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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 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) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program 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-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, 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-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 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 L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System 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 ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 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) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, 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 Applications2023-03-27027 March 2023 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 2024-02-05
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NEXT era*** November 27, 2013 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, POINT BEACH NRC 2013-0105 10 CFR 50.55a 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 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 DIFFICUL TV 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 1 0-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:
Insulation removal: Examination area preparation:
Ultrasonic examination:
Insulation installation:
Scaffold removal: Total person hours: 4 personnel x 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 3 personnel x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2 personnel x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 personnel x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3 personnel x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 4 personnel x 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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. Page 2 of 3
7.0 Precedents
NRC Safety Evaluation to Kewaunee Nuclear Power Plant, dated February 18, 2005, Kewaunee Nuclear Power Plant-Fourth 1 0-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
- (!>--... \ ,/* :*.l .... l il / { l i ' l I 'I I ,II --! *,I ., _../ ! (') \ *, \ I *.\ \ \ \\ . -** \\ ... \ ... ,<-;"!'. ) .. /\\ ,.-* .-** Attachment A Pressurizer layout Page 1 of 2 0 Attachment A Pressurizer Layout Note proximity of heater cables to inner radius region Page 2 of 2