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Category:Letter
MONTHYEARML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-057, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point 2024-09-25
[Table view] Category:Safety Evaluation
MONTHYEARML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter 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 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) 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 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 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 2024-07-16
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420 December 9, 2015
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 -SAFETY EVALUATION FOR RELIEF REQUEST NO. PR-01, FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL REGARDING REQUIREMENTS FOR THE QUARTERLY TESTING OF THE BORIC ACID TRANSFER PUMPS (CAC NOS. MF6252 AND MF6253)
Dear Mr. Nazar:
By letter dated May 12, 2015, as superseded by letter dated September 25, 2015, Florida Power & Light Company (FPL or the licensee) submitted Relief Request No. PR-01 for the fifth 10-year inservice testing (IST) interval of Turkey Point Nuclear Generating Unit Nos. 3 (Turkey Point Unit 3) and 4 (Turkey Point Unit 4). Pursuant to Title 10 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 boric acid transfer (BAT) pumps compared to the requirements of Section ISTB-5121(c) of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants. Based on the review of the submittals, the NRC staff concluded that compliance with the ASME Code BAT 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 BAT pumps are operationally ready. Therefore, relief 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 L. Klett, at (301) 415-0489 or by e-mail at Audrey.Klett@nrc.gov.
Docket Nos. 50-250 and 50-251
Enclosure:
Safety Evaluation cc w/encl.: Distribution via Listserv Sincerely, Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. PR-01 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 May 12, 2015, 1 as superseded by letter September 25, 2015, 2 Florida Power & Light Company (FPL or the licensee) submitted Relief Request No. PR-01 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 10 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) grant relief pertaining to the quarterly testing of the boric acid transfer (BAT) pumps compared to the testing requirements in Section ISTB-5121 (c) of the American Society of Mechanical Engineers (ASME) Code for the Operation and Maintenance of Nuclear Power Plants (OM Code). The licensee proposed an alternative as part of the relief request.
2.0 REGULATORY EVALUATION
It specifies in 10 CFR 50.55a(f) 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. ML 15148A536.
2 ADAMS Accession No. ML 15299A348.
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.
Paragraph 50.55a(f)(6)(i) states that the Commission may grant relief and may impose such alternative requirements as it determines are authorized by law, will not endanger life or property or the common defense and security, and are 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.
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 ASME Code components affected are the BAT pumps (3A, 3B, 4A, and 4B). The BAT pump component numbers are 3P203A, 3P203B, 4P203A and 4P203B. 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-5121 (c), where it is not practical to vary system resistance, then the flow rate and pressure shall be determined and compared to their respective reference values. 3.1.3 Licensee's Proposed Alternative In its letter dated September 25, 2015, the licensee proposes to test the BAT pumps every quarter through a fixed resistance flow path without flow instruments and to measure only differential pressure and vibration.
As an alternative to measuring differential pressure and flow during the quarterly Group A test, the licensee proposed to only measure differential pressure of a fixed resistance flow path and compare it to its reference value. Additionally, the license proposed to record vibration measurements and compare it to its reference values. During the comprehensive pump test when flow, differential pressure, and vibration can be measured, the licensee proposed to perform additional full spectrum vibration analysis above the Code-requirements.
The NRC previously authorized the proposed alternative for Turkey Point Units 3 and 4 for the fourth 10-year IST program interval by letter dated October 6, 2004.3 3 ADAMS Accession No. ML042820470. 3.1.4 Licensee's Basis for the Proposed Alternative The licensee's basis for the proposed alternative is that position 9 of Generic Letter (GL) 89-04, Supplement 1, "Guidance on Developing Acceptable lnservice Testing Programs," dated April 4, 1995, 4 states that in cases where flow can only be established through a non-instrumented flow path during quarterly pump testing and a flow path exists at cold shutdown or refueling outages to perform a test of the pump under full or substantial flow conditions, the increased interval is an acceptable alternative to the Code requirements provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibration is continued.
According to the licensee, the BAT pumps are included in the Turkey Point preventive maintenance (PM) program, which requires a pump inspection and oil analysis to be performed periodically.
Based on the PM inspection results, full spectrum analysis, and continued quarterly and comprehensive testing, an assessment of pump health and operational readiness is determined by FPL. The normal test loop for the BAT pumps consists of fixed resistance flow paths; however, the Code-required flow measuring instruments are not installed in the flow path. Therefore, pump degradation can only be detected by comparing successive measurements of pump differential pressure.
