|
|---|
Category:Graphics incl Charts and Tables
MONTHYEARBYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022
Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)
ML22031A0442022-01-31031 January 2022
Form OAR-1 Owner'S Activity Report
ML21202A1932021-07-21021 July 2021
Owner'S Activity Report (OAR) for Refueling Outage A1R22
RS-20-126, EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart2020-10-13013 October 2020
EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart
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
ML19030B0872019-01-30030 January 2019
Submittal of Inservice Inspection Summary Report
ML15253A9132015-09-11011 September 2015
ACRS Full Committee - Corrections to the Aging Management Programs Table
ML15229A1482015-09-0303 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR 50.54 Information Request - Flood Causing Mechanism Reevaluation
ML15226A5982015-09-0303 September 2015
Tables 1 and 2 8-11-2015 Edited-SB
RS-15-059, Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application2015-02-0606 February 2015
Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application
ML14307B7072014-12-10010 December 2014
Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T
RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013
Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites
ML1106107952011-03-0202 March 2011
E-mail Byron Station Unit 1 Supplemental Information Request to Support Baseline ISI Inspection Procedure
NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010
Re-Submittal of the Exelon Cyber Security Plan
RS-10-105, Byron Parent Guarantee Calculation RS-10-1052010-03-10010 March 2010
Byron Parent Guarantee Calculation RS-10-105
ML0934313182009-12-0101 December 2009
Updated Decommissioning Shortfalls as of December 1, 2009
ML0822700142008-08-13013 August 2008
Transmittal of Response to Request for Additional Information Regarding Fall 2007 Steam Generator Inspection
ML0818300872008-03-31031 March 2008
Steam Generator Eddy Current Inspection Report, Refueling Outage 15, Attachment B, Inspection Scope, Through Attachment B.2, Cold Leg Bobbin Coil Inspection Scope.
ML0802501842008-01-10010 January 2008
Amag Loop Corrosion Factor Vs. Date for Byron Unit 2
ML0802501512008-01-10010 January 2008
Graphs
ML0802501902008-01-10010 January 2008
Amag Corrosion Factor for Reactor Coolant Loop Vs. Date for Byron Unit 1
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0707300272007-03-0707 March 2007
Oak Ridge Institute for Science and Education - Letter Report for 18 Water Samples from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2007-003) (Rfta No. 06-001)
RS-07-022, Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification2007-02-15015 February 2007
Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification
ML0621602722006-07-28028 July 2006
Analytical Results for Fourteen Water Samples, Batch Eight, from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2006-004)(RFTA No. 06-001)
ML0612206832006-04-27027 April 2006
Oak Ridge Institute for Science and Education, Analytical Results for 41 Water Samples in Batch Two from the Vicinity of the Byron Generating Station, Byron Illinois (Inspection Report No. 05000454/2006-003) (Rfta No. 06-001)
ML0617103272006-02-0606 February 2006
Tritium Sample Results
BYRON 2006-0007, Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 222006-01-0303 January 2006
Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 22
ML0617102252005-12-19019 December 2005
Orise Letter Dated 12/19/05, W/Personal Notes, Analytical Results for Water Samples Near the Braidwood Nuclear Generation Station in Braidwood, Illinois, Inspection Report 456/457/2005-010 - Rfta No. 06-001
ML0610106942005-12-16016 December 2005
Schematic of Regional Hydrogeology
ML0609606442005-11-17017 November 2005
Tritium Sample Results; NRC Split Sample Results
ML0522300142005-03-0909 March 2005
