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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:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) ML18249A2402018-09-28028 September 2018 Issuance of Amendment Nos. 320 and 323 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML18257A0172018-09-14014 September 2018 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite Update to ... ML18173A0422018-06-23023 June 2018 Issuance of Amendment Nos. 318 & 321 to Revise Technical Specifications 3.8.1 and 3.8.3, One-Time Change Suspending EDG Surveillance Test Completion Requirements (Emergency Situation) RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML16217A0082016-08-11011 August 2016 Correction to Amendment Nos. 308 and 312 Regarding Surveillance Requirements for High Pressure Coolant Injection System and Reactor Core Isolation Cooling System ML16162A1012016-06-0909 June 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements ML16084A9682016-05-0909 May 2016 Issuance of Amendments Inservice Leak and Hydrostatic Testing Operation ML16034A3722016-03-21021 March 2016 Issuance of Amendments Maximum Extended Load Line Limit Analysis Plus ML15343A1772016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15350A1792016-02-0101 February 2016 Issuance of Amendments Secondary Containment Access Openings ML15275A2652015-10-0202 October 2015 License Amendment Request, Proposed Changes to the Technical Specifications for High Pressure Coolant Injection and Reactor Core Isolation Cooling Surveillance Test Pressure and Clarification of Surveillance Requirements ML15196A5592015-09-0808 September 2015 Issuance of Amendments Extension of Type a and Type C Leak Rate Test Frequencies ML15189A1852015-08-11011 August 2015 Issuance of Amendment No. 305 Change to Replacement Steam Dryer License Condition ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15167A4562015-07-28028 July 2015 Issuance of Amendments Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function ML15162A1392015-07-17017 July 2015 Issuance of Amendments Revise Technical Specification Definition for Recently Irradiated Fuel ML15154A6142015-06-30030 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15093A0532015-03-27027 March 2015 (PBAPS) Unit 1 Decommissioning Status Report - 2014 ML14363A2272015-03-11011 March 2015 Issuance of Amendments Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes ML15055A5062015-02-23023 February 2015 License Amendment Request - Proposed Changes to the Technical Specifications to Address Administrative Control of Secondary Containment Access Openings ML15041A6302015-02-19019 February 2015 Correction to Amendments Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs ML14247A5242014-09-0303 September 2014 License Amendment Request Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function ML14163A5892014-07-28028 July 2014 Issuance of Amendments Delete Non-Conservative Note from Limiting Condition for Operation 3.5.1 ML14192B1432014-07-11011 July 2014 License Amendment Request to Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes ML14136A4852014-06-0505 June 2014 Issuance of Amendments Revise Normal Heat Sink Operability Requirements ML14160A6992014-06-0505 June 2014 Extended Power Uprate License Amendment Request - Supplement 27 Supplemental Information ML14079A1022014-05-0505 May 2014 Issuance of Amendments Safety Relief Valve and Safety Valve Lift Setpoint Tolerance ML14099A5372014-04-0808 April 2014 Response to Request for Additional Information - Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML14092A3152014-03-28028 March 2014 Decommissioning Status Report for 2013 ML13109A4632013-06-18018 June 2013 Issuance of Amendments Revise Technical Specifications to Add Residual Heat Removal System Drywell Spray Function Requirements ML13018A2252013-01-17017 January 2013 Response to Request for Additional Information - Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML12286A0122012-09-28028 September 2012 License Amendment Request - Extended Power Uprate ML12243A2862012-08-29029 August 2012 License Amendment Request to Add LCO 3.0.8 on the Lnoperability of Snubbers Using the Consolidated Line Item Improvement Process ML12200A3882012-07-18018 July 2012 Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML1130814412011-11-0303 November 2011 License Amendment Request - Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks ML1116001802011-06-0808 June 2011 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change ML1109700672011-04-0606 April 2011 License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 2023-08-30
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Exelon Nuclear www.exeloncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 10 CFR 50.90 August 21, 2008 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:
Supplemental Response for License Amendment Request for Alternative Source Term
References:
- 1. Letter from Pamela B. Cowan, Exelon Generation Company, LLC,to U. S. Nuclear Regulatory Commission, "License Amendment Request - Application of Alternative Source Term," dated July 13, 2007
- 2. U. S. Nuclear Regulatory Commission e-mail dated July 18, 2008, draft Request for Additional Information (RAI), Peach Bottom Atomic Power Station, Units 2 and 3, License Amendment Request (LAR), Alternative Source Term Application (five questions)
- 3. U. S. Nuclear Regulatory Commission updated e-mail dated July 25,2008, draft Request for Additional Information (RAI), Peach Bottom Atomic Power Station, Units 2 and 3, License Amendment Request (LAR), Alternative Source Term Application (one question)
- 4. Letter from Pamela B. Cowan, Exelon Generation Company, LLC, to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Concerning License Amendment Request - Application of Alternative Source Term,'* dated July 29, 2008
- 5. Letter from Pamela B. Cowan, Exelon Generation Company, LLC, to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Concerning License Amendment Request - Application of Alternative Source Term," dated August 7,2008
- 6. Teleconference between U. S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, dated August 12, 2008, draft Request for Additional Information (RAI),
Peach Bottom Atomic Power Station, Units 2 and 3, License Amendment Request (LAR), Alternative Source Term Application (two issues)
U.S. Nuclear Regulatory Commission License Amendment Request Alternative Source Term Docket Nos. DPR-44 and DPR-56 August 21, 2008 Page 2 In Reference 1, Exelon Generation Company, LLC (Exelon) submitted an application requesting a change to the Technical Specifications (TS), Appendix A, of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively. The proposed change was requested to support the application of Alternative Source Term (AST) methodology at PBAPS, Units 2 and 3.
