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Category:Federal Register Notice
MONTHYEARML23200A1912023-08-31031 August 2023 Federal Register Notice: Turkey Point Units 3 & 4 Subsequent License Renewal Draft Site-Specific Environmental Impact Statement ML22268A0022022-10-0404 October 2022 Federal Register Notice: Turkey Point Units 3 & 4 Subsequent License Renewal Application Supplement Environmental Review ML22200A0322022-07-20020 July 2022 Federal Register Notice - Florida Power & Light Company Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML22004A2302022-01-20020 January 2022 FRN - Notice of Issuance of COVID-19 Exemptions Issued in December 2021 ML20323A0222020-11-12012 November 2020 11-12-20 Petitioners Supplemental Appendix (DC Cir.)(Case No. 20-1026) ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20097C7282020-04-0909 April 2020 Letter to Florida Power & Light Company with Public Notice of Application for Amendment to Facility Operating License Deferral of Steam Generator Inspection ML20097C7842020-04-0909 April 2020 Public Notice License Amendment Request for Deferral of Steam Generator Inspection ML19295E4272019-10-25025 October 2019 FRN - Notice of Availability of the Final Plant-Specific Supplemental 5, Second Renewal, to the Generic Environmental Impact Statement Regarding Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19007A0222019-04-0101 April 2019 FRN - Notice of Availability of the Draft Supplement 5, Second Renewal, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML18351A0022019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 NRC-2018-0287, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/20192019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 ML18297A2252018-12-18018 December 2018 License Amendment Application; Opportunity to Comment, Request a Hearing and Petition for Leave to Intervene; Order Imposing Procedures for Florida Power & Lighting Company; Turkey Point Nuclear Generating Units Nos. 3 & 4 (Docket Nos.50-25 ML18297A2012018-12-18018 December 2018 Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing & Order Imposing Procedures ML18109A5172018-05-16016 May 2018 Federal Register Notice - Notice of Intent to Prepare an Environmental Impact Statement for the Turkey Point SLR ML18058A7652018-04-19019 April 2018 Federal Register Notice for Issuance of Combined Licenses and Record of Decision for Turkey Point Units 6 and 7 ML18059A1742018-04-19019 April 2018 Federal Register Notice for Notice of Intent to Enter Into a Modified Indemnity Agreement with FPL for Turkey Point Units 6 & 7 NRC-2018-0015, CSP AOT Extension Individual 30-day Proposed FRN2018-01-23023 January 2018 CSP AOT Extension Individual 30-day Proposed FRN ML17360A0032018-01-23023 January 2018 Letter, Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination ML17360A0042018-01-23023 January 2018 CSP AOT Extension Individual 30-day Proposed FRN ML16271A0922016-09-28028 September 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 11, 2016 ML16131A7952016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 20162016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML15231A8382015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 NRC-2015-0204, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 20152015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 ML15204A2792015-07-27027 July 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 4, 2015 ML15120A2272015-05-0101 May 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 12, 2015 NRC-2015-0104, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register2015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register ML15106A9162015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register NRC-2014-0262, Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI2014-12-11011 December 2014 Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Ja ML14336A4122014-12-11011 December 2014 Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Ja NRC-2014-0181, Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393)2014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393) ML14209A0312014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit ML14177A6452014-06-27027 June 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations NRC-2014-0008, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures fo2014-01-22022 January 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Add ML14007A2192014-01-22022 January 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Add ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13014A5232013-01-16016 January 2013 Federal Register Notice - Notice of Consideration for Application of Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination NRC-2013-0015, Federal Register Notice - Notice of Consideration for Application of Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination2013-01-16016 January 2013 Federal Register Notice - Notice of Consideration for Application of Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination ML13014A5052013-01-16016 January 2013 Letter and FRN - Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (TAC Nos. ME9500 and ME9501 ML12233A6272012-08-29029 August 2012 G20120317/EDATS: OEDO-2012-0273 - 2.206 Acknowledgement Letter to T. King on St. Lucy Units 1 and 2, and Turkey Point Units 3 and 4 ML12233A6342012-08-29029 August 2012 G20120317/EDATS: OEDO-2012-0273 - Federal Register Notice - Receipt of Request for Action Regarding St. Lucie Units 1 and 2, and Turkey Point Units 3 and 4 ML12074A2482012-03-27027 March 2012 Transmittal Letter - Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate ML12074A2512012-03-27027 March 2012 Federal Register Notice - Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML11270A3792011-11-0404 November 2011 Transmittal Letter - Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate 2023-08-31
