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| | issue date = 05/14/2015 | | | issue date = 05/14/2015 |
| | title = Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B | | | title = Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B |
| | author name = McCartney E | | | author name = Mccartney E |
| | author affiliation = NextEra Energy Point Beach, LLC | | | author affiliation = NextEra Energy Point Beach, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:May 14, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Unit 1 Dockets 50-266 Renewed License Nos. DPR-24 Relief Requests VR-01 Extension to Perform lnservice Testing of 1 CC-00763B NRC 2015-0025 10 CFR 50.55a Pursuant to 10 CFR 50.55a(z)(2), *this letter requests that the Nuclear Regulatory Commission (NRC) grant NextEra Energy Point Beach, LLC (NextEra), relief on a one-time basis from the requirements of Section l-1350(a) of Mandatory Appendix I of the American Society of Mechanical Engineer's Operation and Maintenance (OM) Code, 2004 Edition through the 2006 Addenda. Relief is requested from performing inservice testing (1ST) of relief valve 1 CC-00763B as detailed in Relief Request VR-01 (Enclosure 1). This relief request applies to Unit 1 of Point Beach Nuclear Plant (PBNP). Compliance with the OM Code would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The proposed alternative will not decrease the level of quality or safety of the relief valve until the end of refueling outage U1 R36, currently scheduled to commence March 12, 2016. The requested duration of this relief request is 7 months. NextEra requests the NRC to review and approve the subject relief request on or before August 15, 2015. If necessary, NextEra personnel will be available to meet with your staff to discuss any concerns you may have. This letter contains no new Regulatory Commitments or revisions to existing Regulatory Commitments. | | {{#Wiki_filter:May 14, 2015 NRC 2015-0025 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Unit 1 Dockets 50-266 Renewed License Nos. DPR-24 Relief Requests VR-01 Extension to Perform lnservice Testing of 1CC-00763B Pursuant to 10 CFR 50.55a(z)(2), *this letter requests that the Nuclear Regulatory Commission (NRC) grant NextEra Energy Point Beach, LLC (NextEra), relief on a one-time basis from the requirements of Section l-1350(a) of Mandatory Appendix I of the American Society of Mechanical Engineer's Operation and Maintenance (OM) Code, 2004 Edition through the 2006 Addenda. |
| | Relief is requested from performing inservice testing (1ST) of relief valve 1CC-00763B as detailed in Relief Request VR-01 (Enclosure 1). |
| | This relief request applies to Unit 1 of Point Beach Nuclear Plant (PBNP). Compliance with the OM Code would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The proposed alternative will not decrease the level of quality or safety of the relief valve until the end of refueling outage U1 R36, currently scheduled to commence March 12, 2016. The requested duration of this relief request is 7 months. |
| | NextEra requests the NRC to review and approve the subject relief request on or before August 15, 2015. If necessary, NextEra personnel will be available to meet with your staff to discuss any concerns you may have. |
| | This letter contains no new Regulatory Commitments or revisions to existing Regulatory Commitments. |
| If you have questions or require additional information, please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845. | | If you have questions or require additional information, please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845. |
| NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 Document Control Desk Page 2 Very truly yours, NextEra Energy Point Beach, LLC Eric McCartney Site Vice-President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW ENCLOSURE lnservice Testing Relief Request No. VR-01 Point Beach Unit 1 1 B RCP Cooling Water Return Header Relief Valve Test Proposed Alternative In Accordance with 10 CFR 50.55a(z)(2) | | NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 |
| Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety | | |
| : 1. ASME Code Components Affected 1 B RCP Component Cooling Water Return Header Relief Valve (1 CC-00763B) | | Document Control Desk Page 2 Very truly yours, NextEra Energy Point Beach, LLC Eric McCartney Site Vice-President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW |
| This is a Class 2 relief valve located in the CCW return header from the RCP 1 P-1 B, between 1 CC-00761 B, RCP thermal barrier cooler outlet isolation valve and the containment penetration. | | |