In References 2 and 3, the U. S. Nuclear Regulatory Commission (NRC) issued draft requests for additional information (RAls) concerning the PBAPS License Amendment Request (LAR).
The NRC identified six questions in the draft RAls in which additional information was requested concerning meteorological and dose consequence aspects related to AST. In References 4 and 5, Exelon responded to the six RAI questions.
In the Reference 6 teleconference, the NRC requested further clarification with regard to: 1) the atmospheric dispersion factors (X/Qs) for the fuel handling accident (FHA) listed in Table 6 of the Reference 5 response, and 2) the basis for establishing an 84-hour decay period in the definition for RECENTLY IRRADIATED FUEL. To address these issues, Exelon has revised Table 6 to show the specific X/Q values used in the FHA analysis. The X/Q values depicted in Table 6 represent the most bounding condition for each of the release points identified. In addition, the definition of RECENTLY IRRADIATED FUEL has been revised to remove the reference to the 84-hour decay period. Therefore, Exelon is hereby replacing the proposed definition for RECENTLY IRRADIATED FUEL as described in Reference 1 with the following proposed definition.
Previous Proposed Definition (Reference 1)
RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has FUEL occupied part of a critical reactor core within the previous 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. This 84-hour time period may be reduced to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if all outside secondary containment ground-level hatches (hatches H15 through H24 and Units 2 and 3 Torus room access hatches) are closed.
New Proposed Definition for Unit 2 and Unit 3 Unit 2 RECENTLY IRRADIATED FUEL is fuel that has occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When using this definition to suspend the Applicability of LCOs, secondary containment ground-level hatches H15, H16, H17, H18, H19, and H33 shall be closed during the movement of any irradiated fuel in Secondary Containment.
U.S. Nuclear Regulatory Commission License Amendment Request Alternative Source Term Docket Nos. DPR-44 and DPR-56 August 21,2008 Page 3 RECENTLY IRRADIATED FUEL is fuel that has occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When using this definition to suspend the Applicability of LCOs, secondary containment ground-level hatches H20, H21, H22, H23, H24, and H34 shall be closed during the movement of any irradiated fuel in Secondary Containment.
Attachment 1 of this letter contains. the Table 6 pages, which supercede the Table 6 contained in the Reference 5 response. Attachment 2 provides the revised Technical Specifications pages 1.1-5 for PBAPS, Units 2 and 3, which include the new proposed definition for RECENTLY IRRADIATED FUEL.
Exelon has concluded that the information provided in this response does not impact the conclusions of the: 1) Technical Analysis, 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 regulatory commitments contained in this letter. If you have any further questions or require additional information, please contact Richard Gropp at 610-765-5557.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21 st day of August 2008.
Respectfully, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC : Supplemental Response to Request for Additional Information (Revised Table 6 from the Reference 5 Supplement) : Revised Technical Specifications Page Mark-ups (Pages 1.1-5 for Units 2 and 3) cc: Regional Administrator - NRC Region I wI Attachments NRC Senior Resident Inspector - PBAPS "
NRC Project Manager, NRR - PBAPS "
Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Protection "
S. T. Gray, State of Maryland "
ATTACHMENT 1 Peach Bottom Atomic Power Station Units 2 and 3 Docket Nos. 50-277 and 50-278 License Amendment Request Supplemental Response Alternative Source Term (AST)
Table 6 (revised) from August 7, 2008 Supplemental Response
Attachment 1 Page 1 of 2 Table 6 3
XlQ (seclm ) Results Summary (from PM-lOSS Rev. 1 Table S-l and PM-10S9 Rev. 3 Table 4-1),
Meteorological Database Utilized, and Dose Calculation Application Bases Controlling Receptor I Release Point I 0-0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I 0-2 hour I 2-8 hour 18-24 houri 1-4 day I 4-30 day I Meteorological Tower Database Justification for Usage I Used in Dose Calculation Utilized Tower 2 is the only representative database Off-Gas Stack 3.31E-06 I 1.00E-15 11.00E-1511.64E-Oal 4.54E-09 I Tower 2 I (See Calculation I PM-I077, Rev. 1 PM-lOSS, Rev 1, Sections 2.2.3 and 2.2.4)
The higher of the XlQs predicted by Tower 2 (0-2 hour) representative Towers PM-I077, Rev.l, Unit 2 Reactor Building Stack 2 and 1A databases PM-lOS?, Rev. 2, Control Room Intake I 1.18E-0319.08E-0414.14E-0412.90E-0412.26&041 Tower IA (all other penods) were sel~ted (See Calculatlon PM-1055, Rev 1, Sections l PM-1059 Rev 3 2.2.3 and 2.2.4)
The higher of the Unit 3 Reactor Building Stack 1.1SE-03 !S.91E-04!4.00E-04!2.51E-04\1.9SE-04 1 Tower 2 XlQs predicted by represeotative Towers 12 and 1A databases I PM-1077, Rev. I, PM-lOS?, Rev. 2, (Unit 2 is limiting) were sel~ted (See PM-1059 Rev 3 CalculatlOn PM- '
1055, Rev 1, Sections 2.2.3 and 2.2.4)
Ground-Level Hatches 1.2SE-02 Tower lA is the most representative and Reactor Building Personnel conservative database 1.04E-03 These are the maximum values for each.