RIC 2005 Presentation - F4 - Dale Ambler - Rop/Cross Cutting Issues
RS-04-191, Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-3192004-12-16016 December 2004
Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-319
ML0422603572004-08-12012 August 2004
Figure 1 and 2, Results of the Spring 2004 Steam Generator Inspections
ML0609605552001-01-31031 January 2001
Revision 5 of Table 11a (Continued) Teen Inhalation Dose Factors
2022-07-15
[Table view]
Category:Memoranda
MONTHYEARML24152A1852024-06-0404 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
ML23044A3662023-02-15015 February 2023
Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III
ML22300A0842022-11-10010 November 2022
Pressure and Temperature Limits Report (Ptlr), Revision 8
ML21349A1062021-12-15015 December 2021
Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273
ML21277A2472021-11-0505 November 2021
Notification of Significant Licensing Action - Proposed Issuance of Order Approving the Transfer of Licenses for Which a Hearing Has Been Requested - Exelon Generation Company, LLC; Et. Al
ML20155K6802020-11-23023 November 2020
Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Corporation, LLC, Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Byron ISFSI
ML20155K6862020-11-23023 November 2020
Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Corporation LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Braidwood ISFSI
ML17335A0442017-12-0404 December 2017
Tvel Lead Test Assembly 3rd Closed Meeting
ML17164A3302017-06-13013 June 2017
Safety Evaluation Regarding the Proposed License Amendment to Revise the Byron Licensing Bases for Protection from Tornado-Generated Missiles (CAC Number MF8446 and 8447)
ML17142A2382017-05-25025 May 2017
OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns
ML16236A2022016-08-24024 August 2016
Backfit Appeal Review Panel Findings Associated with Byron and Braidwood Compliance
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16082A5422016-03-25025 March 2016
Backfit Review Panel Recommendation Regarding Exelon Appeal of Backfit Affecting Braidwood and Byron Stations Regarding Compliance with 10 CFR 50.34(b), GDC 15, GDC 21, GDC 29, and the Licensing Basis
ML16074A3232016-03-21021 March 2016
Forthcoming Meeting with Exelon Nuclear
ML16075A3292016-03-16016 March 2016
OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML16070A3622016-03-15015 March 2016
03/07/2016 Summary of Public Meeting Between U.S. Nuclear Regulatory Commission Staff and Exelon Generation Company, LLC to Discuss an Appeal of a Compliance Backfit
ML15336A0172016-01-20020 January 2016
Renewal of Full-Power Operating License for Braidwood Station, Units 1 and 2
ML15355A0812016-01-12012 January 2016
Backfit Review Panel Charter Regarding December 8, 2015, Exelon Appeal of Imposed Backfit Affecting Braidwood and Byron Stations
ML15267A7342015-11-10010 November 2015
Renewal of Full-Power Operating Licenses for Byron, Units 1 and 2
ML15253A9132015-09-11011 September 2015
ACRS Full Committee - Corrections to the Aging Management Programs Table
ML15187A3272015-07-13013 July 2015
Request for ACRS Review of Byron Braidwood SER
ML15051A3612015-03-0303 March 2015
02/05/2015 Summary of Telephone Conference Call No 2 Held Between the NRC and Exelon Generation Co., LLC Concerning Request for Additional Information, Set 45, Pertaining to the Byron, and Braidwood, License Renewal Application
ML15016A4732015-01-15015 January 2015
Ltr 2014 Byron EP Annual Closeout (Rdj)
ML14317A5432014-11-17017 November 2014
Federal Register Notice Regarding the ACRS Plant License Renewal Subcommittee Meeting (Braidwood/Byron), December 3, 2014
ML14205A5752014-08-11011 August 2014
Summary of Telephone Conference Call Held on June 10, 2014, Between U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Fire Water System Request for Additional Information Responses Pertaining to Byron Station.
