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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
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DOCKET NUMOER NBC roAM 195
'I2 TO) 50-251 FILr NUMBER NRC DISTR>IRUTION roA PART 50 DOCI<ET MATERIAL INCIDENT REPORT TO: FROM: DATE OF DOCUMENT N. C. Moseley ~ Florida Power 6 Light 2-25-76 Miami, Florida -33101 DATE RECEIVED A. D. Schmidt 3-4-76
~ETTER QNOTOR IZED PROP INPUT FOAM NUMBER OF COPIES RECEIVED
&ORIGINAL Q V NC LASS IF I E D Q COPY 1 si ned DESCRIPTION ENCLOSU AE Ltr trans the following reportable Reportable Occurrence'251-76-1. on occurrence: 1-30-76 re High Setpoint for Overtemperature DELTA-T Reactor Trip Channel II (1 cy encl' PLANT NAME. NOTE: XF PERSONNEL EXPOSURE XS INVOLVED T k P $4 SEND DXRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO ' 4 BRANCH CHIEF: LEAR
!?/3 CYS FOR ACTION LXC ~ ASST: Parrish V// CYS ACRS /4,CYS M%%N/ ENT TO LA INTERNAL D IST Rl BUTION E('RC PDR I6 E 3IXP SCHROEDER/IPPOLXTQ JUHMOH-NO AK CHECK XzKXEKQK+~
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FLORIDA POWER 5 LIGHT COMPANY February 25, 1976 PRN-LI-76-30 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 251-76-1 TURKEY POINT UNIT 4 DATE OF OCCURRENCE: JANUARY 30, 1976 HIGH SETPOINT FOR OVERTEMPERATURE DELTA-T REACTOR TRIP CHANNEL II The attached Licensee Event. Report is being submitted in accordance with Technical Specification 6.9.2 to provide 30-day notification of the subject occurrence.
Very truly yours,
.chmidt Vice President Power Resources MAS/jn Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Information and Program Control (3)
HELPING BUILD FLORIDA
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~ LICENSEE EVENT REPORT t'PLEASE PRINT ALL REQUIRED INFORMATION)
UCENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE Jog L'T P 0 0 0 0 4 1 1 1 1 ~0033
~
7 89 14 15 25 26 30 31 32 REPORT REPORT I001IGQNT 7 8 CATEGORY 57 58 TYPE L
59 SOURCE L
60 0
61 5 0 DOCKET NUMBER 0 2 5 1 68 69 0 lEVENT DATE 3 0 7 6 74 0
75 2
REPORT DATE 2'57 80 EVENT DESCRIPTION
[0D2J. Durin a eriodic test. the Channel Two overtem erature delta-T reactor 7 8 9 80 7 89 80
[oO~] ermitted b Technical S ecification 2.3. Redundant, Channels One 7 8 9 80 Qo g and Three were available and o erable thereb satisf in the re-7 8 9 80
[oD~J uirement that at least two overtem erature delta-T channels be 7 89 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER
~0> ~IA ~E I'N 0 T R U N H 0 2 0 Y 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION 7
~08 8 9 The failure of two 500 MFD filter ca acitors in si nal summator 80
[0Dg TM-4-422F, 'Model 4lll084-004, ermitted an a >~c.> si nal to be su er-
- d. c. si'al in th'e corn arator that corn ares the actual 7 8 9 80
@~ 0 im osed on a 7 89 FACIUTY METHOD OF 80 STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION o o NA b NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g z z NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7
~13 89
~I~0 11 z
12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q~~j Loaoo 7 89 11 12 80 PROBABLE'ONSEQUENCES
~15 NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION tj66 z NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Qi g See next a e for continuation of Event Descri tion and Cause 7 89 80
~19 Descri tion.
7 89 80 NAMEI PHONE:
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'eportable Occur ence 251-76-1 Licensees Event Report Pagg. Two Event Descri tion (continued) operable. This is the first Reportable Occurrence related to a non-conservative overtemperature delta-T setpoint. Two capacitors in a signal summator were found to be open and were replaced with new capacitors. The overtemperature delta-T setpoint was then satisfactorily retested. (251-76-1).
Cause Descri tion (continued) delta-T with the overtemperature delta-T setpoint. This caused the setpoint to be raised above the required value.
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