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| {{#Wiki_filter:3 NIIC Fo<<M.195 l I2 76$NRC DISTRIBUTION roA=RT 50 DO U.S.NUCLL'AA REGULATORY COMMISSION Cl(ET MATERIAL DOCKET,NUMOLA Wo-z zw FILE NUMAEA INCIDENT REPORT TO: Mr.Norman C.Moseley FROM: Florida Power 5 Light Company Miami, Florida A~Di Schmidt DATE OF DOCUMENT 3/18/77 DATE RECEIVED 4/1/77 LETTER gOAIOINAL Hcor Y DESCAIPTION ONOTORIZEO RFUNC LASS IF I E D PAOP INPUT FOAM ENCLOSURE NUMOEA OF COPIES AECEIVED Ltr trans the following: | | {{#Wiki_filter:3 U.S. NUCLL'AA REGULATORY COMMISSION DOCKET,NUMOLA NIIC Fo<<M.195 I2 76$ |
| RCKNOWX,EDGED
| | l Wo- z zw FILE NUMAEA NRC DISTRIBUTION roA= RT 50 DO Cl(ET MATERIAL INCIDENT REPORT TO: FROM: DATE OF DOCUMENT Florida Power 5 Light Company 3/18/77 Mr. Norman C. Moseley Miami, Florida DATE RECEIVED A~ Di Schmidt 4/1/77 LETTER ONOTORIZEO PAOP INPUT FOAM NUMOEA OF COPIES AECEIVED gOAIOINAL RFUNC LASS IF I E D Hcor Y DESCAIPTION ENCLOSURE |
| ~~Licensee Event Report (RO 50-33'5/V7-10) on 2/17/77 concerning an alarm being received in the control room indicating, the circuit breaker for the<<C<<steam/riven auxiliafI feedwater pump steam valve cdntrol circuit tripped.~~~~~PLANT NAME: St.Luciq Unit No, 1 (1-P)(2-P)~RJL ,LIO NOT REMOVL('OTE:
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| XF PERSOKKL EXPOSURE XS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS BRANCH CHIEF: 8 3 CYS FOR ACTION LXCo ASST,: M CYS ACRS CYS ROLQQ4Q S NT FOR ACTION/INFORMATION Ch A TI3<<REG EELE R~EcM (2)MIPC SCHROEDER/IPPOLXTO HOUSTON NOVAK/CHECK GRDIE S CASE BUTLER HANAUER TEDESCO/MACCARY EXSENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS 3 ,INTERNAL D I STR I BUTION LPDR4 TIC: EXTERNAL DISTRIBUTION CONTRSL NUMI3ER~7 Q'Qi p/gi y7 N'/NAc ro<<M 106 I2 70) e r p i f ug 1"Y
| | Ltr trans the following: Licensee Event Report (RO 50-33'5/V7-10) on 2/17/77 concerning an alarm being received in the control room indicating, the circuit breaker for the <<C<< steam /riven auxiliafI RCKNOWX,EDGED feedwater pump steam valve cdntrol circuit tripped. ~ ~ ~ ~ ~ |
| ~.(ti~~~j h.f Qllg FLORIDA POWER 8(LIGHT COMPANY March 18, 1977 PRN-LI-77-72 Mr.Norman C.Moseley, Director, Region Al."il f mph Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, Georgia 30303
| | PLANT NAME: |
| | St. Luciq Unit No, 1 (1-P) (2-P ) ~ |
| | RJL XF PERSOKKL EXPOSURE XS INVOLVED |
| | ,LIO NOT REMOVL('OTE: SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION TI3 BRANCH CHIEF: Ch A 8 3 CYS FOR ACTION LXCo ASST,: |
| | M CYS ACRS CYS ROLQQ4Q S NT |
| | ,INTERNAL D I STR I BUTION |
| | <<REG EELE R |
| | ~EcM (2) 3 MIPC SCHROEDER/IPPOLXTO HOUSTON NOVAK/CHECK GRDIE S CASE BUTLER HANAUER TEDESCO/MACCARY EXSENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTRSL NUMI3ER LPDR4 ~ |
| | 7 Q'Qi p /gi y7 TIC: |
| | N '/ |
| | NAc ro<<M 106 I2 70) |
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| ==Dear Mr.Moseley:== | | p e r i |
| REPORTABLE OCCURRENCE 335-77-10 ST., LUCIE UNIT 1 DATE OF OCCURRENCE: | | ug 1 "Y f |
| FEBRUARY 17, 1977 STEAM DRIVEN AUXILIARY FEEDWATER PUMP The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence. | | |
| Very truly yours, D.Schmidt Vice President Power Resources MAS/cpc Attachment. | | ~ .( ti~ ~ |
| cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)'7'll'0'/~0'EOPLE... | | ~ j h. |
