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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) 2024-02-05
[Table view] Category: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
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 22, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - 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 AND MF6389)
Dear Mr. Nazar:
By letter dated June 10, 2015, as superseded by letter dated September 25, 2015, Florida Power & Light Company (FPL or the licensee) submitted Relief Request No. PR-02 for the fifth 10-year inservice testing (IST) interval of Turkey Point Nuclear Generating Unit No. 3 (Turkey Point Unit 3) and Turkey Point Nuclear Generating Unit No. 4 (Turkey Point Unit 4).
Pursuant to Title 1O of the Code of Federal Regulations (10 CFR), Part 50, Section 55a(f)(5)(iii),
the licensee requested the U.S. Nuclear Regulatory Commission (NRC) relief pertaining to the requirements for the quarterly testing of the residual heat removal (RHR) pumps compared to the requirements of Section ISTB-351 O(b)(1) of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME Code).
Based on the review of the submittals, the NRC staff concluded that compliance with the ASME Code RHR pump quarterly testing is impractical for the configurations identified in the subject relief requests, and that compliance with the specified requirements would result in a burden on FPL. The NRC staff also concluded that the proposed testing provides reasonable assurance that the RHR pumps are operationally ready. Therefore, relief is granted pursuant to 10 CFR 55.a(f)(6)(i), is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Relief is granted for the fifth 10-year IST interval at Turkey Point Unit 3, which began February 22, 2015, and for the fifth 10-year IST interval at Turkey Point Unit 4, which began April 15, 2015.
All other ASME Code, Section XI requirements for which the request was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
M. Nazar If you have any questions regarding this issue, please contact the Project Manager, Ms. Audrey Klett, at (301) 415-0489 or by e-mail at Audrey.Klett@nrc.gov.
Sincerely, Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
Safety Evaluation cc w/encl.: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. PR-02 FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By letter dated June 10, 2015, 1 as superseded by letter September 25, 2015, 2 Florida Power & Light Company (FPL or the licensee) submitted Relief Request No. PR-02 for the fifth 10-year inservice testing (IST) interval of Turkey Point Nuclear Generating Unit No. 3 (Turkey Point Unit 3) and Turkey Point Nuclear Generating Unit No. 4 (Turkey Point Unit 4).
Pursuant to Title 1O of the Code of Federal Regulations (10 CFR), Part 50, Section 55a(f)(5)(iii),
the licensee requested the U.S. Nuclear Regulatory Commission (NRC) relief pertaining to the quarterly testing of the residual heat removal (RHR) pumps compared to the testing requirements in Section ISTB-351 O(b)(1) of the American Society of Mechanical Engineers (ASME) Code for the Operation and Maintenance of Nuclear Power Plants (OM Code).
2.0 REGULATORY EVALUATION
It specifies in 10 CFR 50.55a(f), "lnservice testing requirements," that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations.
It specifies in 10 CFR 50.55a(f)(5)(iii) that if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit the information to support the determination.
1 Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML15188A030.
2 ADAMS Accession No. ML15299A350.
Enclosure
Pursuant to 10 CFR 50.55a(f)(6)(i), relief to the ASME OM Code may be granted by the NRC if the licensee demonstrates that conformance with the ASME OM Code requirements is impractical for the facility.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to grant the relief requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Proposed Alternative 3.1.1 ASME Code Components Affected and Applicable Code Edition and Addenda The fifth 10-year IST program intervals began on February 22, 2015, and on April 15, 2015, for Turkey Point Unit 3 and Turkey Point Unit 4, respectively.
The ASME Code components affected are the RHR pumps (3A, 3B, 4A, and 4B). The RHR pump component numbers are 3P210A, 3P210B, 4P210A and 4P210B.
For the fifth 10-year interval, the ASME Code of record for Turkey Point Unit 3 and Unit 4 is the 2004 Edition with the 2005 and 2006 Addenda of the ASME OM Code.
3.1.2 ASME Code Requirement for Which Licensee Proposed an Alternative The licensee requested relief from the requirements of the ASME Code, Section ISTB-3510(b)(1), "Range," where the full-scale range of each analog instrument shall not be greater than three times the reference value.
3.1.3 Licensee's Basis for Requesting Relief For Group A and Group B tests, the Code requires instrument accuracy to be within 2 percent of full scale and the full scale range of each instrument to be no greater than three times the reference value.
