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| | issue date = 12/29/2009 | | | issue date = 12/29/2009 |
| | title = License Amendment Request for Adoption of TSTF-478-A, Revision 2 Supplemental Response to Revise Technical Specifications Page Mark-ups | | | title = License Amendment Request for Adoption of TSTF-478-A, Revision 2 Supplemental Response to Revise Technical Specifications Page Mark-ups |
| | author name = Cowan P B | | | author name = Cowan P |
| | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Exel nExelon Nuclear www.exeloncorp.com 200 Exelon Way Nucea-Kennett Square, PA 19348 1 0CFR50.90 December 29, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278 | | {{#Wiki_filter:Exelon Nuclear www.exeloncorp.com Exel n 200 Exelon Way Nucea-Kennett Square, PA 19348 10CFR50.90 December 29, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278 |
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| ==Subject:== | | ==Subject:== |
| License Amendment Request for Adoption of TSTF-478-A, Revision 2 Supplemental Response to Revise Technical Specifications Page Mark-ups | | License Amendment Request for Adoption of TSTF-478-A, Revision 2 Supplemental Response to Revise Technical Specifications Page Mark-ups |
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| ==References:== | | ==References:== |
| : 1) Letter from Pamela B. Cowan, Exelon Generation Company, LLC, to U.S.Nuclear Regulatory Commission | | : 1) Letter from Pamela B. Cowan, Exelon Generation Company, LLC, to U.S. |
| -License Amendment Request for Adoption of TSTF-478-A, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," Using the Consolidated Line Item Improvement Process, dated July 30, 2009 2) Federal Register Notice 72FR65610 | | Nuclear Regulatory Commission - License Amendment Request for Adoption of TSTF-478-A, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," Using the Consolidated Line Item Improvement Process, dated July 30, 2009 |
| -Notice of Availability on Model Safety Evaluation; Model No Significant Hazards Determination, and Model Application for Licensees that Wish to Adopt TSTF-478, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," dated November 21, 2007 By letter dated July 30, 2009 (Reference 1), Exelon Generation Company, LLC (Exelon)submitted a License Amendment Request (LAR) to revise the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed changes would revise the TS for PBAPS, Units 2 and 3, consistent with NRC-approved Industry TS Task Force (TSTF) Change Traveler TSTF-478-A, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control" (Reference 2). The proposed changes would delete the TS requirements associated with the "Containment Atmospheric Dilution (CAD) System." Subsequently, it was identified that the mark-ups on TS page 3.8-41 for Units 2 and 3 contained an editorial discrepancy. | | : 2) Federal Register Notice 72FR65610 - Notice of Availability on Model Safety Evaluation; Model No Significant Hazards Determination, and Model Application for Licensees that Wish to Adopt TSTF-478, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," dated November 21, 2007 By letter dated July 30, 2009 (Reference 1), Exelon Generation Company, LLC (Exelon) submitted a License Amendment Request (LAR) to revise the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed changes would revise the TS for PBAPS, Units 2 and 3, consistent with NRC-approved Industry TS Task Force (TSTF) Change Traveler TSTF-478-A, Revision 2, "BWR TechnicalSpecification Changes that Implement the Revised Rule for Combustible Gas Control"(Reference 2). The proposed changes would delete the TS requirements associated with the "Containment Atmospheric Dilution (CAD) System." |
| Specifically, there was a strikeout line through the reference to "LCO 3.6.3.1" indicating that the section should be deleted. However, the strikeout line was not completely carried through to include the remaining portion of the reference, i.e., "Containment Atmospheric Dilution (CAD) System." Accordingly, this letter is being submitted to correct this editorial discrepancy. | | Subsequently, it was identified that the mark-ups on TS page 3.8-41 for Units 2 and 3 contained an editorial discrepancy. Specifically, there was a strikeout line through the reference to "LCO 3.6.3.1" indicating that the section should be deleted. However, the strikeout line was not completely carried through to include the remaining portion of the reference, i.e., "Containment Atmospheric Dilution (CAD) System." |
| Attachment 1 contains the revised mark-up for the affected TS page for Units 2 and 3 and Attachment 2 includes the revised re-typed page for the affected Units 2 and 3 TS page.14 f. -- | | Accordingly, this letter is being submitted to correct this editorial discrepancy. Attachment 1 contains the revised mark-up for the affected TS page for Units 2 and 3 and Attachment 2 includes the revised re-typed page for the affected Units 2 and 3 TS page. |
