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| {{#Wiki_filter:NRC FoRM 195 U.S. NUCLEAR REGULATORY C SION DOCKET NUMBER I2-76 I A 50-251 FILE NUMBER NRC D I STR I BUT ION Fo R PART 50 DOC K ET MATER I AL INCIDZFZ REPORT TOI FROM: DATE OF DOCUMENT Florida'Power- & Light Company 6/25/76 Mr,'Norman C, Moseley Miami, Florida DATE RECEIVED A. D, Schmidt 7/6/76 KLEVTER ONOTOR IZED PROP INPUT FORM NUMBE R OF COP I ES RE CE I V E D OORIGINAL @UNCLASSIFIED No original SCOP Y DESCRIPTION ENCLOSURE Ltr.. trans the following: Licensee Event Report ( RO 50-251/76-5) on 6/12/76 concerning the boron concentration of the boron in]ection tank and the "B," Soric acid storage tank were below the, tech spec limit. | | {{#Wiki_filter:NRC FoRM 195 U.S. NUCLEAR REGULATORY C SION DOCKET NUMBER I2-76 I A 50-251 FILE NUMBER NRC D I STR I BUT ION Fo R PART 50 DOC K ET MATER I AL INCIDZFZ REPORT TOI FROM: DATE OF DOCUMENT Florida'Power- & Light Company 6/25/76 Mr,'Norman C, Moseley Miami, Florida DATE RECEIVED A. D, Schmidt 7/6/76 KLEVTER ONOTOR IZED PROP INPUT FORM NUMBE R OF COP I ES RE CE I V E D OORIGINAL @UNCLASSIFIED No original SCOP Y DESCRIPTION ENCLOSURE Ltr.. trans the following: Licensee Event Report ( RO 50-251/76-5) on 6/12/76 concerning the boron concentration of the boron in]ection tank and the "B," Soric acid storage tank were below the, tech spec limit. |
| ACKNO EDGED (1-P) (2-P) DO NO RL'MOVE PLANT NAME: NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.. COLLINS | | ACKNO EDGED (1-P) (2-P) DO NO RL'MOVE PLANT NAME: NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.. COLLINS Turkey Point 04 FOR ACTION/INFORMATION 7 7 76 RJ KgÃCH CHIEF Lear W CYS FOR ACTION LIC..ASST.: Parzish. |
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| Turkey Point 04 FOR ACTION/INFORMATION 7 7 76 RJ KgÃCH CHIEF Lear W CYS FOR ACTION LIC..ASST.: Parzish. | |
| W CYS ACRS CYS HOLDING S TO IA INTERNAL DISTRI BUTION ICE 2 MIPC-SCHROEDER IPPOLITO HOUSKIN NOVAK CHECK GRIMES CASE TEDESCO MACCARY EISENHUT SHAO VOL12KR HJNCH KREGER J. COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: am, a. | | W CYS ACRS CYS HOLDING S TO IA INTERNAL DISTRI BUTION ICE 2 MIPC-SCHROEDER IPPOLITO HOUSKIN NOVAK CHECK GRIMES CASE TEDESCO MACCARY EISENHUT SHAO VOL12KR HJNCH KREGER J. COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: am, a. |
| TIC: | | TIC: |
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| Director, Office of Management Information and | | Director, Office of Management Information and |
| ..Program Control (3) | | ..Program Control (3) |
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| ~~i@O | | ~~i@O |
| . 6'784 HITLPING BUILD FLORIDA | | . 6'784 HITLPING BUILD FLORIDA |
Line 63: |
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| 1 6 (P~ PAINT ALL AEQLIIAED INFORMATION/ | | 1 6 (P~ PAINT ALL AEQLIIAED INFORMATION/ |
| '0 UCENSE EVENT | | '0 UCENSE EVENT |
| 'ICENSEE gij Ez'p 00000, NAME LICENSE NUMBER TYPE TYPE s 4. o 0 0 | | 'ICENSEE gij Ez'p 00000, NAME LICENSE NUMBER TYPE TYPE s 4. o 0 0 1 1 1 ~01 |
| '
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| 1 1 1 ~01 | |
| ,7 89 .. 14'5 25 26 30 31 32 REPORT AEPOAT CATEGORY TYPE'OURCE OOCKET NUMSEA ~ EVENT OATE | | ,7 89 .. 14'5 25 26 30 31 32 REPORT AEPOAT CATEGORY TYPE'OURCE OOCKET NUMSEA ~ EVENT OATE |
| [oa~jccm'' ~z, 0 6 l 2 7 0 ~ | | [oa~jccm'' ~z, 0 6 l 2 7 0 ~ |
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| Maintenance was performed on the inlet isolation valves to stop | | Maintenance was performed on the inlet isolation valves to stop |
| . the leakage. Leakage past the outlet isolation valves was stopped by isolating the leakoff line from those, valves. | | . the leakage. Leakage past the outlet isolation valves was stopped by isolating the leakoff line from those, valves. |
| Similar cases of BIT dilution have occurred, however, this was the first, occurrence attributable directly to leakage past | | Similar cases of BIT dilution have occurred, however, this was the first, occurrence attributable directly to leakage past the isolation valves. .Also, a situation in which cross dilution occurred between a BIT and a BAST was previously discussed in report 251-75-12. |
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| the isolation valves. .Also, a situation in which cross dilution occurred between a BIT and a BAST was previously discussed in report 251-75-12. | |
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| 4 ~}} | | 4 ~}} |
