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MONTHYEARML1022200222010-08-0505 August 2010 Fuel Storage Criticality Analysis Project stage: Request ML1105603352011-02-22022 February 2011 Supplement 1 to Fuel Storage Criticality Analysis Project stage: Request L-2011-401, License Amendment Request No. 207, Fuel Storage Criticality Analysis Supplement 32011-09-22022 September 2011 License Amendment Request No. 207, Fuel Storage Criticality Analysis Supplement 3 Project stage: Supplement L-2011-390, Supplement 2 to the Extended Power Uprate License Amendment Request No. 205 Regarding New and Spent Fuel Storage Requirements2011-11-0909 November 2011 Supplement 2 to the Extended Power Uprate License Amendment Request No. 205 Regarding New and Spent Fuel Storage Requirements Project stage: Supplement L-2011-541, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 2052011-12-22022 December 2011 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 Project stage: Request L-2012-050, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and New Fuel Storage Requirements2012-02-15015 February 2012 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and New Fuel Storage Requirements Project stage: Request L-2012-081, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Spent Fuel Pool Storage Requirements2012-02-23023 February 2012 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Spent Fuel Pool Storage Requirements Project stage: Request L-2012-130, Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications2012-09-14014 September 2012 Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications Project stage: Request ML13077A0052013-03-15015 March 2013 NRR E-mail Capture - Turkey Point, Units 3 and 4-Acceptance Review Regarding License Amendment Request 217 Regarding Administrative Changes to the Technical Specifications Project stage: Acceptance Review ML13137A4602013-05-23023 May 2013 Request for Additional Information Regarding License Request No. 217 and Changes to Operating License Conditions and Technical Specifications Project stage: RAI L-2013-294, Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications2013-10-23023 October 2013 Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications Project stage: Supplement L-2014-070, Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications2014-03-11011 March 2014 Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications Project stage: Supplement ML13329A0922014-06-13013 June 2014 Issuance of Amendments Regarding Operating License Conditions and Technical Specifications Project stage: Approval L-2015-045, License Amendment Request No. 216 - Transition to 10 CFR 50.48(c) - NFPA 805Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2015-02-18018 February 2015 License Amendment Request No. 216 - Transition to 10 CFR 50.48(c) - NFPA 805Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request 2012-02-23
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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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Text
Florida Power & Light, 9760 S.W. 344 St. Homestead, FL 33035 FEB 1 5 2012 L-2012-050 FPL* . 10 CFR 50.90 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 Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and New Fuel Storage Requirements
References:
(1) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request for Extended Power Uprate (LAR 205)," Accession No. ML103560169, October 21, 2010.
(2) J. Paige (U. S. Nuclear Regulatory Commission) to M. Nazar (FPL), "Turkey Point Nuclear Plant, Units 3 and 4 - Issuance of Amendments Regarding Fuel Criticality Analysis (TAC Nos. ME4470 and ME4471)," Accession No. ML11216A057, October 31, 2011.
(3) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2011-390), "Supplement 2 to the Extended Power Uprate License Amendment Request No. 205 Regarding New and Spent Fuel Storage Requirements," Accession No. ML11318A284, November 9, 2011.
(4) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2011-541), "Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205," Accession No. ML11362A356, December 22, 2011.
(5) Email from J. Paige (NRC) to S. Hale (FPL), "RE: SE Open Item on New Fuel Storage Area,"
February 13, 2012.
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 (PTN) 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).
On October 31, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendments 246 and 242 to Renewed Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Units 3 and 4, respectively, addressing both new and spent fuel storage requirements [Reference 2].
By letter L-2011-390 dated November 9, 2011 [Reference 3], FPL revised the originally proposed EPU changes to Technical Specification 5.5.1 Fuel Storage - Criticality to account for the NRC's issuance of Amendments 246 and 242 for Turkey Point Units 3 and 4. This reduced the scope of the remaining TS changes to only TS 5.5.1.1 .d that revises the maximum fuel enrichment loading to 5.0 wt% U-235 and TS 5.5.1.2.b that revises the existing new fuel storage requirements.
AO)D
Turkey Point Units 3 and.4 L-2012-050 Docket Nos. 50-250 and 50-251 Page 2 of 2 On November 18, 2011, the NRC Project Manager (PM) informed FPL that the Reactor Systems Branch (SRXB) Technical Reviewer questioned the language used in the proposed change to TS 5.5.1.2.b. Specifically, the reviewer questioned the inclusion of the parenthetical statement "or an equivalent amount of other burnable absorber.'" On December 22, 2011, FPL provided its response with documentation to support this language, in the proposed TS to the NRC via letter L-2011-541 [Reference 4]. Subsequent review by the SRXB Technical Reviewer resulted in several more questions regarding this issue as documented in. an email from the NRC PM to FPL on February 13, 2012 [Reference 5] and indicated that FPL's position would not be acceptable to the staff. Therefore, in consideration of the schedule constraints, FPL proposes to eliminate the parenthetical statement from TS 5.5:.1.2.b in order to preclude further regulatory review and comment resolution cycles on this issue. FPL's response is provided in Attachment 1 to this letter.