| Valve 1 CC-00763B performs an ACTIVE safety function in the OPEN direction to provide overpressure protection for the low pressure CCW penetration piping and components. | | ENCLOSURE lnservice Testing Relief Request No. VR-01 Point Beach Unit 1 1B RCP Cooling Water Return Header Relief Valve Test Proposed Alternative In Accordance with 10 CFR 50.55a(z)(2) |
| | Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety |
| | : 1. ASME Code Components Affected 1B RCP Component Cooling Water Return Header Relief Valve (1 CC-00763B) |
| | This is a Class 2 relief valve located in the CCW return header from the RCP 1P-1 B, between 1CC-00761 B, RCP thermal barrier cooler outlet isolation valve and the containment penetration. Valve 1CC-00763B performs an ACTIVE safety function in the OPEN direction to provide overpressure protection for the low pressure CCW penetration piping and components. |
| : 2. Applicable Code and Addenda The Fifth Ten-Year Interval commenced on 09/01/2012 and 10/01/2012 for Point Beach Nuclear Plant Units 1 and Unit 2, respectively. | | : 2. Applicable Code and Addenda The Fifth Ten-Year Interval commenced on 09/01/2012 and 10/01/2012 for Point Beach Nuclear Plant Units 1 and Unit 2, respectively. |
| The Code of Record for the Point Beach Units 1 and 2, Fifth Ten-Year Interval lnservice Testing (1ST) Program is the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). 3. Applicable Code Requirement ASME OM Code Mandatory Appendix I lnservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants, Section 1-1350 Test Frequency, Classes 2 and 3 Pressure Relief Valves. l-1350(a) 1 0-year Test Interval, Classes 2 and 3 pressure relief valves, with the exception of PWR main steam safety valves, shall be tested every 10 years, starting with initial electric power generation. | | The Code of Record for the Point Beach Units 1 and 2, Fifth Ten-Year Interval lnservice Testing (1ST) Program is the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). |
| No maximum limit is specified for the number of valves to be tested during any single plant operating cycle; however, a minimum of 20% of the valves from each valve group shall be tested within any 48-month interval. | | |
| This 20% shall consist of valves that have not been tested during the current 10 year test interval, if they exist. The test interval for any individual valve shall not exceed 10 years. 4. Reason for Request Relief valve 1 CC-00763B, 1 P-1 B RCP Component Cooling Return Header Relief Valve testing was to occur in the Unit 1, Refueling Outage 35 (U1 R35) in October of 2014. The valve is one of four valves in Group 1-6 of the Point Beach Nuclear Plant lnservice Testing Program. The valve was inadvertently omitted from the refueling outage schedule. | | ===3. Applicable Code Requirement=== |
| This omission is being reviewed in the corrective action program. Page 1 of 3 The omission was discovered on October 27, 2014. The Component Cooling Water System had already been filled and vented in preparation for start-up. | | ASME OM Code Mandatory Appendix I lnservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants, Section 1-1350 Test Frequency, Classes 2 and 3 Pressure Relief Valves. |
| Plant personnel had also identified that no spare parts were available to support testing. To align the Component Cooling Water System to support relief valve testing and perform testing without adequate spares would have placed Point Beach at a significant disadvantage. | | l-1350(a) 10-year Test Interval, Classes 2 and 3 pressure relief valves, with the exception of PWR main steam safety valves, shall be tested every 10 years, starting with initial electric power generation. No maximum limit is specified for the number of valves to be tested during any single plant operating cycle; however, a minimum of 20% of the valves from each valve group shall be tested within any 48-month interval. This 20% shall consist of valves that have not been tested during the current 10 year test interval, if they exist. The test interval for any individual valve shall not exceed 10 years. |
| 1 CC-00763B was last tested on September 12, 2005. The 1 0-year test interval will expire on September 12, 2015. The next scheduled opportunity for testing will be in Refueling Outage U 1 R36 which is scheduled to begin on March 12, 2016. A seven month extension beyond the 10-Year testing interval is requested to allow time for testing to be completed.