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Category:Letter
MONTHYEARL-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report ML24291A2882024-10-24024 October 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 2024-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing2023-12-13013 December 2023 Unplanned Automatic Scram During RPS Testing 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip2023-11-20020 November 2023 Grid Disturbance in Switchyard Causes Automatic Reactor Trip ML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 05000250/LER-2023-002, Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure2023-10-0202 October 2023 Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure 05000250/LER-2023-001, RCS Pressure Boundary Degraded2023-06-14014 June 2023 RCS Pressure Boundary Degraded 05000250/LER-2021-003, Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown2021-12-0202 December 2021 Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown 05000251/LER-2017-0012017-11-0707 November 2017 Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control, LER 17-001-00 for Turkey Point, Unit 4, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control 05000250/LER-2017-0012017-05-16016 May 2017 Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations and Loss of Safety Injection Function, LER 17-001-00 for Turkey Point, Unit 3, Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation2017-05-11011 May 2017 LER Special Report Regarding Accident Monitoring Instrumentation 05000250/LER-2016-0012016-04-0707 April 2016 Loose Breaker Control Power Fuse Caused 3B Emergency Containment Cooler to be Inoperable Longer Than Allowed, LER 16-001-00 for Turkey Point, Unit 3 Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to be Inoperable Longer Than Allowed 05000250/LER-2015-0012016-01-19019 January 2016 Diesel Generator Start Resulting From Switchyard Protective Relay Actuation, LER 15-001-00 for Turkey Point, Unit 3 Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation L-2015-217, Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation2015-08-27027 August 2015 Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation L-2014-139, Special Report Regarding Accident Monitoring Instrumentation2014-05-14014 May 2014 Special Report Regarding Accident Monitoring Instrumentation L-2009-293, Special Report - Accident Monitoring Instrumentation2009-12-15015 December 2009 Special Report - Accident Monitoring Instrumentation L-2009-155, LER 09-02-00 for Turkey Point, Unit 3 MSIV Drain Line Leak Causes Technical Specification Required Shutdown; Failure to Perform PMT Causes Inoperable MSIV2009-07-0202 July 2009 LER 09-02-00 for Turkey Point, Unit 3 MSIV Drain Line Leak Causes Technical Specification Required Shutdown; Failure to Perform PMT Causes Inoperable MSIV ML0906404452008-10-0606 October 2008 Enclosure 11 - Case Study 7: Turkey Point NCV on TS 3/4.4.10, Structural Integrity (Applicability of Sr'S 'And Actions) - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf ML18227D3941978-08-25025 August 1978 08/25/1978 Letter Attached Report of Abnormal Indications from Metal Impact Monitoring System, Which Occurred During Unit Cooldown for Refueling ML18228A4811978-04-0404 April 1978 04/04/1978 Letter Response to Request for Additional Information on System Disturbance of May 16, 1977 L-78-104, Transmitting Evaluation Report of Abnormal Indications from Metal Impact Monitoring System, Turkey Point Unit No. 4.1978-03-23023 March 1978 Transmitting Evaluation Report of Abnormal Indications from Metal Impact Monitoring System, Turkey Point Unit No. 4. ML18227D4511977-09-30030 September 1977 09/30/1977 Letter Report of Abnormal Indications from Metal Impact Monitoring System ML18227A5101977-09-0606 September 1977 LER 1977-251-07 for Turkey Point, Unit 4 - Pressurizer Heatup Rate L-77-191, 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/19771977-06-23023 June 1977 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977 ML18227B2481977-06-23023 June 1977 06/23/1977 Letter Proposed Amendment to Appendix a of Facility Operating Licenses, Concerning Analysis Performed by Applicant'S NSSS Vendor Results Related to Reactor Core Thermal Power Output ML18227B2491977-06-23023 June 1977 06/23/1977 Letter Proposed Amendment to Appendix a of Facility Operating Licenses, Concerning Analysis Performed by Applicant'S NSSS Vendor Results Related to Reactor Core Thermal Power Output ML18227A4241977-05-0202 May 1977 