At Turkey Point, the RHR pumps are considered Group A pumps. The installed suction and discharge pressure gauges are sized to accommodate pressures up to 600 pounds per square inch gauge (psig) expected under standby, cold shutdown, and emergency operation modes.
The instrument range is 0 to 600 psig for both gauges. During the quarterly testing, the typical RHR pump differential pressure (DP) is approximately 142 psig (discharge pressure approximately 160 psig and suction pressure approximately 18 psig), and as a result, the installed suction and discharge pressure instrument ranges exceed the maximum Code allowed range of three times the reference value for the quarterly surveillances.
FPL requests relief from the instrument range requirements of ISTB-351 O(b)(1 ), which requires that the full scale range of each analog instrument not exceed three times the reference value.
Relief is requested for the suction and discharge pressure instruments for the RHR pumps during the quarterly testing.
Compliance with the requirements of ISTB-3510(b)(1) is impractical, because it would require system modifications and installation of new instrumentation to meet the allowed range of three times the reference value.
3.1.4 Licensee's Proposed Alternative As an alternative, FPL is proposing to use the existing Turkey Point RHR pump instrumentation, without meeting the requirements of ISTB-351 O(b)(1 ), but which exceed the Code required accuracies that will be applied to Group A quarterly tests of the RHR pumps. This relief request does not apply to the comprehensive RHR pump testing.
The installed suction and discharge pressure instruments are calibrated to an accuracy of plus or minus (+/-) 0.25 percent and are of the "twice around" type such that they may accurately indicate pressure over all modes of RHR operations (shutdown cooling and emergency core cooling). The instrument range on the first revolution is 0 to 300 psig and 300 to 600 psig on the second revolution.
Suction pressure measurements are recorded and used to derive the pump DP through calculation. When determining pump DP, the RHR pump DP is approximately 142 psig (discharge pressure approximately 160 psig, while suction pressure is approximately 18 psig).
The maximum effect of suction pressure inaccuracies is 0.25 percent x 600 psig, or 1.5 psig.
The Code maximum gauge range for this suction pressure reference value (18 psig) would be 0 to 54 psig. The Code accuracy requirement of 2 percent would cause a maximum inaccuracy of 2.0 percent x 54 psig, or 1.1 psig.
Discharge pressure measurements are also recorded and used to derive the pump DP through calculation. When determining pump DP, typically the RHR pump DP is approximately 142 psig (discharge pressure approximately 160 psig while suction pressure is approximately 18 psig).
The maximum effect of the discharge pressure inaccuracies is also 0.25 percent x 600 psig, or 1.5 psig. The Code maximum gauge range for this discharge pressure reference value (160 psig) would be Oto 480 psig. The Code accuracy requirement of 2 percent would cause a maximum inaccuracy of 2.0 percent x 480 psig, or 9.6 psig.
Based on the inaccuracies of the installed suction and discharge pressure gauges(+/- 1.5 psig each), the largest possible error in the differential pressure calculation is +/- 3 psig. Using gauges with Code required ranges, and applying the Code accuracy requirements, the largest possible inaccuracies would be 1.1 psig + 9.6 psig, or 10.7 psig.
Therefore, the use of the permanently installed pressure instruments would reduce the overall instrument inaccuracies with respect to the DP for the quarterly test from 10. 7 psig to 3.0 psig when compared to gauges with the code required ranges.
Note that the proposed alternative has been previously authorized for Turkey Point Units 3 and 4 for the fourth 10-year IST program interval by NRC letter dated October 6, 2004 (ADAMS Accession No. ML042820470).
3.1.5 Duration of Proposed Alternative The licensee requested the NRC staff to authorize the relief for the fifth 10-year IST interval for Turkey Point Unit 3, which began on February 22, 2015, and for the fifth 10-year IST interval for Turkey Point Unit 4, which began on April 15, 2015.
3.2 NRC Staff's Evaluation 3.2.1 NRC Staff Evaluation The licensee requests relief from the instrument range requirements of ISTB-351 O(b)(1) for the RHR pump suction and discharge pressure instruments during the quarterly pump test. The Code requires that the full-scale range of each analog instrument shall not be greater than three times the reference value. The licensee proposes to use instruments that do not meet this Code requirement.
