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Category:Letter type:L
MONTHYEARL-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes 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 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 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 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report 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-2024-089, 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 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-2024-100, 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 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 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 L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report 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-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owners Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owners 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-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owners Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owners Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update 2024-09-25
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March 23, 2017 L-2017-047 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D C 20555-0001 RE: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 Fifth Ten-Year lnservice Testing Interval Relief Request No. PR-03 Pursuant to 10 CFR 50.55a(z)(1 ), Florida Power & Light Company (FPL) hereby requests approval of Relief Request PR-03 for the Turkey Point Units 3 and 4 (Turkey Point) Fifth Ten-Year lnservice Testing (IST) Interval. Relief is requested from the applicable American Society of Mechanical Engineers (ASME) Code instrument range requirements, as they relate to Boric Acid Transfer Pump (BATP) inservice testing, on the basis that the proposed alternative would provide an acceptable level of quality and safety.
The enclosure to this letter provides Relief Request PR-03.
This letter contains no new regulatory commitments.
If you have any questions or require additional information, please contact Mr. Mitch Guth, Licensing Manager, at (305) 246-6698.
Sincerely, Mitch Guth Licensing Manager Turkey Point Nuclear Plant Enclosure Relief Request PR-03 cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Florida Power & Light Company 9760 SW 344 St., Florida City, FL 33035
Turkey Point Nuclear Plant L-2017-047 Docket Nos. 50-250 and 50-251 Enclosure Page 2 of 6 ENCLOSURE RELIEF REQUEST NO. PR-03 FIFTH TEN-YEAR INSERVICE TESTING (IST) INTERVAL - TURKEY POINT UNITS 3 AND 4 PROPOSED ALTERNATIVE TO ASME OM CODE, ISTB-3510(B)(1),
FOR BORIC ACID TRANSFER PUMP INSERVICE TESTING 1.0 ASME CODE COMPONENTS AFFECTED..................................................................................... 3 2.0 APPLICABLE CODE EDITION AND ADDENDA ............................................................................. 3 3.0 APPLICABLE CODE REQUIREMENT ............................................................................................ 3 4.0 REASON FOR REQUEST ............................................................................................................... 3 5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE...................................................................... 4 6.0 DURATION OF PROPOSED ALTERNATIVE ................................................................................. 5 7.0 PRECEDENTS................................................................................................................................. 5
8.0 REFERENCES
................................................................................................................................. 5
Turkey Point Nuclear Plant L-2017-047 Docket Nos. 50-250 and 50-251 Enclosure Page 3 of 6 RELIEF REQUEST NO. PR-03 FIFTH TEN-YEAR INSERVICE TESTING (IST) INTERVAL - TURKEY POINT UNITS 3 AND 4 PROPOSED ALTERNATIVE TO ASME OM CODE, ISTB-3510(B)(1),
FOR BORIC ACID TRANSFER PUMP INSERVICE TESTING 1.0 ASME CODE COMPONENTS AFFECTED The components affected by this relief request are listed in the Turkey Point ST Program (Reference 8.1), as follows:
Pump Tag Pump Function Pump Type 3-P203A Boric Acid Transfer Centrifugal 3-P203B Boric Acid Transfer Centrifugal 4-P203A Boric Acid Transfer Centrifugal 4-P203B Boric Acid Transfer Centrifugal 2.0 APPLICABLE CODE EDITION AND ADDENDA The applicable Code edition and addenda for the Turkey Point Fifth Ten-Year IST Interval are the American Society of Mechanical Engineers (ASME) Code for Operations and Maintenance of Nuclear Power Plants, 2004 Edition with Addenda through 2006 (ASME OM Code-2004).
The Turkey Point Fifth Ten-Year IST Interval began on February 22, 2015, for Turkey Point Unit 3, and on April 15, 2015, for Turkey Point Unit 4.
3.0 APPLICABLE CODE REQUIREMENT The applicable Code requirement for which relief is requested, as it relates to BATP inservice testing, is ASME OM Code-2004, paragraph ISTB-3510(b)(1), which states:
The full-scale range of each analog instrument shall not be greater than three times the reference value.
4.0 REASON FOR REQUEST The reason for requesting relief pursuant to 10 CFR 50.55a(z)(1) is that the existing flow rate instrument used for BATP comprehensive testing does not meet the analog instrument range requirement of ASME OM Code-2004, ISTB-3510(b)(1). However, compliance with ISTB-3510(b)(1) would not yield more accurate readings than obtained by the instrument presently installed.
Specifically, the BATP comprehensive test, performed in accordance with ASME OM Code-2004, ISTB-5123, consists of varying the flowrate to an established reference point and comparing the measured pump differential pressure against the requirements of ASME OM Code-2004, Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria. In establishing the reference value for flowrate, FPL utilizes analog flow instruments FI-3/4-110, Emergency Boration Flow Indicator, (where 3/4 designates FI-3-110 for Unit 3 and FI-4-110 for Unit 4). However, the gauges for FI-3/4-110 range from zero to 200 gallons per minute (gpm), whereas the BATP flow reference
Turkey Point Nuclear Plant L-2017-047 Docket Nos. 50-250 and 50-251 Enclosure Page 4 of 6 value for the comprehensive test is 60 gpm. Hence, FI-3/4-110 do not satisfy the analog instrumentation range requirements of ISTB-3510(b)(1) since the 200 gpm full-scale range of FI-3/4-110 exceeds three times the pumps reference value (i.e. 180 gpm).