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 4/18/1977 for Nominal Power ML18227A4251977-02-0707 February 1977 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification, Occurrence on 1/8/1977 for Bfd Relays ML18227D2881977-01-14014 January 1977 Submit Personal Radiation Exposure Report in Accordance with the Requirements of 10 CFR 20.405 ML18227D2871977-01-14014 January 1977 Submit Personal Radiation Exposure Report in Accordance with the Requirements of 10 CFR 20.405 ML18227A4281976-10-20020 October 1976 Submit Licensee Event Report of Turkey Point Unit 3, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 10/6/1976 for Boron Injection Tank ML18227A4261976-10-0606 October 1976 Referring Licensee Event Report Submitted on 8/25/1976 with Occurrence Date of 7/26/1976. in the Report, Reportable Occurrence Report No 250-72-2 Should Be Changed to 250-76-2. Attached Corrected Report ML18227A4271976-08-25025 August 1976 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification, Occurrence on 7/26/1976 for Malfunction of 4B Starting Transformer Breaker ML18227A4291976-08-19019 August 1976 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 8/5/1976 for ECCS Analysis ML18227A4311976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/12/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4321976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/11/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4301976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/12/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4331976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration, Occurred in Unit 4 on 6/11/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227D3541976-06-0404 June 1976 Correction to Licensee Event Report Which Occurred on 5/17/1976 by Correcting Steam Generator 4 to Steam Generator 4C on Event Description ML18227A4351976-06-0404 June 1976 Transmitting Letter to Correct Report Sent on 5/27/1976. Line 2 of Description Words Steam Generator 4 Needs to Be Corrected to Steam Generator 4C Attached Corrected Page 1 ML18227A4341976-05-27027 May 1976 Letter Transmitting Licensee Event Report, Steam Generator Tube Support Plate, Occurred in Unit 4 on 5/17/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4361976-05-27027 May 1976 Letter Transmitting Licensee Event Report, Steam Generator Tube Support Plate, in Unit 4 Occurred on 5/17/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4381976-02-26026 February 1976 Letter Transmitting Licensee Event Report, Low Level in Refueling Water Storage Tank in Unit 4 Occurred on 2/14/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4391976-02-26026 February 1976 Letter Transmitting Licensee Event Report, Low Level in Refueling Water Storage Tank in Unit 4 Occurred on 2/14/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4401976-02-25025 February 1976 Letter Transmitting Licensee Event Report, High Setpoint for Overtemperature Delta-T Reactor Trip Channel II in Unit 4 Occurred on 1/30/1976 in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification ML18227A4411975-12-22022 December 1975 Letter Reporting Abnormal Occurrence of Low Boron Concentration in Unit 4 Boron Injection Tank on 12/12/1975 ML18227B0221975-07-0707 July 1975 Reporting Unusual Event No. 251-75-1 of Revised ECCS Analysis, for Value for Peak Clad Temperature Is in Error 2024-07-10
[Table view] |
Text
NRC FoRM 195 U.S. NUCLEAR REGULATORY C SION DOCKET NUMBER I2-76 I A 50-251 FILE NUMBER NRC D I STR I BUT ION Fo R PART 50 DOC K ET MATER I AL INCIDZFZ REPORT TOI FROM: DATE OF DOCUMENT Florida'Power- & Light Company 6/25/76 Mr,'Norman C, Moseley Miami, Florida DATE RECEIVED A. D, Schmidt 7/6/76 KLEVTER ONOTOR IZED PROP INPUT FORM NUMBE R OF COP I ES RE CE I V E D OORIGINAL @UNCLASSIFIED No original SCOP Y DESCRIPTION ENCLOSURE Ltr.. trans the following: Licensee Event Report ( RO 50-251/76-5) on 6/12/76 concerning the boron concentration of the boron in]ection tank and the "B," Soric acid storage tank were below the, tech spec limit.
ACKNO EDGED (1-P) (2-P) DO NO RL'MOVE PLANT NAME: NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.. COLLINS Turkey Point 04 FOR ACTION/INFORMATION 7 7 76 RJ KgÃCH CHIEF Lear W CYS FOR ACTION LIC..ASST.: Parzish.
W CYS ACRS CYS HOLDING S TO IA INTERNAL DISTRI BUTION ICE 2 MIPC-SCHROEDER IPPOLITO HOUSKIN NOVAK CHECK GRIMES CASE TEDESCO MACCARY EISENHUT SHAO VOL12KR HJNCH KREGER J. COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: am, a.
