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| | issue date = 07/07/2014 | | | issue date = 07/07/2014 |
| | title = June 24, 2014, Summary of Telephone Conference Call Held Between the U.S. NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 36, Pertaining to the Byron Station and Braidwood Station, License Renewa | | | title = June 24, 2014, Summary of Telephone Conference Call Held Between the U.S. NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 36, Pertaining to the Byron Station and Braidwood Station, License Renewa |
| | author name = Robinson L R | | | author name = Robinson L |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = | | | addressee name = |
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| | docket = 05000454, 05000455, 05000456, 05000457 | | | docket = 05000454, 05000455, 05000456, 05000457 |
| | license number = | | | license number = |
| | contact person = Robinson L R, 415-4115 | | | contact person = Robinson L, 415-4115 |
| | case reference number = TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 | | | case reference number = TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 |
| | document type = Meeting Summary, Request for Additional Information (RAI) | | | document type = Meeting Summary, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2014 LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 |
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| LICENSEE: Exelon Generation Company, LLC | |
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| FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
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| The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the staff's draft request for additional information (DRAI),
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| Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAIs.
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| provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.
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| The applicant had an opportunity to comment on this summary.
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| /RA/ Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
| | ==SUMMARY== |
| | | OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) |
| Docket Nos. 50-454, 50-455, 50-456, and 50-457 | | The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the staffs draft request for additional information (DRAI), |
| | Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs DRAIs. provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items. |
| | The applicant had an opportunity to comment on this summary. |
| | /RA/ |
| | Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. List of Participants | | : 1. List of Participants |
| : 2. List of Draft Request for Additional Information | | : 2. List of Draft Request for Additional Information cc w/encls: Listserv |
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| cc w/encls: Listserv
| | ML14183B230 *concurred via email OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 07/2/14 07/7/14 07/7/14 07/7/14 |
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| ML14183B230 *concurred via email OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 07/2/14 07/7/14 07/7/14 07/7/14 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
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| DISTRIBUTION EMAIL: PUBLIC RidsNrrDlr Resource
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| RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource
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| RidsOgcMailCenter
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| RidsNrrPMByron Resource RidsNrrPMBraidwood Resource ----------------------------------
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| LRobinson DMcIntyre, OPA
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| EDuncan, RIII
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| JBenjamin, RIII
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| AGarmoe, RIII JMcGhee, RIII JRobbins, RIII
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| VMitlyng, RIII
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| PChandrathil, RIII ENCLOSURE 1 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS June 24, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) Allen Hiser NRC Seung Min NRC Aloysius Obodoako NRC John Hufnagel Exelon Generating Company, LLC (Exelon)
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| Al Fulvio Exelon Don Warfel Exelon Pete Tamburro Exelon Gary Becknell Exelon Don Brindle Exelon Ralph Wolen Exelon
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| ENCLOSURE 2 DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION June 24, 2014
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| The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
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| DRAI 3.1.2.3.4-1a Applicability
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| : Byron Station (Byron) and Braidwood Station (Braidwood), Unit 1
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| ===
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| Background===
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| : By letter date May 12, 2014, the applicant responded to request for additional information (RAI) 3.1.2.3.4-1 which addressed loss of fracture toughness in Byron and Braidwood, Unit 1 steam generator internal structural supports. In its response, the applicant revised license renewal application Table 3.1.2-4 by deleting the aging management review (AMR) line item which manages loss of fracture toughness for Byron and Braidwood, Unit 1 steam generator tube support lattice bar attachment components made of cast austenitic stainless steel (CASS). The deleted AMR line item indicated that these CASS components are exposed to treated water greater than 482 degrees Fahrenheit and may experience loss of fracture toughness due to thermal aging embrittlement. Byron and Braidwood manage both by the Steam Generators program.
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| The applicant further stated that loss of fracture toughness due to thermal aging embrittlement is not applicable to these steam generator CASS internal components (i.e., internal supports and structures and tube support plates and U-bend supports). The applicant reviewed the Grimes' letter to Walters on License Renewal Issue No. 98-0030, "Thermal Aging Embrittlement of Cast Stainless Steel Components," dated May 19, 2000, (ADAMS Accession Number ML003717179) and provided the following justification for excluding the steam generator tube support lattice bar attachment components, fabricated from SA-351 CF3M CASS, from being susceptible to thermal aging embrittlement.
