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Category:Environmental Assessment
MONTHYEARML21054A3042021-04-22022 April 2021 Final Environmental Assessments and Findings of No Significant Impact of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans Related to Susquehanna ML1008103102010-03-29029 March 2010 ME2839 & ME2840, Correction Letter Correction Fr Notice for EA-FR for Publication in Fr and Corrected Fr Notice for Exemption Prior to Publication in Fr ML1001102532010-03-15015 March 2010 Environmental Assessment and Finding of No Significant Impact Request for Exemption from Implementation Deadline for Physical Security Plans ML0733903062007-12-0707 December 2007 Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level ML0733204082007-08-15015 August 2007 Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level ML0609303652006-03-31031 March 2006 Ltr B Mckinney, PPL Susquehanna, Re Federal Register Notice Publishing an Environmental Assessment and Finding of No Significant Impact for an Exemption from 10 CFR 72.212 and 72.214 (TAC No. L23943) Docket 72-28 2021-04-22
[Table view] Category:Federal Register Notice
MONTHYEARML23073A1192023-03-31031 March 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L-2022-LLM-0003 - FRN - Enclosure 5 ML22299A1122022-11-0303 November 2022 Notice of Consideration of Approval of Indirect Transfer of Licenses & Conforming Amendments & Opportunity to Request Hearing - Susquehanna Steam Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation (EPID L-2022-LLM ML22299A1132022-11-0303 November 2022 Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments & Opportunity to Request Hearing - Susquehanna Steam Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation (EPID L-2022-L ML20335A0902020-12-21021 December 2020 Federal Register Notice - November 2020 COVID-19 Exemptions ML20271A0002020-10-13013 October 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for September 2020 ML20035C4082020-02-18018 February 2020 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 ML18278A2802018-10-10010 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 10/23/2018 NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML17213A1842017-08-0404 August 2017 Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017 NRC-2017-0175, Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 20172017-08-0404 August 2017 Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017 ML16243A3882016-09-28028 September 2016 Federal Register Notice Susquehanna Steam Electric Station, Units 1 and 2, Consideration of Approval of Application Regarding License Transfer of Renewed Facility Operating License Nos. NPF-14 and NPF-22 ML16239A4242016-09-16016 September 2016 Letter with Notice of Consideration of Approval of Transfer of Licenses and Opportunity for a Hearing ML16131A7952016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 20162016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML15202A2252015-07-23023 July 2015 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing ML15202A2292015-07-23023 July 2015 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (Enclosure) ML15054A0582015-04-10010 April 2015 Letter Forwarding Order Approving Transfer of Licenses and Conforming Amendments Related to Susquehanna Steam Electric Station, Units 1 and 2 (TAC MF4426 and MF4427) NRC-2012-0283, PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit Nos. 1 and 2 EDG Amd Frequency Withdraw Federal Register Notice2015-02-0909 February 2015 PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit Nos. 1 and 2 EDG Amd Frequency Withdraw Federal Register Notice ML15027A6032015-02-0909 February 2015 PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit Nos. 1 and 2 EDG Amd Frequency Withdraw Federal Register Notice ML15027A6052015-02-0909 February 2015 Withdrawal of an Amendment Request ML15027A6112015-02-0909 February 2015 Withdrawal of an Amendment Request ML14149A3102014-05-30030 May 2014 FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: June 6, 2014 NRC-2014-0132, FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: June 6, 20142014-05-30030 May 2014 FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: June 6, 2014 ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12056A0432012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0063, Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing2012-03-0909 March 2012 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML12068A4222012-03-0909 March 2012 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML12068A4192012-03-0909 March 2012 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing ML1126504892011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations2011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations NRC-2011-0040, Sholly Report for Fr Publication on February 22, 20112011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 ML1104103732011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 ML1008103102010-03-29029 March 2010 ME2839 & ME2840, Correction Letter Correction Fr Notice for EA-FR for Publication in Fr and Corrected Fr Notice for Exemption Prior to Publication in Fr ML1001102922010-03-19019 March 2010 ME2839 & ME2840, Transmittal Letter to Licensee for Exemption & Fr Request for Exemption from Part 73 Implementation Date ML1001102532010-03-15015 March 2010 Environmental Assessment and Finding of No Significant Impact Request for Exemption from Implementation Deadline for Physical Security Plans ML0931602812009-11-24024 November 2009 FRN: General Notice. Issuance of Renewed Facility Operating