[Table view] 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
[Table view] Category:Regulatory Guide
MONTHYEARML0133304361975-11-26026 November 1975 Issuance of Amendments 13 and 12, Incorporating Into Turkey Point Nuclear Generating Units 3 and 4 TS Changes to Reporting Requirements 1975-11-26
[Table view] Category:Safety Evaluation
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 ML22307A1152022-11-28028 November 2022 Authorization of Relief Request No. 10 Part II Related to Repair of Intake Cooling Water Discharge Piping (EPID L-2022-LLR-0032) (Non-Proprietary) 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 ML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping 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) ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping 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 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques 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 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 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 ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18071A0802018-04-0606 April 2018 Correction to Safety Evaluation for Amendment Nos. 278 and 273 Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) 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 ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation 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) ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML16335A1952017-02-14014 February 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Pumps ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16279A4552016-10-28028 October 2016 Turkey Point Nuclear Generating Station Units 3 & 4 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) 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 ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML16011A4402016-02-0101 February 2016 Safety Evaluation for Relief Request No. 2 for the Fifth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations of the Regenerative Heat Exchanger Welds (MF6384-MF6385) ML16011A2052016-01-22022 January 2016 Safety Evaluation for Relief Request No. PR-02, for the Fifth 10-Year Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Residual Heat Removal Pumps (CAC Nos. MF6388 & MF6389) ML15350A2032015-12-23023 December 2015 Safety Evaluation for Relief Request No. 16, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A1082015-12-0909 December 2015 Safety Evaluation for Relief Request No. PR-01, for the Fifth 10-Yeaer Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Boric Acid Transfer Pumps ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15271A3252015-10-14014 October 2015 Safety Evaluation for Relief Request No. 1, Revision 1 for Fifth 10-Year Inservice Inspection Interval - Repair of Pressurizer Stainless Steel Heater Sleeve Without Flaw Removal ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses 2024-01-22
[Table view] Category:Technical Paper
MONTHYEARML0133304361975-11-26026 November 1975 Issuance of Amendments 13 and 12, Incorporating Into Turkey Point Nuclear Generating Units 3 and 4 TS Changes to Reporting Requirements 1975-11-26
[Table view] |
Text
NRC PDR SVarga Local PDR CHebron November 26, 75 ORB Reading AESteen Attorney, OELD DEisenhut Docket Nos. ,-250. OI&E (3) ACRS (16) and 50-250' NDube bcc: TBAbernathy BJones (w/4 encls) JRBuchanan J4cGough JSaltzmen, OAT (w/o Tech Specs)
WEIlliott GLear Florida Power and Light Company CParrish AmfN: Dr. Robert B. Uhrig Vice President KRGoller P. 0. Box 013100 SKari (w/o Tech Specs)
Miami, Florida 33101 BScharf EPLicensing er Asst.
Gentlemen: Gent Iemen:TJCart TIe Commission has issued the enclosed Amendment No. 13 to Facility Operating License No. DPR-31 and Amendment No. 12 to Facility Operating License No. DPR-41 for the Turkey Point iNuclear Generating Units 3 and 4.
Those anendments include Change No. 25 to the Technical Specifications, Appendix A, and is in response to your request dated December 20, 1974.
These amendments incorporate into the Turkey Point Nuclear Generating, Units 3 1 4 Technical Specifications changes to the reporting requirements.
Changes to your proposal were necessary to meet our requirements. These have been discussed with your staff. The Technical Specifications are based on Regulatory Guide 1.16, "Reporting of Operating Information Appendix A Technical Specifications", Revision We request that you use the formats presented in the Appendices to Regulatory Guide 1.16, Revision 4, for reporting operating informiation and that you report events of the type described under the section "Events of Potential Public Interest". Instructions for using these reporting formats are contained in Regulatory Guide 1.16 (a copy is enclosed for your use), and AEC report 001-SS-001 titled "Instructions or Preparation of D)ata Bntry Sheets for Licensee Event Report (LER)
File" of which you were previously provided a copy. This report is iodified by umiated instructions dated August 21, 1975 which are enclosed. Co*y requirements are summarized in Regulatory Guide 10.1, "Conpilation of Reporting- Requirements for Persons Subject to NRC Regulations", a copy of which is also enclosed. This guide will assist youl in identifying reports that arc required by the Con-mission's regulations set Forth in Title 10 Code of Federal Regulations but are not]L containedl
..reuain in your Tec']Jical Specifications. Reports that.haare fCJic.at.o required by the regulations have not been repeateil in your Technical St ecifi cions.
