|
|
| (One intermediate revision by the same user not shown) |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:LICENSEE: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April25, 2014 LICENSEE: Exelon Generation Company, LLC FACILITY Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 SUBJECT |
| FACILITY SUBJECT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April25, 2014 Exelon Generation Company, LLC Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2
| |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879. MF1880, MF1881, AND 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 April 9, 2014, to discuss and clarify the staff's draft request for additional information (ORAl), Set 23. concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. | | OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879. MF1880, MF1881, AND MF1882) |
| The telephone conference call was useful in clarifying the intent of the staff's ORAls. Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items. The applicant had an opportunity to comment on this summary .f,v 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 | | 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 April 9, 2014, to discuss and clarify the staff's draft request for additional information (ORAl), |
| | Set 23. 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 ORAls. provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items. |
| | The applicant had an opportunity to comment on this summary 1/ft/~ .f,v 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:== | | ==Enclosures:== |
| : 1. List of Participants | | : 1. List of Participants |
| : 2. List of Draft Request for Additional Information cc w/encls: Listserv April 25, 2014 LICENSEE: | | : 2. List of Draft Request for Additional Information cc w/encls: Listserv |
| Exelon Generation Company, LLC FACILITY: | | * ML14107A077 *concurred via email OFFICE LA:DLR PM: RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME IKing LRobinson I ;DiazSanabria LRobinson JUribe for) J fRPiasse for) |
| Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2
| | DATE 4/22/14 4/24/14 4/25/14 4/25/14 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS April 9, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) |
| | John Wise NRC George Thomas NRC Gautam Banerjee NRC Chris Wilson Exelon Generating Company, LLC (Exelon) |
| | Don Wartel Exelon AI Fulvia Exelon Albert Piha Exelon John Hilditch Exelon Jim Annett Exelon Paul Cervenka Exelon Phil O'Donnell Exelon Dylan Cimock Exelon Casey Muggleston Exelon Don Brindle Exelon RalphWolen Exelon ENCLOSURE 1 |
|
| |
|
| ==SUBJECT:==
| | DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION April 9, 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 April9, 2014, to discuss and clarify the following draft request for additional information (DRAI), |
| | Set 23, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA). |
| | ORAl 3.5.2.2.2.2-1 Applicability: |
| | Byron and Braidwood Background; SRP-LR Section 3.5.2.2.2.2, "Reduction of Strength and Modulus due to Elevated Temperature," recommends further evaluation tor any concrete elements of safety-related structures and other concrete structures that exceed temperature limits of 66°C (150°F) for general areas and 93°C (200°F) for local areas. The SRP*LR also states that higher temperatures may be allowed if tests or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations. |
| | LRA Section 3.5.2.2.2.2 states, in part, that: |
| | High energy line penetrations have been designed to limit surrounding concrete surtaces to temperatures less than 200"F, except for the special pipe whip restraints that are located around each feedwater and main steam pipe as it passes through the concrete wall separating the main steam isolation valve room from the main steam tunnel. The design documents for the concrete at these pipe whip restraints include an evaluation for elevated temperatures, which determined that the concrete temperature up to 300"F at the local areas of the pipes was acceptable. |
| | LRA Table 3.5*1, item 3.5.1*48, which references LRA section 3.5.2.2.2.2, states that the aging effect and mechanism of reduction of concrete strength and modulus due to elevated temperature is not applicable to Byron and Braidwood. It further states that the main steam (MS) tunnel and main steam isolation valve (MSIV) room walls have been evaluated and found acceptable tor temperatures up to 300"F. It is not clear if the elevated temperatures experienced by the concrete walls of the MS tunnel and the MSIV room near the special pipe whip restraints remain below the 300°F used in the evaluation and why the AMR line item would not be applicable to these MSIV room and MS tunnel concrete walls. The staff reviewed the Byron and Braidwood updated final safety analyses report (UFSAR), specifically Section 3.8.4, and did not find any discussion of an engineering evaluation that accounted for possible reductions in concrete strength or modulus of elasticity due to elevated temperatures. |
| | ENCLOSURE 2 |
|
| |
|
| ==SUMMARY==
| | Request: |
| OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND 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 April 9, 2014, to discuss and clarify the staff's draft request for additional information (ORAl), Set 23, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application.