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| The concern associated with thermal aging embrittlement is the reduction in fracture toughness of a component at low temperatures (i.e., room temperature) and the potential for non-ductile failure at low temperatures. The material properties at high temperature are not affected. Therefore, fracture of a CASS component is not expected at low temperatures. Since the loading on the CASS components at low temperature is negligible, the possibility that loss of fracture toughness would render the component incapable of performing its function without showing any visual evidence of cracking, deformation, or damage is also negligible.
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| The staff reviewed the Grimes' letter, dated May 19, 2000, and notes that it states that aging of CASS at reactor operating temperatures of 280-350 degrees Celsius (536-662 degrees Fahrenheit) can lead to changes in the mechanical properties of these materials, depending on the characteristics of the material and the environment to which the component is exposed.
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| The effects of thermal aging on materials include increases in the tensile strength, hardness, and Charpy impact energy transition temperature, as well as decreases in ductility, fracture toughness, and impact strength.
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| Further, NUREG/CR-6923, "Expert Panel Report on Proactive Materials Degradation Assessment" February 2007, states that:
| | ==SUMMARY== |
| | OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) |
| | DISTRIBUTION EMAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII |
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| Thermal aging of CASS at boiling water reactor and pressurized water reactor operating temperatures is characterized by an increase in hardness and tensile strength and a decrease in ductility, impact strength and toughness. In addition, the "brittle-ductile" transition temperature increases and the upper shelf decreases (emphasis added).
| | TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS June 24, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) |
| | Allen Hiser NRC Seung Min NRC Aloysius Obodoako NRC John Hufnagel Exelon Generating Company, LLC (Exelon) |
| | Al Fulvio Exelon Don Warfel Exelon Pete Tamburro Exelon Gary Becknell Exelon Don Brindle Exelon Ralph Wolen Exelon ENCLOSURE 1 |
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| The upper shelf decrease described in NUREG/CR-6923 relates directly to behavior of CASS at operating temperatures, contrary to the assertion in the RAI response that the concerns with thermal aging embrittlement only apply at low temperatures. | | DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION June 24, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA). |
| | DRAI 3.1.2.3.4-1a Applicability: |
| | Byron Station (Byron) and Braidwood Station (Braidwood), Unit 1 |
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| As cited in the Grimes' letter, thermal aging of CASS results in reduced toughness, which means that the aged CASS component can tolerate smaller flaw sizes. Since the toughness of CASS is not directly measureable, the Grimes' letter and the Generic Aging Lessons Learned (GALL) Report cite that thermal aging of CASS can be appropriately managed by inspections to demonstrate that flaws of a potentially critical size are not present in the CASS component.
| | ==Background:== |
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| In addition, GALL Report AMP XI.M12 states that for high-molybdenum content steels (SA-351 Grades CF3M, CF3MA, and CF8M or other steels with 2.0 to 3.0 wt. percent Mo), static-cast steels with >14 percent ferrite and centrifugal-cast steels with >20 percent ferrite are potentially susceptible to thermal embrittlement. Static-cast high-molybdenum steels with 14 percent ferrite and centrifugal-cast high-molybdenum steels with 20 percent ferrite are not susceptible. | | By letter date May 12, 2014, the applicant responded to request for additional information (RAI) 3.1.2.3.4-1 which addressed loss of fracture toughness in Byron and Braidwood, Unit 1 steam generator internal structural supports. In its response, the applicant revised license renewal application Table 3.1.2-4 by deleting the aging management review (AMR) line item which manages loss of fracture toughness for Byron and Braidwood, Unit 1 steam generator tube support lattice bar attachment components made of cast austenitic stainless steel (CASS). The deleted AMR line item indicated that these CASS components are exposed to treated water greater than 482 degrees Fahrenheit and may experience loss of fracture toughness due to thermal aging embrittlement. Byron and Braidwood manage both by the Steam Generators program. |
| | The applicant further stated that loss of fracture toughness due to thermal aging embrittlement is not applicable to these steam generator CASS internal components (i.e., internal supports and structures and tube support plates and U-bend supports). The applicant reviewed the Grimes letter to Walters on License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Stainless Steel Components, dated May 19, 2000, (ADAMS Accession Number ML003717179) and provided the following justification for excluding the steam generator tube support lattice bar attachment components, fabricated from SA-351 CF3M CASS, from being susceptible to thermal aging embrittlement. |