License Nos. NPF-14 and NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 NRC-2009-0389, Frn:General Notice, Notice of Withdrawal of Application for Amendment to Facility Operating License2009-08-31031 August 2009 Frn:General Notice, Notice of Withdrawal of Application for Amendment to Facility Operating License ML0924300972009-08-31031 August 2009 Frn:General Notice, Notice of Withdrawal of Application for Amendment to Facility Operating License ML0922300552009-08-31031 August 2009 Letter Regarding Withdrawal of an Amendment Request and FRN ML0911306172009-04-24024 April 2009 Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations ML0908901562009-03-30030 March 2009 Withdrawal of an Amendment Request ML0734404282008-04-25025 April 2008 Notice of Availability of the Draft Supplement 34 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants, and Public Meeting for the Renewal of Plant Name ML0907109672008-03-13013 March 2008 Notice of Availability of the Final Plant-Specific Supplement 35 to the GEIS for License Renewal of Nuclear Plants Regarding Susquehanna Steam Electric Station, Units 1 and 2 (TAC Nos. MD3022, MD3021) FRN 2023-03-31
[Table view] Category:Finding of No Significant Impact
MONTHYEARML21054A3042021-04-22022 April 2021 Final Environmental Assessments and Findings of No Significant Impact of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans Related to Susquehanna ML1008103102010-03-29029 March 2010 ME2839 & ME2840, Correction Letter Correction Fr Notice for EA-FR for Publication in Fr and Corrected Fr Notice for Exemption Prior to Publication in Fr ML1001102532010-03-15015 March 2010 Environmental Assessment and Finding of No Significant Impact Request for Exemption from Implementation Deadline for Physical Security Plans ML0733903062007-12-0707 December 2007 Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level ML0733204082007-08-15015 August 2007 Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level ML0609303652006-03-31031 March 2006 Ltr B Mckinney, PPL Susquehanna, Re Federal Register Notice Publishing an Environmental Assessment and Finding of No Significant Impact for an Exemption from 10 CFR 72.212 and 72.214 (TAC No. L23943) Docket 72-28 2021-04-22
[Table view] Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] |
Text
March 31, 2006 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
FEDERAL REGISTER NOTICE PUBLISHING AN ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR AN EXEMPTION FROM 10 CFR 72.212 AND 72.214 (TAC NO. L23943)
Dear. Mr. McKinney:
In accordance with the PPL Susquehanna, LLC (PPL) exemption request dated January 31, 2006, as supplemented on March 6, 2006, and pursuant to 10 CFR 51.35, the Nuclear Regulatory Commission (NRC), Office of Nuclear Material Safety and Safeguards, Spent Fuel Project Office, is forwarding an Environment Assessment and Finding of No Significant Impact for noticing in the Federal Register. The requested exemption would allow PPL to load Framatome ANP 9x9-2 fuel assemblies in the NUHOMS HD 61BT canister under Certificate of Compliance No. 1004.
NRC will notify you in a timely manner of our decision on this exemption request. Enclosed is a copy of the Federal Register Notice.
Sincerely,
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos. 72-28 (50-387, 50-388)
Enclosure:
Federal Register Notice
March 31, 2006 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
FEDERAL REGISTER NOTICE PUBLISHING AN ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR AN EXEMPTION FROM 10 CFR 72.212 AND 72.214 (TAC NO. L23943)
Dear. Mr. McKinney:
In accordance with the PPL Susquehanna, LLC (PPL) exemption request dated January 31, 2006, as supplemented on March 6, 2006, and pursuant to 10 CFR 51.35, the Nuclear Regulatory Commission (NRC), Office of Nuclear Material Safety and Safeguards, Spent Fuel Project Office, is forwarding an Environment Assessment and Finding of No Significant Impact for noticing in the Federal Register. The requested exemption would allow PPL to load Framatome ANP 9x9-2 fuel assemblies in the NUHOMS HD 61BT canister under Certificate of Compliance No. 1004.
NRC will notify you in a timely manner of our decision on this exemption request. Enclosed is a copy of the Federal Register Notice.
Sincerely,
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos. 72-28 (50-387, 50-388)
Enclosure:
Federal Register Notice Distribution:
NMSS r/f SBaggett RGuzman, NRR MMiller, RI E:\Filenet\ML060930365.wpd "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFC SFPO SFPO E SFPO NAME JSebrosky EZiegler RNelson DATE 3/15/06 3/3/06 3/24/06 OFFICIAL RECORD COPY
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Robert A. Saccone Steven M. Cook Vice President - Nuclear Operations Manager - Quality Assurance PPL Susquehanna, LLC PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Berwick, PA 18603-0467 Aloysius J. Wrape, III Luis A. Ramos General Manager - Performance Community Relations Manager, Improvement and Oversight Susquehanna PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 634 Salem Blvd., SSO Allentown, PA 18101-1179 Berwick, PA 18603-0467 Terry L. Harpster Bryan A. Snapp, Esq General Manager - Plant Support Assoc. General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSA4 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Richard D. Pagodin Supervisor - Document Control Services General Manager - Nuclear Engineering PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSB3 Allentown, PA 18101-1179 Berwick, PA 18603-0467 Richard W. Osborne Rocco R. Sgarro Allegheny Electric Cooperative, Inc.