| | : 1. Provide the maximum temperature that is experienced by the concrete walls of the MSIV room and MS tunnel near the special feedwater and main steam pipe whip restraints. |
| The telephone conference call was useful in clarifying the intent of the staff's ORAls. Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items. The applicant had an opportunity to comment on this summary. IRA Richard Plasse for! 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
| | : 2. Provide a discussion of the engineering evaluation that was conducted to demonstrate the concrete would be able to periarm its intended functions while being exposed to elevated temperatures above the GALL Report recommended limits. Include any reductions in strength or modulus of elasticity that were applied to the design calculations or any test results used in the evaluation. |
| | |
| ==Enclosures:==
| |
| : 1. List of Participants
| |
| : 2. List of Draft Request for Additional Information cc w/encls: Listserv DISTRIBUTION:
| |
| See next page ADAMS Accession No* ML14107A077
| |
| *concurred via email OFFICE LA:DLR PM: RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME I King LRobinson I ;DiazSanabria LRobinson JUribe for) J fRPiasse for) DATE 4/22/14 4/24/14 4/25/14 4/25/14 OFFICIAL RECORD COPY TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION PARTICIPANTS Lindsay Robinson John Wise George Thomas Gautam Banerjee Chris Wilson Don Wartel AI Fulvia Albert Piha John Hilditch Jim Annett Paul Cervenka Phil O'Donnell Dylan Cimock Casey Muggleston Don Brindle RalphWolen LIST OF PARTICIPANTS April 9, 2014 AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC) NRC NRC NRC Exelon Generating Company, LLC (Exelon) Exelon Exelon Exelon Exelon Exelon Exelon Exelon Exelon Exelon Exelon Exelon ENCLOSURE 1
| |
| DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION April 9, 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 April9, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 23, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA). ORAl 3.5.2.2.2.2-1 Applicability:
| |
| Byron and Braidwood Background; SRP-LR Section 3.5.2.2.2.2, "Reduction of Strength and Modulus due to Elevated Temperature," recommends further evaluation tor any concrete elements of safety-related structures and other concrete structures that exceed temperature limits of 66°C (150°F) for general areas and 93°C (200°F) for local areas. The SRP*LR also states that higher temperatures may be allowed if tests or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.
| |
| LRA Section 3.5.2.2.2.2 states, in part, that: High energy line penetrations have been designed to limit surrounding concrete surtaces to temperatures less than 200"F, except for the special pipe whip restraints that are located around each feedwater and main steam pipe as it passes through the concrete wall separating the main steam isolation valve room from the main steam tunnel. The design documents for the concrete at these pipe whip restraints include an evaluation for elevated temperatures, which determined that the concrete temperature up to 300"F at the local areas of the pipes was acceptable.
| |
| LRA Table 3.5*1, item 3.5.1*48, which references LRA section 3.5.2.2.2.2, states that the aging effect and mechanism of reduction of concrete strength and modulus due to elevated temperature is not applicable to Byron and Braidwood.
| |
| It further states that the main steam (MS) tunnel and main steam isolation valve (MSIV) room walls have been evaluated and found acceptable tor temperatures up to 300"F. It is not clear if the elevated temperatures experienced by the concrete walls of the MS tunnel and the MSIV room near the special pipe whip restraints remain below the 300°F used in the evaluation and why the AMR line item would not be applicable to these MSIV room and MS tunnel concrete walls. The staff reviewed the Byron and Braidwood updated final safety analyses report (UFSAR), specifically Section 3.8.4, and did not find any discussion of an engineering evaluation that accounted for possible reductions in concrete strength or modulus of elasticity due to elevated temperatures.