| | |
| In accordance with 10 CFR 50.55a(a)(3)(ii), Point Beach requests relief from applicable ASME Code requirements for 1 CC-00763B relief valve testing until the next Unit 1 refueling outage, U 1 R36. NUREG-1482, Rev 2, Section 2.5, Relief Request and Proposed Alternatives, states that a licensee may propose alternatives to ASME Code requirements if compliance with the specified requirement would result in hardship or unusual difficulty without compensating increase in level of quality and safety. Performance of this testing would require the isolation of component cooling water to the 1 P-1 B RCP. This cannot be performed with the plant on-line. Performance of this testing would require the plant to incur additional thermal cycles and the stopping and starting of several major plant components which induces additional wear and risk unnecessarily. | | ===4. Reason for Request=== |
| : 5. Proposed Alternative and Basis for Use There are four relief valves in this Group, two from each unit. There have been four test completed over the last 10 years of which one was slightly out of tolerance. | | Relief valve 1CC-00763B, 1P-1 B RCP Component Cooling Return Header Relief Valve testing was to occur in the Unit 1, Refueling Outage 35 (U1 R35) in October of 2014. The valve is one of four valves in Group 1-6 of the Point Beach Nuclear Plant lnservice Testing Program. The valve was inadvertently omitted from the refueling outage schedule. This omission is being reviewed in the corrective action program. |
| The singular out of tolerance test result was a reading of one psi (0.6%) above the upper acceptance limit. The valve was refurbished for use. The remaining three tests were successfully completed. | | Page 1 of 3 |
| Valve As-Found Test Results 1CC-00763B 10/18/2005 SAT, 144 and 144.2 psig 2CC-00763A 12/08/2009 SAT, 147.9 and 148.1 psig 2CC-00763B 4/14/2014 SAT, 149.1 psig 1CC-00763A 10/30/2014 UNSAT, 155.5 psig (0.6% high) A review of the performance data for the specific valve serial number (N78089-00-0003) was performed. | | |
| The valve was purchased and factory set at 145 psi on May 25, 1993 under PO 204881000 Rev 05. The valve was placed into service in October of 1993 at location 2CC-00763A under WO 935257. The valve was removed from service and tested in 1998 under WO 9809847. The setpoint failed low at 140 psig (0.65 psi or 0.45% low). The valve was set at 150 psig per a design change and tested on April 26, 2002. The valve was installed in 2CC-00763B under WO 0205878. The valve was removed from service and tested in April of 2005 under WO 0415238. The setpoint failed high at 159.1 psig (4.6 psi or 3.06% high). The most recent as-left test was performed on September 9, 2005 under PO 0305004. The valve was installed in October of 2005 at Page 2 of 3 1 CC-007638. | | The omission was discovered on October 27, 2014. The Component Cooling Water System had already been filled and vented in preparation for start-up. Plant personnel had also identified that no spare parts were available to support testing. To align the Component Cooling Water System to support relief valve testing and perform testing without adequate spares would have placed Point Beach at a significant disadvantage. |
| The 10 year test interval expires September 9, 2015, while the next Unit 1 Outage begins March 12, 2016. The historical data review and the as found setpoint deviation does provide the objective evidence for determining the future quality and safety of the component cooling system. While the as found setpoint testing for this valve has not been consistent, the setpoint deviation is inconsequential with respect to challenging any system design criteria of the component cooling system. Thus the historical setpoint deviation is inconsequential with respect to the risk associated with additional thermal cycles, equipment cycles, and the induce wear associated with these cycles. 6. Duration of Proposed Alternative Completion of the next Unit 1 refueling outage U 1 R36 ending approximately June 1, 2016. 7. Precedents | | 1CC-00763B was last tested on September 12, 2005. The 10-year test interval will expire on September 12, 2015. The next scheduled opportunity for testing will be in Refueling Outage U 1R36 which is scheduled to begin on March 12, 2016. A seven month extension beyond the 10-Year testing interval is requested to allow time for testing to be completed. |
| : 1. NRC Safety Evaluation dated October 29, 2001 (TAC No. MB2979) Donald C. Cook Nuclear Plant, Unit 2, Docket No. 50-316. 2. NRC Safety Evaluation dated April1, 2004 (TAC No. MC2046), Point Beach Nuclear Plant, Unit Docket No. 50-266. 3. NRC Safety Evaluation dated March 5, 2009 (TAC No. ME0784), Salem Generating Station, Unit 2, Docket No, 50-311. Page 3 of 3}} | | In accordance with 10 CFR 50.55a(a)(3)(ii), Point Beach requests relief from applicable ASME Code requirements for 1CC-00763B relief valve testing until the next Unit 1 refueling outage, U1R36. NUREG-1482, Rev 2, Section 2.5, Relief Request and Proposed Alternatives, states that a licensee may propose alternatives to ASME Code requirements if compliance with the specified requirement would result in hardship or unusual difficulty without compensating increase in level of quality and safety. |