ML14227A1092014-07-0909 July 2014
Bryron, Units 1 & 2 - Imposition of Facility-Specific Baskfit Compliance with Licensing Basis Plant Design Requirements
ML14177A4302014-07-0202 July 2014
06/23/2014 Summary of Telephone Conference Call Between NRC and Exelon Generation Co., LLC, Concerning the Byron and Braidwood, License Renewal Application (TAC Nos. MF1879, MF1880, MF1881 and MF1882)
ML14148A3882014-06-0505 June 2014
Summary of Telephone Conference Call Held on May 19, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 28, Pertaining to the Byron Station and Br
ML14126A5432014-05-19019 May 2014
Summary of Telephone Conference Call Held on April 22, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 24, Pertaining to the Byron Station and
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
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
ML14085A1102014-04-30030 April 2014
Summary of Telephone Conference Call Held on March 24, 2014 Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Braidwood Station, License Renew
ML14092A3562014-04-15015 April 2014
Summary of Telephone Conference Call Held on March 31, 2014 Between the U.S. NRC and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Braidwood Station, License Renewal Application
ML14069A3372014-04-0202 April 2014
Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable
ML12194A5002014-03-31031 March 2014
Final TIA Response Byron Braidwood Single Spurious Assumption
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
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
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
ML14063A1742014-01-28028 January 2014
Making Non-Concurrence NCP-2013-014 Public Available
ML13267A0802013-12-0909 December 2013
Reactor Systems Branch Safety Evaluation Input to Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2 Measurement Uncertainty Recapture Power Update
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
ML13240A2342013-10-0404 October 2013
8/10/2013 - Summary of Public Scoping Meetings Conducted Related to the Review of the Byron Nuclear Station, License Renewal Application(Tac Nos. MF1790 and MF1791)
ML13246A4342013-09-27027 September 2013
09/28/2013 Meeting Summary of Public Scoping Meetings Conducted Related to the Review of the Braidwood Station, Unit 1 and 2, License Renewal Application
ML13246A0162013-09-0404 September 2013
Notice of Forthcoming Teleconference Meeting with Exelon Generation Company, LLC to Discuss Future Submittal of License Amendment Request to Clarify Braidwood Nuclear Station Technical Specification 5.5.16
ML13205A0452013-08-0707 August 2013
08/20/2013 Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Exelon Generation Company, Llc(Exelon), Byron Nuclear Station, Units 1 and 2
ML13193A3612013-08-0505 August 2013
08/21/2013 Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Exelon Generation Company, LLC, Braidwood Nuclear Station Units 1 and 2
ML13190A3522013-07-10010 July 2013
Notice of Forthcoming Teleconference with Exelon Generation Company, LLC
ML13094A0922013-04-0404 April 2013
Notice of Forthcoming Meeting with Exelon Generation Company, LLC to Discuss Future Submittal of a License Amendment Request to Modify Technical Specifications for the Main Steam Isolation Valves & Their Actuators
ML13014A7652013-02-0404 February 2013
03/20/2013 Notice of Forthcoming Meeting with Exelon Corporation Regarding License Renewal Application for the Byron and Braidwood Nuclear Power Stations
2024-06-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
September 11, 2015
MEMORANDUM TO: Edwin M. Hackett, Executive Director Advisory Committee on Reactor Safeguards
FROM: Christopher G. Miller, Director /RA by JMarshall for
/ Division of License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REVIEW OF THE BYRON-BRAIDWOOD NUCLEAR STATIONS LICENSE RENEWAL APPLICATION - CORRECTIONS TO THE TABLE OF AGING MANAGEMENT PROGRAMS FOR THE SAFETY EVALUATION REPORT
During the ACRS full committee review for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, license renewal application (LRA) on September 10, 2015, the staff indicated that corrections had been identified for Table 3.0-1, "Byron and Braidwood Aging Management Programs," in the staff's "Safety Evaluation, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2" Safety Evaluation Report (SER) (ADAMS Accession No. ML15182A051). The purpose of this memorandum is to describe those changes in the table that will be incorporated in the NUREG version of the SER.
The staff identified three cases of aging management program (AMP) summaries in the table where corrections need to be made; these are shown in the red-line/strikeout version of the Table in Enclosure 1. Specifically:
- The Water Chemistry AMP is changed in the "SER Section (Disposition)" column (column 6) to "Consistent with exception," as opposed to stating "Consistent."
- The Flux Thimble Tube Inspection AMP is changed in "LRA Initial Comparison to the GALL Report" (column 4) to "Consistent," as opposed to "Consistent with exception and enhancements."
- The Environmental Qualification (EQ) of Electric Components AMP is changed in the "SER Section (Disposition)" column (column 6) to "consistent with enhancement" as opposed to "Consistent."
CONTACT: John Daily, NRR/DLR 301-415-3873
These summary designations in the Enclosure have been reviewed against the corresponding SER sections and verified that these accurately reflect the staff's evaluations. These corrections to Table 3.0-1 will be incorporated into the NUREG version of the SER, which also will include the ACRS letter. This NUREG will be prepared and published after the ACRS letter has been issued.
