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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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 ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 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 IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project 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 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal 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 IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) 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 IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 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 ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
[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
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0 FPL6 L-2014-189 10 CFR § 50.73 JUN 1 8 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 3 Docket No. 50-250 Reportable Event: 2014-003-00 Date of Event: April 23, 2014 Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter The attached Licensee Event Report 05000250/2014-003-00 is submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A) due to a manual actuation of the Reactor Protection System. The reactor was subcritical at the time in Mode 3. The reactor trip breakers were opened in accordance with the site Technical Specifications.
If there are any questions, please call Mr. Robert Tomonto at 305-246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant Florida Power & Light Company 9760 SW 344th St., Florida City, FL 33035 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 01131/2017 (02-20141 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.Reported lessons learned are incorporated into the licensing process and fed back to industry.Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S Nuclear Regulatory Commission, Washington, OC 20555-0001, or by LICENSEE EVENT REPORT (LER) intemet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and..See. PrRegulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC (See Page 2 for required number of 20503. If a means used to impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Turkey Point Unit 3 05000250 1 of 3 4. TITLE Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED SEQUENTIAL Rev FACILITY NAME DOCKET NUMBER NUMBER NO. 05000 FACILITY NAME DOCKET NUMBER 4 23 2014 2014 003 00 6 18 2014 05000 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)W 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C)
E 50.73(a)(2)(vii) 3 E 20.2201 (d) [] 20.2203(a)(3)(ii)
[] 50.73(a)(2)(ii)(A)
[] 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
ED 20.2203(a)(4)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
[:] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
E] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [D 20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
Z 50.73(a)(2)(iv)(A)
[] 50.73(a)(2)(x)
[1 20.2203(a)(2)(iii)
E] 50.36(c)(2)
[1 50.73(a)(2)(v)(A)
E] 73.71 (a)(4)0% 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
[1 50.73(a)(2)(v)(B)
D] 73.71 (a)(5)0D 20.2203(a)(2)(v)
ED 50.73(a)(2)(i)(A)
[I 50.73(a)(2)(v)(C)
[ OTHER Specify in Abstract below or in 20.2203(a)(2)(vi)
E] 50.73(a)(2)(i)(B)
E 50.73(a)(2)(v)(D)
NRC Form 366A 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)Paul F. Czaya 305-246-7150
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THS REPORT CAUSE SYSTEM COMPONENT MANU- REPORTABLE CAUSE SYSTEM COMPONENT MANU- REPORTABLE FACTURER TO EPIX FACTURER TO EPIX 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSSION YES (If yes, complete 15. EXPECTED SUBMISSION DATE) X NO DATE ABSTRACT (Limit to 1400 spaces i.e, approximately 15 single-spaced typewritten lines)On April 23, 2014 at approximately 1302 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.95411e-4 months <br />, Unit 3 entered Technical Specification (TS) 3.1.3.3 Action as a result of the Shutdown Bank B Group 1 step counter failing to increment.
The reactor was subcritical in Mode 3 progressing to reactor startup. The reactor trip breakers were opened as required by the Action of TS 3.1.3.3. The TS requires that the reactor trip breakers be opened if the group step counter demand position indicator (group I and group 2) are not within +/- 2 steps of each other. All rods fully inserted.
The unit remained in Mode 3. This was a manual actuation of the Reactor Protection System. Therefore, an 8-hour report (EN# 50054) was made in accordance with 10 CFR 50.72(b)(3)(iv) to the NRC Operations Center. The cause of the event was a supervisory data logging card not fully seated in the circuit card rack because of insufficient instruction in a functional test procedure.
The supervisory data logging card was re-seated and the testing sequence continued successfully.
A revision to the procedure will require a visual inspection and independent verification to verify proper engagement of the printed circuit cards.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.Reported lessons learned are incorporated into the licensing process and fed back to industry.Send comments regarding burden estimate to the FOIA, Privacy and Information Collections
-.Branch(T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001,or b)LICENSEE EVENT REPORT (LER) intemet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, CONTINUATION SHEET Washington, DC 20503. If a means used to impose an information collection does not display currently valid OMB control number, the NRC may not conduct or sponsor, and a person is nos required to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET 6. LER NUMER 3. PAGE SEQUENTIAL REV YER NUMBER NO. 2 O Turkey Point Unit 3 05000250 of 2014 -003 -00 NARRATIVE DESCRIPTION OF THE EVENT On April 23, 2014 at approximately 1302 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.95411e-4 months <br />, Unit 3 entered Technical Specification (TS) 3.1.3.3 Action as a result of the Shutdown Bank B Group I Step Counter [AA, CTR] failing to increment.
