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MONTHYEARML0221305172002-08-0101 August 2002 Notice of Consideration, Application Dated July 29, 2002, Which Would Revise the Technical Specifications to Allow the Use of Alternate Method of Determining Rod Position for a Control Rod Project stage: Other ML0223204842002-08-20020 August 2002 Exigent Technical Specification Amendment No. 216, Control Rod Position Indication System Project stage: Other ML0225300052002-09-10010 September 2002 Corrections to Turkey Point Unit 4, Letter, Exigent Technical Specifications Amendment Concerning Control Rod Position Indication System Project stage: Other 2002-08-20
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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23249A2412023-09-25025 September 2023 Regulatory Audit Summary for the Review of License Amendment Request to Revise the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23082A0402023-04-0505 April 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment Nos. 260 and 255 ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22098A0902022-04-13013 April 2022 Nextera/Fpl Non-Proprietary Presentation for April 13, 2022 Public Meeting Re Planned Turkey Point Digital Instrumentation and Controls License Amendment Request (EPID L-2021-LRM-0007) (Slides) ML22020A4032022-02-0707 February 2022 Summary of November 17, 2021, Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests (EPIDs L-2021-LLI-0000 and L-2021-LLI-0002) ML21279A0432021-10-15015 October 2021 Summary of Pre-Application Meetings with Florida Power and Light Concerning a Proposed Digital Instrumentation and Control Upgrade for Turkey Point, Units 3 and 4 ML21119A3552021-05-26026 May 2021 Correction to Amendment Concerning Extension of Containment Leak Rate Testing Frequency Amendments ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19310D7772019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 3 Subsequent Renewed Facility Operating License ML19305C8792019-12-0404 December 2019 LTR - Issuance of Subsequent Renewed Facility Operating License Nos. DPR-31 and DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML19310D7782019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 4 Subsequent Renewed Facility Operating License ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 L-2019-088, Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment2019-04-18018 April 2019 Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15205A1742015-08-14014 August 2015 Issuance of Amendments Regarding Removal of Reactor Coolant System Chemistry Requirements from the Technical Specifications and Relocation of Requirements in Licensee-Controlled Documents ML15181A1792015-07-27027 July 2015 Issuance of Amendments Regarding Adoption of Technical Specification Task Force Traveler 523 (TSTF-523), Revision 2 ML13329A0922014-06-13013 June 2014 Issuance of Amendments Regarding Operating License Conditions and Technical Specifications ML13329A1392014-02-21021 February 2014 Issuance of Amendments Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13207A0952013-09-10010 September 2013 Issuance of Amendment No. 258 Regarding a One-Time Extension of Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d ML13059A2242013-04-0202 April 2013 Issuance of Amendments Regarding the Recirculation Ph Control System and Sodium Tetraborate Basket Loading ML12339A1122012-12-17017 December 2012 Issuance of Amendments Regarding Revision of Cyber Security ML12297A2402012-11-0606 November 2012 Issuance of Amendments Regarding Adoption of TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML12291A7302012-11-0505 November 2012 Issuance of Amendments Regarding Revision to Technical Specifications 3.7.5 Control Room Emergency Ventilation System ML12292A3422012-11-0505 November 2012 Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes ML12208A2982012-08-0808 August 2012 Issuance of Amendments Regarding Change to Direct Current Source Surveillance Requirements ML12130A0892012-06-21021 June 2012 Issuance of Amendments Regarding Section 5.0 Design Features 2024-01-22
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Text
September 10, 2002 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
CORRECTIONS TO TURKEY POINT UNIT 4 EXIGENT TECHNICAL SPECIFICATION AMENDMENT CONCERNING CONTROL ROD POSITION INDICATION SYSTEM (TAC NO. MB5703)
Dear Mr. Stall:
On August 20, 2002, Amendment No. 216 to Facility Operating License No. DPR-41 for the Turkey Point Plant Unit 4 was issued. This amendment revised the Technical Specifications (TSs) in response to Florida Power and Light Companys application dated July 29, 2002, as supplemented by letters dated August 14 and August 16, 2002. Your Turkey Point Licensing staff noted minor editorial errors in the amendment and associated safety evaluation (SE).
These editorial corrections are denoted in the attached pages by margin bars. Also to provide consistency and clarity with your submittals, corrections were made in the SE to more accurately reflect those compensatory actions you will be taking as a result of the amendment.