C'ie*s or tne related Safety Evaluation and the Federal Register Notice also are enclosed.
Sincerely, OFFICE*-.
OT,
, " al"'r its'h'"7 5........ .. .. ..! . . y . . ........I-G -!e -ar ..., ... ,.................-t
................ I..........
o A-E. 024 U G OperNMENg Reactors Branch #3 Form AEC-318 (Rev. 9-53) AECM 0240 *U.S. GOVERNMENT PRINTiNG OFFICE: 1974.2128-IS6
Enclosures:
- 1. Amendments Nos. 13 and 12
- 2. Regulatory Guide 1.16
- 3. Updated Instructions
- 4. Regulatory Guide 10.1
- 5. Safety Evaluation
- 6. Federal Register Notice cc w/encls:
Mr. Jack R. Newman, Esquire Lowenstein, Newman, Reis & Axelrad 1025 Connecticut Avenue, N. W.
Suite 1214 Washington, D.C. 20036 Environmental & Urban Affairs Library Florida International University Miami, Florida 33199 Mr. Ed Maroney Bureau of Intergovernmental Relations 725 South Bronough Street Tallahassee, Florida 32304 OFFICE*" I I I I CSrmA TA - .1 ............................................ .............................................. ............................................. .............................................. .............................................. ..................... . ................
wnit AE-318 (RevT. 9-53) ALEC*[ 0240 "*u. S. GOVERNMFNT PRINTING OFFICE: 1974-526-166
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555
'FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3" AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 13 License No. DPR-31
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power & Light Company (the licensee) dated December 20, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulation 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 Co=mission's regulations; and 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.
-2
- 2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-31 is hereby amended to read as follows:
"(B) Technical Specifications The Technical Specificatioils contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 25"
- 3. This license amendment is effective 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fr George Lear, Chief Operating Reactors Branch #3 Division of Reactor Licensing
Attachment:
Change No. 25 Technical Specifications Date of Issuance: November 26, 1975
UNITED STATES
'CLEAR REGULATORY COMMiSSION*.
WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. DPR-41
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power & Light Company (the licensee) dated December 20, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth inli0 CFR Chapter 1; 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 Commission's regulations; and 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.
- 2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-41 is hereby amended to read as follows:
"(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 25"
- 3. This license amendment is effective 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY CO'4IISSION George Lear, Chief Operating Reactors Branch #3 Division of Reactor Licensing
Attachment:
Change No. 25 Technical Specifications Date of Issuance: November 26, 1975
ATTACIMENT TO LICENSE AIMENDMENTS NOS. 13& 12 CHANGE NO. 25 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-31 & DPR-41 DOCKETS NOS. 50-250 AND 50-2SI Replace page i, page ii, page 1-5, page 6-11, page 6-14, and pages 6-16 through 6-27 with the attached revised pages.
TAB LE C: CC' 73..
Section Title lage TECINICAL SPECIFICATIONS 1 DEFINITIONS 1-1 1.1 Safety LLits I-i 1.2 Limiting Safety System Settings 1-i 1.3 Limiting Conditions for Operation 1-.
