ~16 ~ZQ33 ~Z08 ZA 7 10 11 44 45 PKRSONNK!. EXPOSURES NUMSKR TYPE OESCRIPTION Q39, 7 6 |
| | ~oo ' o Qz'zQLc 1 12 13 NA. |
| | 9 50 PPASONNEL INJURI K> |
| | ' |
| | ~is a |
| | ~OO 0 ll Qic 12 NA I.CSS OF CA DAMAGE ~ 0 FACI LIT< |
| | TYPE CESCAIP TION Q43 EK LZlQ2 7 a 7 10 NA PUBLICITY I40 NRC USE ONLY |
| | ~O ISSUco OKSCRIPT K&8a > 10 NA I I I I I NAME oF PREPARER H. A. Sebo man P'IONEI}} |
|
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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
[Table view] |
Text
Dro one'EGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)
DI TRIBUTION FOR INCONING NATERIAL 0-33 REC: QREILLY J P ORG: SCHMIDT A D DOCD ATE: 09/22/78 NRC FL PWR 5 LIGHT DATE RCVD: 10/02l78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-335/78-032) ON 08/30/78 CONCERNING DAILY CALIBRATION OF NUC AND T PWR (TECH SPEC 4. 3. i. Ai. SHORT 1) WAS INADVERTENTLY MAINTENANCE NIS ED DURING ONE SURVEILLANCE INTERVAL ENCOMPASSING OUTAGE AND SUB EGUENT STARTUP.
PLANT NAME: ST LUCIE ei REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:PL.
>><<<<<<>(re<><>w>s>au<<nx DISTRIBUTlQN Qf THlS NATERIAL IS AS FQLLPWS <<<<<<v<<w+<<<<<<<<<<<<<<<<<<<<<<
INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTlON: BR CHIEI N4 BC<<<<W/4 ENCL INTERNAL: ENCL NRC PDR<<<<l)/ENCI I 5 E<<<:W/2 ENCL 'NIPC<<<<W/3 ENCL C SYSTENS BR<<<<l)/ENCL EMERGENCY PLAN BR++W/ENCL NGVAK/CHECK<+W/ENCL EEB<<.<<L I/ENCL AD FOR ENG%<<W/ENCL PLANT SYSTEMS BR++W/EhlCL HANAUER~<W/ENCL AD FOR PLANT SYSTEMS<<<<W/ENCL AD FGR SYS Sc PROJ<<<<W/ENCL REACTOR SAFETY BR++W/EhlCL ENGINEERING BRN<<W/ENCL VGLLMER/BUNCH<<'<<'W/ENCL KREGER/ J. COLL INS<<<<W/ENCL POWER SYS BR<<<W/ENCL K SEYFRIT/IE<<<<W/ENCL EXTERNAL: LPDR'S FT PIERCEi FL<<'.~W/ENCL NS I C<<<<W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 7806801 6 SIZE: 1P+1P r
<<<<<<<<<<<<<<<<%%<<%<<45<<%<<<<<<<<<<<<<<<<<<<<<<%<<<<e><<<<<<<< THE END
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1 FLORIDA POWEII 5 LIGHT COMPANY September 22, 1978 P RN-L I-78-267 Hr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S=. Nuclear Regulatory Commission 101 Harietta Street, Suite 3100 CQ Atlanta, Georgia 30303 4 4 Cf.
Dear Hr. O'Reilly:
REPORTABLE OCCURRENCE 335-78-32 m CJ ST. LUCIE UNIT 1 DATE OF OCCURRENCE: AUGUST "30 1978 g TECHNICAL SPECIFICATION 4. 3.1.1.1 NUCLEAR POWER 5 AT POWER CALIBRATIONS
,The attached Licensee Event Report is being submitted in accordance with Technical Speci fication 6.9 to provi de 30-day notification of the subject occurrence.
Very truly yours, A. D. chmidt Vice President Power Resources hMIJLNIIN Mm HE tmpy HAS/cpc Attachment cc: Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (30)
- /director, Office of Hanagement Information and Program Control (3) 806S0166 PEOPLE... SERVING I'EOPLE
NRC FOAM 366 U. S NUCLEAR REGULATORY COiLIMISSION I7 77)
LlCENSEE EVENT REPORT I
QI ", IPLEASE PRINT OA TYPE AI L AEQIJIAKE7 INFORMATIONI 7 S Fl LlS LICEiNSc LIS f COOK ll IQ20 14 i5 Ol- 0 I0I 0)0I01 LIC .i'ISE 'IU(49'ER 0I0 Qi4I1 26 1
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~O ISSUco OKSCRIPT K&8a > 10 NA I I I I I NAME oF PREPARER H. A. Sebo man P'IONEI