Letter Sequence Response to RAI |
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TAC:ME1624, Administratively Control Containment Penetrations, TSTF-68, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: L-2011-540, Safety Evaluation Report Review Supporting Fuel Storage Criticality Amendments 246 and 242, L-2012-118, Response to NRC ITSB RAI Regarding Clean TS Changes for EPU LAR No. 205 and Incorporation of Amendments 247 and 243 TS Changes on Relocation of Cycle Specific Parameters to the Core Operating Limits Report, L-2012-263, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report, L-2012-293, FPL Review Comments on Extended Power Uprate Safety Evaluation Report, L-2012-426, Extended Power Uprate Cycle 26 Startup Report, ML110960521, ML110960523, ML112280292, ML12074A248, ML12074A251, ML12122A162, NRC-2011-0094, Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information.
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MONTHYEARL-2009-133, License Amendment Request 196 Alternative Source Term and Conforming Amendment2009-06-25025 June 2009 License Amendment Request 196 Alternative Source Term and Conforming Amendment Project stage: Request ML0920205292009-07-22022 July 2009 Supplemental Information Needed for Acceptance of Requested Licensing Action Alternate Source Term Amendment Request (LAR 196) (Tac Nos. ME1624 and ME1625) Project stage: Acceptance Review ML0922206962009-08-18018 August 2009 Supplemental Information Needed for Acceptance of Requested Licensing Action Alternate Source Term Amendment Request (LAR 196) Project stage: Acceptance Review L-2009-195, Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term2009-08-26026 August 2009 Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term Project stage: Response to RAI ML0926005302009-09-25025 September 2009 Acceptance Letter Regarding the Alternative Source Term License Amendment Request Project stage: Acceptance Review ML0935006652009-12-17017 December 2009 RAI, Regarding Alternative Source Term Project stage: RAI L-2010-021, Turkey Points, Units 3 & 4, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request2010-02-10010 February 2010 Turkey Points, Units 3 & 4, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request Project stage: Response to RAI ML1005603882010-02-25025 February 2010 Request for Additional Information Regarding Request to Adopt the Alternate Source Term Project stage: RAI L-2010-048, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 1962010-03-15015 March 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 Project stage: Response to RAI ML1007004462010-03-24024 March 2010 Request for Additional Information Regarding Request to Adopt the Alternate Source Team (TAC ME1624 & ME1625) Project stage: RAI L-2010-065, Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 1962010-04-14014 April 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 196 Project stage: Response to RAI L-2010-083, Supplement to License Amendment Request (LAR) 196 and 3/24/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST)2010-05-21021 May 2010 Supplement to License Amendment Request (LAR) 196 and 3/24/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) Project stage: Supplement L-2010-121, Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 1962010-06-11011 June 2010 Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request L-2010-131, Response to 5/28/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 1962010-06-23023 June 2010 Response to 5/28/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 Project stage: Request L-2010-137, Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 1962010-06-25025 June 2010 Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request ML1024400682010-08-27027 August 2010 Acceptance Review: Fuel Storage Criticality Analysis LAR (ME4470 and ME4471) Project stage: Acceptance Review L-2010-136, Revised Meteorological Data for 2005-2009 with T Bias Supporting Alternative Source Term and Conforming License Amendment Request 1962010-09-0202 September 2010 Revised Meteorological Data for 2005-2009 with T Bias Supporting Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request ML1024602052010-09-0303 September 2010 E-mail Acceptance Review TSTF-448 Project stage: Acceptance Review L-2010-197, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System2010-09-15015 September 2010 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System Project stage: Response to RAI L-2010-226, Summary of NRC Public Meeting Discussion on Meteorological Data for Alternative Source Term and Conforming License Amendment Request 1962010-10-13013 October 2010 Summary of NRC Public Meeting Discussion on Meteorological Data for Alternative Source Term and Conforming License Amendment Request 196 Project stage: Meeting ML1035601692010-10-21021 October 2010 License Amendment Request for Extended Power Uprate (LAR 205) Project stage: Request L-2010-160, Supplement to the Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 Regarding the EPU Related System Impact Study (SIS)2010-10-29029 October 2010 Supplement to the Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 Regarding the EPU Related System Impact Study (SIS) Project stage: Supplement L-2010-293, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) No. 196 and Meteorological Data Sensitivity2010-12-14014 December 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) No. 196 and Meteorological Data Sensitivity Project stage: Response to RAI ML1035601832010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 07; Supplemental Environmental Report Project stage: Supplement ML1035601742010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes Project stage: Request ML1028710232010-12-16016 December 2010 Summary of Meeting with Florida Power & Light Company to Discuss Turkey Point, Units 3 and 4, Alternative Source Term License Amendment Request Project stage: Meeting L-2010-303, Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Equivalent Margin Analysis (EMA)2010-12-21021 December 2010 Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Equivalent Margin Analysis (EMA) Project stage: Supplement ML1036400512010-12-26026 