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| {{#Wiki_filter:U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-001 Re: Turkey Point Unit 3 Docket No. 50-250 Special Report -Accident Monitoring Instrumentation MAY 1 1 2017 L-2017-090 I n accordance with Technical Specifications 6.9.2 and 3.3.3.3, the attached Special Report is provided for your information. | | {{#Wiki_filter:MAY 1 1 2017 L-2017-090 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, D.C. 20555-001 Re: Turkey Point Unit 3 Docket No. 50-250 Special Report -Accident Monitoring Instrumentation In accordance with Technical Specifications 6.9.2 and 3.3.3.3, the attached Special Report is provided for your information. |
| Should there be any questions regarding this information, please contact Mitch Guth, Licensing Manager at (305) 246-6698. Sincerely, Brian Stamp Plant General Manager Turkey Point Nuclear Plant SM cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Li g ht Com p an y 9760 S.W. 344 1 h Street Homestead , FL 33035 L-2017-090, Attachment Page 1 of 2 SPECIAL REPORT Purpose: This special report is being submitted pursuant to the requirements of Turkey Point Unit 3 Technical Specification (TS) 3.3.3.3, Table 3.3 | | Should there be any questions regarding this information, please contact Mitch Guth, Licensing Manager at (305) 246-6698. |
| -5, Accident Monitoring Instrumentation, Instrument 19.c, Action 34, part 2) due to the Condenser Air Ejector for High Range | | Sincerely, Brian Stamp Plant General Manager Turkey Point Nuclear Plant SM cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 S.W. 3441h Street Homestead , FL 33035 |
| -Noble Gas Effluent Monitor (RAD-3-6417) being inoperable for greater than 7 days. | | |
| Required Action 34 of TS 3.3.3.3, Table 3.3 | | L-2017-090, Attachment Page 1 of 2 SPECIAL REPORT |
| -5 states: "With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours, and: | | |
| : 1) Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or | | ==Purpose:== |
| : 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status." | | This special report is being submitted pursuant to the requirements of Turkey Point Unit 3 Technical Specification (TS) 3.3.3.3, Table 3.3-5, Accident Monitoring Instrumentation, Instrument 19.c, Action 34, part 2) due to the Condenser Air Ejector for High Range-Noble Gas Effluent Monitor (RAD-3-6417) being inoperable for greater than 7 days. |
| | Required Action 34 of TS 3.3.3.3, Table 3.3-5 states: |
| | With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours, and: |
| | : 1) Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or |
| | : 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status. |
| This Special Report is being transmitted in accordance with these requirements. | | This Special Report is being transmitted in accordance with these requirements. |
| Event and Action Taken: | | Event and Action Taken: |
| | RAD-3-6417 consists of three channels with the following ranges to cover the total range required (1.0 E-06 to 1.0 E+05 µCi/cc): |
| | Low-Range Channel 5: 1.0 E-07 to 6.0 E-02 µCi/cc Mid-Range Channel 7: 2.5 E-02 to 4.0 E+02 µCi/cc High-Range Channel 9: 1.0 E+00 to 1.0 E+05 µCi/cc On April 23, 2017, at 0522, Turkey Point Unit 3 entered Mode 3, returning to power from the Unit 3, Cycle 29 Refueling Outage. At that time, plant conditions did not support the sample flow rate required to allow the High Range-Noble Gas Effluent Monitor (RAD-3-6417) to be in service, and as such, monitor RAD-3-6417 was rendered inoperable. Additionally, on April 25, 2017, while performing the Channel 5 calibration, it was discovered that the detector efficiency was below the acceptance criteria, and it needed replacement. The monitor was not returned to service until May 5, 2017 at 1940. |
| | In accordance with TS 3.3.3.3, Table 3.3-5, Instrument 19.c, the Condenser Air Ejector Noble Gas Effluent Monitor is required to be OPERABLE for Modes 1-3. Since RAD-3-6417 was not restored to service within 7 days (by April 30, 2017) as required by TS 3.3.3.3, Table 3.3-5, Action 34, this special report is prepared and submitted within the next 14 days (by May 14, 2017) to comply with the TS Action 34 requirements. |
|
| |
|
| RAD-3-6417 consists of three channels with the following ranges to cover the total range required (1.0 E
| | L-2017-090, Attachment Page 2 of 2 The pre-planned alternate method of monitoring the appropriate parameters was established prior to April 23, 2017. The method utilized was grab samples, once per 8 hours, to perform isotopic activity analysis. Sampling was maintained throughout the period of inoperability. |
| -06 to 1.0 E+0 5 µCi/cc):
| |
| Low-Range Channel 5: 1.0 E-0 7 to 6.0 E-02 µCi/cc Mid-Range Channel 7: 2.5 E-02 to 4.0 E+02 µCi/cc High-Range Channel 9
| |
| : 1.0 E+00 to 1.0 E+05 µCi/cc O n April 23, 2017 , at 0522, Turkey Point Unit 3 entered Mode 3, returning to power from the Unit 3, Cycle 29 Refueling Outage. At that time, plant conditions did not support the sample flow rate required to allow the High Range
| |
| -Noble Gas Effluent Monitor (RAD 64 17) to be in service, and as such, monitor RAD 6417 was rendered inoperable. Additionally, on April 25, 2017, while performing the Channel 5 calibration, it was discovered that the detector efficiency was below the acceptance criteria, and it needed replacement. The monitor was not returned to service until May 5, 2017 at 1940.