| |
| ENCLOSURE 2 Request: 1. Provide the maximum temperature that is experienced by the concrete walls of the MSIV room and MS tunnel near the special feedwater and main steam pipe whip restraints.
| |
| : 2. Provide a discussion of the engineering evaluation that was conducted to demonstrate the concrete would be able to peri arm its intended functions while being exposed to elevated temperatures above the GALL Report recommended limits. Include any reductions in strength or modulus of elasticity that were applied to the design calculations or any test results used in the evaluation. | |
| : 3. Justify why AMR line item 3.5.1-48 is not applicable to the MSIV room and MS tunnel concrete walls that experience elevated temperatures above 200°F and the required evaluation. | | : 3. Justify why AMR line item 3.5.1-48 is not applicable to the MSIV room and MS tunnel concrete walls that experience elevated temperatures above 200°F and the required evaluation. |
| Discussion: | | Discussion: The applicant requested clarity on the staff's concern. The applicant requested that requests 2 and 3 be made conditional based on the response to request 1. The staff agreed to make the change and will preface requests 2 and 3 with the following conditional statement, "If the maximum temperature experienced is greater than 200°F." This question will be sent as part of the formal request titled: "RAI 3.5.2.2.2.2-1." |
| The applicant requested clarity on the staff's concern. The applicant requested that requests 2 and 3 be made conditional based on the response to request 1. The staff agreed to make the change and will preface requests 2 and 3 with the following conditional statement, "If the maximum temperature experienced is greater than 200°F." This question will be sent as part of the formal request titled: "RAI 3.5.2.2.2.2-1." ORAl 3.5.2-6 Applicability: | | ORAl 3.5.2-6 Applicability: |
| Byron and Braidwood | | Byron and Braidwood |
|
| |
|
| ==Background:== | | ==Background:== |
|
| |
|
| Item 241ocated in SRP-LR Table 3.5-treferences the GALL Report item II.At.CP-100. | | Item 241ocated in SRP-LR Table 3.5-treferences the GALL Report item II.At.CP-100. The AMP recommended for item II.A1.CP-100 in the GALL Report is XI.S2, "ASME Section XI, Subsection IWL," or XI.S6, "Structures Monitoring." |
| The AMP recommended for item II.A1.CP-100 in the GALL Report is XI.S2, "ASME Section XI, Subsection IWL," or XI.S6, "Structures Monitoring." The GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL," Program Description states that 10 CFR 50.55a imposes the examination requirements of ASME Code, Section XI, Subsection IWL, for Class CC reinforced and prestressed concrete containments. | | The GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL," Program Description states that 10 CFR 50.55a imposes the examination requirements of ASME Code, Section XI, Subsection IWL, for Class CC reinforced and prestressed concrete containments. The GALL Report AMP "Scope of Program" (Program Element 1) states that the components within the scope of Subsection IWL are reinforced concrete and unbonded post-tensioning systems of Class CC containments. Subsection IWL exempts from examination portions of the concrete containment that are inaccessible such as concrete covered by liner, foundation material, or backfill or obstructed by adjacent structures or other components. However, 10 CFR 50.55a(b)(2)(viii) specifies additional requirements for inaccessible areas that requires the licensee to evaluate the acceptability of concrete in inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation of inaccessible areas. |
| The GALL Report AMP "Scope of Program" (Program Element 1) states that the components within the scope of Subsection IWL are reinforced concrete and unbonded post-tensioning systems of Class CC containments. | | Issue: |
| Subsection IWL exempts from examination portions of the concrete containment that are inaccessible such as concrete covered by liner, foundation material, or backfill or obstructed by adjacent structures or other components. | | The corresponding LRA Table 3.5.1, Item 3.5.1-24, states in the "Discussion" column that this item is consistent with the GALL Report and cites the Structures Monitoring (LRA Section 8.2.1.34) program as the AMP for managing this aging effect and mechanism tor inaccessible |
| However, 10 CFR 50.55a(b)(2)(viii) specifies additional requirements for inaccessible areas that requires the licensee to evaluate the acceptability of concrete in inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation of inaccessible areas. Issue: The corresponding LRA Table 3.5.1, Item 3.5.1-24, states in the "Discussion" column that this item is consistent with the GALL Report and cites the Structures Monitoring (LRA Section 8.2.1.34) program as the AMP for managing this aging effect and mechanism tor inaccessible areas of containment concrete exposed to groundwater and soil environments, including groundwater chemistry. | | |