1.4 Operable 1-1 1.5 Containment Integrity 1-2 1.6 Protective Instruzentation Logic 1-2 1.7 Instrumentation Surveillance 1-3 1.8 Shutdown 1-3 1.9 Power Operation 1-4 1.10 Refueling Operation 1-4 1.11 Rated Power 1-4 1.12 Thermal power 1-4 1.13 Design Power 1-4 1.14 (Deleted) iS-2S 1.15 Power Tilt 1-S 1.16 Interim Limits 1-6 1.17 Low Power Physics Tests 1-6 2 SAFETY LI'ITS AND LIMITIXG SAFETY SYSTEM* SETTINGS 2.1-1 2.1 Safety Limit, Reactor Core 2.1-1 2.2 Safety Limit, Reactor Coolant System Pressure 2.2-1 2.3 Limiting Safety System Settings, Protective Instrm*entation 2.3-1 3 LIMITING CONDITIONS FOR OPERATION 3.1-1 3.1 Reactor Coolant System 3.1-1 Operational Components 3.1-1 Heat Up and Cool Dow-n 3.1-2 Leakage 3.1-4 Maximum Reactor Coolant Activity 3.1-5 Reactor Coolant Chemistry 3.1-6 3.2 Control Rod and Power Distribution Limits 3.2-1 Control Rod Insertion Limits 3.2-1 Misaligned Control Rod 3.2-2 Rod Drop Time 3.2-2 Inoperable Control Rods 3.2-2 Control Rod Position Indication 3.2-3 Power Distribution Limits 3.2-3 In-Core Instrumentation 3.2-7 Axi~al Offset Alarms 3.2-8 3.3 Containment 3.3-1 3.4 Engineered Safety Featbres 3.4-1 Safety Injection and MuR Systems 3.4-1 Emergency Containrent Cooling Systems 3.4-3 Emergency Containment Filtering System 3.4-4 Component Cooling System 3.4-4 Intake Cooling h'ater System 3.4-5 3.5 Instrmmentation .3.5-i 3.6 Chemical and Volume Control System 3.6-1 i
TAB~LE OF C0:,-fiI:*'IS (Continu ,
Ti tle FlCCtrical systems 3.7-1 3.8 3.F 3.9 Radioactive'.-'c:iteriais Release 3.0j- 1 Liquid Wastes 3.S-i Gascous '-'astcs 3. 9-21 3.9-3 3.10 3.10-3 3.11 11iscc~cous l oactive l-,vatcrials Soiurccs 3.11-Is 4 4.1-1 4.1 Oper-ov ioxi 1 Sn.f"ty Rve 4.2 Jkcac.Vo Coolanti Systzc, I% Service Is~to 4 .2-)1 4.3 Reactor Co~lant Sy't:t ý Ihrt), 4.3-1 4.4 4.4-1 ln~egrated Lcalac Rate Test - Post Operational 4 .4-1
- Local 1Pc'aetrati on Tosts 4 .4-I Recport oi* Tc:ýtz Results 4.4 -2 ISO) ati on Vl 4 .44- 3 ReSidual IknzRe:ova Systc'.1 4 .4-3 Tenclon ArC11nc End Arnc1oyopgc Concrete Surveillaince 4.4-6 liner Surv'CiM.Incc 4.4-7 4.5 sqýfty 7nT,-j-:ý,n 4I.5S-1 4.6 Elntrgonc~v Cr~rdn irmnnc~t Cool ingz Systemas 4. G-1 Er~'.gecy Cnti~:;c~~tFi) tcrin- and Plost Accidcnt 4.7 Contain;nc'nt Vecnt, Svstc:m^. 4.7-3.
4.8 E~evcmcvPc,,;er Systcrm Pcriodic Tests 4.8-1 4.9 1ai Stanlie atonValves 4.9-1 4.10 Auxi liar-)' cdz ( System' 4.10-1 4.11 Reactivity !xinc.:na) ics 4.11-1 4.12 Iwllirovn-antal R'adiation 'Survey 4.12-1 4.13 Radio,?ct.;vc M'.terlals Sources Surveillance 4.13-1 DESIGN' FElJFU]RES 5.1 Site 5.2 Reactor S.2-1 5.3 Con ta-iirucn t 5.'3-1 S.4 5.*4-1 6 AD.5IN'ISTR!',-f I%-,:- CO:;TrZOLs 6.1-1A 6.1 Responsibil ity 6-1 6.2 Organi zzztioný. 6-1 6.3 Facilitv S t-,f" Qualificat icns 6.4 6-5 Tra inin 6-S 6.5 Rcv~icw., and Audit 6.6 Reportable Occurrence Action 6-5 6.7 6-14 t25 Safety Lirý-.it \'iolaction.
6-14 6.8 Proceduros 6.9 6.14 Reporting Requirements 6-i ii.
1.14 , (Deleted) 25 1.15 POWER TILT The power tilt is the ratio of the maximum to average of the upper out-of-core normalized detector currents or the lower out-of-core mormalized detector currents whichever is greater.
