|
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:April 19, 2017 | | {{#Wiki_filter:April 19, 2017 MEMORANDUM TO: Biweekly Notice Coordinator FROM: Blake Purnell, Project Manager /RA/ |
| | | Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Biweekly Notice Coordinator | |
| | |
| FROM: Blake Purnell, Project Manager | |
| /RA/ Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE- NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (CAC NOS. MF9470-MF9490) | | REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE- NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (CAC NOS. MF9470-MF9490) |
| | Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station, Units 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-352 and No. 50-353, Limerick Generating Station, Units 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York |
|
| |
|
| Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station, Units 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-352 and No. 50-353, Limerick Generating Station, Units 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York Biweekly Notice Coordinator Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit 1, Dauphin County, Pennsylvania Date of amendment request: March 28, 2017. Publicly-available version is in ADAMS under Accession No. ML17087A028. Description of amendment request: The amendments would revise the technical specifications (TSs) based on Technical Specification Task Force (TSTF) Traveler TSTF-529, "Clarify Use and Application Rules" (ADAMS Accession No. ML16062A271). The changes would revise and clarify the TS usage rules for completion times, limiting conditions for operation (LCOs), and surveillance requirements (SRs). Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
| | Biweekly Notice Coordinator Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit 1, Dauphin County, Pennsylvania Date of amendment request: March 28, 2017. Publicly-available version is in ADAMS under Accession No. ML17087A028. |
| | Description of amendment request: The amendments would revise the technical specifications (TSs) based on Technical Specification Task Force (TSTF) Traveler TSTF-529, Clarify Use and Application Rules (ADAMS Accession No. ML16062A271). The changes would revise and clarify the TS usage rules for completion times, limiting conditions for operation (LCOs), and surveillance requirements (SRs). |
| | Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: |
| | : 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? |
| Response: No. | | Response: No. |
| The proposed changes to [TS] Section 1.3 and LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 3.0.3 (or equivalent) states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed. | | The proposed changes to [TS] Section 1.3 and LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 3.0.3 (or equivalent) states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed. |
| Since the proposed changes do not significantly affect system Operability, the proposed changes will have no significant effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously | | Since the proposed changes do not significantly affect system Operability, the proposed changes will have no significant effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously evaluated. |
| | |
| evaluated. | |
| Biweekly Notice Coordinator Therefore, it is concluded that these changes do not involve a significant increase in the probability or consequences of an accident previously
| |
|
| |
|
| evaluated. | | Biweekly Notice Coordinator Therefore, it is concluded that these changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| : 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? | | : 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? |
| Response: No. | | Response: No. |
| The proposed changes to the TS usage rules do not affect the design or function of any plant systems. The proposed changes do not change the | | The proposed changes to the TS usage rules do not affect the design or function of any plant systems. The proposed changes do not change the Operability requirements for plant systems or the actions taken when plant systems are not operable. |
| | | Therefore, it is concluded that the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| Operability requirements for plant systems or the actions taken when plant systems are not operable. | | : 3. Does the proposed amendment involve a significant reduction in a margin of safety? |
| Therefore, it is concluded that the changes do not create the possibility of a new or different kind of accident from any accident previously | |
| | |
| evaluated. | |
| : 3. Does the proposed amendment involve a significant reduction in a margin of safety? | |
| Response: No. | | Response: No. |