| | The concern associated with thermal aging embrittlement is the reduction in fracture toughness of a component at low temperatures (i.e., room temperature) and the potential for non-ductile failure at low temperatures. The material properties at high temperature are not affected. |
| | Therefore, fracture of a CASS component is not expected at low temperatures. Since the loading on the CASS components at low temperature is negligible, the possibility that loss of fracture toughness would render the component incapable of performing its function without showing any visual evidence of cracking, deformation, or damage is also negligible. |
| | The staff reviewed the Grimes letter, dated May 19, 2000, and notes that it states that aging of CASS at reactor operating temperatures of 280-350 degrees Celsius (536-662 degrees ENCLOSURE 2 |
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| Issue: Thermal aging embrittlement of CASS may result in reduction in fracture toughness of a component at operating conditions (i.e., 536-662 degrees Fahrenheit), contrary to the assertion in the RAI response that it only applies at low temperatures. The reduction in fracture toughness of CASS requires adequate aging management. | | Fahrenheit) can lead to changes in the mechanical properties of these materials, depending on the characteristics of the material and the environment to which the component is exposed. |
| | The effects of thermal aging on materials include increases in the tensile strength, hardness, and Charpy impact energy transition temperature, as well as decreases in ductility, fracture toughness, and impact strength. |
| | Further, NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment February 2007, states that: |
| | Thermal aging of CASS at boiling water reactor and pressurized water reactor operating temperatures is characterized by an increase in hardness and tensile strength and a decrease in ductility, impact strength and toughness. In addition, the "brittle-ductile" transition temperature increases and the upper shelf decreases (emphasis added). |
| | The upper shelf decrease described in NUREG/CR-6923 relates directly to behavior of CASS at operating temperatures, contrary to the assertion in the RAI response that the concerns with thermal aging embrittlement only apply at low temperatures. |
| | As cited in the Grimes letter, thermal aging of CASS results in reduced toughness, which means that the aged CASS component can tolerate smaller flaw sizes. Since the toughness of CASS is not directly measureable, the Grimes letter and the Generic Aging Lessons Learned (GALL) |
| | Report cite that thermal aging of CASS can be appropriately managed by inspections to demonstrate that flaws of a potentially critical size are not present in the CASS component. |
| | In addition, GALL Report AMP XI.M12 states that for high-molybdenum content steels (SA-351 Grades CF3M, CF3MA, and CF8M or other steels with 2.0 to 3.0 wt. percent Mo), static-cast steels with >14 percent ferrite and centrifugal-cast steels with >20 percent ferrite are potentially susceptible to thermal embrittlement. Static-cast high-molybdenum steels with 14 percent ferrite and centrifugal-cast high-molybdenum steels with 20 percent ferrite are not susceptible. |
| | Issue: |
| | Thermal aging embrittlement of CASS may result in reduction in fracture toughness of a component at operating conditions (i.e., 536-662 degrees Fahrenheit), contrary to the assertion in the RAI response that it only applies at low temperatures. The reduction in fracture toughness of CASS requires adequate aging management. |
| | Request: |
| | : 1. Please provide the composition, ferrite content, and the fabrication method to determine if the SA-351 CF3M CASS components are susceptible to thermal aging embrittlement in accordance with the guidance of aging management program (AMP) XI.M12. If so, a) Justify the assertion in the response to RAI 3.1.2.3.4-1 that the concern associated with thermal aging embrittlement is a reduction in fracture toughness and a potential for non-ductile failure at low temperatures (i.e., room temperature). |
| | b) Discuss how the proposed examinations will be adequate to provide assurance that the CASS components will not have flaws that could either (a) challenge the ability of the component to perform its intended safety function during normal operation, |
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| Request: 1. Please provide the composition, ferrite content, and the fabrication method to determine if the SA-351 CF3M CASS components are susceptible to thermal aging embrittlement in accordance with the guidance of aging management program (AMP) XI.M12. If so, a) Justify the assertion in the response to RAI 3.1.2.3.4-1 that the concern associated with thermal aging embrittlement is a reduction in fracture toughness and a potential for non-ductile failure at low temperatures (i.e., room temperature).
| | transient, and accident conditions; or (b) result in the generation of loose parts that could adversely affect the performance of other parts of the steam generator or downstream components. |
| b) Discuss how the proposed examinations will be adequate to provide assurance that the CASS components will not have flaws that could either (a) challenge the ability of the component to perform its intended safety function during normal operation, transient, and accident conditions; or (b) result in the generation of loose parts that could adversely affect the performance of other parts of the steam generator or downstream components.