December 2010 Logbook Entry for 12/26/2010 Project stage: Request ML1036400522010-12-27027 December 2010 Logbook Entry for 12/27/2010 Project stage: Request L-2011-004, Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Mechanical/Civil Engineering Issues2011-01-0707 January 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Mechanical/Civil Engineering Issues Project stage: Response to RAI ML1103101842011-01-12012 January 2011 Crocodile Log Book 1/12/2011 Project stage: Request ML1035500302011-01-19019 January 2011 Summary of Meeting with Florida Power & Light Company, Regarding Turkey Point, Units 3 & 4, Spent Fuel Criticality Analysis License Amendment Request Project stage: Meeting L-2011-027, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Fire Protection Issues2011-02-22022 February 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Fire Protection Issues Project stage: Response to RAI L-2011-030, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Human Performance Issues - Round 12011-03-0303 March 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Human Performance Issues - Round 1 Project stage: Response to RAI ML1107000212011-03-11011 March 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review L-2011-102, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Unit 3 Mechanical/Civil Engineering Issues2011-03-25025 March 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Unit 3 Mechanical/Civil Engineering Issues Project stage: Response to RAI L-2011-081, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Electrical Engineering Branch Issues2011-03-31031 March 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Electrical Engineering Branch Issues Project stage: Response to RAI ML1108907262011-03-31031 March 2011 Slides for Turkey Point, 3 and 4, Regarding Extended Power Uprate and Spent Fuel Criticality Project stage: Request ML11095A0122011-04-21021 April 2011 Summary of Public Meeting with Florida Power & Light Company, on Turkey Points, Units 2 and 4 Extended Power Uprate License Amendment Request Currently Under Review (TAC Nos. ME4907 and ME4908) Project stage: Meeting L-2011-153, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues2011-04-22022 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues Project stage: Response to RAI L-2011-084, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues2011-04-28028 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues Project stage: Response to RAI L-2011-142, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Health Physics and Human Performance Issues2011-04-29029 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Health Physics and Human Performance Issues Project stage: Response to RAI NRC-2011-0094, Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information.2011-05-0202 May 2011 Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information. Project stage: Other ML1109605232011-05-0202 May 2011 Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information. Project stage: Other ML1109605212011-05-0606 May 2011 Letter, Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information Project stage: Other L-2011-141, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Systems Issues2011-05-11011 May 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Systems Issues Project stage: Response to RAI L-2011-170, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues2011-05-19019 May 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues Project stage: Response to RAI L-2011-154, Response to NRC Request for Additional Information Regarding Fuel Storage Criticality Analysis License Amendment Request No. 2072011-05-20020 May 2011 Response to NRC Request for Additional Information Regarding Fuel Storage Criticality Analysis License Amendment Request No. 207 Project stage: Response to RAI L-2011-210, Regarding Supplementary Information Related to Fpl'S Response to NRC Request for Additional Information (RAI) IHPB-1.52011-06-0707 June 2011 Regarding Supplementary Information Related to Fpl'S Response to NRC Request for Additional Information (RAI) IHPB-1.5 Project stage: Supplement ML11174A1652011-06-21021 June 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues Project stage: Response to RAI 2010-06-25
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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
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Text
Florida Power & Light, 9760 S.W. 344 St. Homestead, FL 33035 0JUN 2 1 2011 FPL. L-2011-190 10 CFR 50.90 10 CFR 2.390 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues
References:
(1) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request No. 205: Extended Power Uprate (EPU)," (TAC Nos. ME4907 and ME4908), Accession No. ML 103560169, October 21, 2010.(2) Email from J. Paige (NRC) to T. Abbatiello (FPL), "Turkey Point EPU -Instrumentation and Controls (EICB) Request for Additional Information
-Round 1.2 (Part 2)", Accession No. ML 1 147A056, May 27, 2011.By letter L-2010-113 dated October 21, 2010 [Reference 1], Florida Power and Light Company (FPL) requested to amend Renewed Facility Operating Licenses DPR-31 and DPR-41 and revise the Turkey Point Units 3 and 4 Technical Specifications (TS). The proposed amendment will increase each unit's licensed core power level from 2300 megawatts thermal (MWt) to 2644 MWt and revise the Renewed Facility Operating Licenses and TS to support operation at this increased core thermal power level. This represents an approximate increase of 15% and is therefore considered an extended power uprate (EPU).By email from the U.S. Nuclear Regulatory Commission (NRC) Project Manager (PM) dated May 27, 2011 [Reference 2], additional information regarding instrumentation and controls issues was requested by the NRC staff in the Instrumentation and Controls Branch (EICB) to support the review of the EPU License Amendment Request (LAR) [Reference 1]. The Request for Additional information (RAI) consisted of one question regarding the methodology in WCAP- 17070-P used to calculate OTAT and OPAT protection values and additional information regarding the power range neutron flux high setpoint.