| | Performance of this testing would require the isolation of component cooling water to the 1P-1 B RCP. This cannot be performed with the plant on-line. Performance of this testing would require the plant to incur additional thermal cycles and the stopping and starting of several major plant components which induces additional wear and risk unnecessarily. |
| | : 5. Proposed Alternative and Basis for Use There are four relief valves in this Group, two from each unit. There have been four test completed over the last 10 years of which one was slightly out of tolerance. The singular out of tolerance test result was a reading of one psi (0.6%) above the upper acceptance limit. The valve was refurbished for use. The remaining three tests were successfully completed. |
| | Valve As-Found Test Results 1CC-00763B 10/18/2005 SAT, 144 and 144.2 psig 2CC-00763A 12/08/2009 SAT, 147.9 and 148.1 psig 2CC-00763B 4/14/2014 SAT, 149.1 psig 1CC-00763A 10/30/2014 UNSAT, 155.5 psig (0.6% high) |
| | A review of the performance data for the specific valve serial number (N78089-00-0003) was performed. |
| | The valve was purchased and factory set at 145 psi on May 25, 1993 under PO 204881000 Rev 05. The valve was placed into service in October of 1993 at location 2CC-00763A under WO 935257. The valve was removed from service and tested in 1998 under WO 9809847. The setpoint failed low at 140 psig (0.65 psi or 0.45% low). |
| | The valve was set at 150 psig per a design change and tested on April 26, 2002. The valve was installed in 2CC-00763B under WO 0205878. The valve was removed from service and tested in April of 2005 under WO 0415238. The setpoint failed high at 159.1 psig (4.6 psi or 3.06% high). The most recent as-left test was performed on September 9, 2005 under PO 0305004. The valve was installed in October of 2005 at Page 2 of 3 |
| | |
| | 1CC-007638. The 10 year test interval expires September 9, 2015, while the next Unit 1 Outage begins March 12, 2016. |
| | The historical data review and the as found setpoint deviation does provide the objective evidence for determining the future quality and safety of the component cooling system. |
| | While the as found setpoint testing for this valve has not been consistent, the setpoint deviation is inconsequential with respect to challenging any system design criteria of the component cooling system. Thus the historical setpoint deviation is inconsequential with respect to the risk associated with additional thermal cycles, equipment cycles, and the induce wear associated with these cycles. |
| | : 6. Duration of Proposed Alternative Completion of the next Unit 1 refueling outage U 1R36 ending approximately June 1, 2016. |
| | : 7. Precedents |
| | : 1. NRC Safety Evaluation dated October 29, 2001 (TAC No. MB2979) Donald C. Cook Nuclear Plant, Unit 2, Docket No. 50-316. |
| | : 2. NRC Safety Evaluation dated April1, 2004 (TAC No. MC2046), Point Beach Nuclear Plant, Unit Docket No. 50-266. |
| | : 3. NRC Safety Evaluation dated March 5, 2009 (TAC No. ME0784), Salem Generating Station, Unit 2, Docket No, 50-311. |
| | Page 3 of 3}} |
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Category:Code Relief or Alternative
MONTHYEARML23279A0672023-11-0909 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 ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 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) ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) NRC 2013-0020, CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval2013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13079A1412013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12286A1042012-11-15015 November 2012 Evaluation of Relief Requests RR-2 & RR-3 (ME7974 & ME7975) ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 ML0527001972006-01-18018 January 2006 Relief Request - Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 ML0526503122005-09-27027 September 2005 Relief Requests - the Previsions of ASME Section XI, IWA-5244, Buried Components, RR-1-26 and RR-2-34 NRC 2005-0084, Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 22005-07-0101 July 2005 Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 NRC 2005-0016, Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 162005-02-0404 February 2005 Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 NRC 2005-0015, Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 152005-01-21021 January 2005 Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 ML0408601612004-04-0101 April 2004 Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0323104022003-09-10010 September 2003 Relief, MR 02 018-2 Pertaining to Reactor Vessel Closure Head Penetration Repair ML0306203282003-03-21021 March 2003 Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404 ML0225401092003-03-21021 March 2003 Relief Request No 8 - Requirement for Scheduling of Components for Examination ML0302101262003-02-27027 February 2003 Relief, Alternative to Examine All Three Vessels of the Regenerative Heat Exchanger, MB5401 & MB5402 ML0225300062002-10-0808 October 2002 Code Relief, ASME Code Section XI, Relief Request 5 Regarding Visual Examination of Insulted Bolting on Borated Systems ML0225300232002-10-0808 October 2002 Relief, Granted for ASME Code Section XI, Relief Request 6 Regarding Evaluation of Leakage with Bolting In-Place NRC 2002-0073, Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-22002-08-28028 August 2002 Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 2023-11-09
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2022-161, U1R40 Steam Generator Tube Inspection Report2022-10-13013 October 2022 U1R40 Steam Generator Tube Inspection Report 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 L-2022-124, Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections2022-07-20020 July 2022 Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections 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 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 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 2019-0040, Owner'S Activity Report: 48th Year Iwl for Class CC Examinations2019-12-18018 December 2019 Owner'S Activity Report: 48th Year Iwl for Class CC Examinations NRC 2019-0020, Refueling Outage U1 R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2019-07-11011 July 2019 Refueling Outage U1 R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2018-0005, Refueling Outage U1R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2018-01-26026 January 2018 Refueling Outage U1R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2017-0046, Spring 2017 (U2R35) Steam Generator Tube Inspection Report2017-09-21021 September 2017 Spring 2017 (U2R35) Steam Generator Tube Inspection Report NRC 2017-0030, Refueling Outage U2R35 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2017-07-12012 July 2017 Refueling Outage U2R35 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2016-0044, Spring 2016 U1R36 180-Day Steam Generator Tube Inspection Report2016-09-20020 September 2016 Spring 2016 U1R36 180-Day Steam Generator Tube Inspection Report NRC 2016-0026, Refueling Outage U1 R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2016-06-30030 June 2016 Refueling Outage U1 R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2016-0004, Refueling Outage U2R34 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2016-01-26026 January 2016 Refueling Outage U2R34 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B NRC 2015-0010, Filing of Owner'S Inservice Inspection Summary Report for Tendon Surveillance and Concrete Containment Examinations2015-02-27027 February 2015 Filing of Owner'S Inservice Inspection Summary Report for Tendon Surveillance and Concrete Containment Examinations NRC 2015-0009, Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueliong Outage U1R352015-01-29029 January 2015 Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueliong Outage U1R35 NRC 2015-0008, Filing of Owner'S Inservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U1R352015-01-29029 January 2015 Filing of Owner'S Inservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U1R35 NRC 2014-0048, Submittal of Filing of Owner'S Lnservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R332014-07-15015 July 2014 Submittal of Filing of Owner'S Lnservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R33 NRC 2014-0049, Submittal of Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueling Outage U2R332014-07-15015 July 2014 Submittal of Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueling Outage U2R33 NRC 2014-0022, 10 CFR 50.55a Requests Relief Requests RR-8 and RR-9 Fifth Ten-Year Lnservice Inspection Program Interval2014-05-13013 May 2014 10 CFR 50.55a Requests Relief Requests RR-8 and RR-9 Fifth Ten-Year Lnservice Inspection Program Interval NRC 2013-0108, Response to 10 CFR 50.54(f) Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns2013-11-27027 November 2013 Response to 10 CFR 50.54(f) Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns NRC 2013-0067, Spring 2013 Unit 1(U1R34) Steam Generator Tube Inspection Report2013-09-24024 September 2013 Spring 2013 Unit 1(U1R34) Steam Generator Tube Inspection Report NRC-2013-0008, Submittal of Fall 2012 Steam Generator Tube Inspection Report2013-05-16016 May 2013 Submittal of Fall 2012 Steam Generator Tube Inspection Report NRC 2013-0018, CFR 50.55a Request. Relief Request RR-4L1 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspections Program Interval2013-03-19019 March 2013 CFR 50.55a Request. Relief Request RR-4L1 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspections Program Interval NRC 2013-0016, Filing of Owner'S Inservice Inspection Summary Report, IWE Class Mc and Iwl Class CC for Refueling