If one out-of-core detector is out of service, the remaining three detectors are to be used to compute the average.
1-5
than a minority--of the quorum shall have line `eesponsibility for operation of the facility.
6.5.2.7 REVII.Y The CNRB shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems and, 2) tests or experiments completed under the pro vision of Section 50.59, 10 CFR, to verify that such actic;s dia not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which in volve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- c. Proposed tests or experiments which involve an unreviewcd safety question as defined in Section 50.59, 10 CFR.
- d. Proposed changes in Technical Specifications or Licenses.
- e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal pro cedures or instructions having nuclear safety significance.
- f. -Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety
- g. All events which are required by regqlations or Technical 125 Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6-11
- RE PCPORI,ABLE OCCUPTi'J-( AC'IIUN, 6.6.1 'The following actions shall be taken in the event of a REPORTABLE . 25
- a. The REPORTABLE OCCUPRENCE shall be reported to the Commission 25 pursuant to the requirements of Section 6i9.
- b. A Reportable Occurrence Report shall be prepared. The report 125 shall be reviewed by the Plant Nuclear Safety Coý=.ittee.
- c. The Reportable Occurrence Report shall be submitted to the CNRB, 25 the Vice President of Power Resources, and the Conu,ission within the time allotted in Section 6.9, 6.7 SAFETY LIMIT VIOLkTION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The provisions of 10 CFR 50.36(c)(i)(i) shall be complied within
.immediately.
- b. The Safety Linit violation shall be reported imnediately to the Commission, the Vice President of Power Resources and to the CNRB.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PINSC. This report shall describe
- 1) applicable circumstances preceding the violation, 2) effects of the violation upon facility components; systems or structures, and 3) corrective action taken to'prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the CNRB, the Vice President of Power Resources and the Commission within ten (10) days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section-5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USNRC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.
6-14
6.9 REPOPlTING REQUIREUfENTS In addition to ti*-_applicable reperting requirc --Ls of Title 10, Code of Federal Regulitions, the follow.,ing identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcei:-ent unless otherwiise noted.
6.9.1. ROUTINE REPORTS
- a. Startup Rpeort. A su:mary report of plant startup and pow:cr cscalation testing shall be submitted f'll'o-;*.n (1) receipt of an operating license, (2) am nd.ent to the license involving a pl-rnned increase in power level, or (3) installation of fuel that has a diffe.rent design and has been nanufactured by a different fuel supplier, the:
(4) modifications thn: may havG siclnificantly altercd plant.
nuclear, thermal, o- hydraulic performance of the of the tests identified in The report shall address each include a description of the the FSAR%and shall in general measured values of the op.rating conditions or character of istics obtained durirq'. the test program and a coip:.rison these values with design predictions and specifications.
Any corrective actiens that were required to obtain satisfactory operation shall also bc described. Any details required in license conditions additionnl specific this report.
based on other co-.mitrients shall be included in Startup reports shall be submitted within (1) 90 days (2) 90 foll6wing completion of the startup test program, of cor*.1crcial
.days following resimiption or commencement power operation, or (3) 9 months follorwing initial criti cality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of comner.cial power operation), supplc'entary reports shall be submitted at least every three months until all three events have been completed.
b, Annual OneratinQ P1enrortl/ Routine operating reports covering the operation of the unit during the previous calendar year should be submitted prior to March 1 of each year. The initial report shall be submitted prior to March I of the year following initial criticality.
The annual operating reports made by licensees shall provide a comprehensive summary of the operating experience gained during the year, even though some repetition of previously reported information may be involved. References in the annual op-efating report to previously submitted reports shall be clear.
1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
6-16 0
Each ar, !1 operating report shall inc? -e:
(1) A narrative summary of o,)er ating expericnce during the report period relating to safe operation of tnc I,,,clity, includlnr'- sa`fc, relatedc maintenance no- covered in itci I.b. (2)(e) below.