An alternate test circuit is available in which flow rate may be measured.
However, this flow path requires injection of highly concentrated boric acid solution into the reactor coolant system. During power operation, this test loop is highly impractical since severe power fluctuations would be created that would lead to a potential transient and subsequent trip of the reactor. Using the alternate flow path at cold shutdown intervals would also result in excessive boration of the reactor coolant system (RCS) resulting in potential difficulties and delays in restarting the plant. As such, compliance with the code requirements would require significant system modifications and installation of flow instruments or injection of highly borated water into RCS, which would lead to a potential plant transient, and is impractical.
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 3, which began on February 22, 2015, and for the fifth 10-year IST interval for Turkey Point 4, which began on April 15, 2015. 3.2 NRC Staff's Evaluation 3.2.1 Evaluation of Compliance with ASME Code Requirements Section ISTB-5121(c) specifies that where it is not practical to vary system resistance, then the flow rate and pressure shall be determined and compared to their respective reference values. 4 ADAMS Accession No. ML031140075. 3.2.2 Evaluation of Impracticality The ASME OM Code requires that flow rate be measured during a Group A test and that a Group A inservice test be run on each Group A pump quarterly.
At Turkey Point, the normal test loop for the BAT pumps consists of fixed resistance flow paths to limit flow; however, flow measuring instruments are not installed in the flow path. An alternate test circuit is available in which flow rate may be measured; however, this flow path requires injection of highly concentrated boric acid solution into the RCS. This alternate test circuit would result in severe power fluctuations during power operation.
This alternate test circuit would result in excessive boration of the RCS during cold shutdown.
Compliance with the ASME Code Section ISTB-5121(c) would require system modifications and installation of flow instruments in the fixed resistance flow path or injection of highly borated water into the RCS if the alternate test circuit was used. The NRC staff finds that compliance with the ASME Code BAT pump quarterly testing is impractical for the configurations identified in the subject relief request, and that compliance with the specified requirements would result in a burden on FPL. 3.2.3 Operational Readiness FPL proposes to test the BAT pumps every quarter through a fixed resistance flow path without flow instruments and to measure only differential pressure and vibration.
Accordingly, differential pressure will be measured and compared to its reference value by the licensee.
Since the system resistance is fixed and can be assumed to be constant, pump degradation can be detected by FPL by comparing successive measurements of pump differential pressure.
Additionally, vibration measurements will also be recorded by the licensee and compared to its reference values. During the comprehensive pump test when flow can be measured, full spectrum vibration analysis will be performed by the licensee above the required vibration analysis required by the ASME OM Code. When performing the comprehensive pump test, all required parameters will be measured and compared to their reference values by FPL. Position 9 of GL 89-04 notes that in cases where flow can only be established through a non-instrumented flow path during quarterly pump testing and a path exists at cold shutdown or refueling outages to perform a test of the pump under full or substantial flow conditions, the comprehensive test combined with quarterly test measuring at least pump differential pressure and vibration is an acceptable alternative to the Code requirements.
Furthermore, the BAT pumps are included in the station PM program, which requires a pump inspection and oil analysis to be performed periodically as well as additional full spectrum vibration analysis, and continued quarterly and comprehensive BAT pump testing. Based on proposed testing by FPL, the NRC staff has reasonable assurance that the BAT pumps are operationally ready.
4.0 CONCLUSION
Based on the review of the submittals, the NRC staff concludes that compliance with the ASME Code BAT 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 BAT pumps are operationally ready. Therefore, relief 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:
J. Huang Date:December 9, 2015 M. Nazar If you have any questions regarding this issue, please contact the project manager, Ms. Audrey L. 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:
Safety Evaluation cc w/encl.: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLABClayton RidsNrrPMTurkeyPoint RidsNrrDeEpnb LPL2-2 R/F RidsACRS_MailCTR CRosales-Cooper, EDO ADAMS A ccess1on N ML 15328A108 o.: OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA NAME AKlett (JLamb for) BClayton DATE 11/20/2015 11/27/2015 RidsNrrDorlLpl2-2 RidsRgn2MailCenter JHuang, NRR *b 1y e-memo NRR/DE/EPNB/BC*
DAiiey 11/20/2015 OFFICIAL RECORD COPY NRR/DORL/LPLll-2/BC BBeasley 12/09/2015