For Group A quarterly tests, the Code requires instrument accuracy to be within 2 percent of full-scale and the full-scale range of each instrument be no greater than three times the reference value. The combination of these two requirements results in an effective maximum inaccuracy limit of +/- 6 percent of the reference suction and discharge pressure measurements and an even somewhat higher maximum inaccuracy for the calculated delta pressure value.
The licensee has demonstrated that by using gauges with higher accuracy than required by code yet with ranges that would otherwise exceed what the code allows, the overall accuracy required by the code for the combined DP value can still be met and, in fact, exceeded.
In complying with the Code requirements, the licensee would not obtain information that would be more useful than the information that is currently available. For example, installing an analog gauge with a range of three times the reference value (or less) to comply with Code requirements would not yield more accurate readings than those provided by the gauges that are presently installed. This justification is consistent with the long held staff position described in NUREG 1482 Rev. 2, "Guidelines for lnservice Testing at Nuclear Power Plants," concerning pressure gauge ranges and code compliance and, therefore, provides reasonable assurance that the RHR pumps are operationally ready (Reference NUREG 1482 R2, para. 2.5.1.1.).
3.2.2 Evaluation of Compliance with ASME Code Requirements The licensee requests relief from the instrument range requirements of ISTB-3510(b)(1) for the RHR pump suction and discharge pressure instruments during the quarterly pump test. The Code requires that the full-scale range of each analog instrument shall not be greater than three times the reference value. The licensee proposes to use instruments that do not meet this Code requirement.
3.2.3 Evaluation of Impracticality For Group A and Group B tests, the Code requires instrument accuracy to be within 2 percent of full-scale and the full-scale range of each instrument be no greater than three times the reference value. The combination of these two requirements results in an effective accuracy requirement of +/- 6 percent of the reference value.
Compliance with the ASME Code Section ISTB-3510(b)(1) would require system modifications and installation of new instruments to meet the allowed range of three times the reference value.
The NRC staff finds that compliance with the ASME Code RHR pump quarterly testing is impractical for the configurations identified in the subject relief requests, and that compliance with the specified requirements would result in a burden on FPL.
3.2.3 Operational Readiness The maximum inaccuracy of the installed suction and discharge pressure instruments individually is 1.5 psig. The maximum inaccuracy of the combination of suction and discharge pressure readings is 3 psig. The accuracies of the installed RHR pump suction and discharge instruments(+/- 0.25 percent) when combined with the instrument range (600 psig) yield DP readings at least equivalent to the readings achieved from instruments that meet Code requirements.
Based on the overall instrument inaccuracies, the NRC staff has reasonable assurance that the RHR pumps are operationally ready using the proposed alternative of the permanently installed pressure instrumentation.
4.0 CONCLUSION
Based on the review of the submittals, the NRC staff concludes that compliance with the ASME Code RHR pump quarterly testing is impractical for the configurations identified in the subject relief requests, and that compliance with the specified requirements would result in a burden on FPL. The NRC staff also concludes that the proposed testing provides reasonable assurance that the RHR pumps are operationally ready.
Therefore, relief is granted pursuant to 10 CFR 55.a(f)(6)(i), is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Relief is granted for the fifth 10-year IST interval at Turkey Point Unit 3, which began February 22, 2015, and for the fifth 10-year IST interval at Turkey Point Unit 4, which began April 15, 2015.
All other ASME Code, Section XI requirements for which the request was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: John G. Billerbeck Date: January 22, 2016
M. Nazar If you have any questions regarding this issue, please contact the Project Manager, Ms. Audrey Klett, at (301) 415-0489 or by e-mail at Audrey.Klett@nrc.gov.
Sincerely, IRA/
Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
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PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLABClayton RidsAcrsAcnw_MailCTR RidsRgn2MailCenter RidsNrrPMTurkeyPoint RidsNrrDeEpnb YHuang, NRR JBillerbeck, NRR CRosales-Cooper, EDO ADAMS A ccess1on No.: ML16011A205 *b 1 e-ma1 OFFICE N RR/DORL/LP LI 1-2/PM NRR/DORL/LPLll-2/LA NRR/DE/EPNB/BC* NRR/DORL/LPLll-2/BC NAME (JLamb for) AKlett BClayton DAiiey BBeasley DATE 1/12/2016 1/12/2016 1/08/2016 1/22/2016 OFFICIAL RECORD COPY