The Turkey Point Plant Nuclear Safety Committee (PNSC) has reviewed the proposed TS change, This proposed TS change 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.eonmmitments.
In accordance with 1Q CFR 50.91(b)(1), a copy of this letter is being forwarded to the State Designee of Florida.
Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto, Licensing Manager, at (305) 246-7327.
1.declare under penalty of perjury that the foregoing is true and correct.
Executed on February /5-, 2012.
Very truly yours, Michael Kiley Site Vice President.
Turkey Point Nuclear Plant Attachment 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.
Turkey Point Units 3 and 4 L-2012-050 Docket Nos. 50-250 and 50-251 Attachment I Page 1 of 5 Turkey Point Units 3 and 4 RESPONSE TO NRC REACTOR SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST NO. 205 AND NEW FUEL STORAGE REQUIREMENTS ATTACHMENT 1
Turkey Point Units 3 and 4 L-2012-050 Docket Nos. 50-250 and 50-251 Attachment I Page 2 of 5 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 Information (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-2010-113) dated October 21, 2010 (Reference 1).
On October 31, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendments 246 and 242 to Renewed Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Units 3 and 4, respectively, addressing both new and spent fuel storage requirements (Reference 2).
By letter L-2011-390 dated November 9, 2011 (Reference 3), FPL revised the originally proposed EPU changes to Technical Specification 5.5.1 Fuel Storage - Criticality to account for the NRC's issuance of Amendments 246 and 242 for Turkey Point Units 3 and 4. This reduced the scope of the remaining TS changes to only TS 5.5.1.1 .d that revises the maximum fuel enrichment loading to 5.0 wt% U-235 and TS 5.5.1.2.b that revises the existing new fuel storage requirements.
On November 18, 2011, the NRC Project Manager (PM) informed FPL that during review of the supplemental submittal the Reactor Systems Branch (SRXB) Technical Reviewer questioned the language used in the proposed change to TS 5.5.1.2.b. Specifically, the reviewer questioned the basis for the inclusion of the parenthetical statement "or an equivalent amount of other burnable absorber" and requested that the parenthetical statement be deleted. The basis for the NRC's request was apparently that the criticality analysis provided in WCAP-17094-P, Revision 3, "Turkey Point Units 3 and 4 New Fuel Storage Rack and Spent Fuel Pool Criticality Analysis,"
dated February 2011 (Reference 4) did not discuss how an equivalent amount of another burnable absorber would be determined. Also, there was nothing in the analysis about how a different absorber would affect the criticality analysis for both fresh and depleted fuel.
On November 22, 2011, FPL informed the NRC PM during the weekly telephone call that it intended to keep the parenthetical statement as written and indicated that further documentation would be provided to support the technical basis for the change. FPL provided the supporting documentation to the NRC via letter L-2011-541 [Reference 5] on December 22, 2011. Subsequent review by the SRXB Technical Reviewer resulted in several more questions regarding this issue as documented in an email from the NRC PM to FPL on February 13, 2012 [Reference 6] which indicated that FPL's position would not be acceptable to the staff. Therefore, in consideration of the schedule constraints, i.e., Advisory Committee on Reactor Safeguards (ACRS) subcommittee hearing on February 24, 2012 and the NRC staff's Draft Safety Evaluation Report, FPL proposes to simply eliminate the parenthetical statement from TS 5.5.1.2.b in order to preclude any further regulatory review and comment resolution cycles on this issue. FPL's response is provided below.
Response
FPL letter L-2011-390 dated November 9, 2011 (Reference 3) supplemented the EPU application by a proposed revision to TS 5.5.1 of the TS Amendments 246 and 242, which were approved on October 31, 2011 (Reference 2). Specifically, the supplement proposed a revision to TS 5.5.1.1 .d and 5.5.1.2.b to increase the maximum allowable enrichment in the Spent Fuel Pool (SFP) storage racks and the New Fuel Storage Area (NFSA) from 4.5 wt% 23 5U to 5.0 wt% 235U. The proposed change to TS 5.5.1.2.b required that storage of fresh fuel assemblies in the NFSA with nominal enrichments greater than 4.5 wt% 2 35U have 16 or more Integral Fuel Burnable Absorber (IFBA)
Turkey Point Units 3 and 4 L-2012-050 Docket Nos. 50-250 and 50-251 Attachment 1 Page 3 of 5 rods or an equivalent amount of other burnable absorber. As the staff has indicated that the parenthetical statement will not be acceptable without further substantiating analyses, FPL proposes to credit only IFBA rods in the NFSA and to delete the previously proposed parenthetical phrase "or an equivalent amount of other burnable absorber." A description of the proposed TS change is provided below.