| SERVING PEOPLE | | f Qllg FLORIDA POWER 8( LIGHT COMPANY March 18, 1977 PRN-LI-77-72 Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement A l."il fmph U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia 30303 |
| ~~I C A l c~,,~),+<$+<C.i r | | |
| ~"~ir~CONTROL 8LOCK: LICENSEE EVENT REPORT gP~SE PAINT ALL AEOUIAEO INFORMATION) | | ==Dear Mr. Moseley:== |
| UCENSEE NAME,[op)FLsLsi o 7'9 14 15 UCENSE NUMBER 0-0 0 0 0 0-0 0 25 UCENSE TYPE EVENT TYPF I, 1 1 1 1~0 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE[OO1jcoN'r | | |
| ~~L L 7 8 57 58 59 60 EVENT DESCRIPTION Jog OOCKET NUMBER~EVENT OATE REPORT OATE 0 0-0 0 2 l 7 7 61 68 69 74 75 80 7 8 9 I circuit breaker for the"C" steam d iven aux ia fe d at r um e 7 89[OD4}circuit ad s etio f t e circu t show t d te m 7 8 9 Qg sensin a d control circuit.The s orted erminal was re i ed an thp 7 aa controller re laced.ee ao 80 80 ao I 7 8 9 SYSTEM CAUSE COOE COOE[007]LHHJ~B o 7 8 9 10 11 12 CAUSE DESCRIPTION Q~g he v v COMPONENT COOE K T B R K~A 17'3 b COMPONENT MANUFD~iFER W 2 lo 44 47 N 4a 80 7 8 9 toom tri ed due to a shorted terminal caused b moisture buildu in a control box.7 8 9~10 80 ao OTHER STATUS NA AMOUNT OF ACTIVITY NA 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
| | REPORTABLE OCCURRENCE 335-77-10 ST., LUCIE UNIT 1 DATE OF OCCURRENCE: FEBRUARY 17, 1977 STEAM DRIVEN AUXILIARY FEEDWATER PUMP The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence. |
| ~16~Z, 7 89 10 PUBLICITY 7 89 FACIUTY STATUS.%POWER EE.L~J 7.8 9.10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE KIH 7 8 9 10 11 PERSONNEL EXPOSURES , NUMBER TYPE OESCRIPTION | | Very truly yours, D. Schmidt Vice President Power Resources MAS/cpc Attachment. |
| ~~~oo o Lzj 7 8 9 11 12 13'EFISONNEL IN JURIFS Kl LZYJaJ PROBABLE CONSEQUENCES Q~g METHOO OF OISCOVERY 44 45 NA NA CISCOVERY OESCRIPTION LOCATION OF RELEASE NA ao ao ao 80 ao 7 8 9 ADDITIONAL FACTORS Q~I See a e two for continuation of Event Descri tion.7 89.ao 80 7 89 NAME.M.A.Scho man PHONE.305/552-3779 GPO 441 80 t REPORTABLE-OCCURRENCE 335-77-10 LICENSEE EVENT REPORT.PAGE T)'(0 EVENT DESCRIPTION (Continued) | | cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30) |
| During the time the"C" auxiliary feedwater pump was out of service, both electric-driven auxiliary feedvrater pumps were operable as required by Technical Specification 3.7.1.2.The"C" auxiliary feedwater pump was returned to'operable status within 72 hours as required by the Technical Specification. | | Director, Office of Management Information and Program Control (3) |
| This was the fifth reportable occurrence associated with the steam driven auxiliary feedwater pump.Two previous occurrences involved an open circuit in a solder joint (335-76-11) and a wiring diagram error (335-76-13) and are unrelated. | | '7 |
| The other three occurrences (335-76-22, 335-76-36 and 335-7>6-47) are related in that they involve control circuit corrosion. | | 'll'0'/~0'EOPLE... |
| Action taken since the last reportable occurrence (335-76-47) has been the completion of jerouting of nearby steam drains away from the vicinity of the turbine.c)I Other means of long term corrective action are being studied.One possibility'~ | | SERVING PEOPLE |
| under consideration to further correct the situation is to replace the+resent | | |
| ~junction boxes and relocate them to a position off the turbine, making:<hem less susceptible to the effects of heat and moisture buildup.This will require a cold shutdown of the plant of sufficient duration to permit accomplishment.
