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Category:E-Mail
MONTHYEARML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23317A2012023-11-22022 November 2023 (External_Sender) Supplement - Byron Security Rule Exemption Request ISFSI Docket No. Reference ML23321A2012023-11-17017 November 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML23311A1692023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Exam Categories B-B, B-D, and C-A SG Pressure Retaining Welds and Full Penetration Welded Nozzles (L-2023-LLR-0055 and L-2023-LLR-00 ML23311A1682023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections (L-2023-LLR-0053 and L-2023-LLR-005 ML23305A2992023-11-0101 November 2023 NRR E-mail Capture - NRC Acceptance Review of Byron, Unit 2, Relief Request I4R-24 ML23304A0222023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Braidwood 1 & 2 - Exemption from Security Rule (L-2023-LLE-0030) ML23304A0202023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Byron 1 & 2 - Exemption from Security Rule (L-2023-LLE-0027) ML23272A0602023-09-29029 September 2023 NRR E-mail Capture - NRC Acceptance Review of Byron, Unit 1, Relief Request I4R-25 ML23187A0092023-07-0606 July 2023 NRR E-mail Capture - NRC Acceptance Review of Byron and Braidwood Request to Adopt TSTF-370 ML23103A4692023-04-12012 April 2023 NRR E-mail Capture - NRC Acceptance Review of Braidwood Request for Amendment to Revise TS 3.7.9 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 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 ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML22284A1022022-10-0606 October 2022 NRR E-mail Capture - NRC Acceptance Review for Byron, Unit 2, License Amendment Request (LAR) to Reinsert an Accident Tolerant Fuel (ATF) Lead Test Assembly (LTA) (L-2022-LLA-0131) NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22255A0132022-09-0909 September 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, Calvert Cliffs, Ginna - License Amendment Request to Adopt TSTF-577 ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22189A0602022-07-0707 July 2022 NRR E-mail Capture - Draft RAI for Byron/Braidwood TSTF-501 ML22136A2722022-05-16016 May 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood and Byron Adoption of TSTF-501 ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22116A0242022-04-25025 April 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, and Ginna Request to Adopt TSTF-246 ML22105A0722022-04-15015 April 2022 NRR E-mail Capture - Braidwood/Byron Verbal Authorization for Proposed Alternative I4R-15/I4R-21 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) ML22088A1562022-03-0202 March 2022 NRR E-mail Capture - Byron, Braidwood, Calvert Cliffs, and Ginna - Non-acceptance of Application to Revise Technical Specifications 5.6.5.b, the Core Operating Limits Report (COLR) ML22091A0842022-02-24024 February 2022 NRR E-mail Capture - Braidwood and Byron - Withdrawal of Draft 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 ML23089A0152022-01-0505 January 2022 NRR E-mail Capture - NRC Acceptance Review of Byron - Proposed Alternative for Examinations of Categories B-B, B-D, and C-A SG Welds and Nozzles ML23089A0172022-01-0505 January 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood - Proposed Alternative for Examinations of Categories B-B, B-D, and C-A SG Welds and Nozzles ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21272A1492021-09-29029 September 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood and Byron - Proposed Alternative for Examinations of Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0172021-09-0303 September 2021 NRR E-mail Capture - NRC Acceptance Review - Braidwood - License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink ML21252A0042021-08-26026 August 2021 NRR E-mail Capture - NRC Acceptance Review - Braidwood/Byron/Clinton - Adoption of TSTF-273, Safety Function Determination Program Clarifications ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI 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 ML21154A0162021-06-0202 June 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood - Proposed Alternative for Exam of Pzr Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Shell Welds ML21154A0172021-06-0202 June 2021 NRR E-mail Capture - Acceptance Review of Byron - Proposed Alternative for Exam of Pzr Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Shell Welds ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21123A2442021-05-0303 May 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood/Byron/Ginna - Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5 and NSAL-15-1 (L-2021-LLA-0066) ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21081A0972021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events (EPID L-2021-JLD-0004) (E-mail) 2023-09-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23339A0452023-12-0505 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 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 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 ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment 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 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 ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 ML19350B2952019-12-16016 December 2019 NRR E-mail Capture - Draft Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Impractical Inservice Inspection Requirements (L-2019-LLA-0081) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application 2023-07-31
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Text
From: Mozafari, Brenda Sent: Wednesday, January 18, 2012 10:49 AM To: Leslie.Holden@exeloncorp.com
Subject:
Draft RAIs regarding June 23, 2011 MUR
- Leslie, Pursuant to 10 CFR 50.90, by letter to the Nuclear Regulatory Commission (NRC) dated June 23, 2011, the Exelon Generation Company, LLC (the licensee), submitted a license amendment request (LAR) for the Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2. The proposed measurement uncertainty recapture power uprate would increase the current licensed thermal power at Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2, by approximately 1.63 percent. The NRC staff has identified additional information (shown below) that is needed to complete the technical review.