Changes to the PTN Technical Specifications Technical Specification 5.5.1 Fuel Storage - Criticality Approved TS (Proposed TS per L-2011-390 dated November 9, 2011) 5.5.1.2 The racks for new fuel storage are designed to store fuel in a safe subcritical array and shall be maintained with:
- b. Fuel assemblies placed in the New Fuel Storage Area shall contain no more than a nominal 4.5 weight percent of U-235 if the assembly contains no burnable absorber rods and no more than 5.0 weight percent of U-235 if the assembly contains at least 16 IFBA rods (or an equivalent amount of other burnable absorber).
Revised TS 5.5.1.2 The racks for new fuel storage are designed to store fuel in a safe subcritical array and shall be maintained with:
- b. Fuel assemblies placed in the New Fuel Storage Area shall contain no more than a nominal 4.5 weight percent of U-235 if the assembly contains no burnable absorber rods and no more than 5.0 weight percent of U-235 if the assembly contains at least 16 IFBA rods.
Basis for the Chanize:
Integral burnable absorbers credited in the NFSA will be limited to IFBA rods. The proposed parenthetical phrase "or an equivalent amount of other burnable absorber" in TS 5.5.1.2.b will be deleted in order to preclude further regulatory review and comment resolution cycles on this issue and to facilitate the NRC staff's review and approval of the proposed TS change and EPU LAR No. 205.
See attached TS 5.5.1.2.b (TS page 5-5) markup. The TS change previously proposed for TS 5.5.1.1.d under Reference 3 is also shown in the markup.
Turkey Point Units 3 and 4 L-2012-050 Docket Nos. 50-250 and 50-251 Attachment I Page 4 of 5 DESIGN FEATURES 5.5 FUEL STORAGE 5.5.1 CRITICALITY 5.5.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. A k. less than 1.0 when flooded with unborated water, which includes an allowance for biases and uncertainties as described in UFSAR Chapter 9.
- b. A I* less than or equal to 0.95 when flooded with water borated to 500 ppm, which includes an allowance for biases and uncertainties as described in UFSAR Chapter 9.
- c. A nominal 10.6 inch center-to-center distance for Region I and 9.0 inch center-to-center distance for Region IIfor the two region spent fuel pool storage racks. A nominal 10.1 inch center-to-center distance in the east-west direction and a nominal 10.7 inch center-to-center distance in the north-south direction for the cask area storage rack. ,'JE
- d. A maximum enrichment loading for fuel assemblies of 4.5 weight percent of U-235.
- e. No restriction on storage of fresh or irradiated fuel assemblies in the cask area storage rack.
- f. Fresh or irradiated fuel assemblies not stored in the cask area storage rack shall be stored in accordance with Specification 5.5.1.3.
- g. The Metamic neutron absorber inserts shall have a minimum certified 1%8 areal density greater than or equal to 0.015 grams "'Blcmi.
5.5.1.2 The racks for new fuel storage are designed to store fuel in a safe subcritical array and shag be maintained with:
- a. A nominal 21 inch center-to-center spacing to assure keg equal to or less than 0.98 for optimum moderation conditions and equal to or less than 0.95 for fully flooded conditions.
- b. Fuel assemblies placed in the New Fuel Storage Area shall contain noor,ne thn 4.5 wcight no more than a nominal 4.5 weight percent of U-235 if the assembly contains no burnable absorber rods and no more than 5.0 weight percent of U-235 if the assembly contains at least 16 IFBA rods.
TURKEY POINT-UNITS 3 &4 5-5. AMENDMENT NOS. AND
Turkey Point Units 3 and 4 L-2012-050 Docket Nos. 50-250 and 50-251 Attachment I Page 5 of 5 References
- 1. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request for Extended Power Uprate (LAR 205)," Accession No. ML103560169, October 21, 2010.
- 2. J. Paige (U. S. Nuclear Regulatory Commission) to M. Nazar (FPL), "Turkey Point Nuclear Plant, Units 3 and 4 - Issuance of Amendments Regarding Fuel Criticality Analysis (TAC Nos. ME4470 and ME4471)," Accession No. ML11216A057, October 31, 2011.
- 3. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2011-390), "Supplement 2 to the Extended Power Uprate License Amendment Request No. 205 Regarding New and Spent Fuel Storage Requirements," Accession No. ML11318A284, November 9, 2011.
- 4. WCAP-17094-P, Revision 3, "Turkey Point Units 3 and 4 New Fuel Storage Rack and Spent Fuel Pool Criticality Analysis," February 2011.
- 5. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2011-54 1), "Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205," Accession No. ML11362A356, December 22, 2011.
- 6. Email from J. Paige (NRC) to S. Hale (FPL), "RE: SE Open Item on New Fuel Storage Area," February 13, 2012.