| In the context of the LRA, the description for Item II.A1.CP-100 in the GALL Report does include containment pressure-resisting boundary concrete components in inaccessible areas above grade in an "Air-Outdoor'' | | areas of containment concrete exposed to groundwater and soil environments, including groundwater chemistry. In the context of the LRA, the description for Item II.A1.CP-100 in the GALL Report does include containment pressure-resisting boundary concrete components in inaccessible areas above grade in an "Air- Outdoor'' environment as well as below-grade areas in a "Groundwater/Soil" environment. The applicant has not addressed inaccessible components in the "Air- Outdoor" environment for this AMR line item. Further, the ASME Sect1on XI, Subsection IWL program, mandated by the GALL Report and 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for AMR line item 3.5.1*24 and the corresponding line items in LRA Table 3.5.2-4. |
| environment as well as below-grade areas in a "Groundwater/Soil" environment. | | Request: |
| The applicant has not addressed inaccessible components in the "Air-Outdoor" environment for this AMR line item. Further, the ASME Sect1on XI, Subsection IWL program, mandated by the GALL Report and 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for AMR line item 3.5.1*24 and the corresponding line items in LRA Table 3.5.2-4. Request: With regard to AMR line item 3.5.1-24 in LRA Table 3.5-1 that corresponds to Hem II. A 1.CP-1 00 in the GALL Report, provide the technical basis to justify why the ASME Code, Section XI, Subsection IWL program, recommended by the GALL Report and required by 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for the line item and corresponding line items in LRA Table 3.5.2-4. Update the LRA, as necessary, based on the response to this request. Discussion: | | With regard to AMR line item 3.5.1-24 in LRA Table 3.5-1 that corresponds to Hem II. A 1.CP-1 00 in the GALL Report, provide the technical basis to justify why the ASME Code, Section XI, Subsection IWL program, recommended by the GALL Report and required by 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for the line item and corresponding line items in LRA Table 3.5.2-4. Update the LRA, as necessary, based on the response to this request. |
| The applicant requested clarity on the staff's concern. No edits were proposed. | | Discussion: The applicant requested clarity on the staff's concern. No edits were proposed. |
| The applicant mentioned that this question is closely related to another question listed in Set 24 and asked that it be removed from Set 23 and added to Set 24. The staff agreed to remove this question from Set 23 and add it to Set 24. ORAl 8.2.1.12-1a Applicability: | | The applicant mentioned that this question is closely related to another question listed in Set 24 and asked that it be removed from Set 23 and added to Set 24. The staff agreed to remove this question from Set 23 and add it to Set 24. |
| Byron and Braidwood | | ORAl 8.2.1.12-1a Applicability: |
| | Byron and Braidwood |
|
| |
|
| ==Background:== | | ==Background:== |
|
| |
|
| The response to RAI B.2.1.12-1, dated February 27, 2014, stated that existing station procedures require a general visual inspection of internal surfaces of components within the scope of the Closed Treated Water Systems program when the systems are opened. In addition, the personnel performing the inspections are qualified to Exelon job qualifications and in accordance with the Institute of Nuclear Power Operations (INPO) National Academy for Nuclear Training accredited training program. The staff notes that, similar to the Closed Treated Water Systems program, the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program uses opportunistic visual inspections to monitor aging effects of component internal surfaces. | | The response to RAI B.2.1.12-1, dated February 27, 2014, stated that existing station procedures require a general visual inspection of internal surfaces of components within the scope of the Closed Treated Water Systems program when the systems are opened. In addition, the personnel performing the inspections are qualified to Exelon job qualifications and in accordance with the Institute of Nuclear Power Operations (INPO) National Academy for Nuclear Training accredited training program. |
| However, during its AMP audit, the staff noted that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program does not rely on the use of existing station procedures to identify age-related degradation. | | The staff notes that, similar to the Closed Treated Water Systems program, the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program uses opportunistic visual inspections to monitor aging effects of component internal surfaces. However, during its AMP audit, the staff noted that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program does not rely on the use of existing station procedures to identify age-related degradation. Rather, a new procedure was proposed to inspect for evidence of loss of material, leakage, cracking, and reduction of heat transfer when the internal surfaces of metallic components were made accessible. |