After you have had time to consider your responses, we can schedule a call to provide any clarifications and discuss your planned responses. I will provide the questions formally after our discussion, however would expect this set of RAI questions to be responded to by letter within 30 days (by February 20, 2012). This is one set of RAIs. I will be providing other sets shortly.
Brenda L. Mozafari Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission 301-415-2020 email: brenda.mozafari@nrc.gov REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NOS. ME6587, ME6588, ME6589 AND ME6590)
EMCB RAI-1 Section IV.1.A.ii.f of Attachment 7 to the license amendment request (LAR) discusses the structural evaluation of the lower and upper core support assemblies for the effects of increased heat generation rates. Provide further information and confirm that (1) the proposed measurement uncertainty recapture (MUR) power uprate only affects the design loads associated with heat generation rates and all other design loads associated with the design of the reactor vessel internals are unaffected by the proposed MUR power uprate; (2) all design loading conditions, as noted in Section 3.9.5.2 of the Byron and Braidwood Updated Final safety Analysis Report (UFSAR), were considered in the structural re-evaluation of the reactor vessel internal components to assess the impact of the proposed MUR power uprate; and (3) the original design codes of record were utilized in the structural re-evaluation of the reactor vessel internal components.
Also, provide the maximum calculated stresses and cumulative fatigue usage factor for the most limiting component of the reactor vessel internals and their respective comparison with the Byron
and Braidwood stations design basis acceptance criteria.
EMCB RAI-2 Section 3.9.5.1 of the Byron and Braidwood UFSAR describes the reactor vessel internals as three parts consisting of the lower core support structure, the upper core support structure, and the incore instrumentation support structure.Section IV of Attachment 7 to the LAR does not discuss the incore instrumentation support structures. Provide further information relative to the impact of the design conditions associated with the proposed MUR power uprate on the incore instrumentation support structures.
EMCB RAI-3 Provide further information and confirm that, for the proposed MUR power uprate conditions, the maximum deflection values allowed for the reactor vessel internal support structures, as noted in Table 3.9-4 of the Byron and Braidwood UFSAR, are maintained.
EMCB RAI-4 Section IV.1.B.iv.1 of Attachment 7 to the LAR states that there is an approximate 1.2°F increase in temperature difference across the core (Thot increases approximately 0.6°F and Tcold decreases approximately 0.6°F) from current operating conditions due to the MUR power uprate.
Section IV.1.A.i of Attachment 7 to the LAR discusses reactor vessel structural evaluation and states that due to operational restrictions, the MUR minimum vessel inlet and maximum vessel outlet temperatures are limited to 538.2°F and 618.4°F, respectively. Provide further clarification on temperature effects relative to the values in Tables 3-1 and 3-2 of Attachment 1 to the LAR, the statements in Sections IV.1.B.iv.1 and IV.1.A.i of the LAR, and the temperatures used in the analysis of record.
Furthermore, the lifting lug loads and evaluation are discussed in Section IV.1.A.i of to the LAR. The terminology of lifting lug and its relation to and its inclusion in the proposed MUR power uprate license amendment is not clear.Provide further information to clarify which reactor vessel component is referred to as lifting lug. Also, regarding the affected reactor vessel component, (1) provide a table summarizing the comparison of design parameters for the current operation conditions, MUR power uprate conditions, and design basis conditions; and (2) provide the maximum calculated stresses and cumulative fatigue usage factors at the most critical location of the affected component and their respective comparison with the Byron and Braidwood stations design basis acceptance criteria.
EMCB RAI-5 Section IV.1.A.iii of Attachment 7 to the LAR discusses the control rod drive mechanism (CRDM). In this section, it is stated that updated seismic and loss of coolant accident (LOCA) loads remain less than the allowable loads provided in the analysis of record. This statement implies that the seismic loads have been updated. Also, this statement is not consistent with Section IV.1.A.ii.e of Attachment 7 to the LAR where it is stated that the proposed MUR power uprate conditions do not affect the current design basis for seismic and LOCA loads. Provide further clarification.
Furthermore,Section IV.1.A.iii of Attachment 7 to the LAR states that CRDM is subjected to Tcold temperatures and reactor coolant system (RCS) pressures and these are the only design parameters considered in the CRDM evaluation. Elaborate and confirm confirm that:
(1) the design basis loading conditions and operational requirements, as noted in Section 3.9.4 of the Byron and Braidwood UFSAR, have been considered in the structural evaluation of the control rod drive system for the proposed MUR power uprate conditions; and (2) the control rod drive system will continue to be in compliance with the Byron and Braidwood stations design basis acceptance criteria under the proposed MUR power uprate conditions.
EMCB RAI-6 Provide further information and confirm that the design basis pressure and temperatures (normal operating and accident temperatures) used in the design of the containment structure, including the steel liner plate, and its internal structures remain bounding following the proposed MUR power uprate.