Outage U2R322013-02-19019 February 2013 Filing of Owner'S Inservice Inspection Summary Report, IWE Class Mc and Iwl Class CC for Refueling Outage U2R32 NRC 2013-0015, Filing of Owner'S Lnservice Lnspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R322013-02-19019 February 2013 Filing of Owner'S Lnservice Lnspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R32 NRC 2013-0009, Fall 2011 Refueling Outage (U1R33) Steam Generator Tube Inspection Report2013-01-31031 January 2013 Fall 2011 Refueling Outage (U1R33) Steam Generator Tube Inspection Report NRC 2012-0075, Fifth Interval Inservice Inspection Program Plan and Schedule2012-09-10010 September 2012 Fifth Interval Inservice Inspection Program Plan and Schedule NRC 2012-0015, Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report2012-05-29029 May 2012 Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report NRC 2012-0019, Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R332012-03-0707 March 2012 Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R33 NRC 2012-0014, Filing of Owner'S Containment Inservice Inspection Summary Report for Refueling Outage U1R332012-03-0202 March 2012 Filing of Owner'S Containment Inservice Inspection Summary Report for Refueling Outage U1R33 NRC 2012-0011, CFR 50.55a Request, Relief Requests RR-2 and RR-3, Fifth Ten-Year Inservice Inspection Program Interval2012-02-15015 February 2012 CFR 50.55a Request, Relief Requests RR-2 and RR-3, Fifth Ten-Year Inservice Inspection Program Interval NRC 2011-0083, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outrage U2R312011-09-12012 September 2011 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outrage U2R31 NRC 2011-0084, Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R312011-09-12012 September 2011 Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R31 NRC 2010-0096, Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R322010-06-25025 June 2010 Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R32 NRC 2010-0094, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R322010-06-24024 June 2010 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R32 ML1004707792010-02-11011 February 2010 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refuleing Outage U2R30 NRC 2009-0014, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R312009-02-10010 February 2009 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R31 NRC 2008-0043, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R292008-08-0404 August 2008 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R29 NRC 2008-0017, CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval2008-03-14014 March 2008 CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval ML0724806122007-09-20020 September 2007 Forth 10-Year Interval Inservice Inspection Request for Relief No. 15, Alternate Methods for Pressure Testing of Buried Components NRC 2007-0059, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R302007-08-0606 August 2007 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R30 NRC 2007-0048, Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R272007-06-15015 June 2007 Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R27 NRC 2007-0020, 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval2007-04-0606 April 2007 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval NRC 2007-0009, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R282007-02-19019 February 2007 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R28 NRC-2006-0078, 10 CFR 50.55a Request, Resubmittal of Relief Request 15, Fourth Ten-Year Interval Inservice Inspection (ISI) Program2006-11-20020 November 2006 10 CFR 50.55a Request, Resubmittal of Relief Request 15, Fourth Ten-Year Interval Inservice Inspection (ISI) Program NRC 2006-0019, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R292006-02-22022 February 2006 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R29 NRC 2006-0001, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing2006-01-20020 January 2006 Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing NRC 2005-0132, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R272005-10-11011 October 2005 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R27 2022-09-30
[Table view] Category:Letter type:NRC
MONTHYEARNRC 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 NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] |
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May 14, 2015 NRC 2015-0025 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Unit 1 Dockets 50-266 Renewed License Nos. DPR-24 Relief Requests VR-01 Extension to Perform lnservice Testing of 1CC-00763B Pursuant to 10 CFR 50.55a(z)(2), *this letter requests that the Nuclear Regulatory Commission (NRC) grant NextEra Energy Point Beach, LLC (NextEra), relief on a one-time basis from the requirements of Section l-1350(a) of Mandatory Appendix I of the American Society of Mechanical Engineer's Operation and Maintenance (OM) Code, 2004 Edition through the 2006 Addenda.