Note that the RAI response involves a proposed change to TS Table 2.2-1, Function 2a, Power Range Neutron Flux High Setpoint.
The RAI question and the FPL response are documented in the Attachments 1-6 to this letter.Attachments 4 and 6 contain the applications for withholding the proprietary information contained in Attachments 3 and 5, respectively, from public disclosure.
As Attachments 3 and 5 contain information proprietary to Westinghouse Electric Company, LLC (Westinghouse), they are each supported by an affidavit signed by Westinghouse, the owner of the information.
The affidavits set forth the basis for which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of§2.390 of the Commission's' regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commission's regulations.
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Page 2 of 2 Correspondence with respect to the copyright or proprietary aspects of items in the response to the RAI question in Attachment 3 and in WCAP- 17070-P in Attachment 5 of this letter or the supporting Westinghouse affidavits should reference CAW- 11-3173 and CAW- 11-3194, respectively, and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, Suite 428, 1000 Westinghouse Drive, Cranberry Township, PA 16066.The Turkey Point Plant Nuclear Safety Committee (PNSC) has reviewed the proposed license amendments.
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the State Designee of Florida.This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2010-113
[Reference 1].This submittal contains no new commitments and no revisions to existing commitments.
Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto, Licensing Manager, at (305) 246-7327.I declare under penalty of perjury that the foregoing is true and correct.Executed on June ?/.,2011.Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachments cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Resident Inspector, Turkey Point Nuclear Plant Mr. W. A. Passetti, Florida Department of Health (w/o Attachments 3 and 5)
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2011-190 Attachment 1 Page 1 of 8 Turkey Point Units 3 and 4 RESPONSE TO NRC RAI REGARDING EPU LAR NO. 205 AND EICB INSTRUMENTATION AND CONTROLS ISSUES (NON-PROPRIETARY)
ATTACHMENT 1
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Attachment 1 Page 2 of 8 Response to Request for Additional Information The following information is provided by Florida Power and Light Company (FPL) in response to the U. S. Nuclear Regulatory Commission's (NRC) Request for Additional Infornation (RAI).This information was requested to support License Amendment Request (LAR) 205, Extended Power Uprate (EPU), for Turkey Point Nuclear Plant (PTN) Units 3 and 4 that was submitted to the NRC by FPL via letter (L-2010-1
- 13) dated October 21, 2010 [Reference 1].By email from the NRC Project Manager (PM) dated May 27, 2011 [Reference 2], additional information regarding instrumentation and controls issues was requested by the NRC staff in the Instrumentation and Controls Branch (EICB) to support the review of the EPU LAR [Reference 1].The RAI consisted of one question with two parts, the first part involving OTAT and OPAT calculations and the second part involving the setpoint safety margin calculation per the WCAP-17070-P methodology.
The RAI question and the FPL response are documented below.EICB-1.2.1 TSTF-493, Option A "with changes to setpoint values" requires the licensee to provide summary calculations for each type of setpoint being revised, including Limiting Trip Setpoint (LTSP), Nominal Trip Setpoint (NTSP), Allowable Value (AV), As-Found Tolerance (AFT), and As-Left Tolerance (ALT). It is not clear to the NRC staff how the following two setpoint calculations, as explained in your letter dated April 22, 2011, are performed.