| | Discussion: The applicant requested clarification on the staffs concern. No edits were made to this request. This question will be sent as a formal request titled: RAI 3.1.2.3.4-1a.}} |
| Discussion | |
| : The applicant requested clarification on the staff's concern. No edits were made to this request. This question will be sent as a formal request titled: "RAI 3.1.2.3.4-1a."}} | |
Letter Sequence Draft RAI |
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Results
Other: ML13212A367, ML14050A304, ML14071A620, ML14072A369, ML14092A346, ML14177A430, ML14238A691, ML15098A181, ML15106A736, RS-14-183, Updated Responses to NRC Set 14 Requests for Additional Information, Related License Renewal Application, RS-14-249, Results of Detailed Review Performed in Response to Request 1 of NRC RAI B.2.1.7-7 from Set 17, Related to License Renewal Application
|
MONTHYEARML13212A3672013-08-12012 August 2013
Plan for the Aging Management Program Regulatory Audits Regarding the Byron and Braidwood Nuclear Stations License Renewal Application Review (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: Other
ML13281A5742013-11-25025 November 2013
Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 3 (TAC Nos. MF1879, MF1880, MF1881, and MF1882
Project stage: RAI
ML13303B4632013-11-25025 November 2013
Summary of Telephone Conference Call Held on October 22, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 3 for the Byron-Braidwood LRA
Project stage: RAI
ML13281A5692013-12-12012 December 2013
Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and the Braidwood Nuclear Station Units 1 and 2, LRA - Aging Management, Set 4
Project stage: RAI
ML13282A3692013-12-13013 December 2013
Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882
Project stage: RAI
RS-13-273, Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application2013-12-17017 December 2013
Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application
Project stage: Response to RAI
RS-13-274, Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application2013-12-19019 December 2013
Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application
Project stage: Response to RAI
ML13317A0752014-01-13013 January 2014
Requests for Additional Information for Review of Byron, Units 1 & 2, and Braidwood, Units 1 & 2, License Renewal Applications, Set 6
Project stage: RAI
RS-14-003, Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application2014-01-13013 January 2014
Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application
Project stage: Response to RAI
ML14007A6582014-01-22022 January 2014
Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 9 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML13309A9322014-01-23023 January 2014
Summary of Telephone Conference Call Held on October 31, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braid
Project stage: Draft RAI
RS-14-030, Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application2014-02-0404 February 2014
Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application
Project stage: Response to RAI
ML14006A0212014-02-0606 February 2014
Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application- Aging Management, Set 8 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14023A5642014-02-0707 February 2014
RAI for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 13 (TAC MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14030A5962014-02-10010 February 2014
Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 12 (TAC MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14007A6032014-02-18018 February 2014
Request for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, LRA - Aging Management - Set 17
Project stage: RAI
ML14035A1892014-02-20020 February 2014
Summary of Telephone Conference Call Held on January 30, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron Station and Braidw
Project stage: Draft RAI
ML14035A5342014-02-20020 February 2014
January 22, 2014, Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, Llc., Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braidwood Station, License Renewal Applica
Project stage: Draft RAI
RS-14-051, Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application2014-02-27027 February 2014
Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application
Project stage: Response to RAI
ML14063A4952014-03-0404 March 2014
Units 1 & 2, Response to NRC Requests for Additional Information, Set 13, Dated February 7, 2014 Re License Renewal Application
Project stage: Response to RAI
ML14050A1672014-03-0404 March 2014
Summary of Telephone Conference Call on January 23, 2014, Between U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 11, for Byron-Braidwood License Renewal Application (TAC Nos. MF1879, MF1880, MF1881
Project stage: RAI
ML14036A3102014-03-0404 March 2014
Summary of Telephone Conference Call Held on January 28, 2014, Between NRC and Exelon, Concerning RAI Set 10, for the Byron and Braidwood Station, LRA
Project stage: RAI
ML14051A4312014-03-0404 March 2014
Summary of Telephone Conferene Call Held on January 29, 2014, Between the NRC and Exelon Generating Company, Llc., Concerning RAI Set 10, for the Byron and Braidwood Station License Renewal Application (TAC Nos. MF1879, MF1880, MF1881, and
Project stage: RAI
ML14051A4282014-03-0606 March 2014
January 13, 2014, Summary of Telephone Conference Call Held Between the NRC and Exelon RAI Set 8, for the Byron and Braidwood Station LRA
Project stage: RAI
ML14050A0812014-03-0707 March 2014
Correction to Request for Additional Information B.2.1.10-1, Letter Dated February 7, 2014, for the Review of the Byron Station and Braidwood Station, Units 1 and 2, LRA Set 13
Project stage: RAI
ML14058B1802014-03-11011 March 2014
Summary of Telephone Conference Call on February 18, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Regarding Byron & Braidwood Stations, License Renewal
Project stage: Draft RAI
ML14064A4032014-03-11011 March 2014
Summary of Telephone Conference Call on February 27, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Re Byron Station & Braidwood Station License Renewal