| | ~ ~ |
| (-335-77-10). | | I C |
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| | LICENSEE EVENT REPORT |
| | ~ "~ir ~ |
| | CONTROL 8LOCK: gP ~SE PAINT ALL AEOUIAEO INFORMATION) |
| | UCENSEE UCENSE |
| | [op) FLsLsi EVENT NAME, UCENSE NUMBER TYPE TYPF 0 0 7'9 o 0 0 0 0 0 0 I, 1 1 1 1 ~0 |
| | ~ |
| | 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER ~ EVENT OATE REPORT OATE |
| | [OO1jcoN'r ~L L 0 0 0 0 2 l 7 7 7 8 57 58 59 60 61 68 69 74 75 80 I |
| | EVENT DESCRIPTION Jog 7 8 9 ao circuit breaker for the "C" steam d iven aux ia fe d at r um e 7 89 80 7 |
| | [OD4} |
| | 8 9 circuit ad s etio ft e circu t show t d te m 80 7 |
| | Qg aa sensin a d control circuit. The s orted erminal was re i ed an thp ee ao controller re laced. I 7 8 9 80 SYSTEM CAUSE COMPONENT COOE COOE COMPONENT COOE MANUFD~iFER |
| | [007] |
| | 7 8 9 10 LHHJ CAUSE DESCRIPTION |
| | ~B 11 12 o K T B R K 17 '3~A 44 W 2 lo 47 N |
| | 4a Q~g he v v b 7 8 9 80 toom 7 8 9 tri ed due to a shorted terminal caused b moisture buildu in a control box. |
| | ao |
| | ~10 7 89 FACIUTY METHOO OF STATUS . % POWER OTHER STATUS OISCOVERY CISCOVERY OESCRIPTION EE . L~J NA |
| | : 7. 8 9 . 10 12 13 ao FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE KIH NA NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES |
| | , NUMBER TYPE OESCRIPTION |
| | ~~ ~oo o Lzj 7 8 9 11 12 ao INJURIFS 13'EFISONNEL Kl LZYJaJ NA ao PROBABLE CONSEQUENCES Q~g NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION |
| | ~16 ~Z, 7 89 10 ao PUBLICITY 7 8 9 .ao ADDITIONAL FACTORS 7 |
| | Q~ I89 See a e two for continuation of Event Descri tion. |
| | 80 7 89 80 NAME. M. A. Scho man PHONE. 305/552-3779 GPO 441 |
| | |
| | REPORTABLE- OCCURRENCE t |
| | 335-77-10 LICENSEE EVENT REPORT |
| | . PAGE T)'(0 EVENT DESCRIPTION (Continued) |
| | During the time the "C" auxiliary feedwater pump was out of service, both electric-driven auxiliary feedvrater pumps were operable as required by Technical Specification 3.7.1.2. The "C" auxiliary feedwater pump was returned to'operable status within 72 hours as required by the Technical Specification. |
| | This was the fifth reportable occurrence associated with the steam driven auxiliary feedwater pump. Two previous occurrences involved an open circuit in a solder joint (335-76-11) and a wiring diagram error ( 335-76-13) and are unrelated. The other three occurrences (335-76-22, 335-76-36 and 335-7>6-47) are related in that they involve control circuit corrosion. Action taken since the last reportable occurrence (335-76-47) has been the completion of jerouting of nearby steam drains away from the vicinity of the turbine. c )I Other means of long term corrective action are being studied. One possibility'~ |
| | under consideration to further correct the situation is to replace the+resent ~ |
| | junction boxes and relocate them to a position off the turbine, making:<hem less susceptible to the effects of heat and moisture buildup. This will require a cold shutdown of the plant of sufficient duration to permit accomplishment. (-335-77-10). |
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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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Text
3 U.S. NUCLL'AA REGULATORY COMMISSION DOCKET,NUMOLA NIIC Fo<<M.195 I2 76$
l Wo- z zw FILE NUMAEA NRC DISTRIBUTION roA= RT 50 DO Cl(ET MATERIAL INCIDENT REPORT TO: FROM: DATE OF DOCUMENT Florida Power 5 Light Company 3/18/77 Mr. Norman C. Moseley Miami, Florida DATE RECEIVED A~ Di Schmidt 4/1/77 LETTER ONOTORIZEO PAOP INPUT FOAM NUMOEA OF COPIES AECEIVED gOAIOINAL RFUNC LASS IF I E D Hcor Y DESCAIPTION ENCLOSURE
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Ltr trans the following: Licensee Event Report (RO 50-33'5/V7-10) on 2/17/77 concerning an alarm being received in the control room indicating, the circuit breaker for the <<C<< steam /riven auxiliafI RCKNOWX,EDGED feedwater pump steam valve cdntrol circuit tripped. ~ ~ ~ ~ ~
PLANT NAME:
St. Luciq Unit No, 1 (1-P) (2-P ) ~
RJL XF PERSOKKL EXPOSURE XS INVOLVED