These changes do not affect the conclusion of the SE. We apologize for any inconvenience this may have caused. Enclosed please find the corrected pages.
Sincerely,
/RA/
Eva A. Brown, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-251
Enclosure:
Corrected Pages cc w/encls: See next page
ML OFFICE PDII-2/PM PDII-2/LA PDII-2/SC(A)
NAME EBrown BClayton KJabbour DATE 09/6/02 09/9/02 09/9/02 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-41
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. The application for amendment by Florida Power and Light Company (the licensee) dated July 29, 2002, as supplemented by letters dated August 14 and August 16, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility l Operating License No. DPR-41 is hereby amended to read as follows:
2.0 BACKGROUND
TS 3.1.3.2 currently requires the RPI System to be operable and capable of determining the respective actual and demanded shutdown and control rod positions. With a maximum of one RPI per bank inoperable, the TS ACTION statement requires that the licensee determine the position of the non-indication rod(s) indirectly by using the movable incore detectors once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for any movement of the non-indicating rod which exceeds 24 steps in one direction. The licensee also has the option to reduce power to 75 percent of rated thermal power.
The proposed change would permit the licensee to monitor the stationary gripper coil of the CRDM for control rod C-9 in lieu of the RPI system, thus partially restoring the ability to determine RPI for control rod C9. This alternate method would be used for control rod C-9 RPI in TS Sections 3.1.3.1, 3.1.3.2, and 3.1.3.5. The licensee would be required to verify every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> that the gripper coil has not changed state. The absence of movement of the gripper coil would indicate that the control rod had not moved.
Additionally, the proposed change will add a footnote to TSs 3/4.1.3.1, 3/4.1.3.2 and l 3/4.3.1.3.5, which states that during Cycle 20 the position of control rod C-9 will be determined l indirectly by an alternate method, other than the Analog Rod Position Indication system, until the repair of the indication system for this rod is completed. Additionally, a footnote stating that the use of the alternate method for control rod C-9 does not require the 4-hour comparison of demand versus actual position will be added to SRs 4.1.3.1.1 and 4.1.3.2.1. This change would not affect the existing TS surveillance requirements to determine control rod C-9s position by flux map every 31 days, but would require the licensee to determine control rod C-9s position l using the movable incore system at least once every 31 days. However, it would relieve the l licensee from performing this determination every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> as the existing TSs require.
3.0 EVALUATION According to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, General Design Criteria 13, Instrumentation and Controls, instrumentation to monitor variables and systems over their operating ranges during normal operation, anticipated operational occurrences, and accident conditions must be OPERABLE. TS 3.1.3.2 requires OPERABILITY l of the control rod position indicators to determine control rod positions and, thereby, ensure compliance with the control rod alignment and insertion limits. The OPERABILITY, including position indication, of the shutdown and control rods is an initial assumption in all safety analyses that assume rod insertion upon reactor trip.
The objectives of the control rod system are to ensure that control rod alignment and insertion limits are maintained, acceptable power distributions as well as minimum shutdown margins are maintained, and that the potential effects of rod misalignment on associated accidents are limited.
The control rod in question is C-9, which is a shutdown bank A rod. This control rod is required to be fully withdrawn when the reactor is critical. In order to evaluate the proposed TS changes, the following conditions were considered: rod drop or rod misalignment during power operation, rod drop or rod misalignment during reactor startup, and a reactor trip. These are the only
conditions that need to be considered since control rod C-9 will be fully withdrawn at all other times that the TS is applicable.
A full rod drop of control rod C-9 during power operation would be detectable by indications other than the position indication system. Such an event would cause an urgent failure alarm and a noticeable change in the core parameters as evident by the response of the excore detectors. Thus, the status of control rod C-9s individual rod position indication would not affect the operator actions. Similarly, a rod misalignment, greater than that analyzed for, would also be detected by an urgent failure alarm and the response by the excore detectors.
Therefore, the likelihood of an undetected rod drop or misalignment is considered negligible.
In addition to the analysis provided in the submittal of July 29, 2002, FPL has revised the Shutdown Margin Calculation 0-OP-028.2, to ensure that shutdown margin limits continue to be met for the remainder of this cycle. The use of the alternate methodology requires that the pertinent procedures are modified to account for the inoperable RPI. FPL has indicated that additional training, including operator training with the instrumentation required for the alternate l methodology, will be provided to the reactor operators and technicians to assure familiarity with new plant conditions and modified procedures.
