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Category:Letter
MONTHYEARML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23110A2402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Table of Contents ML23173A0132023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Structures and Shielding, Sections 1 Thru 4 - Redacted ML23110A2462023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 00, Cover Page and General Table of Contents ML23110A2472023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Table of Contents ML23110A2372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary, Table of Contents ML23110A2422023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation, Table of Contents ML23110A2592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix N, Peach Bottom Site Meteorology ML23110A2392023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix D, Table of Contents ML23110A2532023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations, Sections 1 Thru 8 ML23110A2202023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit IV, Vessel Fabrication and Assembly ML23173A0552023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Station Atmospheric Release Limit Calculations - Redacted ML23110A2232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix G, Plant Nuclear Safety Operational Analysis ML23173A0402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation - Redacted ML23173A0382023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix M Containment Report - Redacted ML23172A2812023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Figures - Redacted ML23173A0582023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Figures - Redacted ML23110A2312023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 11, Table of Contents ML23110A2602023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 3, Figures ML23173A0162023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Figures - Redacted Rev1 ML23173A0172023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Sections 10 Thru 23 - Redacted ML23172A2802023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Figures - Redacted ML23110A2652023-04-10010 April 2023 Submittal of Revision 29 to Updated Final Safety Analysis Report and Rev. 24 to Fire Protection Program ML23173A0452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Table of Contents - Redacted ML23172A2752023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Table of Contents - Redacted ML23173A0332023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 2, Site - Redacted ML23172A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Figures - Redacted ML23173A0482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents - Redacted ML23110A2562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML23110A2322023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix P, Environmental Technical Specifications ML23173A0232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Figures - Redacted ML23110A2242023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit Vi.B Unit 3, Deleted ML23110A2612023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix O, Table of Contents ML23173A0592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix J, Identification-Resolution of AEC-ACRS and Staff Concerns - Redacted ML23173A0492023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Figures - Redacted ML23110A2512023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 6, Figures ML23173A0572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Structural Design Criteria - Redacted ML23173A0562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Auxiliary Systems, Sections 1 Thru 24 - Redacted ML23173A0292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Figures - Redacted ML23173A0432023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Electrical Power Systems - Redacted ML23172A2842023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Table of Contents - Redacted ML23173A0372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Pressure Integrity of Piping and Equipment Pressure Parts - Redacted ML23110A2482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit III, Summary Stress Report ML23110A2452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix H, Table of Contents ML23110A2502023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Table of Contents ML23110A2292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Table of Contents ML23110A2572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Containment ML23110A2212023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Figures ML23110A2282023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix F, Interaction of Units 2 and 3 ML23110A2412023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix Q, Figure ML23110A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Table of Contents 2023-04-10
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Exelon Nuclear www.exeloncorp.com Exelon.
200 Exelon Way Nucea-Kennett Square, PA 19348 10CFR50.71 (e)(4)
August 14, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Peach Bottom Atomic Power Station, Unit 1 Facility Operating License No. DPR-12 NRC Docket No. 50-171
Subject:
Peach Bottom Atomic Power Station, Unit 1 Updated Final Safety Analysis Report, Revision 5 In accordance with 10CFR50.71 (e)(4) and 10CFR50.4(b)(6), this letter submits Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1.
The attached copy is being provided to the NRC with page revision listings that identify the latest revision date of all current pages in accordance with 10CFR50.71 (e)(1). Page replacement instructions for incorporating Revision 5 into the UFSAR are also included in the Attachment. As required by 1 OCFR50.71 (e)(5), each replacement page contains a bold vertical line in the margin adjacent to each area changed along with the date of the change. Two (2)
Engineering Change Requests (ECRs) were incorporated in Revision 5 of the PBAPS, Unit 1, UFSAR (ECRs 09-00023 and 08-00414).
As required by 10CFR50.71 (e)(2)(i), I certify that to the best of my knowledge, Revision 5 to the PBAPS Unit 1 UFSAR accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. In addition, as required by 10CFR50.71 (e)(2)(ii), no changes under the provisions of 1 OCFR50.59, but not previously submitted to the NRC, have been made.
If you have any questions or require further information, please contact Tom Loomis at (610) 765-5510.