Project stage: Draft RAI
ML14064A3912014-03-11011 March 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 15 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14071A6202014-03-13013 March 2014
Aging Management Programs Audit Report Regarding the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (Tac Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: Other
ML14072A3692014-03-13013 March 2014
AMP Audit Enclosure (3)
Project stage: Other
ML14050A3042014-03-14014 March 2014
Scoping and Screening Methodology Audit Report Regarding the Byron Station, and Braidwood Station, Units 1 and 2, LRA
Project stage: Other
ML14058B1822014-03-18018 March 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 14 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14051A5032014-03-20020 March 2014
Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Set 17 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application2014-03-28028 March 2014
Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application
Project stage: Response to RAI
ML14084A3352014-04-0303 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 16 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14073A7052014-04-0303 April 2014
Summary of Telephone Conference Call Held on February 12, 2014, Between the NRC and Exelon, Concerning Drais Pertaining to the Byron and Braidwood Station, LRA
Project stage: RAI
ML14092A3462014-04-0707 April 2014
Project Manager Change for the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: Other
ML14092A2612014-04-0707 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 20 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14084A4882014-04-0707 April 2014
03/04/2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron and Braidwood License Renewal Application Set 16
Project stage: Draft RAI
ML14094A3662014-04-0808 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 19
Project stage: RAI
ML14093B2472014-04-10010 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 18 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14099A4852014-04-17017 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 & 2, and Braidwood Station, Units 1 & 2, License Renewal Application, Set 21, (TAC Nos. MF1879, MF1880, MF1881, and MF1882)
Project stage: RAI
ML14099A4932014-04-22022 April 2014
April 03, 2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 21, Pertaining to Byron, Units 1 & 2, Braidwood, Units 1 & 2, License Renewal Appl
Project stage: Draft RAI
ML14111A1182014-04-24024 April 2014
Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 22
Project stage: RAI
ML14107A0772014-04-25025 April 2014
Summary of Telephone Conference Call Held on April 9, 2014, Between the U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 23, Pertaining to the Byron Station & Braid
Project stage: Draft RAI
ML14107A2262014-05-14014 May 2014
Summary of Telephone Conference Call Held on March 26, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 21, Pertaining to the Byron Station and
Project stage: Draft RAI
ML14092A4402014-05-14014 May 2014
Summary of Telephone Conference Call Held on March 19, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 18, Pertaining to the Byron Station and
Project stage: Draft RAI
ML14112A4182014-05-14014 May 2014
Summary of Telephone Conference Call Held on April 10, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 22, Pertaining to the Byron Station and
Project stage: Draft RAI
ML14094A4252014-05-14014 May 2014
Summary of Telephone Conference Call Held on April 1, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 19, Pertaining to the Byron Station and B
Project stage: Draft RAI
ML14129A3392014-05-14014 May 2014
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
2014-03-11
[Table View] |
June 24, 2014, Summary of Telephone Conference Call Held Between the U.S. NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 36, Pertaining to the Byron Station and Braidwood Station, License Renewa| ML14183B230 |
| Person / Time |
|---|
| Site: |
Byron, Braidwood  |
|---|
| Issue date: |
07/07/2014 |
|---|
| From: |
Robinson L
License Renewal Projects Branch 1 |
|---|
| To: |
|
|---|
| Robinson L, 415-4115 |
| References |
|---|
| TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 |
| Download: ML14183B230 (7) |
|
|
|---|
Category:Meeting Summary
MONTHYEARML24170A8392024-06-18018 June 2024
June 12, 2024, Summary of the Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Byron Station, Units 1 and 2
ML24164A0182024-06-12012 June 2024
May 29, 2024, Summary of the Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2
ML24152A1852024-06-0404 June 2024
Summary of March 28, 2024, Closed Hybrid Pre-Submittal Meeting Between Constellation Energy Generation, LLC and the U.S. Nuclear Regulatory Commission Regarding a Future Amendment Request for Fuel Transition
ML24128A2512024-05-14014 May 2024
Summary of April 11, 2024, Public Meeting with Constellation Energy Generation, LLC Regarding Proposed Alternative to Implement American Society of Mechanical Engineers Operation and Maintenance Code Case OMN-32
ML24113A2872024-04-25025 April 2024
Summary of Public Meeting with Constellation Energy Generation, LLC Regarding Hooded Masks
ML24079A2382024-03-19019 March 2024
Summary of March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood Station, Unit 2
ML24009A0552024-01-24024 January 2024
Summary of January 8, 2024, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Removal of the Power Distribution Monitoring System from Technical Specifications
ML24018A1772024-01-19019 January 2024
Summary of August 30, 2023, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Relaxation of Inspection Requirements for the Head Penetration P-75 Flaw
ML23363A0942024-01-0303 January 2024
Summary of October 4, 2023, Pre Submittal Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding Revising Technical Specification 3.7.9. Ultimate Heat Sink (UHS)
ML23362A0042024-01-0202 January 2024
