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| | number = ML15005A069 | | | number = ML15005A069 |
| | issue date = 01/06/2015 | | | issue date = 01/06/2015 |
| | title = Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief (TAC No. MF3406 and MF3407) | | | title = Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief |
| | author name = Lamb J | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 January 6, 2015 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 6, 2015 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OYSTER CREEK NUCLEAR GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF (TAC NOS. MF3406 AND MF3407) | | OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF (TAC NOS. MF3406 AND MF3407) |
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 1 0-year in service inspection interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAI is contained in the enclosure. | | |
| A draft of these questions was previously sent to Mr. Dave Helker of your staff on August 28, 2014, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. | | By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 10-year in service inspection interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAI is contained in the enclosure. A draft of these questions was previously sent to Mr. Dave Helker of your staff on August 28, 2014, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. |
| A conference call was held on December 23, 2014, and Mr. Tom Loomis of your staff agreed that Exelon would respond to the RAI in 30 days from the date of the letter. Please note that if you do not respond to the RAI within 30 days from the date of the letter, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information." | | A conference call was held on December 23, 2014, and Mr. Tom Loomis of your staff agreed that Exelon would respond to the RAI in 30 days from the date of the letter. Please note that if you do not respond to the RAI within 30 days from the date of the letter, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information." |
| M. Pacilio If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100. | | |
| Docket No. 50-219 | | M. Pacilio If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100. |
| | G. Lamb, Senior Project Manager t Licensing Branch 1-2 1sion of Operating Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-219 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/encl: Distribution via Listserv G. Lamb, Senior Project Manager t Licensing Branch 1-2 1sion of Operating Reactor Licensing ice of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS R-44 AND R-45 OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATING COMPANY, LLC DOCKET NO. 50-219 By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation Company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 1 0-year inservice inspection (lSI) interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAis are below. 1.0 REQUEST FOR ADDITIONAL INFORMATION CRAll 1) The examination limitations for ASME Code, Section XI, Examination Category B-F, Item B5.11, weld NR02 4-565D, N1 D Recirc Outlet Nozzle-to-Safe End, is discussed in the licensee's RAI response dated November 14, 2014. Attachment A.40 to the licensee's submittal dated January 7, 2014, contains a sketch of this weld. However, this sketch appears to be a drawing of a cladded nozzle "set-in" design weld rather than a nozzle-to-safe end weld. Please clarify this sketch or provide another sketch clearly indicating the Item B5.11 nozzle and the safe end components. | | Request for Additional Information cc w/encl: Distribution via Listserv |
| Please include sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities.
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| These are typically the most highly stressed regions, exposed to operating environments where service degradation would be expected to occur, should it be manifested.
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| The photos provided in the original submittal in Attachments A30 and A40 for the Item B5.11 welds are indecipherable.
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| Please provide replacement images that are clear or alternative information to clarify the limitations these photos were intended to represent.
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| Enclosure 2) For R-45, Examination Category B-J, Item 89.11 welds NE 5-0002, NE 5-0022A, and NG-5-D-0002, shown in Figures 2, 3, and 4, respectively, please provide cross-sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities.
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| M. Pacilio If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100.