Very truly yours, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC /i----
Updated Final Safety Analysis Report, Revision 5 August 14, 2009 Page 2
Attachment:
Revision 5 of the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland L. Kauffman, USNRC, Region I
PBAPS PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REPLACEMENT INSTRUCTIONS Revision 5, August 14, 2009 Remove Page Insert Page
[Revisions indicated by revision bar at right margin]
Page Revision Listing (page 1 & 2) Page Revision Listing (pages 1 & 2)
Page 14 Page 14 Page 68 Page 68
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT Page Revision Listing TITLE REVISION DATE Updated Final Safety Analysis Report Title Page 4 8/27/03 Note Page 3/27/98 Table of Contents 3/27/98 Pages 1 - 13 3/27/98 Page 14 5 8/14/09 Pages 15 - 35 3/27/98 Pages 36 - 39 2 11/15/99 Page 40 3/27/98 Pages 41 - 44 2 11/15/99 Page 45 3/27/98 Page 46 3 8/27/01 Page 47 2 11/15/99 Page 48 3 8/27/01 Pages 49 - 50 2 11/15/99 Page 51 3 8/27/01 Pages 52 - 53 3/27/98 Pages 54 - 56 2 11/15/99 Pages 57 - 58 3/27/98 Pages 59 - 61 2 11/15/99 Pages 62 - 63 3/27/98 Pages 64 - 66 2 11/15/99 Page 67 3 8/27/01 Page 68 5 8/14/09 Pages 69-79 3/27/98 Appendix 1 Licensing Documents 4 8/27/03 License Reference Letters November 24, 1975 Letter to NRC 3/27/98 March 4,1987 Letter to NRC 3/27/98 December 16, 1988 Letter to NRC 3/27/98 July 12, 1989 Letter to NRC 3/27/98 August 23, 1989 Letter to NRC 3/27/98 License/Technical Specifications Amendment No. 11 to License No. DPR-12 4 8/27/03 Technical Specifications (4 pages)
Page 1 3 8/27/01 Page 2 4 8/27/03 Page 3 4 8/27/03 Page 4 4 8/27/03 AUG 14 2009 I Revision 5 I
PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REVISION LISTING (Continued)
NRC SERs Safety Evaluation Supporting Amendment No. 7 3/27/98 Safety Evaluation Supporting Amendment No. 8 3/27/98 Safety Evaluation Supporting Amendment No. 9 1 10/27/98 Safety Evaluation Supporting Amendment No. 10 3 8/27/01 Safety Evaluation Supporting Amendment No. 11 4 8/27/03 AUG 14 2009 Revision 5 i
water is required to prevent overheating of the delay beds. Therefore, the emergency cooling system for the water cooled delay beds will be removed from service soon after reactor shutdown to permit decommissioning work on this system early in the schedule.
3.4.7 All piping connections which penetrate the contain-ment will be severed, capped and welded outside the containment, except for the containment vacuum breaker assembly and associated penetration.
Electrical penetrations will be left as is. The ventilation supply and exhaust ducts will be severed and welded shut outside the containment.
A six inch pressure equalization line equipped with a replaceable absolute filter will be installed on the containment to prevent a pressure differential from developing between the inside and outside of the containment. In addition, the containment vacuum breaker assembly was left as-is per NCR 95-00043.
3.4.8 The outer door of the emergency air lock and the equipment door on Elevation 116' will be welded closed. The inner doors of the personnel air lock on Elevation 116' and the access lock on Elevation 176'-6" will be welded in the open position. The interlock mechanisms in these two latter locks will be disabled and the outer door on each lock will be secured with a heavy duty padlock.
3.4.9 Flammable materials other than electrical cables and solid graphite left in the sealed reactor vessel will be removed from the containment.
AUG 14 2009 Revision 5
Other possible radiological hazards could occur in the event of a fire, flooding, or severe local storm damage. Since all readily flammable material has been removed as appropriate from the SAFSTOR facility, the chance of fire has been reduced considerably.
Flooding has been discussed in Section 4.2.
Since this SAFSTOR facility is in the immediate vicinity of Units 2-3, which are operating, any local condition which may require emergency action will be apparent to the Unit 2-3 operating staff so that they can take appropriate, timely action.
4.4.7 Processing of Unit 1 Liquid Radwaste Any liquid waste created or found at Unit 1 will be designated as Unit 1 waste and appropriately reported to the NRC in accordance with Technical Specifications. This waste will be transferred to the PBAPS radwaste facility located between Units 2 and 3 for processing. This waste will be clearly designated as belonging to the Unit 1 facility. This process will be controlled by written procedures.
AUG 14 2009 Revision 5