| U.S. Nuclear Regulatory Commission License Amendment Request Supplemental Response Deletion of CAD System from TS Docket Nos. DPR-44 and DPR-56 December 29, 2009 Page 2 Exelon has concluded that the information provided in this supplemental response does not impact the conclusions of the: 1) Technical Evaluation, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal (Reference 1).There are no new commitments contained in this submittal. | | 14 f.-- |
| Should you have any questions concerning this letter, please contact Mr. Richard Gropp at (610) 765-5557.I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of December 2009.Respectfully, Pamela B. Cowan Director -Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments: | | |
| 1 -Revised Mark-ups of Technical Specifications Pages 2 -Revised Re-typed Technical Specifications Pages cc: S. J. Collins, Administrator, Region I, USNRC F. L. Bower, USNRC Senior Resident Inspector, PBAPS J. Hughey, Project Manager, USNRC R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland A'TACHMENT 1 Revised Mark-ups of Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES......Unit2 Unit3........... | | U.S. Nuclear Regulatory Commission License Amendment Request Supplemental Response Deletion of CAD System from TS Docket Nos. DPR-44 and DPR-56 December 29, 2009 Page 2 Exelon has concluded that the information provided in this supplemental response does not impact the conclusions of the: 1) Technical Evaluation, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal (Reference 1). |
| 3 .8 -41.....................................................3 | | There are no new commitments contained in this submittal. |
| .8 -41................................ | | Should you have any questions concerning this letter, please contact Mr. Richard Gropp at (610) 765-5557. |
| ............. | | I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of December 2009. |
| -.............
| | Respectfully, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments: 1 - Revised Mark-ups of Technical Specifications Pages 2 - Revised Re-typed Technical Specifications Pages cc: S. J. Collins, Administrator, Region I, USNRC F. L. Bower, USNRC Senior Resident Inspector, PBAPS J. Hughey, Project Manager, USNRC R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland |
| Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR)Shutdown Cooling System-Hot Shutdown," LCO 3.5.1,"ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LC=G0..1 "Containmolnt Atmolspher-ie Dilution (CAD)Syste.....
| | |
| LCO 3.6.4.3, "Standby Gas Treatment (SGT)System," LCO 3.7.1, "High Pressure Service Water (HPSW)System," LCO 3.7.2, "Emergency Service Water (ESW)System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating." APPLICABILITY: | | A'TACHMENT 1 Revised Mark-ups of Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES Unit2 Unit3 . . . . .. |
| MODES 1, 2, and 3.PBAPS UNIT 2 3.8-41 Amendment No. 2-1-GXXX Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1,"ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LCO ,Cntinmnt Atm.o.. pher.i. Dilution (CAD) / | | . 3 8 -41.....................................................3 .8 -41......................... |
| 3.6.4.3, "Standby Gas Treatment (SGT)System," LCO 3.7.1, "High Pressure Service Water (HPSW)System," LCO 3.7.2, "Emergency Service Water (ESW)System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4, "Main Control Room Emergency Ventilation (MCREV) System," and LCO 3.8.1, "AC Sources-Operating." APPLICABILITY:
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| MODES 1, 2, and 3.PBAPS UNIT 3 3.8-41 Amendment No. 244XXX ATTACHMENT 2 Revised Re-typed Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES..............................- | | Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: |
| -............
| | : a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and |
| un .. 2. .... -..................
| | : b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR) |
| ................... | | Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," |
| ................ | | LC=G0..1 "Containmolnt Atmolspher-ie Dilution (CAD) |
| .... .............................. | | Syste..... LCO 3.6.4.3, "Standby Gas Treatment (SGT) |
| ........ ......... ..............
| | System," LCO 3.7.1, "High Pressure Service Water (HPSW) |
| .................
| | System," LCO 3.7.2, "Emergency Service Water (ESW) |
| ..... .... ..... ..... ................. | | System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating." |
| ............ | | APPLICABILITY: MODES 1, 2, and 3. |
| ...... ........ .................................... | | PBAPS UNIT 2 3.8-41 Amendment No. 2-1-GXXX |
| U ni iiii~ i ii i i t ii 2 U n it 3i ii iiiiiii iii ii iiii ii ii ii iiii ii iiiii ii i ii ii ii ii iii .....................................