| The proposed changes clarify the application of [TS] Section 1.3 and LCO 3.0.4 and do not result in changes in plant operation. SR 3.0.3 (or equivalent) is revised to allow application of SR 3.0.3 when an SR has not been previously performed if there is reasonable expectation that the SR | | The proposed changes clarify the application of [TS] Section 1.3 and LCO 3.0.4 and do not result in changes in plant operation. SR 3.0.3 (or equivalent) is revised to allow application of SR 3.0.3 when an SR has not been previously performed if there is reasonable expectation that the SR will be met when performed. This expands the use of SR 3.0.3 while ensuring the affected system is capable of performing its safety function. |
| | |
| will be met when performed. This expands the use of SR 3.0.3 while ensuring the affected system is capable of performing its safety function. | |
| As a result, plant safety is either improved or unaffected. | | As a result, plant safety is either improved or unaffected. |
| Therefore, it is concluded that the changes do not involve a significant reduction in a margin of safety. | | Therefore, it is concluded that the changes do not involve a significant reduction in a margin of safety. |
| The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration. | | The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration. |
| Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555. | | Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555. |
| NRC Branch Chief: David J. Wrona | | NRC Branch Chief: David J. Wrona |
|
| |
|
| ML17108A384 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC DORL/LPL3/PM NAME BPurnell SRohrer DWrona BPurnell DATE 4/18/2017 4/18/2017 4/19/2017 4/19/2017}} | | ML17108A384 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC DORL/LPL3/PM NAME BPurnell SRohrer DWrona BPurnell DATE 4/18/2017 4/18/2017 4/19/2017 4/19/2017}} |
Letter Sequence Other |
---|
CAC:MF9470, (Approved, Closed) CAC:MF9471, (Approved, Closed) CAC:MF9472, (Approved, Closed) CAC:MF9473, (Approved, Closed) CAC:MF9474, (Approved, Closed) CAC:MF9475, (Approved, Closed) CAC:MF9476, (Approved, Closed) CAC:MF9477, (Approved, Closed) CAC:MF9478, (Approved, Closed) CAC:MF9479, (Approved, Closed) CAC:MF9480, (Approved, Closed) CAC:MF9481, (Approved, Closed) CAC:MF9482, (Approved, Closed) CAC:MF9483, (Approved, Closed) CAC:MF9484, (Approved, Closed) CAC:MF9485, (Approved, Closed) CAC:MF9486, (Approved, Closed) CAC:MF9487, (Approved, Closed) CAC:MF9488, (Approved, Closed) CAC:MF9489, (Approved, Closed) CAC:MF9490, (Approved, Closed) |
|
MONTHYEARML0726804681954-12-31031 December 1954 New Jersey Department of Environmental Protection, Division of Parks and Forestry, State Forest Service, New Jersey'S Big Trees Project stage: Other ML0726705561963-01-31031 January 1963 Us Fish and Wildlife Service, 1963. Distribution of Shellfish Resources in Relation to the New Jersey Intracoastal Waterway -- Manasquan Inlet to Little Egg Harbor. Boston, Ma. January Project stage: Other ML20260G1161965-06-17017 June 1965 Fuel Storage Building Sections & Details. Sheet 1 Project stage: Other ML20260G1231965-08-20020 August 1965 Fuel Storage Building Section & Details. Sheet 7.Field Change Request & Drawing Change Notices Encl Project stage: Other ML20260G1201967-01-31031 January 1967 Fuel Storage Building Sections & Details. Sheet 4 Project stage: Other ML0725407921968-06-0404 June 1968 Drawing 11D-190, 6 Inch Roof Vent. Project stage: Other ML20264B5281971-04-0101 April 1971 Reactor Protection System. Sheet 5 of 13 Project stage: Other ML20206K6391972-05-31031 May 1972 Ack Receipt of Re Technical Basis for Accepting Weld Surface Area W/Bluish Tint.No Further Questions Project stage: Other ML20263J0731972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly a, as-built Project stage: Other ML20263J0711972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly D (48 of 50), as-built Project stage: Other ML20263J0781972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly C Project stage: Other ML20263J0751972-07-18018 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly B (46 of 50), as-built Project stage: Other ML19326C1141972-07-19019 July 1972 SLR Tech Specs from Authority File Project stage: Acceptance Review ML0726405941972-11-17017 November 1972 Jersey Central Power & Light Company, Oyster Creek Nuclear Generating Station Environmental Report, Amendment 2 Project stage: Other ML20263N4591973-01-14014 January 1973 Auxiliary Building Unit 1 Spent Fuel Pool Sections Reinforcing. Sheet 4 Project stage: Other ML20262H5551973-12-14014 December 1973 Watertight Door Assy. Sheet 1 of 3 Project stage: Other ML20262H5581973-12-14014 December 1973 Details:1,2,17 & 21 Thru 27,32,33 & 34. Sheet 2 of 3 Project stage: Other ML20262H5611973-12-14014 December 1973 Details:3,13,19,24,28,35 & 36. Sheet 3 of 3 Project stage: Other ML20263T0291974-04-0909 April 1974 Shore Line Contours. Sheet 3 of 4 Project stage: Other ML20263N4901974-07-15015 July 1974 Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Concrete. Sheet 1 Project stage: Other ML20235X2491974-07-16016 July 1974 Forwards Revised Operator Requalification Program for Plant, Per Recipient 740618 Request Project stage: Other ML20263N4981974-10-10010 October 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Concrete. Sheet 2 Project stage: Other ML20263N4751974-10-11011 October 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 2 Project stage: Other ML0725408181974-10-22022 October 1974 Drawing M-79, Rev. 3, Main Steam Relief Valve Discharge Stack Modification. Project stage: Other ML20263N4621974-11-0505 November 1974 Auxiliary Building Unit 1 Spent Fuel Pool - Sections Reinforcing. Sheet 2 Project stage: Other ML20263N4741974-11-0505 November 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 3 Project stage: Other ML20263N4671974-11-0505 November 1974 Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Reinforcing. Sheet 1 Project stage: Other ML20235X2331974-12-10010 December 1974 Discusses 741206 Meeting W/Util to Review Responsibilities & Outline Scope of Exam for Fuel Handling & Senior Operators at Facility.Addl Info to Develop Written & Operating Test Needed Project stage: Meeting ML20263N4561974-12-13013 December 1974 Auxiliary Building Spent Fuel Pool - Unit 1 Plan and Sections Reinforcing. Sheet 4 Project stage: Other ML20263N4711974-12-13013 December 1974 Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 4 Project stage: Other ML20264B5261975-04-24024 April 1975 Single Line Diagram:125 Volt D-C System Project stage: Other ML0606805861975-05-23023 May 1975 May 23, 1975 - Final Summary Report Startup, Enclosure 4 Project stage: Other ML0607202531975-05-23023 May 1975 May 23, 1975 - Final Summary Report Unit 2 Startup Project stage: Other ML20140F9811975-06-16016 June 1975 Forwards Request for Info Re Ebasco Containment Structures Design Rept,Per 750530 Request.Info for Assessing Design Adequacy of Piping & Mechanical Components Affected by Suppression Pool Dynamic Loadings Needed Project stage: Other ML20235Z6961975-06-17017 June 1975 Requests Listed Info Re Application for Permit to Const Plant,Including Necessary Info to Evaluate Means Employed for Keeping Radioactivity in Effluents to Unrestricted Areas as Low as Practicable,Within 12 Months from 750604 Project stage: Other ML20262H5711975-06-18018 June 1975 Details 2,3,4 & 5. Sheet 3 of 3 Project stage: Other ML20262H5691975-06-18018 June 1975 Details 1 & 6. Sheet 2 of 3 Project stage: Other ML20262H5671975-06-18018 June 1975 4 Ft X 8 Ft Opening Lhrb Door & Frame Assembly. Sheet 1 of 3 Project stage: Other ML20263N4791975-08-15015 August 1975 Auxiliary Building Unit 2 Spent Fuel Pool Plans and Sections Reinforcing. Sheet 1 Project stage: Other ML20236A0651975-10-15015 October 1975 Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days Project stage: Other ML20263N4651975-11-18018 November 1975 Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 5 Project stage: Other ML20155J7791976-01-0505 January 1976 Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl Project stage: Other ML20262D8641976-03-26026 March 1976 Piping & Instrumentation Diagram: Type Gs,Oil Piping Diagram Project stage: Other ML20148F2811976-06-0707 June 1976 Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads Project stage: RAI ML20196H3251976-06-29029 June 1976 Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl Project stage: Meeting ML20205H9841976-07-0606 July 1976 Forwards Draft Amends 18 & 23 to Licenses DPR-24 & DPR-27, Respectively, & Safety Evaluation.Amends Revise Tech Specs to Add Surveillance Requirements & Place Limit on Max Weight of Spent Fuel Shipping Cask Used Project stage: Draft Approval ML20245C3281976-07-0909 July 1976 Requests Amend to Fsar,Describing Rupture Discs & Administrative Controls,Tests & Surveillance That Recipient Has or Intends to Have Over Discs,Within 30 Days of Ltr Receipt.Listed Items Should Be in Tech Spec Format Project stage: Other ML20236C3041976-09-14014 September 1976 Notification of 760928 Meeting W/Util in Bethesda,Md to Discuss Util Concepts for Proposed Neutron Shield for Plant. Summary of Neutron Streaming Problem Encl Project stage: Meeting ML20265C7261976-09-17017 September 1976 Elementary Wiring Diagram:Reactor Cooling System Przr Heater Project stage: Other ML20070J8961976-09-29029 September 1976 RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated Project stage: Other 1974-12-13 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:CAC:MF9470]] OR [[:CAC:MF9471]] OR [[:CAC:MF9472]] OR [[:CAC:MF9473]] OR [[:CAC:MF9474]] OR [[:CAC:MF9475]] OR [[:CAC:MF9476]] OR [[:CAC:MF9477]] OR [[:CAC:MF9478]] OR [[:CAC:MF9479]] OR [[:CAC:MF9480]] OR [[:CAC:MF9481]] OR [[:CAC:MF9482]] OR [[:CAC:MF9483]] OR [[:CAC:MF9484]] OR [[:CAC:MF9485]] OR [[:CAC:MF9486]] OR [[:CAC:MF9487]] OR [[:CAC:MF9488]] OR [[:CAC:MF9489]] OR [[:CAC:MF9490]] </code>.