EMCB RAI-7 Section IV.1.A.iv Reactor Coolant Piping and Supports of Attachment 7 to the LAR discusses the effects of the proposed MUR power uprate mostly on a qualitative basis and the term no significant changes has been used in several areas to describe the impact of the proposed MUR power update.
Discuss in more detail the information relative to the revised design conditions, before and after the proposed MUR power uprate, for those components evaluated under Section IV.1.A.iv of to the LAR. Summarize the results of any additional evaluations performed for the affected components and indicate whether these components remain bounded by the current analysis of record. For those components that were not bounded by the analysis of record, (1) provide the maximum calculated stresses and cumulative fatigue usage factors at the most critical location; and (
- 2) provide further clarification that the re-evaluation was performed in accordance with the design basis code of record and the affected components continue to remain in compliance with the Byron and Braidwood stations design basis acceptance criteria.
EMCB RAI-8 Section IV.1.A.v of Attachment 7 to the LAR discusses the evaluation of balance of plant (BOP) piping systems. Confirm that other BOP piping systems (for example, chemical and volume control, auxiliary feedwater, fuel pool cooling, containment spray, essential service water, safety injection) that may be affected by the MUR uprate conditions have been evaluated and provide a
complete list of BOP piping systems evaluated in support of MUR power uprate. Discuss the methodology used for evaluating BOP piping, including pipe supports, and provide further information relative to the design conditions in each BOP piping system, before and after the proposed MUR power uprate. Summarize the results of the additional evaluations performed for the affected piping systems and indicate whether these piping systems remain bounded by the current analysis of record. For those BOP piping systems that were not bounded by the current analysis of record, (1) provide the maximum calculated stresses and cumulative fatigue usage factors at the most critical location in each unbounded piping system; and (2) provide further clarification that the re-evaluation of the piping system, including pipe supports, was performed in accordance with the design basis code of record and in compliance with the Byron and Braidwood stations design basis acceptance criteria. Furthermore, state whether any piping or pipe support modifications are required to support the proposed MUR power uprate.
EMCB RAI-9 Section IV.1.A.viii of Attachment 7 to the LAR discusses the pressurizer structural evaluation. In this section of the LAR, it is stated that the revised design parameters have an insignificant impact on the fatigue analysis results. It is also stated that the proposed MUR power uprate has a negligible impact on the qualification of the pressurizer surge, spray, safety and relief nozzle structural weld overlay designs. Provide further information to support the above qualitative statements and to demonstrate compliance with the Byron and Braidwood stations design basis acceptance criteria. Also, provide a table summarizing the comparison of pressurizer design parameters for the current operation conditions, MUR power uprate conditions, and design basis conditions.
EMCB RAI-10 Section IV.1.B.iii of Attachment 7 to the LAR discusses the evaluation of the reactor vessel internal components for flow induced vibration (FIV) impact under MUR power uprate conditions.
Also,Section IV.1.A.ii.e of Attachment 7 to the LAR states that the FIV stress levels on the core barrel assembly and upper internals are below the material high-cycle fatigue endurance limit and the proposed MUR uprated conditions do not affect the structural margin for FIV.
Provide further information relative to those design parameters, before and after MUR power uprate, which could potentially influence FIV response of the reactor internals. Also, Discuss the comparison of alternating stress intensities to design basis allowable limits for the most critical components demonstrating compliance with the Byron and Braidwood stations design basis acceptance criteria.
EMCB RAI-11 Discuss further information and confirm that NSSS component supports, as discussed in Section 3.9.3.4 of the Byron and Braidwood UFSAR, will continue to be in compliance with the Byron and Braidwood stations design basis acceptance criteria at the proposed MUR power uprate conditions. Also, confirm that the operating temperatures for support elements, as defined in Table 3.9-17 of the Byron and Braidwood UFSAR, are not affected by the MUR power uprate.
EMCB RAI-12 Section IV.1.A.vi.1.b of Attachment 7 to the LAR discusses the structural evaluation of Byron and Braidwood stations Unit 1 replacement steam generators and states that a reconciliation analysis was performed to address the structural integrity of the entire steam generator pressure boundary for the MUR power uprate conditions. Discuss further information relative to, before and after uprate, the maximum stress intensity and the cumulative fatigue usage factors for the critical components of the primary and secondary sides, including nozzles, of the replacement steam generators and the respective service conditions. Also, confirm that the reconciliation analysis was performed in accordance with the original design code of record and in compliance with the Byron and Braidwood stations design basis acceptance criteria.
EMCB RAI-13 Discuss further information to demonstrate that, for the expected post-uprate conditions, the spent fuel pool (SFP) structure, including SFP liner and the spent fuel racks, remain capable of performing their intended design functions and will continue to be in compliance with the Byron and Braidwood stations design basis code of record(s) and acceptance criteria.