|
---|
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] |
Text
August 31, 2006 Florida Power and Light Company ATTN: Mr. J. A. Stall, Senior Vice President Nuclear and Chief Nuclear Officer P. O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - TURKEY POINT NUCLEAR PLANT
Dear Mr. Stall:
On August 2, 2006, the NRC staff completed its performance review of the Turkey Point Nuclear Power Plant for the first half of the calendar year 2006 assessment cycle. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results over the previous twelve months. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and the enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in Accordance with 10 CFR 2.390 will include the physical protection review and a resultant inspection plan.
Overall, Turkey Point Units 3 and 4 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter for both units was within the Regulatory Response column of the NRCs Action Matrix due to a White finding associated with extended inoperability of the B Auxiliary Feedwater Pump due to an incorrectly installed bearing. This White inspection finding, involving the mitigating systems cornerstone, reflected performance at a level requiring increased regulatory response. A Supplemental Inspection using Inspection Procedure (IP) 95001, Inspection for One or Two White Inputs In a Strategic Performance Area, was conducted the week of May 15, 2006 and no findings of significance were identified. Additionally, both units crossed the threshold from Green to White for the PI Heat Removal System Unavailability in the fourth quarter 2005.
However with implementation of the Mitigating Systems Performance Index in the second quarter 2006, both units were determined to be Green.
Additionally, the NRC has identified a substantive cross-cutting issue in the area of problem identification and resolution (PI&R). This substantive cross-cutting issue was based on five findings identified in the last 12-month assessment period which share a cross-cutting theme involving the thoroughness with which your staff has evaluated problems and the completeness of the subsequent corrective actions.
FP&L 2 Examples in the Mitigating Systems cornerstone involved inadequate corrective action associated with; a longstanding issue with incorrectly setting the Auxiliary Feedwater system manual speed control knob; extended inoperability of the B Turbine Driven Auxiliary Feedwater pump due to an incorrectly installed bearing; repeated heat damage to pressurizer level instrument cables; and multiple examples of scaffolds erected in the area of safety related equipment. One example in the Public Radiation Safety cornerstone involved inadequate corrective action associated with the main plant vent radiation monitor. The NRC is aware that you have already initiated some corrective actions to address the individual cross-cutting aspects, but have only recently initiated corrective actions to address the substantive cross-cutting theme. Therefore, in the Fall of 2006, the NRC will conduct an assessment of the effectiveness of your actions as a PI&R follow-up inspection item in accordance with Inspection Procedure 71152, Identification and Resolution of Problems, section 03.02. Additionally, because your actions taken to date have not been effective in resolving this cross-cutting theme, we intend to conduct an additional PI&R team inspection during the Spring 2007, as described in section 06.06.i of Manual Chapter 0305, Operating Reactor Assessment Program. Upon completion of these inspections, the NRC will consider this substantive cross-cutting theme clear if there is evidence that your corrective actions have been effective; specifically, that there are no new greater-than-green findings that share this cross-cutting theme, there is no increasing trend in green findings that share this cross-cutting theme, and that the entry conditions for the cross-cutting theme are no longer met.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through March 31, 2008. In addition, we plan to conduct non-ROP inspections involving containment sump blockage, Implementation of Key Shutdown Voluntary Initiatives, and verification of Mitigating Systems Performance Index. We will contact you to schedule the inspection involving Implementation of Key Shutdown Voluntary Initiatives. The inspection plan is provided to minimize the resource impact on your staff and to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite.
Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last twelve months of the inspection plan are tentative and may be revised at the end-of-cycle review meeting.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
FP&L 3 If circumstances arise which cause us to change the inspection plan, we will contact you to discuss the change as soon as possible. Please contact Joel Munday at (404) 562-4560 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Charles A. Casto, Director Division of Reactor Projects Docket Nos.: 50-250, 50-251 License Nos.: DPR-31, DPR-41
Enclosure:
Turkey Point Inspection/Activity Plan cc w/encl: (See page 4)
ML062430288 OFFICE RII:DRP RII:DRP SIGNATURE SON SON for NAME SNinh JMunday DATE 08/29/2006 08/28/2006 9/ /2006 9/ /2006 9/ /2006 9/ /2006 9/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO FP&L 4 cc w/encl:
T. O. Jones Attorney General Site Vice President Department of Legal Affairs Turkey Point Nuclear Plant The Capitol Florida Power and Light Company Tallahassee, FL 32304 Electronic Mail Distribution William A. Passetti Walter Parker Bureau of Radiation Control Licensing Manager Department of Health Turkey Point Nuclear Plant Electronic Mail Distribution Florida Power and Light Company Electronic Mail Distribution County Manager Metropolitan Dade County Michael O. Pearce Electronic Mail Distribution Plant General Manager Turkey Point Nuclear Plant Craig Fugate, Director Florida Power and Light Company Division of Emergency Preparedness Electronic Mail Distribution Department of Community Affairs Electronic Mail Distribution William E. Webster Vice President, Nuclear Operations Curtis Ivy Florida Power & Light Company City Manager of Homestead Electronic Mail Distribution Electronic Mail Distribution Mark Warner, Vice President Distribution w/encl: (See page 5)
Nuclear Operations Support Florida Power & Light Company Electronic Mail Distribution Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company Electronic Mail Distribution M. S. Ross, Managing Attorney Florida Power & Light Company Electronic Mail Distribution Marjan Mashhadi, Senior Attorney Florida Power & Light Company Electronic Mail Distribution Alejandro Sera Miami-Dade County Emergency Management Coordinator Electronic Mail Distribution
FP&L 5 Letter to J. A. Stall from Charles A. Casto dated August 31, 2006
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - TURKEY POINT NUCLEAR PLANT Distribution w/encl:
B. Moroney, NRR C. Evans L. Slack, RII EICS OE Mail RIDSNRRDIRS PUBLIC