- item 2 Overtemperature AT* item 3 Overpower AT a. Provide the analytical limit (AL) values with units, sample setpoint calculations and/or diagrams for the above two setpoints.
The convention for the Overtemperature (OTAT) and Overpower (OPAT)setpoints and safety analysis limits in the Westinghouse analysis and setpoint methodology are unit-less values. They are a ratio of Rated Thermal Power (RTP) because these are not discrete value trip functions, but are variable trip functions (as noted in Chapter 14 of the UFSAR) and are normalized to 100 %RTP conditions.
However if units were to be assigned they would be percent RTP units. The following example calculations are shown using information provided in WCAP -17070-P Rev. 0.Overtemperature AT: From Table 3-2: Page 23, channel statistical allowance (CSA) = [ ]a,c Page 21, AT span = 159.4 % RTP From Table 3-12: Page 45, K1 (nominal)
= 1.31 Page 45, Ki (safety analysis limit)' = [ ]a~c Page 46, Total Allowance (TA) = 8.8 % AT span From Table 3-11: Margin = [ I ac 0 Example: Calculations similar to the examples found on page 16 of the WCAP assuming the values above were presented in percent RTP:
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Attachment I Page 3 of 8 K1 Nominal = 131 % RTP K1 safety analysis limit = [a TA = [ ]a,c CSA = [ ]ac Margin = [ ]a,c.............................................................................................
..................................
]ac Overpower AT: From Table 3-3: Page 26, channel statistical allowance (CSA) = [ ]a.,c Page 25, AT span = 159.4 % RTP From Table 3-13: Page 47, K4 (nominal)
= 1.10 Page 47, K4 (safety analysis limit)1 = [ ]'Page 47, Total Allowance
= 3.8 % AT span From Table 3-11: Margin = [ ]a,c* Example: Calculation similar to the examples found on page 16 of the WCAP assuming the values above were presented in percent RTP: K4 Nominal = 110 % RTP K4 safety analysis limit = [r, TA= [ ]a,c CSA = [ ]ac Margin = [ ]ax.............................................................................................
..........................
]ac As shown here, the calculations provide the same results -only the units change. These results are consistent with the TSTF-493 requirements and NRC expectations regarding its implementation.
Notes:] The safety analysis limits are shown in L 2010-113 Attachment 4, Section 2.4.1.2.3.2.3, Pages 2.4.1-15 and 2.4.1-16.
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Attachment 1 Page 4 of 8 b. While calculating the setpoint safety margin, the licensee did not include the ALT value in the calculation.
For example, item 1 "Power Range Neutron Flux -High" in Table 3-12: AL = 115% RTP NTS = 109% RTP CSA = 5.52% RTP (4.6% Span with Span = 120%RTP)ALT = 0.6% RTP (0.5% Span with Span = 120%RTP)NTS + ALT + CSA = 109%RTP + 0.6%RTP + 5.52%RTP = 115.12%RTP, which is greater than AL (115%RTP).
Therefore, the actual trip can result in the potential for the instrument channel to be operated beyond its analytical limit (AL) and there is no safety margin. Explain why the ALT is not included in your safety margin calculation for each proposed setpoint change.The basic Westinghouse methodology uses a Square Root Sum of the Squares (SRSS) approach, as defined by equation 2.1 on page 3 of WCAP-17070-P, Rev. 0. With this approach the various uncertainty terms are determined to be either two-sided, random terms that are combined into sets of independent terms within the SRSS or are treated as bias terms outside of the SRSS. In the Westinghouse methodology, the Rack Calibration Accuracy (RCA) term is defined as the two-sided, random as left calibration tolerance (ALT), defined in the plant surveillance procedures.
Therefore, the RCA term is the ALT. For calculation purposes, the RCA/ALT term is defined as the maximum permitted procedure tolerance value. However, in actual practice the magnitude is typically much less, 1/4 th to 1/3 rd the allowed tolerance on a 95/95 basis and demonstrates the characteristics of a truncated Logistic or Laplace distribution (very centralized).