Manager - Nuclear Regulatory Affairs 212 Locust Street PPL Susquehanna, LLC P.O. Box 1266 Two North Ninth Street, GENPL4 Harrisburg, PA 17108-1266 Allentown, PA 18101-1179 Director, Bureau of Radiation Protection Walter E. Morrissey Pennsylvania Department of Supervising Engineer Environmental Protection Nuclear Regulatory Affairs Rachel Carson State Office Building PPL Susquehanna, LLC P.O. Box 8469 769 Salem Blvd., NUCSA4 Harrisburg, PA 17105-8469 Berwick, PA 18603-0467 Senior Resident Inspector Michael H. Crowthers U.S. Nuclear Regulatory Commission Supervising Engineer P.O. Box 35, NUCSA4 Nuclear Regulatory Affairs Berwick, PA 18603-0035 PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Regional Administrator, Region 1 Allentown, PA 18101-1179 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803
7590-01-P U.S. NUCLEAR REGULATORY COMMISSION PPL SUSQUEHANNA, LLC INDEPENDENT SPENT FUEL STORAGE INSTALLATION DOCKET NO. 72-28 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of an Environmental Assessment and Finding of No Significant Impact.
FOR FURTHER INFORMATION CONTACT: Joseph M. Sebrosky, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone: (301) 415-1132; Fax number: (301) 415-8555; E-mail: jms3@nrc.gov.
SUPPLEMENTARY INFORMATION:
The U.S. Nuclear Regulatory Commission (NRC or Commission) is considering issuance of an exemption to PPL Susquehanna, LLC (PPL) pursuant to 10 CFR 72.7, from specific provisions of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7), and 72.214. The licensee wants to use the Transnuclear, Inc. (TN) NUHOMS Storage System, Certificate of Compliance No. 1004 (CoC or Certificate) Amendment No. 8 (61BT dry shielded canister), to store spent nuclear fuel under a general license in an Independent Spent Fuel Storage Installation (ISFSI) associated with the operation of the Susquehanna Steam Electric Station
(SSES), Units 1 and 2, located in Luzerne County, Pennsylvania. PPL is requesting an exemption from CoC No. 1004 to allow loading of Framatome ANP 9x9-2 fuel assemblies in the NUHOMS 61BT dry shielded canister (DSC).
ENVIRONMENTAL ASSESSMENT (EA)
Identification of Proposed Action: The proposed action would exempt PPL from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7), and 72.214 and enable PPL to use the TN NUHOMS 61BT DSC with modifications at SSES. These regulations specifically require storage in casks approved under the provisions of 10 CFR Part 72 and compliance with the conditions set forth in the CoC for each dry spent fuel storage cask used by an ISFSI general licensee. The TN NUHOMS CoC provides requirements, conditions, and operating limits in Attachment A, Technical Specifications. The proposed action would exempt PPL from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(7) and 10 CFR 72.214 from a condition in Amendment 8 to CoC No. 1004 so that Framatome ANP 9x9-2 fuel assemblies can be loaded in a NUHOMS -61BT DSC. Specifically, the exemption would be from CoC No. 1004 Attachment A, Technical Specification, Table 1-1d, BWR Fuel Assembly Design Characteristics for the NUHOMS - 61BT DSC, which allows for the storage of General Electric (or equivalent) 9x9-2 fuel assemblies that contain 66 full and 8 partial fuel rods. The exemption would allow PPL to store Framatome ANP 9x9 - 2 fuel assemblies that contain 79 full fuel rods and no partial fuel rods in the NUHOMS -61BT DSC.
PPL committed in its January 31, 2006, submittal to a maximum decay heat load per fuel assembly of 210 watts. This is less than the CoC No. 1004 Attachment A, Technical Specification, Table 1-1c maximum decay heat limit of 300 watts per assembly. In addition, in its March 6, 2006, supplement PPL provided the parameters found in Table 1 below associated
with the Framatome ANP 9x9-2 fuel assembly.
Table 1 Parameters for Framatome ANP 9x9-2 Fuel Assembly Manufacturer: Framatome ANP Array: 9x9 Version: FANP9 Active Fuel Length 150 (inches):
Number of Fuel Rods 79 full Pitch (inches): 0.572 per Assembly:
Fuel Pellet Outside 0.3565 Clad Thickness 0.030 Diameter (inches): (inches):
Clad Outside 0.424 Water Rod Outside 0.425 Diameter (inches): Diameter (inches):
Water Rod Inside 0.364 Diameter (inches):
The NRC has determined that the exemption, if granted, will contain the following 3 conditions:
- 1) PPL will be limited to loading a total of five 61BT DSCs under this exemption if granted,
- 2) PPL shall limit the decay heat level per fuel assembly to 210 watts to ensure cask loadings are bounded by the analyses supporting TN CoC No. 1004, Amendment No. 8., and 3) the exemption will pertain only to Framatome ANP 9x9 -2 fuel assemblies that meet the nominal un-irradiated design parameters contained in Table 1 above.
