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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 G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000219 | | | docket = 05000219 |
| | license number = DPR-016 | | | license number = DPR-016 |
| | contact person = Lamb J G | | | contact person = Lamb J |
| | case reference number = TAC MF3406, TAC MF3407 | | | case reference number = TAC MF3406, TAC MF3407 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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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. ML 14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML 14321A044), 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. ML 14028A579), as supplemented by letter dated November 14, 2014 (ADAMS Accession No. ML 14321A044), 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.: ML 15005A069 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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2021-04-08
[Table view] |
Text
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