Documentation of Cancelled September 1, 2023, Presubmittal Meeting Between the NRC and Constellation Energy Generation, LLC, Regarding 6-Month Extension of Certain Reactor Pressure Vessel Weld Inspections
ML23352A3822023-12-19019 December 2023
Summary of December 11, 2023, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Deletion of Technical Specification 5.6.5.b.5
ML23320A2472023-11-17017 November 2023
Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591
ML23263B1062023-09-22022 September 2023
R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary
ML23164A2112023-06-14014 June 2023
Summary of the June 1, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2
ML23129A0202023-05-30030 May 2023
Summary of March 22, 2023, Closed Meeting with Constellation Energy Generation, LLC, to Discuss a Future License Amendment Request That Allows Byron Station and Braidwood Station to Utilize a New Citicality Analysis for the Spent Fuel Pools
ML23055A0352023-03-24024 March 2023
Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels
ML23033A6662023-02-0909 February 2023
Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna
ML22264A1992022-11-14014 November 2022
Summary of August 22, 2022, Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Steam Generator Welds (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and
ML22305A5992022-11-10010 November 2022
Summary of Closed Presubmittal Meeting Between the U. S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Transition to Framatome Fuel
ML22159A2232022-06-0909 June 2022
Summary of the June 2, 2022, Public Outreach to Discuss the NRC 2021 End of Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2
ML22115A2122022-05-12012 May 2022
Summary of April 11, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding a Future Amendment to Place One High Burnup Lead Test Assembly Into the Byron, Unit 2, Reactor
ML22111A2852022-05-0909 May 2022
Summary of April 4, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Pressurizer Welds (EPIDs L-2022-LLR-0035/36)
ML22111A3362022-05-0909 May 2022
Summary of April 7, 2022, Meeting Between the NRC and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Pressurizer Welds (Epids L-2022-LRR-0035 and 0036)
ML21330A0722021-12-0303 December 2021
Summary of November 17, 2021, Meeting with Exelon Generation Company, LLC, Related to a Future License Amendment to Remove License Condition 2.C.(12)(d) for Braidwood Station, Unit 2
ML21333A1532021-11-30030 November 2021
Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval
ML21237A0412021-08-30030 August 2021
Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28,
ML21176A0822021-07-0606 July 2021
June 15, 2021, Summary of Meeting with Exelon Generation Company, LLC Vessel Nozzle Repair Related to a Planned Request for an Alternative Related to Reactor Pressure
ML21139A1852021-06-22022 June 2021
Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting
ML21167A2152021-06-16016 June 2021
June 8, 2021, Summary of the Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2
ML21147A4262021-06-0303 June 2021
Summary of May 12, 2021, Meeting with Exelon Generation Company, Llc, Related to a Planned License Amendment to Modify the Ultimate Heat Sink Technical Specifications
ML21033A6582021-02-0404 February 2021
Summary of October 13, 2020, Presubmittal Meeting Between the U. S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Post Shutdown Emergency Plan Staffing to Support the Planned Early Closures
ML21011A2822021-01-21021 January 2021
Summary of January 6, 2021, Presubmittal Meeting Between the NRC and Exelon Generation Company, LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Unit Nos. 1 and 2 and Dresden, Units 2 and 3
ML20351A2832020-12-18018 December 2020
Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Exemption to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs
ML20342A3522020-12-10010 December 2020
Summary of November 13, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alterantive to Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting (EPID-L-2020-LRM-0102)
ML20323A0332020-12-0101 December 2020
Summary of November 4, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs
ML20280A2482020-10-0707 October 2020
Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3
ML20171A3812020-08-12012 August 2020
(COVID-19) Presubmittal Meeting Summary - Byron Unit 2 LAR - One-Time Extension of Steam Generator Tube Inspections
ML20218A5302020-08-0505 August 2020
July 14, 2020, Summary of the Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2
ML20181A0002020-06-29029 June 2020
Summary of 6/24/20 Meeting with Exelon Generation Company, LLC Regarding Planned Request for Alternative to Supplemental Valve Position Indication Testing Requirements for Braidwood, Calvert Cliffs, Clinton, Limerick, Nine Mile, Peach Botto
ML19326A3152019-12-0303 December 2019
Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements
ML19326C3582019-12-0303 December 2019
Summary of November 20, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Revise the Quality Assurance Program
ML19162A0272019-06-21021 June 2019
Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves
ML20108F0902019-04-20020 April 2019
April 15, 2020, Meeting Summary with Exelon Generation Company, LLC Regarding Planned Request to Defer Submittal of Owner'S Activity Report (Braidwood 2,Byron 2,Calvert Cliffs 1, LaSalle 1, Limerick 1, Nine Mile Point 2, Quad 2, R. E. Ginna
ML19036A8832019-02-0707 February 2019
Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879
ML18354B1712019-01-0202 January 2019
Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines
ML18325A1712018-11-28028 November 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas
ML18297A1722018-10-26026 October 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427
ML18225A3042018-08-16016 August 2018
Summary of August 8, 2018, Meeting with Exelon Generation Company, LLC, on a Future Relief Request to Extend the Post Peening Follow-Up Inspections for Certain Reactor Pressure Vessel Head Penetrations
ML18135A0222018-05-14014 May 2018
Summary of the May 10th, 2018, Public Open House Regarding Braidwood Nuclear Power Station