| Rather, a new procedure was proposed to inspect for evidence of loss of material, leakage, cracking, and reduction of heat transfer when the internal surfaces of metallic components were made accessible. Issue: It is unclear to the staff how the existing station opportunistic inspections will be capable of detecting the specific applicable aging effects of components internal surtaces in the Closed Treated Water Systems program. The RAI response did not provide sufficient information regarding: | | |
| : 1. The details within the IN PO training program and Exelon job qualifications that demonstrate that personnel periorming the opportunistic inspections are qualified to identify the applicable aging effects, and 2. The details within the existing station procedures that demonstrate that, when piping internal surlaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of aging effects. Request: 1. State the details within the INPO training program and Exelon job qualifications that demonstrate that personnel pertorming the opportunistic inspections are qualified to identify loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking. | | Issue: |
| | It is unclear to the staff how the existing station opportunistic inspections will be capable of detecting the specific applicable aging effects of components internal surtaces in the Closed Treated Water Systems program. The RAI response did not provide sufficient information regarding: |
| | : 1. The details within the IN PO training program and Exelon job qualifications that demonstrate that personnel periorming the opportunistic inspections are qualified to identify the applicable aging effects, and |
| | : 2. The details within the existing station procedures that demonstrate that, when piping internal surlaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of aging effects. |
| | Request: |
| | : 1. State the details within the INPO training program and Exelon job qualifications that demonstrate that personnel pertorming the opportunistic inspections are qualified to identify loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking. |
| : 2. State the process-based (in lieu of knowledge-based) controls that exist in station procedures that will ensure that, when component internal suriaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking (e.g., prejob brief details, checklists within the work order). Alternatively, propose a new procedure that specifically addresses these controls. | | : 2. State the process-based (in lieu of knowledge-based) controls that exist in station procedures that will ensure that, when component internal suriaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking (e.g., prejob brief details, checklists within the work order). Alternatively, propose a new procedure that specifically addresses these controls. |
| Discussion: | | Discussion: The applicant requested clarity on the staff's concern. The applicant requested that the second question either be merged with the first question or be made conditional on the first question. The staff will have to conduct additional review to evaluate the applicant's request. Therefore, this question will be removed from Set 23 and added to Set 24. |
| The applicant requested clarity on the staff's concern. The applicant requested that the second question either be merged with the first question or be made conditional on the first question. | |
| The staff will have to conduct additional review to evaluate the applicant's request. Therefore, this question will be removed from Set 23 and added to Set 24. | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND MF1882) DISTRIBUTION EMAIL: PUBLIC RidsNrrDir Resource RidsNrrD1rRpb1 Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcln1yre, OPA EDuncan, Rill JBenjamin, Alii AGarmoe, Rill JMcGhee, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill}} | | OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND MF1882) |
| | DISTRIBUTION EMAIL: |
| | PUBLIC RidsNrrDir Resource RidsNrrD1rRpb1 Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcln1yre, OPA EDuncan, Rill JBenjamin, Alii AGarmoe, Rill JMcGhee, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill}} |
Letter Sequence Draft RAI |
|---|
|
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] |
|
|---|
Category:Letter
MONTHYEARML24297A2702024-10-23023 October 2024
Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000455/2025002
RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024
Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality
ML24291A0012024-10-17017 October 2024
Submittal of Core Operating Limits Report, Cycle 25
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024
Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals
ML24281A1502024-10-0707 October 2024
Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024
Cycle 27 Core Operating Limits Report
RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024
Relief Requests Associated with the Fifth Inservice Inspection Interval