The staff also presented a table showing a summary of the AMPs reflecting which ones were evaluated by the staff as "consistent," "consistent with exceptions," "consistent with enhancements," and "consistent with enhancements and exceptions." The following table is provided to clarify the staff dispositions of the AMPs for each station:
Total AMPs in SER Staff's Disposition Byron AMPs Braidwood AMPs New 13 New Programs 13 New Programs Consistent 11 10 (Fuse Holders AMP is N/A for Braidwood) Consistent with exceptions 2 2 Existing 32 Existing Programs 32 Existing Programs Consistent 5 (Includes Flux Thimble Tube Inspection AMP for Byron) 4 Consistent with enhancements 20 20 Consistent with exceptions 1 1 Consistent with enhancements and exceptions 6 7 (Includes Flux Thimble Tube Inspection AMP for Braidwood) 45 Total AMPs 45 AMPs 44 AMPs
A disposition of a program as "consistent" means that it is consistent with the GALL Report (Revision 2), as amended by approved Interim Staff Guidance (ISGs). An "enhancement" is an addition to an existing program to bring it into consistency with the GALL Report (as amended by ISGs). An "exception" is a portion of a GALL Report recommendation (as amended by ISGs) that the applicant does not intend to implement. These are evaluated for acceptability by the staff.
The Electrical Fuse holders AMP is a new program, and is applicable only to Byron. Braidwood does not have any components to be managed by this AMP. Therefore, Byron has 45 total applicable AMPs, whereas Braidwood has 44 applicable. The total count of AMPs that have exceptions for Byron is 9; the total count for Braidwood is 10.
As stated in SER Section 3.0.3.2.11, the staff considered 2 instances of the applicant's Fire Water System program to be exceptions to the recommendations of LR-ISG-2012-02. The staff determined that the exceptions were acceptable and that the program, with enhancements and exceptions, is adequate to manage the effects of aging for the fire water system.
The Flux Thimble Tube Inspection program is an existing program and has an exception and three enhancements applicable only to Braidwood; therefore for Braidwood it is "consistent with enhancements and exceptions," and for Byron it is considered "consistent." This is reflected in the count of "consistent" programs for Byron and the "consistent with enhancements and exceptions" count for Braidwood.
If you have any questions, please contact John Daily, the license renewal Safety Project Manager for this application, at 301-415-3873 or by email at John.Daily@NRC.Gov.
Docket Nos. 50-454, 50-455, 50-456, and 50-457
Enclosure:
Table 3.0-1 Byron and Braidwood Aging Management Programs (changes in
redline/strikeout)
ML15253A913 *concurred via email OFFICE LA:DLR* PM:DLR:RPB1BC:DLR:RPB1 D:DLR NAME YEdmonds JDaily YDiaz-SanabriaJMarshall for CMiller DATE 9/10/2015 9/10/2015 9/11/2015 9/11/2015 ENCLOSURE Table 3.0-1 Byron and Braidwood Aging Management Programs (changes in redline/strikeout)
Applicant AMP LRA Sections New or Existing Program LRA Initial Comparison to the GALL Report GALL Report AMP(s)
SER Section (Disposition)
American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection, Subsections IWB, IWC, and IWD A.2.1.1 B.2.1.1 Existing Consistent with enhancement XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD 3.0.3.2.1 (Consistent with enhancement)
Water Chemistry A.2.1.2 B.2.1.2 Existing Consistent XI.M2, Water Chemistry 3.0.3.1.1 (Consistent with exception
) Reactor Head Closure Stud Bolting A.2.1.3 B.2.1.3 Existing Consistent with exception and enhancement XI.M3, Reactor Head Closure Stud Bolting 3.0.3.2.2 (Consistent with exception
and enhancement)