ML18120A1772018-05-0101 May 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing
2024-06-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24297A2702024-10-23023 October 2024
Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000455/2025002
ML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
ML24113A2892024-04-22022 April 2024
Notification of NRC Baseline Inspection and Request for Information
ML24053A3382024-02-22022 February 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062)
ML24039A0412024-01-30030 January 2024
NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18)
ML23339A0452023-12-0505 December 2023
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010
ML23297A2352023-10-26026 October 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection
ML23209A7242023-07-31031 July 2023
Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010
ML23198A0372023-07-17017 July 2023
Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant
ML23191A8442023-07-10010 July 2023
05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23172A1172023-06-22022 June 2023
Notification of NRC Fire Protection Team Inspection Request for Information
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML23094A1352023-04-0404 April 2023
Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010
ML23069A0332023-03-0606 March 2023
Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1
ML23069A0342023-03-0606 March 2023
Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary)
ML23115A2412023-01-20020 January 2023
NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly
ML23018A1632023-01-18018 January 2023
Notification of NRC Baseline Inspection and Request for Information
ML22241A0522022-08-29029 August 2022
Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004
ML22237A0272022-08-25025 August 2022
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML22271A0772022-05-0606 May 2022
NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request
ML22129A0132022-05-0606 May 2022
NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10
ML22116A1272022-04-26026 April 2022
Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002
ML22091A0852022-04-0101 April 2022
NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036)
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22034A9862022-02-0404 February 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402
ML21350A4372021-12-16016 December 2021
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010
ML21273A3312021-10-0404 October 2021
Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21228A2352021-08-17017 August 2021
Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004
ML21203A3112021-07-21021 July 2021
NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI
ML21193A0942021-07-12012 July 2021
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML21189A1602021-07-0808 July 2021
NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs
ML21189A1612021-07-0808 July 2021
NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21057A1022021-02-25025 February 2021
Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML21036A1102021-02-0404 February 2021
NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
ML21029A3302021-01-29029 January 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885
ML21020A1292021-01-20020 January 2021
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002
ML21004A1452020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18
ML20329A4852020-11-24024 November 2020
Notification of NRC Fire Protection Team Inspection Request for Information
ML20294A5492020-10-21021 October 2020
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML20289A1142020-10-0909 October 2020
NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20104C1452020-04-10010 April 2020
NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections
2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2014 LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the staffs draft request for additional information (DRAI),
Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs DRAIs. provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457
Enclosures:
- 1. List of Participants
- 2. List of Draft Request for Additional Information cc w/encls: Listserv
ML14183B230 *concurred via email OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 07/2/14 07/7/14 07/7/14 07/7/14
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JUNE 24, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 36, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
DISTRIBUTION EMAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII
TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS June 24, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)
Allen Hiser NRC Seung Min NRC Aloysius Obodoako NRC John Hufnagel Exelon Generating Company, LLC (Exelon)
Al Fulvio Exelon Don Warfel Exelon Pete Tamburro Exelon Gary Becknell Exelon Don Brindle Exelon Ralph Wolen Exelon ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION June 24, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 24, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 36, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
DRAI 3.1.2.3.4-1a Applicability:
Byron Station (Byron) and Braidwood Station (Braidwood), Unit 1
Background:
By letter date May 12, 2014, the applicant responded to request for additional information (RAI) 3.1.2.3.4-1 which addressed loss of fracture toughness in Byron and Braidwood, Unit 1 steam generator internal structural supports. In its response, the applicant revised license renewal application Table 3.1.2-4 by deleting the aging management review (AMR) line item which manages loss of fracture toughness for Byron and Braidwood, Unit 1 steam generator tube support lattice bar attachment components made of cast austenitic stainless steel (CASS). The deleted AMR line item indicated that these CASS components are exposed to treated water greater than 482 degrees Fahrenheit and may experience loss of fracture toughness due to thermal aging embrittlement. Byron and Braidwood manage both by the Steam Generators program.