| |
| In accordance with TS 3.3.3.3, Table 3.3
| |
| -5, Instrument 19.c, the Condenser Air Ejector Noble Gas Effluent Monitor is required to be OPERABLE for Modes 1
| |
| -3. Since RAD-3-6417 was not restored to service within 7 days (by April 30, 201 7) as required by TS 3.3.3.3, Table 3.3
| |
| -5, Action 34, this special report is prepared and submitted within the next 14 days (by May 1 4 , 2017) to comply with the TS Action 34 requirements
| |
| .
| |
| L-20 17-090, Attachment Page 2 of 2 T he pr e-planned alternate method of monitoring the appropriate parameters was established prior to April 23, 2017. The method utilized was grab samples
| |
| , once per 8 hours , to perform isotopic activity analysis. | |
| Sampling was maintained throughout the period of inoperability. | |
| Cause: | | Cause: |
| The sampling flow path was bypassed due to the plant conditions, which rendered monitor RAD-3-6417 inoperable. Additionally, the RAD-3-6417 Channel 5 detector was degraded and needed replacement. | | The sampling flow path was bypassed due to the plant conditions, which rendered monitor RAD-3-6417 inoperable. Additionally, the RAD-3-6417 Channel 5 detector was degraded and needed replacement. |
| | |
| Schedule for Restoration: | | Schedule for Restoration: |
|
| |
| The detector was replaced and the monitor was declared operable on May 5, 2017 at 1940.}} | | The detector was replaced and the monitor was declared operable on May 5, 2017 at 1940.}} |
|
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Category:Letter type:L
MONTHYEARL-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) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule 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, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-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 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. 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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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 L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 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 ML18227D2871977-01-14014 January 1977 Submit Personal Radiation Exposure Report in Accordance with the Requirements of 10 CFR 20.405 ML18227D2881977-01-14014 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 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 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 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 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 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 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 2023-11-13
[Table view] |
Text
MAY 1 1 2017 L-2017-090 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, D.C. 20555-001 Re: Turkey Point Unit 3 Docket No. 50-250 Special Report -Accident Monitoring Instrumentation In accordance with Technical Specifications 6.9.2 and 3.3.3.3, the attached Special Report is provided for your information.
Should there be any questions regarding this information, please contact Mitch Guth, Licensing Manager at (305) 246-6698.
Sincerely, Brian Stamp Plant General Manager Turkey Point Nuclear Plant SM cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 S.W. 3441h Street Homestead , FL 33035
L-2017-090, Attachment Page 1 of 2 SPECIAL REPORT
Purpose:
This special report is being submitted pursuant to the requirements of Turkey Point Unit 3 Technical Specification (TS) 3.3.3.3, Table 3.3-5, Accident Monitoring Instrumentation, Instrument 19.c, Action 34, part 2) due to the Condenser Air Ejector for High Range-Noble Gas Effluent Monitor (RAD-3-6417) being inoperable for greater than 7 days.
Required Action 34 of TS 3.3.3.3, Table 3.3-5 states:
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 1) Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or
- 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
This Special Report is being transmitted in accordance with these requirements.
Event and Action Taken:
RAD-3-6417 consists of three channels with the following ranges to cover the total range required (1.0 E-06 to 1.0 E+05 µCi/cc):
Low-Range Channel 5: 1.0 E-07 to 6.0 E-02 µCi/cc Mid-Range Channel 7: 2.5 E-02 to 4.0 E+02 µCi/cc High-Range Channel 9: 1.0 E+00 to 1.0 E+05 µCi/cc On April 23, 2017, at 0522, Turkey Point Unit 3 entered Mode 3, returning to power from the Unit 3, Cycle 29 Refueling Outage. At that time, plant conditions did not support the sample flow rate required to allow the High Range-Noble Gas Effluent Monitor (RAD-3-6417) to be in service, and as such, monitor RAD-3-6417 was rendered inoperable. Additionally, on April 25, 2017, while performing the Channel 5 calibration, it was discovered that the detector efficiency was below the acceptance criteria, and it needed replacement. The monitor was not returned to service until May 5, 2017 at 1940.
In accordance with TS 3.3.3.3, Table 3.3-5, Instrument 19.c, the Condenser Air Ejector Noble Gas Effluent Monitor is required to be OPERABLE for Modes 1-3. Since RAD-3-6417 was not restored to service within 7 days (by April 30, 2017) as required by TS 3.3.3.3, Table 3.3-5, Action 34, this special report is prepared and submitted within the next 14 days (by May 14, 2017) to comply with the TS Action 34 requirements.
L-2017-090, Attachment Page 2 of 2 The pre-planned alternate method of monitoring the appropriate parameters was established prior to April 23, 2017. The method utilized was grab samples, once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, to perform isotopic activity analysis. Sampling was maintained throughout the period of inoperability.
Cause:
The sampling flow path was bypassed due to the plant conditions, which rendered monitor RAD-3-6417 inoperable. Additionally, the RAD-3-6417 Channel 5 detector was degraded and needed replacement.
Schedule for Restoration:
The detector was replaced and the monitor was declared operable on May 5, 2017 at 1940.