The magnitude and the random characteristics of this term are confirmed by evaluations of plant data.The following should be noted about the check equation defined in the part b question above; NTS + ALT + CSA.1. CSA is a 95/95 statistical combination of the uncertainties, as identified in equation 2.1 of WCAP-17070-P.
- 2. Equation 2.1 includes the independent, two-sided, random quantity (RMTE+ RCA)2.3. RCA is summed with RMTE due to the inherent dependent nature of the two terms.4. ALT = RCA, thus the check equation, NTS + ALT + CSA = NTS + RCA +CSA. Thus, the check equation treats RCA twice: a. Once, as a two-sided, random term within CSA.b. Once, as a one-sided, systematic term, a presumption of the summation.
Thus the check equation is overly conservative for the following reasons: 1. It treats the RCA term twice.2. It presumes the RCA term is systematic and one-sided, contrary to supporting plant data.
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Attachment 1 Page 5 of 8 3. It does not recognize the conservative treatment in equation 2.1 (dependent with RMTE).4. It does not recognize the conservative nature of the typical RCA probability distribution function characteristics, supported by typical plant data.5. Treatment of the check equation is deterministic rather than statistical in nature.In addition, to presume a simple deterministic evaluation ignores the basic SRSS assumption that other terms may be in the opposite direction or at lower than assumed magnitudes that can offset the presumed RCA/ALT magnitude and direction.
For example, RCA/ALT could be at its maximum allowed value, but the temperature effect for the process racks could be in the opposite direction at the same time, or the calorimetric normalization uncertainty is less than 2 % RTP, an extremely likely occurrence with plants utilizing ultrasonic feedwater flow measurements and a very likely occurrence with plants utilizing a venturi for feedwater flow measurement.
It should be recognized that anytime a deterministic evaluation is compared to an SRSS statistical evaluation, the magnitude of margin determined for each evaluation will be different, with the deterministic margin always less than the statistical margin. Thus, it would be expected that there would be instances where positive margin is demonstrated with a statistical evaluation, but not for a deterministic evaluation.
Relative to the probability of exceeding a safety analysis limit (SAL), the Westinghouse uncertainty calculations are performed in a manner such that the overall result is determined at a 95 % probability, at a 95 % confidence level.However, it is again noted that Westinghouse evaluations of RCA (ALT) and RD (AFT) data for multiple plants, has demonstrated the conservative nature of the uncertainty calculation assumptions for these terms. Therefore, it is suggested that the Westinghouse calculations do result in a very low probability that the SAL will be exceeded and do meet the intent of RIS 2006-17 to provide ALT and AFT values that result in meaningful criteria by which to judge equipment operability based on expected performance.
The example provided for Power Range Neutron Flux -High is the only case where the RCA/ALT term when added as a deterministic value will result in the presumption that the safety analysis limit could be exceeded.
All other functions in WCAP- 17070-P have sufficient margin to pass the NRC check calculation.
This is demonstrated by the margin as noted by Table 3-11 being larger than the RCA term. To alleviate any concern regarding the check calculation margin for the Power Range Neutron Flux-High trip, FPL has elected to change the nominal trip setpoint from 109 % RTP to 108 % RTP. Therefore using the check calculation approach the result of the nominal trip setpoint change would be 108 % RTP + []C which is less than the safety analysis limit of 115 % RTP.With the change to the nominal trip setpoint, the following values in WCAP-17070-P, Rev. 0 and responses to previous NRC RAIs provided via FPL letter L-2011-005
[Reference 3] will also change.0 From letter L-2011-005
[Reference 3]:
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2011-190 Attachment 1 Page 6 of 8 Table 3-12 Nominal Trip Setpoint will change from 109 % RTP to 108 % RTP.Table 3 -12 Total Allowance will change from 5.0 % span to 5.8 % span.Table 3-12 Allowable Value will change from 109.6 % RTP to 108.6 % RTP.Table 3-12 Margin will change from [ I ac 0 Example: Calculation for TA found on page 16 of WCAP -17070-P Rev. 0: SAL NTS TA 115 % RTP-108 % RTP 17 % RTP I If the instrument span = 120 % RTP, then: TA = (7 % RTP) * ( 100 % span) = 5.8 % span (120 % RTP)* Example: Calculation from FPL letter L-2011-005
[Reference 3] for Power Range Neutron Flux -High will change to: Allowable Value Determination ALT/AFT Determination NTS = 108 % RTP SPAN = 120 % RTP RCA = 0.6 % RTP (0.5% span)SAL= 115 % RTP AV = NTS + RCA AV = 108 % RTP + 0.6 % RTP AV = 108.6 % RTP NTS = 108 % RTP SPAN = 120 % RTP RCA = 0.6 % RTP (0.5% span)ALT = +/- RCA ALT = 108.6% RTP (+ 0.5% span)ALT = 107.4% RTP (- 0.5% span)AFT = +/- RCA AFT = 108.6% RTP (+ 0.5% span)AFT = 107.4% RTP (- 0.5% span)Revision 1 of WCAP-17070-NP is provided in Attachment 2.A discussion of the proposed TS changes for this parameter (Power Range Neutron Flux High Setpoint) is provided on the following page.