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FLORIOA PO'AER 5 LIGHT CO>.TRACY
'June 25, 1976 PRN-LI-76-164 Mr.'orman C. Moseley, Director, Region Office of Inspection and Enforcement ~
II U. S. Nuclear Regulatory'ommission 230 Peachtree Street, N. Wot Suite 818 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 251-76-5'URKEY POINT UNIT 4 DATE OF OCCURRENCE: JUNE .12, 1976 LOW BORON CONCENTRATION
.The attached Licensee Event. Report is being submitted in
'accordance with Technical Specification 6.9.2 to provide
. prompt notification of the subject occurrence.
Very truly yours, POCKETED' NIIIIEI
~
A. D. Schm'idt Vice President Power Resources 4ItL )IS>6=,
U:5 ~ NVCIEAR RECIlihTDRT COMMIEE MAS/cpc EocIIon ID'IaII v,
Attachment cc:. Jack R. Newman, Esquire Director, Office of Inspection and Enforcement'(40)
Director, Office of Management Information and
..Program Control (3)
~~i@O
. 6'784 HITLPING BUILD FLORIDA
0
~ CONTROL BLOCK:
1 6 (P~ PAINT ALL AEQLIIAED INFORMATION/
'0 UCENSE EVENT
'ICENSEE gij Ez'p 00000, NAME LICENSE NUMBER TYPE TYPE s 4. o 0 0 1 1 1 ~01
,7 89 .. 14'5 25 26 30 31 32 REPORT AEPOAT CATEGORY TYPE'OURCE OOCKET NUMSEA ~ EVENT OATE
[oa~jccm ~z, 0 6 l 2 7 0 ~
REPORT OATE 6 2 5 7 6
,,7 8 57 58 59
~
p 60 68 69 74 75 80 EVENT'ESCRIPTION
[oats] tha the bo on concentration of the boron 7 8 9 80 IOO~] in ection tank BIT and the "B" boric acid stora e tank (BAST) were 7 89 80 below the Technical Sp'ecification limit of 20,000 ppm. This had
~
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7 8 9 80 7 's discussed in 7 8 9 80 l006 Re ortable Occurrence 251-76-4. C'orrective action was to initiate a 7 8 9 PRME 80 SYSTEM CAUSE COMPONEs4T COMPONENT CODE COOS COMPONENT COOE SUPPLER MANUFACTURER VIOLATE)N Rl8 9L$10J~H A L 02
.11 CAUSE DESCRIPTION 12 V E X 17, 43 44 D .5 47 Qo g [ Dilution of the Unit 4 BIT was caused by inleakage from the RNST via the 7 8 9 60 toOj9 BIT inlet and outlet isolation valves. Since the BIT was bein re-7 8 9 80
~10 Il A a s diluted.
7 89 METHOO OF 80 OTHER STATUS OLSCOVEAY OISCOVERY OESCRIPTION pig A N A 7 8 9 10 12 13 45 46 80 FORM OF ACTIVITY COATENT RELEASED OF AELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE KG~ Lzl L~J N/A N/A 7 8 9 10 11 80 PERSONNEL EXPOSURES 7
t"g 8 9
~I JgJ NUMSEA
. 11 TYPE Z
12 13 OESCRIPTION N A 80 PERSONNEL INJURIES NUMSER OESCAIPTION
'7 f47 LoaooJ 89 11 12 80 PROB44IBLE CONSEQUENCES Qs] N 7 89 80 LOSS OR OAMAGE TO FACILITY TYP OESCAPTION z N A 7, 89 10 =
80 PUBLICITY N A 7 89 ~ 80 AOOITIONAL FACTORS" Eee' e 2. for continuation of Event Descii tion and Cause Description; 7 89 60 7 89 80
'M. A. Scho man PHONE. 305 552-3779 CFO 4A'I ~ E ~ 7
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REPORTABLE OCCURRENCE 251-76-5 LICENSEE EVENT, REPORT PAGE TWO Event. Descri Cion '(cont'inued) shutdown in accordance with Administrative Procedure 103.8 and to commence adding a concentrated boric acid solution to the tanks.
The boron concentration of the tanks, was returned to within specification and normal operation was resumed. ('251-76-5).
Cause Descri tion (continued) f I
Maintenance was performed on the inlet isolation valves to stop
. the leakage. Leakage past the outlet isolation valves was stopped by isolating the leakoff line from those, valves.
Similar cases of BIT dilution have occurred, however, this was the first, occurrence attributable directly to leakage past the isolation valves. .Also, a situation in which cross dilution occurred between a BIT and a BAST was previously discussed in report 251-75-12.
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