IR 05000456/20240112024-09-12012 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011
ML24164A0032024-09-10010 September 2024
Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024
Both Trains of Control Room Ventilation Temperature Control System Inoperable
ML24227A0522024-08-29029 August 2024
Audit Plan for LAR to Remove ATWS Mtc Limit
IR 05000456/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005)
IR 05000454/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005)
ML24225A1112024-08-13013 August 2024
Notification of NRC Fire Protection Team Inspection Request for Information
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000454/20240112024-08-0808 August 2024
Phase 2 Post- Approval License Renewal Report 05000454/2024011
IR 05000456/20240022024-08-0808 August 2024
Integrated Inspection Report 05000456/2024002 and 05000457/2024002
ML24172A1252024-07-26026 July 2024
Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter
IR 05000454/20240022024-07-26026 July 2024
Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion
ML24179A3262024-07-23023 July 2024
LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056)
05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024
Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024
Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller
ML24163A3922024-06-25025 June 2024
Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter
ML24170A7652024-06-19019 June 2024
Confirmation of Initial License Examination
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24164A2132024-06-13013 June 2024
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant
RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024
License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink
IR 05000456/20240102024-05-31031 May 2024
License Renewal Phase 1 Report 05000456/2024010
RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024
License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024
Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024
Completion of License Renewal Activities Prior to Entering the Period of Extended Operation
ML24136A0132024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
ML24136A2452024-05-15015 May 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004
IR 05000454/20240012024-05-10010 May 2024
Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001
BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024
Annual Radiological Environmental Operating Report (AREOR)
ML24128A1212024-05-0707 May 2024
Response to Braidwood and Dresden FOF Dates Change Request (2025)
BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024
2023 Regulatory Commitment Change Summary Report
ML24122A6522024-05-0101 May 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
IR 05000456/20243012024-04-29029 April 2024
NRC Initial License Examination Report 05000456/2024301; 05000457/2024301
ML24116A0052024-04-25025 April 2024
Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25
RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
2024-09-06
[Table view]
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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April25, 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 APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879. MF1880, MF1881, AND 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 April 9, 2014, to discuss and clarify the staff's draft request for additional information (ORAl),
Set 23. 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 ORAls. provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary 1/ft/~ .f,v 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
- ML14107A077 *concurred via email OFFICE LA:DLR PM: RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME IKing LRobinson I ;DiazSanabria LRobinson JUribe for) J fRPiasse for)
DATE 4/22/14 4/24/14 4/25/14 4/25/14 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS April 9, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)
John Wise NRC George Thomas NRC Gautam Banerjee NRC Chris Wilson Exelon Generating Company, LLC (Exelon)
Don Wartel Exelon AI Fulvia Exelon Albert Piha Exelon John Hilditch Exelon Jim Annett Exelon Paul Cervenka Exelon Phil O'Donnell Exelon Dylan Cimock Exelon Casey Muggleston Exelon Don Brindle Exelon RalphWolen Exelon ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION April 9, 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 April9, 2014, to discuss and clarify the following draft request for additional information (DRAI),
Set 23, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
ORAl 3.5.2.2.2.2-1 Applicability:
Byron and Braidwood Background; SRP-LR Section 3.5.2.2.2.2, "Reduction of Strength and Modulus due to Elevated Temperature," recommends further evaluation tor any concrete elements of safety-related structures and other concrete structures that exceed temperature limits of 66°C (150°F) for general areas and 93°C (200°F) for local areas. The SRP*LR also states that higher temperatures may be allowed if tests or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.