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| Docket No. 50-219
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| ==Enclosure:==
| | REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS R-44 AND R-45 OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATING COMPANY, LLC DOCKET NO. 50-219 By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation Company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 10-year inservice inspection (lSI) interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAis are below. |
| | 1.0 REQUEST FOR ADDITIONAL INFORMATION CRAll |
| | : 1) The examination limitations for ASME Code, Section XI, Examination Category B-F, Item B5.11, weld NR02 4-565D, N1 D Recirc Outlet Nozzle-to-Safe End, is discussed in the licensee's RAI response dated November 14, 2014. Attachment A.40 to the licensee's submittal dated January 7, 2014, contains a sketch of this weld. However, this sketch appears to be a drawing of a cladded nozzle "set-in" design weld rather than a nozzle-to-safe end weld. Please clarify this sketch or provide another sketch clearly indicating the Item B5.11 nozzle and the safe end components. Please include cross-sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities. These are typically the most highly stressed regions, exposed to operating environments where service degradation would be expected to occur, should it be manifested. |
| | The photos provided in the original submittal in Attachments A30 and A40 for the Item B5.11 welds are indecipherable. Please provide replacement images that are clear or alternative information to clarify the limitations these photos were intended to represent. |
| | Enclosure |
| | : 2) For R-45, Examination Category B-J, Item 89.11 welds NE 5-0002, NE 5-0022A, and NG-5-D-0002, shown in Figures 2, 3, and 4, respectively, please provide cross-sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities. |
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| Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
| | ML15005A069 *via memo OFFICE DORLILPL 1-2/PM DORLILPL 1-2/LA DE/EVIB/BC DORLILPL 1-2/BC DORL/LPL 1-2/PM NAME Jlamb ABaxter SRosenberg* MKhanna Jlamb DATE 12/19/2014 12/22/2014 12/16/2014 1/5/2015 1/6/2015}} |
| PUBLIC LPL 1-2 R/F RidsRgn1 MaiiCenter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrPMOysterCreek Resource RidsNrrLAABaxter Resource RidsNrrDorllpl1-2 Resource JJenkins, NRR SCumblidge, NRR SRosenberg, NRR ADAMS Accession No.: ML15005A069 OFFICE DORLILPL 1-2/PM DORLILPL 1-2/LA NAME Jlamb ABaxter DATE 12/19/2014 12/22/2014 Sincerely, IRA! John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| *via memo DE/EVIB/BC DORLILPL 1-2/BC DORL/LPL 1-2/PM SRosenberg*
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| MKhanna Jlamb 12/16/2014 1/5/2015 1/6/2015 OFFICIAL RECORD COPY}} | |
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Category:Letter
MONTHYEARML24274A0822024-09-25025 September 2024 Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000219/20240022024-09-0505 September 2024 – NRC Inspection Report 05000219/2024002 and 07200015/2024001 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24214A0372024-08-0101 August 2024 License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements ML24179A1842024-07-23023 July 2024 June 20, 2024, Clarification Call on Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000219/20240012024-05-14014 May 2024 Decommissioning Intl, LLC Oyster Creek Nuclear Generating Station - NRC Inspection Report No. 05000219/2024001 ML24120A0412024-04-29029 April 2024 Annual Radioactive Environmental Operating Report for 2023 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24120A0402024-04-29029 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24094A2142024-04-19019 April 2024 Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24089A2492024-03-29029 March 2024 Reply to Notice of Violation EA-2024-024 L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24085A7902024-03-28028 March 2024 – Preapplication Readiness Assessment of the License Termination Plan ML24081A2882024-03-21021 March 2024 Request Preliminary Review and Feedback on Chapter 6 of the Draft License Termination Plan ML24046A1242024-02-29029 February 2024 – NRC Inspection Report 05000219/2023003 ML24033A3272024-02-0202 February 2024 Request Preliminary Review and Feedback on Chapter 5 of the Draft License Termination Plan ML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML21099A0442021-04-0808 April 2021 Enclosure - Request for Additional Information Related to Request for Approval of Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Only Emergency Plan Holtec Decommissioning International, LLC