Access Doors (See Calculation PM-I PM-1059, Rev 3 0-2 hour values conservatively utilized for the Tower 1A 1059, Rev 3, Roof Scuttles 1.90E-03 Fuel Handling Accident Attachment G, Section 3.1 and Table Railway Bay Doors 4.54E-04 I 1 14 -1)
Page 2 of 2 Table 6 (continued)
Controlling I 0-0.5 I
8-24 Meteorological Justification for I Used in Dose Receptor Release Point I 28 hour3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> I 0-2 hour 1 - hour hour Tower Database Usage Calculation Utilized Tower 2 is the only representative OfT-Gas Stack I 5.30E-05 I 9.17E-06 I 3.24E-06* I 1.92E-06 I 6.22E-07 I I.23E-07 I Tower 2 ,database. , PM-lOn, Rev. 1 (See CalculatIon PM-1055, Rev 1, Sections 3.2.3,3.2.4, and 4.1)
EAB I Units 2 and 3 Reactor Building The highest of the XJQs predicted by the (823 m)
Stacks, Turbine Building, and Personnel Access Doors, Railway Bay Doors, and Roof
- 9. llE-04 4.67E-04* 3.35E-04 l.64E-04 6.26E-05 Tower IA representative Towers 2, IA, and River Tower/lA databases I PM-1077, Rev. I, PM-1057, Rev. 2, were selected (See PM-1059, Rev 3 Scuttle, and Ground-Level Calculation PM-Hatches. 1055, Rev 1, Sections 3.2.4 and 4.1)
Tower 2 is the only Irepresentative OfT-Gas Stack I 1.75E-05 I 9.05E-06 14.0IE-06* 12.67E-0611.1OE-061 3.lOE-07 I Tower 2 ~tab~s~
ee a culatIon
' PM' - PM-IOn, Rev. 1 1055, Rev 1, Sections 3.2.3,3.2.4, and 4.1)
LPZ The higher of the (7,300 m) Units 2 and 3 Reactor Building XJQs predicted by the Stacks, Turbine Building, and Personnel Access Doors, representative Towers 2 and IA databases I PM-Ion, Rev. I, PM-105?, Rev. 2, I.38E-04 5.8IE-05* 3.77E-05 IA8E-05 4.15E-06 Tower lA Railway Bay Doors, and Roof were sel~cted (See PM-1059, Rev 3 Scuttle, and Ground-Level CalculatIon PM-Hatches. 1055, Rev 1, Sections 3.2.4 and 4.1)
ATTACHMENT 2 Peach Bottom Atomic Power Station Units 2 and 3 Docket Nos. 50-277 and 50-278 License Amendment Request Supplemental Response Alternative Source Term (AST)
Revised Technical Specifications Page Mark-ups Unit 2 Unit 3 1.1-5 1.1-5
Definitions 1.1 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Commission.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 MWt.
REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.
RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has occupied FUEL part of a critical reactor core within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When using this definition to suspend the Applicability of LCOs, secondary containment ground-level hatches H15, H16, H17, H18, H19, and H33 shall be closed during the movement of any irradiated fuel in Secondary Containment.
SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:
- a. The reactor is xenon free;
- b. The moderator temperature is 68°F; and
- c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
PBAPS UNIT 2 1.1-5 Amendment No. -rl4+XXX
Definitions 1.1 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Cormnission.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 MWt.
REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.
RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has occupied FUEL part of a critical reactor core within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When using this definition to suspend the Applicability of LCOs, secondary containment ground-level hatches H20, H21, H22, H23, H24, and H34 shall be closed during the movement of any irradiated fuel in Secondary Containment.
SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:
- a. The reactor is xenon free;
- b. The moderator temperature is 68°F; and
- c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
PBAPS UNIT 3 1.1-5 Amendment No. ~XXX