Relief is requested from performing inservice testing (1ST) of relief valve 1CC-00763B as detailed in Relief Request VR-01 (Enclosure 1).
This relief request applies to Unit 1 of Point Beach Nuclear Plant (PBNP). Compliance with the OM Code would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The proposed alternative will not decrease the level of quality or safety of the relief valve until the end of refueling outage U1 R36, currently scheduled to commence March 12, 2016. The requested duration of this relief request is 7 months.
NextEra requests the NRC to review and approve the subject relief request on or before August 15, 2015. If necessary, NextEra personnel will be available to meet with your staff to discuss any concerns you may have.
This letter contains no new Regulatory Commitments or revisions to existing Regulatory Commitments.
If you have questions or require additional information, please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845.
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 Very truly yours, NextEra Energy Point Beach, LLC Eric McCartney Site Vice-President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
ENCLOSURE lnservice Testing Relief Request No. VR-01 Point Beach Unit 1 1B RCP Cooling Water Return Header Relief Valve Test Proposed Alternative In Accordance with 10 CFR 50.55a(z)(2)
Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
- 1. ASME Code Components Affected 1B RCP Component Cooling Water Return Header Relief Valve (1 CC-00763B)
This is a Class 2 relief valve located in the CCW return header from the RCP 1P-1 B, between 1CC-00761 B, RCP thermal barrier cooler outlet isolation valve and the containment penetration. Valve 1CC-00763B performs an ACTIVE safety function in the OPEN direction to provide overpressure protection for the low pressure CCW penetration piping and components.
- 2. Applicable Code and Addenda The Fifth Ten-Year Interval commenced on 09/01/2012 and 10/01/2012 for Point Beach Nuclear Plant Units 1 and Unit 2, respectively.
The Code of Record for the Point Beach Units 1 and 2, Fifth Ten-Year Interval lnservice Testing (1ST) Program is the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
3. Applicable Code Requirement
ASME OM Code Mandatory Appendix I lnservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants, Section 1-1350 Test Frequency, Classes 2 and 3 Pressure Relief Valves.
l-1350(a) 10-year Test Interval, Classes 2 and 3 pressure relief valves, with the exception of PWR main steam safety valves, shall be tested every 10 years, starting with initial electric power generation. No maximum limit is specified for the number of valves to be tested during any single plant operating cycle; however, a minimum of 20% of the valves from each valve group shall be tested within any 48-month interval. This 20% shall consist of valves that have not been tested during the current 10 year test interval, if they exist. The test interval for any individual valve shall not exceed 10 years.
4. Reason for Request
Relief valve 1CC-00763B, 1P-1 B RCP Component Cooling Return Header Relief Valve testing was to occur in the Unit 1, Refueling Outage 35 (U1 R35) in October of 2014. The valve is one of four valves in Group 1-6 of the Point Beach Nuclear Plant lnservice Testing Program. The valve was inadvertently omitted from the refueling outage schedule. This omission is being reviewed in the corrective action program.
