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Category:Letter type:NRC
MONTHYEARNRC 2024-0007, Ile Post-Exam Submittal Letter2024-03-18018 March 2024 Ile Post-Exam Submittal Letter NRC-2024-0026, Ile Proposed Exam Submittal Letter2023-12-20020 December 2023 Ile Proposed Exam Submittal Letter NRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 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 NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary 2024-03-18
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POINT BEACH November 27, 2013 NRC 2013-0105 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 10 CFR 50.55a Request, Relief Request RR-5 Examination of the Unit 1 and Unit 2 Pressurizer Surge Nozzle Inner Corner Region Fifth Ten-Year lnservice Inspection Program Interval In accordance with 10 CFR 50.55a, "Codes and Standards," Paragraph (a)(3)(ii), this letter requests that the Nuclear Regulatory Commission (NRC) grant NextEra Energy Point Beach, LLC (NextEra) relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code),Section XI, 2007 Edition with 2008 Addenda for the examination of the Point Beach Nuclear Plant (PBNP) Unit 1 and 2 Pressurizer Surge Nozzle Inner Corner Region. Relief is requested on the basis of hardship or unusual difficulty due to the location of the examination area.
NextEra requests approval of this request prior to December, 2014. The requested duration of this relief request is until the end of the Fifth Inspection Interval, which is scheduled to end on July 30, 2022.
This submittal contains no new commitments or revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC
~YVl~ icr L. All.ttw Larry Meyer Site Vice President Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Mr. Mike Verhagan, Department of Commerce, State of Wisconsin NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE POINT BEACH NUCLEAR POWER PLANT UNITS 1 AND 2 10 CFR 50.55a REQUEST RELIEF REQUEST 5, PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a{a){3)(11)
HARDSHIP OR UNUSUAL DIFFICULTV WITHOUT COMPENSATING INCREASE IN LEVEL OF QUALITY OR SAFETY 1.0 ASME Code Component{s) Affected Code Class: 1 Component Numbers: PZR-SurgeNoz-IRS (Unit 1 and Unit 2)
Examination Category: B-D Item Number(s): B3.120
Description:
Full Penetration Welded Nozzles In Vessels 2.0 Applicable ASME Code Edition and Addenda Point Beach Nuclear Plant (PBNP) started the Fifth 10-year lnservice Inspection (lSI)
Program Interval on August 1, 2012 and is required to follow the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," (ASME Section XI), 2007 Edition with the 2008 Addenda with the conditions of 10 CFR 50.55a.
3.0 Applicable Code Requirement
Examination category B-D, Item B3.120 [1998 Edition of Section XI per 10 CFR 50.55a(b)(2)(xxi)(A)], requires 100% volumetric examination, as defined in Figures IWB-2500-7(a) through (d) as applicable, of Class 1 pressurizer nozzle inside corer regions (aka inner radius), during each inspection interval.
4.0 Reason for Request
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested from the requirements of ASME Section XI, IWB-2500, Category B-D, Item B3.120, on the basis of hardship or unusual difficulty due to the location of the examination area. The Unit 1 and Unit 2 pressurizer surge nozzles (PBNP identification number PZR-SurgeNoz-IRS) are located in a cubicle underneath the pressurizer which includes ventilation duct work, as well as the electrical cabling leading to the 78 pressurizer heater penetrations (see Attachment A). This configuration limits safe access to the examination area. Accessing the area requires personnel to build a scaffold platform, remove insulation around the surge nozzle, clean the examination region, and then perform the examination while being within inches of the electrical cabling running to the heaters. While the heaters themselves can be de-energized for personnel safety, the possibility of damage occurring to either the Page 1 of 3
cables or the heaters is increased due to this activity. In addition, the extremely cramped location does not allow personnel to move away froni the primary source of radiation, (the surge piping and nozzle), which subjects personnel to an expected radiation field of 60-200 mR per hour. This field rate is based upon previous Radiation Protection dose surveys. The radiation exposures to all personnel associated with the performance of these examinations are as follows:
Scaffold erection: 4 personnel x 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Insulation removal: 3 personnel x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Examination area preparation: 2 personnel x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Ultrasonic examination: 2 personnel x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Insulation installation: 3 personnel x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Scaffold removal: 4 personnel x 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Total person hours: 64 x 100 mR average rate =6.4R The pressurizer surge nozzles are integrally cast into the lower head of the pressurizer, thus there are no nozzle-to-vessel welds requiring examination (see Attachment A). In review of industry operability assessments, PBNP has found no examples of pressurizer nozzle inner radius failures over 40 years of operating experience. In addition, PBNP has performed a total of six (6) previous examinations between the two units with no recorded indications.
5.0 Proposed Alternative and Basis for Use .
Proposed Alternative:
A visual (VT-2) examination is performed at the end each refueling outage during the system leakage test as required by Table IWB-2500-1, Examination Category B-P, Item B 15.1 0, of the 2007 Edition through 2008 Addenda of Section XI. The required VT-2 visual examination provides reasonable assurance of continued structural integrity.
Basis for Use:
The pressurizer cast surge inner corner region is subject to a VT-2 visual examination as part of the system leakage test on the pressurizer vessel conducted each refueling outage as specified in Table IWB-2500-1, Examination Category B-P of the 2007 Edition through 2008 Addenda of ASME Section XI.
It is PBNP's position that based on the acceptable results of VT -2 visual examinations performed during the Class 1 system leakage test, there is a reasonable assurance of continued structural integrity of the subject component and an acceptable level of quality and safety is maintained without performing the required inner radius section examinations required by Table IWB-2500-1, Category B-0, Item B3.120.
6.0 Duration of Proposed Alternative The proposed alternative will be used for the Fifth 10-Year lnservice Inspection Interval of the lnservice Inspection Program for the PBNP that is scheduled to end on July 30, 2022.
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7.0 Precedents NRC Safety Evaluation to Kewaunee Nuclear Power Plant, dated February 18, 2005, Kewaunee Nuclear Power Plant - Fourth 10-Year lnservice Inspection Interval Program Requests for Relief (TAC Nos. MC 2497, MC2498, MC2499, MC2500, MC2501, MC2503, MC2504, MC2505, MC2506, MC2507 and MC2509) (ML050350225) 8.0 References None Page 3 of 3
Attachment A Pressurizer layout
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Attachment A Pressurizer Layout Note proximity of heater cables to inner radius region Page 2 of 2