ML20335A3102020-11-30030 November 2020 RAI November 2020 Part 73 FOF Exemption Request ML20297A2382020-10-22022 October 2020 Fleet DQAP RAIs - Enclosure ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20134H8732020-05-12012 May 2020 E-mail - Request for Additional Information: Oyster Creek Request for Temporary Exemption from Part 73, Appendix B Requirements ML19263D2142019-09-20020 September 2019 Hdi PSDAR Environmental RAI Enclosure (002) ML19158A2772019-05-28028 May 2019 NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS ML19025A1172019-01-24024 January 2019 NRR E-mail Capture - for Your Action - RAI for Oyster Creek EP Exemption (Change to Adiabatic Heat-Up Calculation) ML18256A0022018-09-12012 September 2018 NRR E-mail Capture - for Your Action: RAIs for Oyster Creek Post Shutdown Decommissioning Activities Report (PSDAR) ML18135A0732018-05-15015 May 2018 NRR E-mail Capture - RAIs - Oyster Creek - Request Approval of the Decommissioning Quality Assurance Program ML18068A6582018-03-0909 March 2018 NRR E-mail Capture - RAIs - Oyster Creek Defueled TS LAR ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18024B0642018-01-24024 January 2018 NRR E-mail Capture - for Your Action - RAI for Oyster Creek Permanently Defueled EP and EAL Scheme LAR (CAC No. MG0160; EPID: L-2017-LLA-0307) ML18012A0782018-01-12012 January 2018 NRR E-mail Capture - for Your Review - Draft RAI for Oyster Creek Permanently Defueled EP and EAL Scheme LAR (CAC No. MG0160; EPID: L-2017-LLA-0307) ML18003A4122018-01-0303 January 2018 NRR E-mail Capture - for Your Action - RAI - Oyster Creek BWRVIP LAR (CAC No. MG0180; EPID No. L-LLA-2017-0304) ML17320A6372017-11-16016 November 2017 NRR E-mail Capture - Oyster Creek Nuclear Generating Station - Request for Additional Information Regarding License Amendment Request for Emergency Plan Exemption (CAC No. MG0153; EPID L-2017-LLE-0020) ML17319A9422017-11-15015 November 2017 NRR E-mail Capture - Oyster Creek Nuclear Generating Station - Request for Additional Information Regarding License Amendment Request for Emergency Plan Exemption (CAC No. MG0153; EPID L-2017-LLE-0020) ML17208A7472017-09-14014 September 2017 Request for Additional Information, License Amendment Request to Revise the Site Emergency Plan for On-Shift and Emergency Response Organization Staffing for Permanently Defueled Condition ML17136A3852017-05-12012 May 2017 NRR E-mail Capture - (External_Sender) Oyster Creek Response to NRC Flood MSA Audit Review Questions ML17038A5152017-02-0303 February 2017 NRR E-mail Capture - (External_Sender) Oyster Creek Nuclear Generating Station Response to Environmental Questions Regarding the Mitigating Strategies Final Integrated Plan and SPF Instrumentation Compliance Letter ML16244A3112016-10-0707 October 2016 Request for Additional Information Regarding License Amendment Request for Technical Specifications Section 6.0, Administrative Controls for Permanently Defueled Condition ML16125A2452016-05-16016 May 2016 Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program ML16060A1722016-03-0707 March 2016 Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate and Spent Fuel Management Program ML16056A0012016-02-24024 February 2016 NRR E-mail Capture - Request for Additional Information - Oyster Creek Security Plan - Revision 14 ML17144A3702015-05-0606 May 2015 NRC Email J. Hughey( NRC) to Dave Distel (Exelon)- Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109, Dated May 6, 2015 ML15005A0692015-01-0606 January 2015 Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief ML14246A5182014-09-17017 September 2014 Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief ML14252A7032014-09-17017 September 2014 Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate and Annual Decommissioning Funding Status Reports ML14247A5862014-09-16016 September 2014 Request for Additional Information Regarding License Amendment Request to Revise Snubber Surveillance Requirements (Tac No. MF4124) ML14114A5632014-09-10010 September 2014 Request for Additional Information Regarding License Amendment Request Related to Reactor Building Vital Area Access Control ML14220A0272014-08-27027 August 2014 Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML14083A1602014-03-31031 March 2014 Request for Additional Information Regarding Bulletin 2012-01, Design Vulnerability in Electric Power System ML13351A3142013-12-20020 December 2013 Request for Additional Information Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power System. ML13268A0312013-11-0808 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13227A3042013-08-28028 August 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13196A3382013-07-15015 