(2) For each outage.or forced reduction in pjowcr2/
of over 20% of design power ]evel where the reduction extends for greater than four hours:
(a) the proxir:atc c3use and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction);
(b) a brief discu.csn of.(or refcrcnce to reports of) any reportable occurrences pertaining to the outage or power reduction; (c) corrective action taken to reduce the proba bility of recurrence, if appropriate; (d) operating time lost as a result of the outage or powNer reduction (for schc*cu]ed or forced outages,3/ use the generator off-line hours; for forcK'd reduction in po;..'er, use the approximate duration of operation at reduced power);
(e) a description of major safety-related corrective 25 maintenance performed during the outage or power reduction, including-n the system and cor.:ponent involved and identification of the critical path activity dictating the length of the outage or power reduction; and (f) a report of any single release of radioactivity or radiation exposure specifically associated with the.outage iwhich accounts for more than 10% of the allowable annual values.
2/ The term "forced reduction in power" 'is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend.
Note that routine preventive maintenanc-e, surveillance and calibration activities requiring power reductions are not covered by this action.
_ The term "forced outage" is normally defined in the 61ectric power industry as the occurrence of a component failure or other condition
.which requires that the unit be removed from service for corrective action immediately or up to and including the very next weekend.
6-17
(3) A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions, 4- e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
(4) Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.
- c. Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, to arrive no later than the tenth of each month following the calendar month covered by the report.
6.9.2 REPORTABLE OCCURRENCES Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
4/ This tabulation supplements the requirements of 920.407 of 10 CFR Part 20 6-18
- a. Prompt Noti. ation With W'ritten FollowUn. "e types of events listee below shall be reported as"exp-itiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirpied by telegraph, mailgram, or facsimile transmission to the.
Director of the appropriate Regional Office, or his-designate no later than the first working day following the event, with a written followup report within two weeks. The written folloiup report shall include, as a minimum, a completed copy of a licensee event report form. Information providcd'on the licensee event report form shall be supple-ented,.
as needed, by additional narrative material to provide c.gm plete explanation of the circumstances surrounding the event.
(1) Failure of the reactor protection system or other -.
systems subject to limiting. safety system settings to initiate the required protective function by the time a monitored parameter ruaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
Note: Instrument drift discover'ed as a result of testing need not be reported under this item but may be reportable under items.2.a(S), 2.a(6), or 2.b(l) " 25 below.
(2) Operation of the unit or affected systems when any- .
para-meter or operation subject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications*.
Note: If specified action is taken when a system, is found to be operating between the most conservative and the least conservative aspects of a limiting condition for operation listed in the technical specifications, the limiting condition for operation is not &onsidered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below.
(3) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
Note: Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical spec ifications need not be reported under this item..
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(4) React_-..ity anomalies, involving disa<,ment with the predicted value of reFic ivtv 1aL,:nc- under .,-cýdy .*t;Ke conditions during i);.er op*.ration, greater than or equal to 1% Ak/k; a calculated rcactivit), balance indicating a shut down margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if sub-critical, an unplanned rcactivity insertion of more than 0.5% Ak/k or occurrence of any unplanned criticality.
(5) Failure or malfunction of ohe or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.
(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirer.ients of systems required to cope with accidents analyzed in the SAR.
Note: For items 2.a(S) and 2.a(6) reduced redundancy that does not result -in a loss of system function need not be reportcd under this section but may be 25 reportable under items 2.b(2) and 2.b(3) below.
(7) Conditions arising from natural or man-made events that, as a direct result of the event r-quire plart shutdown, operation of safety systems, or other protective measures required by technical specifications.
(8) Errors discovered in the transient or accident analyses or in the ffiethods used for such analyses as described in the safety analysis report or in the bases for the technical specifications. tlhat have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
(9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a ranner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically con sidered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
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Note: This em is intended to provide for - norting of potentially generic problems.
- b. Thirty Day V'ritten Reports. The reportable occurrences discussed the Director below shall be the su',Jcot of written reports to of of thei appropri-ate Regional Office within thirty days occurrence of the event. The written report shall include, as report forim,.
a minimum, a conpleted copy of a licensee event event report form shall Information provided on the licensee additional narrative material be supplemented, as needed, by the circumstances surrounding to provide complete explanation of the event.
fclfatu (1) Reactor protection systerm or en-ineered a less conserv instrument settings which are found to be specifications ative than those established by the technical functional but which do not prevent the fulfillment of the requirements of affected systems.
mode (2) Conditions leading to operation in a degraded for operation or permitted by a limiting condition condition for plant shutdown required by a limiting operation. 25 Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system 2.b(2) configurations as described in items 2.b(l) and themselves need not be reported except where test results reveal a degraded mode as described above.