The applicant further stated that loss of fracture toughness due to thermal aging embrittlement is not applicable to these steam generator CASS internal components (i.e., internal supports and structures and tube support plates and U-bend supports). The applicant reviewed the Grimes letter to Walters on License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Stainless Steel Components, dated May 19, 2000, (ADAMS Accession Number ML003717179) and provided the following justification for excluding the steam generator tube support lattice bar attachment components, fabricated from SA-351 CF3M CASS, from being susceptible to thermal aging embrittlement.
The concern associated with thermal aging embrittlement is the reduction in fracture toughness of a component at low temperatures (i.e., room temperature) and the potential for non-ductile failure at low temperatures. The material properties at high temperature are not affected.
Therefore, fracture of a CASS component is not expected at low temperatures. Since the loading on the CASS components at low temperature is negligible, the possibility that loss of fracture toughness would render the component incapable of performing its function without showing any visual evidence of cracking, deformation, or damage is also negligible.
The staff reviewed the Grimes letter, dated May 19, 2000, and notes that it states that aging of CASS at reactor operating temperatures of 280-350 degrees Celsius (536-662 degrees ENCLOSURE 2
Fahrenheit) can lead to changes in the mechanical properties of these materials, depending on the characteristics of the material and the environment to which the component is exposed.
The effects of thermal aging on materials include increases in the tensile strength, hardness, and Charpy impact energy transition temperature, as well as decreases in ductility, fracture toughness, and impact strength.
Further, NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment February 2007, states that:
Thermal aging of CASS at boiling water reactor and pressurized water reactor operating temperatures is characterized by an increase in hardness and tensile strength and a decrease in ductility, impact strength and toughness. In addition, the "brittle-ductile" transition temperature increases and the upper shelf decreases (emphasis added).
The upper shelf decrease described in NUREG/CR-6923 relates directly to behavior of CASS at operating temperatures, contrary to the assertion in the RAI response that the concerns with thermal aging embrittlement only apply at low temperatures.
As cited in the Grimes letter, thermal aging of CASS results in reduced toughness, which means that the aged CASS component can tolerate smaller flaw sizes. Since the toughness of CASS is not directly measureable, the Grimes letter and the Generic Aging Lessons Learned (GALL)
Report cite that thermal aging of CASS can be appropriately managed by inspections to demonstrate that flaws of a potentially critical size are not present in the CASS component.
In addition, GALL Report AMP XI.M12 states that for high-molybdenum content steels (SA-351 Grades CF3M, CF3MA, and CF8M or other steels with 2.0 to 3.0 wt. percent Mo), static-cast steels with >14 percent ferrite and centrifugal-cast steels with >20 percent ferrite are potentially susceptible to thermal embrittlement. Static-cast high-molybdenum steels with 14 percent ferrite and centrifugal-cast high-molybdenum steels with 20 percent ferrite are not susceptible.
Issue:
Thermal aging embrittlement of CASS may result in reduction in fracture toughness of a component at operating conditions (i.e., 536-662 degrees Fahrenheit), contrary to the assertion in the RAI response that it only applies at low temperatures. The reduction in fracture toughness of CASS requires adequate aging management.
Request:
- 1. Please provide the composition, ferrite content, and the fabrication method to determine if the SA-351 CF3M CASS components are susceptible to thermal aging embrittlement in accordance with the guidance of aging management program (AMP) XI.M12. If so, a) Justify the assertion in the response to RAI 3.1.2.3.4-1 that the concern associated with thermal aging embrittlement is a reduction in fracture toughness and a potential for non-ductile failure at low temperatures (i.e., room temperature).
b) Discuss how the proposed examinations will be adequate to provide assurance that the CASS components will not have flaws that could either (a) challenge the ability of the component to perform its intended safety function during normal operation,
transient, and accident conditions; or (b) result in the generation of loose parts that could adversely affect the performance of other parts of the steam generator or downstream components.
Discussion: The applicant requested clarification on the staffs concern. No edits were made to this request. This question will be sent as a formal request titled: RAI 3.1.2.3.4-1a.