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| iiiiiiii ~ ~ ii iiii~ ii Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2,"Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating." APPLICABILITY:
| | Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: |
| MODES 1, 2, and 3.PBAPS UNIT 2 3.8-41 Amendment No.
| | : a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and |
| Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1,"ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2, "Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4,"Main Control Room Emergency Ventilation (MCREV) System, and LCO 3.8.1, "AC Sources-Operating." APPLICABILITY:
| | : b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," |
| MODES 1, 2, and 3.PBAPS UNIT 3 3.8-41 Amendment No.}}
| | LCO 36*31 / |
| | pher.i. Dilution (CAD) |
| | ,Cntinmnt Atm.o.. |
| | Sys..*e....LCO 3.6.4.3, "Standby Gas Treatment (SGT) |
| | System," LCO 3.7.1, "High Pressure Service Water (HPSW) |
| | System," LCO 3.7.2, "Emergency Service Water (ESW) |
| | System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4, "Main Control Room Emergency Ventilation (MCREV) System," and LCO 3.8.1, "AC Sources-Operating." |
| | APPLICABILITY: MODES 1, 2, and 3. |
| | PBAPS UNIT 3 3.8-41 Amendment No. 244XXX |
| | |
| | ATTACHMENT 2 Revised Re-typed Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES U |
| | iiiiiii~ |
| | un nit.. |
| | 2 i-............ |
| | iii iiiiiiiii iiiiiiiii |
| | ..............................-ii iiiiiiii.... |
| | : 2. iii.............................. |
| | ................... i i iiiiiiiiiiiiii |
| | ..... iiiiiiii U~n........ |
| | .................it 3i |
| | ...... ~iiiiii~ ii |
| | |
| | Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: |
| | : a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and |
| | : b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2, "Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating." |
| | APPLICABILITY: MODES 1, 2, and 3. |
| | PBAPS UNIT 2 3.8-41 Amendment No. |
| | |
| | Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE: |
| | : a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and |
| | : b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," |
| | LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2, "Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4, "Main Control Room Emergency Ventilation (MCREV) System, and LCO 3.8.1, "AC Sources-Operating." |
| | APPLICABILITY: MODES 1, 2, and 3. |
| | PBAPS UNIT 3 3.8-41 Amendment No.}} |
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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:Report
MONTHYEARML23346A2392024-01-17017 January 2024 Seismic Hazard Report by the Office of Nuclear Reactor Regulation ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022 (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20329A3452020-11-24024 November 2020 Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses ML20314A0282020-11-0606 November 2020 Verbal Relief for Penetration Nozzle ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML19053A4692019-06-10010 June 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML19007A3302019-01-0707 January 2019 Final Report PBAPS Thermal Study ML18354B0662018-12-20020 December 2018 Summary of Monitoring Well Installation Details RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...2018-09-28028 September 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2018-08-28028 August 2018 Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ML18093A3822018-03-30030 March 2018 Decommissioning Status Report - 2017 RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML17093A6972017-03-30030 March 2017 Decommissioning Status Report - 2016 ML19064B2232017-02-24024 February 2017 Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station ML17027A0152017-01-27027 January 2017 ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16 ML16342B6212016-12-0707 December 2016 Results of Visual Inspections of Replacement Steam Dryer RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16048A4412016-02-17017 February 2016 Transmittal of Extended Power Uprate: Results of Replacement Steam Dryer Power Ascension Testing ML19064B2162015-12-31031 December 2015 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015 ML15275A1682015-10-0202 October 2015 Attachment 2, LTR-BWR-ENG-15-076-NP, Revision 1, Replacement Steam Dryer Report at Predicted EPU Conditions (Non-Proprietary) and Attachment 3, Affidavit ML15233A0952015-08-20020 August 2015 Revision 0 to LTR-BWR-ENG-15-076-NP, Replacement Steam Dryer Report at Predicted EPU Conditions ML15219A6182015-08-0707 August 2015 Extended Power Uprate: Results of Unit 2 Replacement Steam Dryer Power Ascension Testing ML15051A2622015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Related to Recommendation 2.1 ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information ML15026A4692015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents) ML15029A6402015-01-29029 January 2015 Mellla+ License Amendment Request Supplement 1 Supplemental Reload Licensing Report ML15028A3812015-01-28028 January 2015 Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14 ML19064B2142014-12-31031 December 2014 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2014 RS-14-300, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1..2014-12-19019 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1.. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14119A0572014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262) ML14086A6242014-04-30030 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158) ML14105A3862014-04-11011 April 2014 Attachment 9: WCAP-17649-NP, Rev. 2, ASME Code Stress Report (Enclosure B.3) ML14105A3852014-04-11011 April 2014 Attachment 8: WCAP-17635-NP, Rev. 3, Comprehensive Vibration Assessment Program ML14105A3882014-04-11011 April 2014 Attachment 11: WCAP-17655-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate ML14105A3872014-04-11011 April 2014 Attachment 10: WCAP-17654-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate ML14072A0262014-03-31031 March 2014 WCAP-17655-NP, Rev 3,Peach Bottom Unit 3 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate. ML14072A0232014-03-31031 March 2014 WCAP-17635-NP, Rev 2, Peach Bottom Atomic Power Station Unit 2 and Unit 3 Replacement Steam Dryer Comprehensive Vibration Assessment Program. ML14072A0242014-03-31031 March 2014 WCAP-17609-NP, Rev 2, Peach Bottom Units 2 and 3 Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads. ML14072A0252014-03-31031 March 2014 WCAP-17654-NP, Rev 3, Peach Bottom Unit 2 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate. ML19007A3282014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration ML14070A1462014-02-28028 February 2014 WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer. ML14070A1452014-02-28028 February 2014 WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature. ML14070A1442014-02-28028 February 2014 WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report. ML14070A1432014-02-28028 February 2014 WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition. 2024-01-17
[Table view] Category:Miscellaneous
MONTHYEARML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022 (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18093A3822018-03-30030 March 2018 Decommissioning Status Report - 2017 ML17093A6972017-03-30030 March 2017 Decommissioning Status Report - 2016 ML19064B2232017-02-24024 February 2017 Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station ML17027A0152017-01-27027 January 2017 ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16 ML16342B6212016-12-0707 December 2016 Results of Visual Inspections of Replacement Steam Dryer RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML19064B2162015-12-31031 December 2015 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015 ML15051A2622015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Related to Recommendation 2.1 ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information ML15026A4692015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents) ML15028A3812015-01-28028 January 2015 Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14 ML14119A0572014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262) ML14086A6242014-04-30030 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158) ML19064B2202014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration: Peach Bottom Atomic Power Station Part 1 of 2 ML14070A1462014-02-28028 February 2014 WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer. ML14070A1452014-02-28028 February 2014 WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature. ML14070A1442014-02-28028 February 2014 WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report. ML14070A1432014-02-28028 February 2014 WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition. ML19064B2332013-12-0606 December 2013 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2013 RS-13-085, Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency...2013-04-30030 April 2013 Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency... ML13109A0522013-04-18018 April 2013 Revised Gnf Response to NRC RAI 44 for License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts, Attachment 3, Enclosures 2, 3 and 4 ML19064B2372013-02-25025 February 2013 Entrainment Characterization Study 2012 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee NEI 99-04, Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 122013-01-28028 January 2013 Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 12/ ML19064B2302012-12-0707 December 2012 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2012 ML13003A0272012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-76 ML13003A0262012-11-16016 November 2012 Report No. MPR-3812, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-372 Through End ML13003A0252012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104 ML13003A0282012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-77 Through Page C-156 ML13003A0292012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-157 Through Page C-249 ML13003A0302012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-250 Through Page C-333 ML13003A0312012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-334 Through Page C-399 ML13003A0322012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-400 Through End ML13003A0332012-11-16016 November 2012 Report No. MPR-3812, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104 ML13003A0342012-11-16016 November 2012 Report No. MPR-3812, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-67 2023-11-30
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Text
Exelon Nuclear www.exeloncorp.com Exel n 200 Exelon Way Nucea-Kennett Square, PA 19348 10CFR50.90 December 29, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278
Subject:
License Amendment Request for Adoption of TSTF-478-A, Revision 2 Supplemental Response to Revise Technical Specifications Page Mark-ups
References:
- 1) Letter from Pamela B. Cowan, Exelon Generation Company, LLC, to U.S.