July 2013 2013 Decommissioning Fund Report RAI ML12229A4332012-09-0606 September 2012 Request for Additional Information Regarding Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 12 (TAC No. D91660) ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12032A1872012-02-21021 February 2012 Request for Additional Information Related to the Response to License Renewal Commitment No. 10 Regarding Thermal Aging Irradiation Embrittlement of Cast Austenitic Stainless Steel ML12025A2542012-01-23023 January 2012 Request for Additional Information - License Renewal Commitment Regarding Thermal Aging and Neutron Irradiation Embrittlement of CASS Materials ML1200603242012-01-19019 January 2012 Fleet, RAI, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-789 (N-789) ML1131200572011-11-22022 November 2011 Fleet - Bulletin 2011 01, Mitigating Strategies Request for Additional Information Regarding 60-Day Response ML1123604472011-08-24024 August 2011 E-mail, Miller to Loomis, Oyster Creek Flaw Evaluation Draft RAI Questions ML1120910012011-07-22022 July 2011 Generation Station - Licensed Operator Request for Additional Information ML1116805642011-07-0707 July 2011 Fleet, Request for Additional Information, 2011 Report on Status of Decommissioning Funding for Reactors 2021-04-08
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 6, 2015 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF (TAC NOS. MF3406 AND MF3407)
Dear Mr. Pacilio:
By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 10-year in service inspection interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAI is contained in the enclosure. A draft of these questions was previously sent to Mr. Dave Helker of your staff on August 28, 2014, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed.
A conference call was held on December 23, 2014, and Mr. Tom Loomis of your staff agreed that Exelon would respond to the RAI in 30 days from the date of the letter. Please note that if you do not respond to the RAI within 30 days from the date of the letter, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information."
M. Pacilio If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100.
G. Lamb, Senior Project Manager t Licensing Branch 1-2 1sion of Operating Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS R-44 AND R-45 OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATING COMPANY, LLC DOCKET NO. 50-219 By letter dated January 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML14321A044), Exelon Generation Company, LLC (Exelon or the licensee) submitted Requests for Relief R-44 AND R-45 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for Oyster Creek Nuclear Generating Station (Oyster Creek). The requests for relief apply to the fourth 10-year inservice inspection (lSI) interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Relief Requests R-44 and R-45, and has determined that a request for additional information (RAI) is needed to complete its technical review. The NRC staff's RAis are below.
1.0 REQUEST FOR ADDITIONAL INFORMATION CRAll
- 1) The examination limitations for ASME Code,Section XI, Examination Category B-F, Item B5.11, weld NR02 4-565D, N1 D Recirc Outlet Nozzle-to-Safe End, is discussed in the licensee's RAI response dated November 14, 2014. Attachment A.40 to the licensee's submittal dated January 7, 2014, contains a sketch of this weld. However, this sketch appears to be a drawing of a cladded nozzle "set-in" design weld rather than a nozzle-to-safe end weld. Please clarify this sketch or provide another sketch clearly indicating the Item B5.11 nozzle and the safe end components. Please include cross-sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities. These are typically the most highly stressed regions, exposed to operating environments where service degradation would be expected to occur, should it be manifested.
The photos provided in the original submittal in Attachments A30 and A40 for the Item B5.11 welds are indecipherable. Please provide replacement images that are clear or alternative information to clarify the limitations these photos were intended to represent.
Enclosure
- 2) For R-45, Examination Category B-J, Item 89.11 welds NE 5-0002, NE 5-0022A, and NG-5-D-0002, shown in Figures 2, 3, and 4, respectively, please provide cross-sectional plots showing volumetric coverage obtained with specific volumetric coverages near the inner surface, using appropriate ultrasonic wave angles and modalities.
ML15005A069 *via memo OFFICE DORLILPL 1-2/PM DORLILPL 1-2/LA DE/EVIB/BC DORLILPL 1-2/BC DORL/LPL 1-2/PM NAME Jlamb ABaxter SRosenberg* MKhanna Jlamb DATE 12/19/2014 12/22/2014 12/16/2014 1/5/2015 1/6/2015