"'(3) Observed inadequacies in the implementation of admin to istrative or procedural controls which threaten provided in cause reduction of degree of redundancy safety feature reactor protection systems.or enginered systems.
(4) Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.
included Note: Sealed sources or calibration sources are not of valve packing or gaskets under this item. Leakage leakage set forth in within the limits' for identified technical specifications need not be reported under this item.
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6.9.3 SPECIAL REP 'S Special reports shall be submitted covering the activitie's identified below pursuant to the requirements of the applicable reference specification where appropriate.
Twenty copies of the following reports should be sent to the Director, Nuclear Reactor Regulation.
- a. In-service inspection, reference'4.2.
- b. Tendon surveillance, reference 4.4.
6.9.4 UNIQUE REPORTING REQUIREmeNTS
- a. Radioactive Effluent Releases A report of the quantities of radioactive effluents released from the plant, with data summarized on a monthly basis following the format of U. S. NRC Regulatory Guide 21.
The report shall be submitted within 60 days after January I and 60 days after July 1 specifying qLuantities of radioactive effluents released during the pievious 6 months of operation.
- 1. Gaseous Releases (a) Total radioactivity (in curies) releases of noble and activation gases.
(b) Maximum noble gas release rate during any one-hour period.
(c) Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.
(d) Percent of technical specification limit.
- 2. Iodine Releases (a) Total (1-131, 1-133, 1-135) radioactivity (in curies) released.
(b) Total radioactivIty (in curies) released, by nuclide, based on representative isotopic analyses performed.
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(c) ý'orcent of technical specificati*.'limit.
- 3. Particulate Releases (a) Gross radioactivity (*, y) released (in curies) excluding background radioactivity.
(b) Gross alpha radioactivity released (in curies) excluding background radioactivity.
(t) Total radioactivity released (in curies) of nuclides with half-lives greater than eight days.
(d) Percent of technical specification limit.
- 4. Liquid Releases (a) Gross radioactivity (0, y) released (in curies) excluding tritium and average concentration released to the unrestricted area.
(b) Total tritium and alpha radioactivity (in curies) released and average concentration released to the unrestricted area.
25 (c) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.
(d) Total volume (in liters) of liquid waste released.
(e) Total volumie (in liters) of dilution water used prior to release from the restricted area.
(f) The maximum concentration of gross radioactivity (0, y) released to the unrestricted area (averaged over the period of release).
(g) Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.
- 1) Percent of technical specification limit for total activity released.
- 5. Solid Waste (a) The total amount of solid waste packaged (in cubic feet) 6-23
(b) -,he total estimated radioactivi\ (in curies) involved.
(c) The dates of shipment and dfsposition (if shipped off-site).
- b. Environmental Radiological Monitoring A report on the environmental monitoring program shall be submitted within 60 days after January 1 and 60 days after July 1 covering the previous 6 months of operation. This report may be combined with the report of the quantities of radioactive effluents.
- 1. For each medium sampled e.g., air, baybottom, surface water, soil, fish including:
(a) Number of sampling locations (b) Total number of samples (c) Number of locations at which levels are found to be significantly above local backgrounds (d) Highest, low'est, and the annual average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
- 2. If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 3% of those that could result from continuous exposure to the concentration values listed in Appendix B, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
- 3. If statistically significant variations of off-site environmental concentrations with time are observed, correlation of these results with effluent releases shall be provided.
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3/4 LEFT BLANK INTENITIONALLY 6-25 I
LEFT BLANK INTENTIONALLY 6-26
6.10 RECORD RETrV':TTOI 6.10.1 The following records shall be retnine'd for at least five (5) years:
- a. Records and legs of facility operation covering time in:cr %,,l at each pcw'er level.
- b. Records and logs of principal niintenance activities, j z, ticns, A
repair and replacement of pfinripil itehs of c-quiip,-.pnt r>l:c.
to nuclear safeLy>.
C. REPORTABLE OCCUl,:RNCE Reports.
25
- d. Records of surveillance activitieu, inspection- and caiib-'rtions requirvd by these Technical Specifications.
- e. Records of reactor tests and experirmnts.
- f. Records of changes made to Operating Procedures.
- g. Records of radioactive shipments.
- h. Records of sealed source leak tests and results.