The reactor was subcritical in Mode 3 progressing to reactor startup. The reactor operator opened the reactor trip breakers in accordance with the Action of TS 3.1.3.3, which requires that the reactor trip breakers be opened if the group step counter demand position indicator (group 1 and group 2) are not within +/- 2 steps of each other. All rods fully inserted.
The unit remained in Mode 3.This was a manual actuation of the Reactor Protection System. Therefore, an 8-hour report (EN# 50054)was made in accordance with 10 CFR 50.72(b)(3)(iv) to the NRC Operations Center. This report is in accordance with 10 CFR 50.73(a)(2)(iv)(A).
CAUSE OF THE EVENT The direct cause of the event was the failure of the group step counter demand position indicator to increment because the supervisory data logging card A 114 was not fully seated in the circuit card rack.The root cause is attributed to lack of sufficient instruction in a functional test procedure to verify proper card seating. Card Al 14 gave a false indication of being fully seated by allowing the urgent failure alarm to clear although complete contact was not established.
ANALYSIS OF THE EVENT During operation of the Rod Control System (RCS), the Logic Cabinet generates and sends pulses to the Power Cabinets.
When the Power Cabinet receives this pulse it initiates a Rod Step. When the Rod Step cycle is complete a reply pulse is sent back to the Logic Cabinet. Once this reply pulse is received at the Logic Cabinet, the Logic Cabinet then triggers a relay which in turn sends out a 100 Vdc pulse to the associated Group (demand) Step Counter on the Control Room Operator's Console. When this pulse is received at the Group (demand) Step Counter the step counter increments in the required direction
(+1 if rods out and -1 if rods in). These Group (demand) Step Counters rely on continuity with the RCS. At time of discovery, the A 114 printed circuit card was found not fully seated and confirmed as protruding beyond the edge of the card cage assembly by approximately YA -'A inch. The A 114 card was tight, however additional force was required to ensure the card was fully seated.On April 23, 2014, early in the dayshift, RCS testing was performed in accordance with 0-PMI-028.05, Rod Control System Preventative Maintenance and Power Cabinet Functional Test. In accordance with this procedure, card A 114 was withdrawn to verify proper operation of the Urgent Failure Alarm and then re-seated in the card cage. The Urgent Failure Alarm cleared.Later, while performing cold rod stepping, Operations personnel observed that while the Shutdown Bank B (SBB) rods were withdrawn, the group 2 step counter indicated 7 steps withdrawn, but the group 1 step NRC (02-201 FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 41/1 LICENSEE EVENT REPORT (LER)CONTINUATION SHEET APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01131/2017 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.Reported lessons learned are incorporated into the licensing process and fed back to industry.Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (1-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
or by intemet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Turkey Point Unit 3 3. PAGE 3 of 3 2014 -003 -00 counter remained at 0 steps. The console and the Digital Control System rod position indication both indicated that both the group 1 and group 2 SBB were withdrawn to approximately 7 steps. Operations personnel concluded that the shutdown bank group step counters were not indicating properly and the decision was made to open the Unit 3 reactor trip breakers.Reportability The event (a manual actuation of the Reactor Protection System) is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) because the reactor trip breakers were required to be opened in response to a plant condition.
ANALYSIS OF SAFETY SIGNIFICANCE At the time of the event, the reactor was in Mode 3 (sub-critical) and the plant remained in Mode 3. The reactor trip breakers were opened and all systems functioned as required.
Significant subcriticality margin was available based on the balance of the control rods being fully inserted and the boron concentration being greater than the predicted dilution value for criticality.
There was no impact on safety.CORRECTIVE ACTIONS Corrective action is in accordance with condition report ARI 960842 and includes: Revise plant procedure 0-PMI-028.05, Rod Control System Preventive Maintenance and Power Cabinet Functional Test, to require a visual inspection and independent verification to verify the engagement of the printed circuit boards (PCB) by ensuring the front edge of the PCBs are flush with the card cage assembly.
An additional supervisor visual inspection step will also be added to the procedure.
ADDITIONAL INFORMATION EIIS Codes are shown in the format [IEEE system identifier, component function identifier, second component function identifier (if appropriate)].
Condition Report 1960842 was initiated due to this event.FAILED COMPONENTS IDENTIFIED:
None.PREVIOUS SIMILAR EVENTS: None in the last five years.