LRA Section 3.5.2.2.2.2 states, in part, that:
High energy line penetrations have been designed to limit surrounding concrete surtaces to temperatures less than 200"F, except for the special pipe whip restraints that are located around each feedwater and main steam pipe as it passes through the concrete wall separating the main steam isolation valve room from the main steam tunnel. The design documents for the concrete at these pipe whip restraints include an evaluation for elevated temperatures, which determined that the concrete temperature up to 300"F at the local areas of the pipes was acceptable.
LRA Table 3.5*1, item 3.5.1*48, which references LRA section 3.5.2.2.2.2, states that the aging effect and mechanism of reduction of concrete strength and modulus due to elevated temperature is not applicable to Byron and Braidwood. It further states that the main steam (MS) tunnel and main steam isolation valve (MSIV) room walls have been evaluated and found acceptable tor temperatures up to 300"F. It is not clear if the elevated temperatures experienced by the concrete walls of the MS tunnel and the MSIV room near the special pipe whip restraints remain below the 300°F used in the evaluation and why the AMR line item would not be applicable to these MSIV room and MS tunnel concrete walls. The staff reviewed the Byron and Braidwood updated final safety analyses report (UFSAR), specifically Section 3.8.4, and did not find any discussion of an engineering evaluation that accounted for possible reductions in concrete strength or modulus of elasticity due to elevated temperatures.
ENCLOSURE 2
Request:
- 1. Provide the maximum temperature that is experienced by the concrete walls of the MSIV room and MS tunnel near the special feedwater and main steam pipe whip restraints.
- 2. Provide a discussion of the engineering evaluation that was conducted to demonstrate the concrete would be able to periarm its intended functions while being exposed to elevated temperatures above the GALL Report recommended limits. Include any reductions in strength or modulus of elasticity that were applied to the design calculations or any test results used in the evaluation.
- 3. Justify why AMR line item 3.5.1-48 is not applicable to the MSIV room and MS tunnel concrete walls that experience elevated temperatures above 200°F and the required evaluation.
Discussion: The applicant requested clarity on the staff's concern. The applicant requested that requests 2 and 3 be made conditional based on the response to request 1. The staff agreed to make the change and will preface requests 2 and 3 with the following conditional statement, "If the maximum temperature experienced is greater than 200°F." This question will be sent as part of the formal request titled: "RAI 3.5.2.2.2.2-1."
ORAl 3.5.2-6 Applicability:
Byron and Braidwood
Background:
Item 241ocated in SRP-LR Table 3.5-treferences the GALL Report item II.At.CP-100. The AMP recommended for item II.A1.CP-100 in the GALL Report is XI.S2, "ASME Section XI, Subsection IWL," or XI.S6, "Structures Monitoring."
The GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL," Program Description states that 10 CFR 50.55a imposes the examination requirements of ASME Code,Section XI, Subsection IWL, for Class CC reinforced and prestressed concrete containments. The GALL Report AMP "Scope of Program" (Program Element 1) states that the components within the scope of Subsection IWL are reinforced concrete and unbonded post-tensioning systems of Class CC containments. Subsection IWL exempts from examination portions of the concrete containment that are inaccessible such as concrete covered by liner, foundation material, or backfill or obstructed by adjacent structures or other components. However, 10 CFR 50.55a(b)(2)(viii) specifies additional requirements for inaccessible areas that requires the licensee to evaluate the acceptability of concrete in inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation of inaccessible areas.