,LIO NOT REMOVL('OTE: SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION TI3 BRANCH CHIEF: Ch A 8 3 CYS FOR ACTION LXCo ASST,:
M CYS ACRS CYS ROLQQ4Q S NT
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~EcM (2) 3 MIPC SCHROEDER/IPPOLXTO HOUSTON NOVAK/CHECK GRDIE S CASE BUTLER HANAUER TEDESCO/MACCARY EXSENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTRSL NUMI3ER LPDR4 ~
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f Qllg FLORIDA POWER 8( LIGHT COMPANY March 18, 1977 PRN-LI-77-72 Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement A l."il fmph U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 335-77-10 ST., LUCIE UNIT 1 DATE OF OCCURRENCE: FEBRUARY 17, 1977 STEAM DRIVEN AUXILIARY FEEDWATER PUMP The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
Very truly yours, D. Schmidt Vice President Power Resources MAS/cpc Attachment.
cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)
Director, Office of Management Information and Program Control (3)
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UCENSEE UCENSE
[op) FLsLsi EVENT NAME, UCENSE NUMBER TYPE TYPF 0 0 7'9 o 0 0 0 0 0 0 I, 1 1 1 1 ~0
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14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER ~ EVENT OATE REPORT OATE
[OO1jcoN'r ~L L 0 0 0 0 2 l 7 7 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION Jog 7 8 9 ao circuit breaker for the "C" steam d iven aux ia fe d at r um e 7 89 80 7
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8 9 circuit ad s etio ft e circu t show t d te m 80 7
Qg aa sensin a d control circuit. The s orted erminal was re i ed an thp ee ao controller re laced. I 7 8 9 80 SYSTEM CAUSE COMPONENT COOE COOE COMPONENT COOE MANUFD~iFER
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7 8 9 10 LHHJ CAUSE DESCRIPTION
~B 11 12 o K T B R K 17 '3~A 44 W 2 lo 47 N
4a Q~g he v v b 7 8 9 80 toom 7 8 9 tri ed due to a shorted terminal caused b moisture buildu in a control box.
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~10 7 89 FACIUTY METHOO OF STATUS . % POWER OTHER STATUS OISCOVERY CISCOVERY OESCRIPTION EE . L~J NA
- 7. 8 9 . 10 12 13 ao FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE KIH NA NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES
, NUMBER TYPE OESCRIPTION
~~ ~oo o Lzj 7 8 9 11 12 ao INJURIFS 13'EFISONNEL Kl LZYJaJ NA ao PROBABLE CONSEQUENCES Q~g NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
~16 ~Z, 7 89 10 ao PUBLICITY 7 8 9 .ao ADDITIONAL FACTORS 7
Q~ I89 See a e two for continuation of Event Descri tion.
80 7 89 80 NAME. M. A. Scho man PHONE. 305/552-3779 GPO 441
REPORTABLE- OCCURRENCE t
335-77-10 LICENSEE EVENT REPORT
. PAGE T)'(0 EVENT DESCRIPTION (Continued)
During the time the "C" auxiliary feedwater pump was out of service, both electric-driven auxiliary feedvrater pumps were operable as required by Technical Specification 3.7.1.2. The "C" auxiliary feedwater pump was returned to'operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as required by the Technical Specification.
This was the fifth reportable occurrence associated with the steam driven auxiliary feedwater pump. Two previous occurrences involved an open circuit in a solder joint (335-76-11) and a wiring diagram error ( 335-76-13) and are unrelated. The other three occurrences (335-76-22, 335-76-36 and 335-7>6-47) are related in that they involve control circuit corrosion. Action taken since the last reportable occurrence (335-76-47) has been the completion of jerouting of nearby steam drains away from the vicinity of the turbine. c )I Other means of long term corrective action are being studied. One possibility'~
under consideration to further correct the situation is to replace the+resent ~
junction boxes and relocate them to a position off the turbine, making:<hem less susceptible to the effects of heat and moisture buildup. This will require a cold shutdown of the plant of sufficient duration to permit accomplishment. (-335-77-10).
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