[Table View]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:CAC:MF9470]] OR [[:CAC:MF9471]] OR [[:CAC:MF9472]] OR [[:CAC:MF9473]] OR [[:CAC:MF9474]] OR [[:CAC:MF9475]] OR [[:CAC:MF9476]] OR [[:CAC:MF9477]] OR [[:CAC:MF9478]] OR [[:CAC:MF9479]] OR [[:CAC:MF9480]] OR [[:CAC:MF9481]] OR [[:CAC:MF9482]] OR [[:CAC:MF9483]] OR [[:CAC:MF9484]] OR [[:CAC:MF9485]] OR [[:CAC:MF9486]] OR [[:CAC:MF9487]] OR [[:CAC:MF9488]] OR [[:CAC:MF9489]] OR [[:CAC:MF9490]] </code>. |
Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (CAC Nos. MF9470-MF9490)ML17108A384 |
Person / Time |
---|
Site: |
Byron, Braidwood ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
04/19/2017 |
---|
From: |
Blake Purnell Plant Licensing Branch III |
---|
To: |
|
---|
Purnell B, NRR/DORL/LPLIII, 415-1380 |
References |
---|
CAC MF9470, CAC MF9471, CAC MF9472, CAC MF9473, CAC MF9474, CAC MF9475, CAC MF9476, CAC MF9477, CAC MF9478, CAC MF9479, CAC MF9480, CAC MF9481, CAC MF9482, CAC MF9483, CAC MF9484, CAC MF9485, CAC MF9486, CAC MF9487, CAC MF9488, CAC MF9489, CAC MF9490 |
Download: ML17108A384 (4) |
|
|
---|
Category:Biweekly Notice Memoranda
MONTHYEARML17208A2922017-08-0707 August 2017 and Braidwood - Biweekly Fr Notice of Consideration of Issuance of Amendments to Facility Operating Licenses Proposed No. Sig Hazards Consideration Determination and Opportunity for Hearing ML17088A7052017-07-0505 July 2017 Biweekly Fr Notice of Issuance of Amendments of Facility Operating Licenses ML17073A0702017-05-26026 May 2017 Request for Publication in Biweekly Fr Notice - Notice of Issuance of Amendments to Facility Operating Licenses (CAC Nos. MF8238-MF8256) ML17108A3842017-04-19019 April 2017 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (CAC Nos. MF9470-MF9490) ML16229A2552016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 NRC-2016-0180, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 20162016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 ML14247A1542014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 NRC-2014-0917, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 20142014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 ML14233A2082014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 NRC-2014-0193, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 20142014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML14205A3142014-07-28028 July 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Published July 22, 2014 ML14051A6712014-03-0404 March 2014 FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014 NRC-2014-0037, FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 20142014-03-0404 March 2014 FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014 ML0213002692002-05-16016 May 2002 Biweekly Notice Memo, Notice of Consideration, Revising TS 3.6.6 Surveillance Requirements 3.6.6 to Verify Each Spray Nozzle on the Containment Spray Ring Headers at the Top of Containment Dome Is Unobstructed 2017-08-07
[Table view] |
Text
April 19, 2017 MEMORANDUM TO: Biweekly Notice Coordinator FROM: Blake Purnell, Project Manager /RA/
Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE- NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (CAC NOS. MF9470-MF9490)
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station, Units 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-352 and No. 50-353, Limerick Generating Station, Units 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York
Biweekly Notice Coordinator Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit 1, Dauphin County, Pennsylvania Date of amendment request: March 28, 2017. Publicly-available version is in ADAMS under Accession No. ML17087A028.
Description of amendment request: The amendments would revise the technical specifications (TSs) based on Technical Specification Task Force (TSTF) Traveler TSTF-529, Clarify Use and Application Rules (ADAMS Accession No. ML16062A271). The changes would revise and clarify the TS usage rules for completion times, limiting conditions for operation (LCOs), and surveillance requirements (SRs).
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes to [TS] Section 1.3 and LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 3.0.3 (or equivalent) states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed.
Since the proposed changes do not significantly affect system Operability, the proposed changes will have no significant effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously evaluated.
Biweekly Notice Coordinator Therefore, it is concluded that these changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes to the TS usage rules do not affect the design or function of any plant systems. The proposed changes do not change the Operability requirements for plant systems or the actions taken when plant systems are not operable.
Therefore, it is concluded that the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed changes clarify the application of [TS] Section 1.3 and LCO 3.0.4 and do not result in changes in plant operation. SR 3.0.3 (or equivalent) is revised to allow application of SR 3.0.3 when an SR has not been previously performed if there is reasonable expectation that the SR will be met when performed. This expands the use of SR 3.0.3 while ensuring the affected system is capable of performing its safety function.
As a result, plant safety is either improved or unaffected.
Therefore, it is concluded that the changes do not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555.
NRC Branch Chief: David J. Wrona
ML17108A384 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC DORL/LPL3/PM NAME BPurnell SRohrer DWrona BPurnell DATE 4/18/2017 4/18/2017 4/19/2017 4/19/2017