FPL has determined that the objectives stated above can be met with an inoperable RPI in a shutdown bank without subjecting the movable incore system to unnecessary additional wear.
FPL stated in its submittal that it has installed a recorder to track parameters of the stationary gripper coil of the CRDM on the non-indicating rod. FPL also intends to verify every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> that the coil has not changed state. This 8-hour surveillance period is consistent with the current compensatory operational requirements for control rod C-9 position determination.
The NRC staff has reviewed all the material submitted and performed an assessment of the conditions. The staff agrees that personnel safety concerns and maintaining personnel dose as low as reasonablely achievable prevent safe completion of repairs with the reactor at power and that constant use of the incore detector system is not advisable. The proposed TS changes provide adequate controls to ensure that the rod position is known and that any rod misalignment is detectable. Since the increase in the likelihood of an undetected rod drop or misalignment is determined to be negligible, the integrity of the accident analysis is maintained.
The staff concurs with the licensees analysis and conclusions regarding the use of an alternate method to monitor the RPI associated with control rod C-9. Based on the licensees submittal and additional information provided, the staff acknowledges the necessity for a repair of the installed RPI for control rod C9 as soon as reasonably achievable and, therefore, concurs that the performance of the repair be conducted at the next outage of sufficient duration or during the upcoming refueling outage, whichever comes first. Based on the above, the staff concludes that the proposed TS changes, applicable to control rod C-9 only for the remainder of Cycle 20, are acceptable.
4.0 STATEMENT OF EXIGENT CIRCUMSTANCES The Commission's regulation, as stated in 10 CFR 50.91, provides special exceptions for the issuance of amendments when the usual 30-day public notice cannot be met. One type of special exception is an exigency. An exigency exists when the staff and the licensee need to act quickly and time does not permit the staff to publish a Federal Register notice allowing
Mr. J. A. Stall TURKEY POINT PLANT Florida Power and Light Company cc:
M. S. Ross, Attorney Attorney General Florida Power & Light Company Department of Legal Affairs P.O. Box 14000 The Capitol Juno Beach, FL 33408-0420 Tallahassee, Florida 32304 Mr. John P. McElwain, Site Vice President T. O. Jones, Plant General Manager Turkey Point Nuclear Plant Turkey Point Nuclear Plant Florida Power and Light Company Florida Power and Light Company 9760 SW. 344th Street 9760 SW. 344th Street Florida City, FL 33035 Florida City, FL 33035 County Manager Walter Parker Miami-Dade County Licensing Manager 111 NW 1 Street, 29th Floor Turkey Point Nuclear Plant Miami, Florida 33128 9760 SW 344th Street Florida City, FL 33035 Senior Resident Inspector Turkey Point Nuclear Plant Mr. Don Mothena U.S. Nuclear Regulatory Commission Manager, Nuclear Plant Support Services 9762 SW. 344th Street P.O. Box 14000 Florida City, Florida 33035 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Mr. Rajiv S. Kundalkar Department of Health Vice President - Nuclear Engineering Bureau of Radiation Control Florida Power & Light Company 2020 Capital Circle, SE, Bin #C21 P.O. Box 14000 Tallahassee, Florida 32399-1741 Juno Beach, FL 33408-0420 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100
PD II-2 DOCUMENT COVER PAGE DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022530005.wpd
SUBJECT:
Correction letter for TP4 Exigent Amendment ORIGINATOR: E. Brown SECRETARY: Marilyn Wohl DATE: September 10, 2002
ROUTING LIST
NAME DATE
- 1. E. Brown 09/ /02
- 2. B. Clayton 09/ /02
- 3. K. Jabbour 09/ /02
- 5. Secretary/dispatch 09/ /02 ADAMS STEPS Enter profile into ADAMS ________
Accession Number __________
NRR Template Number NRR-064 (Mtg. Not.) _____
NRR-088 (RAI) _____
NRR-028 (Relief) _____
NRR-106 (Letters, Memo, Sholly) ___X__
NRR- (Other) _____
Enter dates, concurrences, etc. (Secy) _______
QC Electronic copy against hard copy (LA) _______
QC profile and declare Official Record (RC) _______
Can Document be Deleted after Dispatch? X