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The omission was discovered on October 27, 2014. The Component Cooling Water System had already been filled and vented in preparation for start-up. Plant personnel had also identified that no spare parts were available to support testing. To align the Component Cooling Water System to support relief valve testing and perform testing without adequate spares would have placed Point Beach at a significant disadvantage.
1CC-00763B was last tested on September 12, 2005. The 10-year test interval will expire on September 12, 2015. The next scheduled opportunity for testing will be in Refueling Outage U 1R36 which is scheduled to begin on March 12, 2016. A seven month extension beyond the 10-Year testing interval is requested to allow time for testing to be completed.
In accordance with 10 CFR 50.55a(a)(3)(ii), Point Beach requests relief from applicable ASME Code requirements for 1CC-00763B relief valve testing until the next Unit 1 refueling outage, U1R36. NUREG-1482, Rev 2, Section 2.5, Relief Request and Proposed Alternatives, states that a licensee may propose alternatives to ASME Code requirements if compliance with the specified requirement would result in hardship or unusual difficulty without compensating increase in level of quality and safety.
Performance of this testing would require the isolation of component cooling water to the 1P-1 B RCP. This cannot be performed with the plant on-line. Performance of this testing would require the plant to incur additional thermal cycles and the stopping and starting of several major plant components which induces additional wear and risk unnecessarily.
- 5. Proposed Alternative and Basis for Use There are four relief valves in this Group, two from each unit. There have been four test completed over the last 10 years of which one was slightly out of tolerance. The singular out of tolerance test result was a reading of one psi (0.6%) above the upper acceptance limit. The valve was refurbished for use. The remaining three tests were successfully completed.
Valve As-Found Test Results 1CC-00763B 10/18/2005 SAT, 144 and 144.2 psig 2CC-00763A 12/08/2009 SAT, 147.9 and 148.1 psig 2CC-00763B 4/14/2014 SAT, 149.1 psig 1CC-00763A 10/30/2014 UNSAT, 155.5 psig (0.6% high)
A review of the performance data for the specific valve serial number (N78089-00-0003) was performed.
The valve was purchased and factory set at 145 psi on May 25, 1993 under PO 204881000 Rev 05. The valve was placed into service in October of 1993 at location 2CC-00763A under WO 935257. The valve was removed from service and tested in 1998 under WO 9809847. The setpoint failed low at 140 psig (0.65 psi or 0.45% low).
The valve was set at 150 psig per a design change and tested on April 26, 2002. The valve was installed in 2CC-00763B under WO 0205878. The valve was removed from service and tested in April of 2005 under WO 0415238. The setpoint failed high at 159.1 psig (4.6 psi or 3.06% high). The most recent as-left test was performed on September 9, 2005 under PO 0305004. The valve was installed in October of 2005 at Page 2 of 3
1CC-007638. The 10 year test interval expires September 9, 2015, while the next Unit 1 Outage begins March 12, 2016.
The historical data review and the as found setpoint deviation does provide the objective evidence for determining the future quality and safety of the component cooling system.
While the as found setpoint testing for this valve has not been consistent, the setpoint deviation is inconsequential with respect to challenging any system design criteria of the component cooling system. Thus the historical setpoint deviation is inconsequential with respect to the risk associated with additional thermal cycles, equipment cycles, and the induce wear associated with these cycles.
- 6. Duration of Proposed Alternative Completion of the next Unit 1 refueling outage U 1R36 ending approximately June 1, 2016.
- 7. Precedents
- 1. NRC Safety Evaluation dated October 29, 2001 (TAC No. MB2979) Donald C. Cook Nuclear Plant, Unit 2, Docket No. 50-316.
- 2. NRC Safety Evaluation dated April1, 2004 (TAC No. MC2046), Point Beach Nuclear Plant, Unit Docket No. 50-266.
- 3. NRC Safety Evaluation dated March 5, 2009 (TAC No. ME0784), Salem Generating Station, Unit 2, Docket No, 50-311.
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