Nuclear Regulatory Commission - License Amendment Request for Adoption of TSTF-478-A, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," Using the Consolidated Line Item Improvement Process, dated July 30, 2009
- 2) Federal Register Notice 72FR65610 - Notice of Availability on Model Safety Evaluation; Model No Significant Hazards Determination, and Model Application for Licensees that Wish to Adopt TSTF-478, Revision 2, "BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control," dated November 21, 2007 By letter dated July 30, 2009 (Reference 1), Exelon Generation Company, LLC (Exelon) submitted a License Amendment Request (LAR) to revise the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed changes would revise the TS for PBAPS, Units 2 and 3, consistent with NRC-approved Industry TS Task Force (TSTF) Change Traveler TSTF-478-A, Revision 2, "BWR TechnicalSpecification Changes that Implement the Revised Rule for Combustible Gas Control"(Reference 2). The proposed changes would delete the TS requirements associated with the "Containment Atmospheric Dilution (CAD) System."
Subsequently, it was identified that the mark-ups on TS page 3.8-41 for Units 2 and 3 contained an editorial discrepancy. Specifically, there was a strikeout line through the reference to "LCO 3.6.3.1" indicating that the section should be deleted. However, the strikeout line was not completely carried through to include the remaining portion of the reference, i.e., "Containment Atmospheric Dilution (CAD) System."
Accordingly, this letter is being submitted to correct this editorial discrepancy. Attachment 1 contains the revised mark-up for the affected TS page for Units 2 and 3 and Attachment 2 includes the revised re-typed page for the affected Units 2 and 3 TS page.
14 f.--
U.S. Nuclear Regulatory Commission License Amendment Request Supplemental Response Deletion of CAD System from TS Docket Nos. DPR-44 and DPR-56 December 29, 2009 Page 2 Exelon has concluded that the information provided in this supplemental response does not impact the conclusions of the: 1) Technical Evaluation, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal (Reference 1).
There are no new commitments contained in this submittal.
Should you have any questions concerning this letter, please contact Mr. Richard Gropp at (610) 765-5557.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of December 2009.
Respectfully, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments: 1 - Revised Mark-ups of Technical Specifications Pages 2 - Revised Re-typed Technical Specifications Pages cc: S. J. Collins, Administrator, Region I, USNRC F. L. Bower, USNRC Senior Resident Inspector, PBAPS J. Hughey, Project Manager, USNRC R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland
A'TACHMENT 1 Revised Mark-ups of Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES Unit2 Unit3 . . . . ..
. 3 8 -41.....................................................3 .8 -41.........................
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and
- b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR)
Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray,"
LC=G0..1 "Containmolnt Atmolspher-ie Dilution (CAD)
Syste..... LCO 3.6.4.3, "Standby Gas Treatment (SGT)
System," LCO 3.7.1, "High Pressure Service Water (HPSW)
System," LCO 3.7.2, "Emergency Service Water (ESW)
System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating."
APPLICABILITY: MODES 1, 2, and 3.
PBAPS UNIT 2 3.8-41 Amendment No. 2-1-GXXX
Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and
- b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray,"
LCO 36*31 /
pher.i. Dilution (CAD)
,Cntinmnt Atm.o..
Sys..*e....LCO 3.6.4.3, "Standby Gas Treatment (SGT)
System," LCO 3.7.1, "High Pressure Service Water (HPSW)
System," LCO 3.7.2, "Emergency Service Water (ESW)
System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4, "Main Control Room Emergency Ventilation (MCREV) System," and LCO 3.8.1, "AC Sources-Operating."
APPLICABILITY: MODES 1, 2, and 3.
PBAPS UNIT 3 3.8-41 Amendment No. 244XXX
ATTACHMENT 2 Revised Re-typed Technical Specifications Pages PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 TECHNICAL SPECIFICATIONS PAGES U
iiiiiii~
un nit..
2 i-............
iii iiiiiiiii iiiiiiiii
..............................-ii iiiiiiii....
- 2. iii..............................
................... i i iiiiiiiiiiiiii
..... iiiiiiii U~n........
.................it 3i
...... ~iiiiii~ ii
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and
- b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray," LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2, "Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating."
APPLICABILITY: MODES 1, 2, and 3.
PBAPS UNIT 2 3.8-41 Amendment No.
Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. Unit 3 Division I and Division II AC and DC electrical power distribution subsystems; and
- b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR Shutdown Cooling System-Hot Shutdown," LCO 3.5.1, "ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray,"
LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.7.1, "High Pressure Service Water (HPSW) System," LCO 3.7.2, "Emergency Service Water (ESW) System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," LCO 3.7.4, "Main Control Room Emergency Ventilation (MCREV) System, and LCO 3.8.1, "AC Sources-Operating."
APPLICABILITY: MODES 1, 2, and 3.
PBAPS UNIT 3 3.8-41 Amendment No.