Issue:
The corresponding LRA Table 3.5.1, Item 3.5.1-24, states in the "Discussion" column that this item is consistent with the GALL Report and cites the Structures Monitoring (LRA Section 8.2.1.34) program as the AMP for managing this aging effect and mechanism tor inaccessible
areas of containment concrete exposed to groundwater and soil environments, including groundwater chemistry. In the context of the LRA, the description for Item II.A1.CP-100 in the GALL Report does include containment pressure-resisting boundary concrete components in inaccessible areas above grade in an "Air- Outdoor environment as well as below-grade areas in a "Groundwater/Soil" environment. The applicant has not addressed inaccessible components in the "Air- Outdoor" environment for this AMR line item. Further, the ASME Sect1on XI, Subsection IWL program, mandated by the GALL Report and 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for AMR line item 3.5.1*24 and the corresponding line items in LRA Table 3.5.2-4.
Request:
With regard to AMR line item 3.5.1-24 in LRA Table 3.5-1 that corresponds to Hem II. A 1.CP-1 00 in the GALL Report, provide the technical basis to justify why the ASME Code,Section XI, Subsection IWL program, recommended by the GALL Report and required by 10 CFR 50.55a for concrete containment pressure-resisting boundary components in both accessible and inaccessible areas, is not included as an applicable AMP for the line item and corresponding line items in LRA Table 3.5.2-4. Update the LRA, as necessary, based on the response to this request.
Discussion: The applicant requested clarity on the staff's concern. No edits were proposed.
The applicant mentioned that this question is closely related to another question listed in Set 24 and asked that it be removed from Set 23 and added to Set 24. The staff agreed to remove this question from Set 23 and add it to Set 24.
ORAl 8.2.1.12-1a Applicability:
Byron and Braidwood
Background:
The response to RAI B.2.1.12-1, dated February 27, 2014, stated that existing station procedures require a general visual inspection of internal surfaces of components within the scope of the Closed Treated Water Systems program when the systems are opened. In addition, the personnel performing the inspections are qualified to Exelon job qualifications and in accordance with the Institute of Nuclear Power Operations (INPO) National Academy for Nuclear Training accredited training program.
The staff notes that, similar to the Closed Treated Water Systems program, the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program uses opportunistic visual inspections to monitor aging effects of component internal surfaces. However, during its AMP audit, the staff noted that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program does not rely on the use of existing station procedures to identify age-related degradation. Rather, a new procedure was proposed to inspect for evidence of loss of material, leakage, cracking, and reduction of heat transfer when the internal surfaces of metallic components were made accessible.
Issue:
It is unclear to the staff how the existing station opportunistic inspections will be capable of detecting the specific applicable aging effects of components internal surtaces in the Closed Treated Water Systems program. The RAI response did not provide sufficient information regarding:
- 1. The details within the IN PO training program and Exelon job qualifications that demonstrate that personnel periorming the opportunistic inspections are qualified to identify the applicable aging effects, and
- 2. The details within the existing station procedures that demonstrate that, when piping internal surlaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of aging effects.
Request:
- 1. State the details within the INPO training program and Exelon job qualifications that demonstrate that personnel pertorming the opportunistic inspections are qualified to identify loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking.
- 2. State the process-based (in lieu of knowledge-based) controls that exist in station procedures that will ensure that, when component internal suriaces are made accessible, personnel will be inspecting for parameters that are capable of detecting the presence and extent of loss of material due to general, pitting, crevice, and galvanic corrosion; and cracking due to stress corrosion cracking (e.g., prejob brief details, checklists within the work order). Alternatively, propose a new procedure that specifically addresses these controls.
Discussion: The applicant requested clarity on the staff's concern. The applicant requested that the second question either be merged with the first question or be made conditional on the first question. The staff will have to conduct additional review to evaluate the applicant's request. Therefore, this question will be removed from Set 23 and added to Set 24.
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 23, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAG NOS. MF1879, MF1880, MF1881, AND MF1882)
DISTRIBUTION EMAIL:
PUBLIC RidsNrrDir Resource RidsNrrD1rRpb1 Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson DMcln1yre, OPA EDuncan, Rill JBenjamin, Alii AGarmoe, Rill JMcGhee, Rill JRobbins, Rill VMitlyng, Rill PChandrathil, Rill