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SAFETY EVALUATION BY THE OFFICE OF NUJCLEAR REtTOR REGULATION SULPPORTING AMENDIENT NO. 13 TO FACILITY LICENSE NO. DPR-31, AND AMENDMENT NO. 12 TO LICENSE NO. DPR-41 .
CHANGE NO. 25 TO TECHNICAL SPECIFICATIONS FLORIDA POKER AND LIGHT COMPAXY TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 DOCKET NOS. 50-250 AND 50-251 Introduction By letter dated December 20, 1974, Florida Power and Light Company (FPL) proposed changes to the Technical Specifications appended to Facility Operating Licenses No. DPR-31 and DPR-41 for the Turkey Point Nuclear Generating Units 3 and 4. The proposed chanpes involve changes to the reporting requirements.
Discussion The proposed changes would be administrative in nature and would affect the conduct of operation. The proposed changes are intended to provide uniform license requirements. Areas covered by the proposed uniform specifications include reporting requirements and an abnormal occurrence definition change.
In Section 208 of the Energy Reorganization Act of 1974 "abnormal occurrences" is defined as an unscheduled incident or event which the Commission determines is significant from the standpoint of public health or safety. The term "abnormal occurrence" is reserved for usage by NRC. Regulatory Guide 1.16, "Reporting of Operating Information Appendix A Technical Specifications", Revision 4, enumerates required reports consistent with Section 208. The proposed change to required reports identifies the reports required of all licensees not already identified by the regulations and those unique to this facility. The proposal would formalize present reporting and would delete any reports no longer needed for assessment of safety related activities.
2 Evaluation The new guidance for reporting operating information does not identify any event as an "abnormal occurrence". The proposed reporting require ments also delete reporting of information no longer required and duplica tion of reported information. The standardization of required reports and desired format for the information will permit more rapid recognition of potential problems.
During our review of the proposed changes, we found that certain modifi cations to the proposal were necessary to have conformance with the desired regulatory position. These changes were discussed with your staff and have been incorporated into the proposal.
We have concluded that the proposal as modified improves the licensee's program for evaluating plant performance and the reporting of the operating information needed by the Commission to assess safety related activities and is acceptable. The modified reporting program is consi~stent with the guidance provided by Regulatory Guide 1.16, "Reporting of Operating Information - Appendix A Technical Specifications",
Revision 4. The administrative controls are consistent with requirements being incorporated in Technical Specifications for new licensed facilities.
Conclusion We have'-concluded, based on the considerations discussed above, that:
(1) because the change does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a.safety margin, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: November 26, 1975
UNITF- STATES NUCLEAR REGULATORY COMMISSION DOCKETS NOS. 50-250 AND 5O-251 FLORIDA POWER AND LIGHT CO)*ANY NOTICE OF ISSUNINCE OF AMENDMENTS TO FACILITY OPERATING LICENSES Regulatory Commission Notice is hereby given that the U.S: Nuclear (the Commission) has issued Amendments Nos. 13 and 12 to Facility Operating Licenses Nos. DPR-31 and DPR-41 issued to Florida Power and for operation of the Light Company which revised Technical Specifications 3 and 4, located in Dade Turkey Point Nuclear Generating Units Nos.
County, Florida. Tle amendment is effective 60 days from the date of issuance.
of the The amendment modifies the reporting requirements Generating, Units Technical Specifications for the Turkey Point Nuclear 3 and 4.
standards and The application for the amendment complies with the as amended (the Act), and requirements of the Atomic Energy Act of 1954, the Commission's rules and regulations. The Commission has made the Commission's rules appropriate findings as required by the Act and forth in the license and regulations in 10 CFR Chapter I, which are set since amendment. Prior public notice of this amendment is not required consideration.
the amendment does not involve a significant hazards (1) the For further details with respect to this action, see 1974, (2) Amendments Nos.
application for amendment dated December 20, with Change No. 25 and (3) 13 and 12 to Licenses Nos. DPR-31 and DPR-41,
t
-2 the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N. W., Washington, D. C. and at the Environmental SUrban Affairs Library, Florida International University, Miami, Florida 33199.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: Director, Division of Reactor Licensing.
-Dated at Bethesda, Maryland, this 26 day of November, 1975.
FOR THE NUCLEAR REGULATORY CO=IISSION Donald M4. Elliott, Acting Chief Operating Reactors Branch 43
- Division of Reactor Licensing