Non-compliance with the ISTB-3510(b)(1) instrument range requirement for FI-3/4-110 was first identified in 2016. The issue was entered into the Corrective Action Program (CAP), whereby a request for relief from ISTB-3510(b)(1) was determined to be the appropriate corrective action.
FPL requests relief from the instrument range requirement of ISTB-3510(b)(1), which requires that the full-scale range of each analog instrument shall not be greater than three times the reference value. Relief is requested for flow instruments FI-3/4-110.
5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE FPL proposes as an alternative to ASME OM Code-2004, ISTB-3510(b)(1), continued use of FI-3/4-110 when conducting the BATP comprehensive test. The basis for the proposed alternative is that compliance with the instrumentation range requirement of ASME OM Code-2004, ISTB-3510(b)(1), would not result in obtaining information more useful than that currently available using the existing flow instrumentation. FPLs determination is based upon the following:
NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants (Reference 8.2),
states that when the range of a permanently installed analog instrument is greater than three times the reference value but the accuracy of the instrument is more conservative than required by the Code, the staff may grant relief when the combination of the range and accuracy yields a reading at least equivalent to the reading achieved using instruments meeting the Code requirements. NUREG-1482 further states that the use of any available instrument that meets the intent of the Code for the actual reading yield an acceptable level of quality and safety for testing.
ASME OM Code-2004, ISTB-3510(a) states that the instrument accuracy shall be within the limits of Table ISTB-3510-1, Required Instrument Accuracy. For the measured flowrate during comprehensive pump testing, Table ISTB-3510-1 requires an instrument accuracy of
+/- 2% of full scale. The accuracy of installed flowrate instruments, FI-3/4-110, is +/- 1.5%
and thereby exceeds the requirements of Table ISTB-3510-1 for BATP comprehensive test flow measurements. Moreover, the overall measured reading using FI-3/4-110, equates to
+/- 3.0 gpm (i.e. +/- 1.5% of 200 gpm) whereas the measured reading using a Code compliant flow meter equates to +/- 3.6 gpm (i.e. +/- 2% of 180 gpm). Hence even though the instrument range of FI-3/4-110 is above the limits of ISTB-3510(b)(1), the combination of range and accuracy yield an overall measured reading more accurate than the measured reading for a flow meter compliant with the instrumentation requirements of ISTB-3510(a) and ISTB-3510(b)(1). Accordingly, the installed flow instruments, FI-3/4-110, meet the recommendations in NUREG-1482, Section 5.5.1, Range and Accuracy of Analog Instruments, for requesting relief from ISTB-3510(b)(1). Table 1 to this enclosure summarizes the combined effect of range and accuracy for flow instruments FI-3/4-110 versus a Code compliant instrument.
Based upon the foregoing, FPL asserts that continued use of the installed instruments, FI-3/4-110, yields a measured reading of greater overall accuracy than the reading achieved from a Code compliant instrument, providing thus an acceptable level of quality and safety to the ASME Code ISTB-3510(b)(1) requirements. FPL will use installed flow instruments, FI-3/4-110, when performing BATP comprehensive inservice testing for the remainder of the Fifth Ten-Year IST Interval as an alternative to ASME Code ISTB-3510(b)(1) requirement.
Turkey Point Nuclear Plant L-2017-047 Docket Nos. 50-250 and 50-251 Enclosure Page 5 of 6 6.0 DURATION OF PROPOSED ALTERNATIVE The duration of the proposed alternative from ASME OM Code-2004, ISTB-3510(b)(1), is for the remainder of the Turkey Point Units 3 and 4 Fifth Ten-Year IST Interval. The Fifth Ten-Year IST Interval expires on February 21, 2025, for Unit 3, and on April 14, 2025, for Unit 4.
7.0 PRECEDENTS In 2016, the NRC Staff approved a similar relief request for Turkey Points Fifth Ten-Year IST Interval (Reference 8.3).
8.0 REFERENCES
8.1 FPL letter L-2016-139, Inservice Testing (IST) Program Plan, dated July 6, 2016 (ADAMS Accession No. ML16202A067) 8.2 NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 2 (ADAMS Accession No. ML13295A020) 8.3 NRC letter dated January 22, 2016, 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), (ADAMS Accession No. ML16011A205)
Turkey Point Nuclear Plant L-2017-047 Docket Nos. 50-250 and 50-251 Enclosure Page 6 of 6 Inservice Testing Program Relief Request No. PR-03 Table 1 Comparison of Flow Instrument (Gauge) Range and Accuracy Affected Flowrate Instrumentation:
FI-3-110 EMERGENCY BORATION FLOW INDICATOR FI-4-110 EMERGENCY BORATION FLOW INDICATOR Combined Flow Gauge Range Accuracy Instrument Inaccuracy Turkey Point Instrumentation 0 - 200 gpm +/- 1.5 % +/- 3.0 gpm (1) (2)
ASME CODE 0 - 180 gpm +/- 2.0 % +/- 3.6 gpm (1)
ISTB 3510(b)(1) [percent full-scale]
(2)
Table ISTB-3510-1