Boric Acid Corrosion A.2.1.4 B.2.1.4 Existing Consistent XI.M10, Boric Acid Corrosion 3.0.3.1.2 (Consistent)
Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components A.2.1.5 B.2.1.5 Existing Consistent XI.M11B, Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components (Pressurized Water Reactors (PWRs) only) 3.0.3.1.3 (Consistent)
Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)
A.2.1.6 B.2.1.6 New Consistent XI.M12, Thermal Aging Embrittlement of CASS 3.0.3.1.4 (Consistent)
PWR Vessel Internals A.2.1.7 B.2.1.7 New Consistent with exception XI.M16A, PWR Vessel Internals 3.0.3.2.3 (Consistent with exception)
Flow-Accelerated Corrosion A.2.1.8 B.2.1.8 Existing Consistent XI.M17, Flow-Accelerated Corrosion 3.0.3.1.5 (Consistent with enhancement)
Applicant AMP LRA Sections New or Existing Program LRA Initial Comparison to the GALL Report GALL Report AMP(s)
SER Section (Disposition)
Bolting Integrity A.2.1.9 B.2.1.9 Existing Consistent with enhancements XI.M18, Bolting Integrity 3.0.3.2.4 (Consistent with enhancements)
Steam Generators A.2.1.10 B.2.1.10 Existing Consistent with exception and enhancements XI.M19, Steam Generators 3.0.3.2.5 (Consistent with exception and enhancements)
Open-Cycle Cooling Water System A.2.1.11 B.2.1.11 Existing Consistent with enhancement XI.M20, Open-Cycle Cooling Water System 3.0.3.2.6 (Consistent with enhancements)
Closed Treated Water Systems A.2.1.12 B.2.1.12 Existing Consistent with enhancements XI.M21A, Closed Treated Water Systems 3.0.3.2.7 (Consistent with enhancements)
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems A.2.1.13 B.2.1.13 Existing Consistent with enhancements XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems 3.0.3.2.8 (Consistent with enhancements)
Compressed Air Monitoring A.2.1.14 B.2.1.14 Existing Consistent with exception and enhancement XI.M24, Compressed Air Monitoring 3.0.3.2.9 (Consistent with exception and enhancement)
Fire Protection A.2.1.15 B.2.1.15 Existing Consistent with enhancements XI.M26, Fire Protection 3.0.3.2.10 (Consistent with enhancements)
Fire Water System A.2.1.16 B.2.1.16 Existing Consistent with enhancements XI.M27, Fire Water System 3.0.3.2.11 (Consistent with exceptions and enhancements)
Aboveground Metallic Tanks A.2.1.17 B.2.1.17 New Consistent with exception XI.M29, Aboveground Metallic Tanks 3.0.3.2.12 (Consistent with exception)
Fuel Oil Chemistry A.2.1.18 B.2.1.18 Existing Consistent with enhancements XI.M30, Fuel Oil Chemistry 3.0.3.2.13 (Consistent with enhancements)
Applicant AMP LRA Sections New or Existing Program LRA Initial Comparison to the GALL Report GALL Report AMP(s)
SER Section (Disposition)
Reactor Vessel Surveillance A.2.1.19 B.2.1.19 Existing Consistent with enhancement XI.M31, Reactor Vessel Surveillance 3.0.3.2.14 (Consistent with enhancements)
One-Time Inspection A.2.1.20 B.2.1.20 New Consistent XI.M32, One-Time Inspection 3.0.3.1.6 (Consistent)
Selective Leaching A.2.1.21 B.2.1.21 New Consistent XI.M33, Selective Leaching 3.0.3.1.7 (Consistent)
One-Time Inspection of ASME Code Class 1 Small Bore Piping A.2.1.22 B.2.1.22 New Consistent XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore-Piping 3.0.3.1.8 (Consistent)
External Surfaces Monitoring of Mechanical Components A.2.1.23 B.2.1.23 New Consistent XI.M36, External Surfaces Monitoring of Mechanical Components 3.0.3.1.9 (Consistent)
Flux Thimble Tube Inspection A.2.1.24 B.2.1.24 Existing Consistent with exception and enhancements XI.M37, Flux Thimble Tube Inspection 3.0.3.1.10 (Consistent with exception and enhancements)
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components A.2.1.25 B.2.1.25 New Consistent XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components 3.0.3.1.11 (Consistent)