Turkey Point Units 3 and 4 L-2011-190 Docket Nos. 50-250 and 50-251 Attachment 1 Page 7 of 8 Technical Specification Table 2.2-1 RTS Instrumentation Trip Setpoints Function 2a, Power Range Neutron Flux -High Current TS ALLOWABLE VALUE TRIP SETPOINT 2. Power Range, Neutron Flux a. High Setpoint < 112.0% RTP** < 109.0% RTP**Proposed TS ALLOWABLE VALUE TRIP SETPOINT 2. Power Range, Neutron Flux a. High Setpoint < 108.6% RTP ** 108.0%(a),(b) of RTP**Basis for the Change: The EPU accident and transient analyses determined that for some accidents the Safety Analysis Limit (SAL) for the Power Range Neutron Flux -High reactor trip would need to be reduced from the current 118% to 115% Rated Thermal Power (RTP).Accordingly, the current Nominal Trip Setpoint (NTS) of 109% RTP will decrease to 108% RTP in order to accommodate the new SAL limit and still maintain sufficient margin. Similarly, the Allowable Value (AV) will decrease from 112.0% RTP to 108.6% RTP in order to comply with the methodology as described in WCAP-1 7070-P. The trip setpoint is considered a nominal value (i.e., expressed as a value without inequalities) for purposes of Channel Operability Test (COT) and Channel Calibration.
Notes (a) and (b) are inserted here as well as in Table 4.3-1 to enhance the ability of the operator to readily recognize the trip functions affected by TSTF-493.See Figure 1 for TS Table 2.2-1 indicated changes. Associated TS Bases remain unchanged.
References
- 1. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request No. 205: Extended Power Uprate (EPU)," (TAC Nos. ME4907 and ME4908), Accession No. ML103560169, October 21, 2010.2. Email from J. Paige (NRC) to T. Abbatiello (FPL), "Turkey Point EPU -Instrumentation and Controls (EICB) Request for Additional Information
-Round 1.2 (Part 2)", Accession No. ML11147A056, May 27, 2011.3. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2011-005), "Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Instrumentation and Control (I&C) Issues -Round I," Accession No. ML1 10330190, January 28, 2011.
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 m.-u 01 L-2011-190 Attachment 1 Page 8 of 8 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Z Cn W FUNCTIONAL UNIT 1. Manual Reactor Trip 2. Power Range, Neutron Flux a. High Setpoint b. Low Setpoint 3. Intermediate Range, Neutron Flux 4. Source Range, Neutron Flux 5. Overtemperature AT 6. Overpower AT 7. Pressurizer Pressure-Low
- 8. Pressurizer Pressure-High
- 9. Pressurizer Water Level-High
- 10. Reactor Coolant Flow-Low 11. Steam Generator Water Level Low-Low m Z m Z--I z ALLOWABLE VALUE s 442% of RTP** 28.0% of RTP** 31.0% of RTP**< 1.4 X 10 5 cps See Note 2 See Note 4> 1817 psig< 2403 psig_992.2% of instrument span>8",% of loop design flow*> -46% of narrow range instrument span TRIP SETPOINT N.A. 25% of RTP- 25% of RTP--< 10 5 cps See Note 1(a), (b)for K, See Note 3 (a), (b) for K 4> 1835 psig-2385 psig92% of instrument span E190% of loop: design flow 169o r3-1-% of narrow range instrument span 86,900* Loop design flow = SOQQ gpm RTP = Rated Thermal Power Figure 1