Lubricating Oil Analysis A.2.1.26 B.2.1.26 Existing Consistent XI.M39, Lubricating Oil Analysis 3.0.3.1.12 (Consistent)
Monitoring of Neutron-Absorbing Materials Other than Boraflex A.2.1.27 B.2.1.27 Existing Consistent XI.M40, Monitoring of Neutron-Absorbing Materials Other than Boraflex 3.0.3.1.13 (Consistent with enhancement)
Buried and Underground Piping A.2.1.28 B.2.1.28 Existing Consistent with exceptions and enhancements XI.M41, Buried and Underground Piping and Tanks 3.0.3.2.15 (Consistent with exceptions and enhancements)
ASME Section XI, Subsection IWE A.2.1.29 B.2.1.29 Existing Consistent with enhancement XI.S1, ASME Section XI, Subsection IWE 3.0.3.2.16 (Consistent with enhancements)
Applicant AMP LRA Sections New or Existing Program LRA Initial Comparison to the GALL Report GALL Report AMP(s)
SER Section (Disposition)
ASME Section XI, Subsection IWL A.2.1.30 B.2.1.30 Existing Consistent with enhancements XI.S2, ASME Section XI, Subsection IWL 3.0.3.2.17 (Consistent with enhancements)
ASME Section XI, Subsection IWF A.2.1.31 B.2.1.31 Existing Consistent with exceptions and enhancements XI.S3, ASME Section XI, Subsection IWF 3.0.3.2.18 (Consistent with exceptions and enhancements) 10 CFR Part 50, Appendix J A.2.1.32 B.2.1.32 Existing Consistent XI.S4, 10 CFR Part 50, Appendix J 3.0.3.1.14 (Consistent)
Masonry Walls A.2.1.33 B.2.1.33 Existing Consistent with enhancements XI.S5, Masonry Walls 3.0.3.2.19 (Consistent with enhancements)
Structures Monitoring A.2.1.34 B.2.1.34 Existing Consistent with enhancements XI.S6, Structures Monitoring 3.0.3.2.20 (Consistent with enhancements)
RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants A.2.1.35 B.2.1.35 Existing Consistent with enhancements XI.S7, RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants 3.0.3.2.21 (Consistent with enhancements)
Protective Coating Monitoring and Maintenance Program A.2.1.36 B.2.1.36 Existing Consistent with enhancements XI.S8, Protective Coating Monitoring and Maintenance Program 3.0.3.2.22 (Consistent with enhancements)
Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements A.2.1.37 B.2.1.37 New Consistent XI.E1, Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements 3.0.3.1.15 (Consistent)
Applicant AMP LRA Sections New or Existing Program LRA Initial Comparison to the GALL Report GALL Report AMP(s)
SER Section (Disposition)
Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits A.2.1.38 B.2.1.38 New Consistent XI.E2, Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits 3.0.3.1.16 (Consistent)
Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements A.2.1.39 B.2.1.39 New Consistent XI.E3, Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements 3.0.3.1.17 (Consistent)
Metal Enclosed Bus A.2.1.40 B.2.1.40 Existing Consistent with enhancements XI.E4, Metal Enclosed Bus 3.0.3.2.23 (Consistent with enhancements)
Fuse Holders (Byron Only) A.2.1.41 B.2.1.41 New Consistent XI.E5, Fuse Holders 3.0.3.1.18 (Consistent)
Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements A.2.1.42 B.2.1.42 New Consistent XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements 3.0.3.1.19 (Consistent)
Fatigue Monitoring A.3.1.1 B.3.1.1 Existing Consistent with enhancements X.M1, Fatigue Monitoring 3.0.3.2.24 (Consistent with enhancements)
Concrete Containment Tendon Prestress A.3.1.2 B.3.1.2 Existing Consistent with enhancement X.S1, Concrete Containment Tendon Prestress 3.0.3.2.25 (Consistent with enhancement)
Environmental Qualification (EQ) of Electric Components A.3.1.3 B.3.1.3 Existing Consistent X.E1, Environmental Qualification (EQ) of Electrical Components 3.0.3.1.20 (Consistent with enhancement
)