The proposed action is in accordance with the licensees request for exemption dated January 31, 2006, as supplemented March 6, 2006.
Need for the Proposed Action: The proposed action is needed because SSES will loose full core offload capability in December 2006 following the receipt and staging of new fuel for the scheduled 2007 Unit 2 refueling outage. PPL has determined that it is necessary to start the dry fuel storage (DFS) campaign in May 2006 to ensure full core offload capability. PPL had originally scheduled a DFS campaign to begin in October of 2006. However, because of recent SSES Unit 1 fuel channel performance problems, 54 fuel channels were replaced and stored in the spent fuel pool. As a result of this fuel channel problem, a possible Unit 2 mid-cycle maintenance outage may be necessary to inspect and replace, if necessary, any affected fuel channels. This mid-cycle outage is tentatively scheduled for the Fall of 2006 and access to the spent fuel pool is needed to store fuel channels that are replaced. This activity would conflict with loading dry fuel storage casks. There is also a conflict with performing the DFS campaign in the Summer of 2006. Specifically, PPL has contracted to perform a spent fuel pool cleanout beginning in June 2006 so adequate pool space is restored to support the Unit 2 2007 refueling outage. The DFS campaign and the spent fuel pool cleanout campaign cannot occur simultaneously. Rescheduling the spent fuel cleanout campaign for later in the year is difficult. In summary, space available in the spent fuel pool has become limited much sooner than anticipated, and PPL is requesting the exemption to support a DFS campaign in May 2006. A DFS campaign in May 2006 will also allow PPL flexibility for fuel storage options related to managing decay heat loads within the spent fuel pool.
The proposed action is necessary because the NRC has not yet received an amendment to CoC No. 1004 to allow loading of a Framatome ANP 9x9-2 in a NUHOMS 61BT DSC. The staff would have to review such an amendment request and only after making the appropriate findings would the staff initiate 10 CFR 72.214 rulemaking to implement the change. This process typically takes at least 10 months from the receipt of the amendment request for simple license amendments. Complex license amendments can take over 30
months. Therefore, an amendment to allow loading of Framatome ANP 9x9-2 fuel assemblies in the NUHOMS -61BT DSC can not be completed in time to support PPLs stated needs.
Environmental Impacts of the Proposed Action: The NRC has completed its evaluation of the proposed action and concludes that there will be no significant environmental impact if the exemption is granted. The staff has determined that the proposed action would not endanger life or property. The potential environmental impact of using the NUHOMS system was initially presented in the Environmental Assessment (EA) for the Final Rule to add the TN Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel to the list of approved spent fuel storage casks in 10 CFR 72.214 (59 FR 65898, dated December 22, 1994). The potential environmental impact of using the NUHOMS -61BT DSC was initially presented in the Environmental Assessment (EA) for the Final Rule to add the 61BT DSC to the Standardized NUHOMS system, Amendment No. 3 (66 FR 34523, dated June 29, 2001).
The staff performed a safety evaluation of the proposed exemption. The staff has determined that the Framatome ANP 9x9-2 assemblies, which PPL plans to load into the 61BT DSC are bounded by the design basis fuel assemblies for the 61BT DSC previously evaluated by the staff. The staffs thermal safety evaluation review notes that PPL committed to only loading Framatome ANP 9x9-2 fuel assemblies with a maximum decay heat load per assembly of 210 watts. This is less than the CoC No. 1004 Attachment A, Technical Specification, Table 1-1c maximum decay heat limit of 300 watts per assembly and is therefore bounding. In the criticality area, the staff evaluated the criticality code and the selected cross sectional data that were used by PPL and determined that they were sufficiently documented and validated, and that they are appropriate for the Framatome 9x9-2 fuel assembly. The staff also performed
independent confirmatory criticality calculations for normal conditions of storage and transfer based on the parameters for the Framatome ANP 9x9-2 fuel assembly identified in Table 1 above.
The loading of Framatome ANP 9x9-2 fuel assemblies in the NUHOMS 61BT DSC does not increase the probability or consequences of accidents, no changes are being made in the types of any effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
The exemption only affects the requirements associated with the fuel assemblies that can be loaded in the casks and does not affect non-radiological plant effluents or any other aspects of the environment. Therefore, there are no significant non-radiological impacts associated with the proposed action.
Accordingly, the Commission concludes that there are no significant environmental impacts associated with the proposed action.
Alternative to the Proposed Action: Because there is no significant environmental impact associated with the proposed action, alternatives with equal or greater environmental impact were not evaluated. As an alternative to the proposed action, the staff considered denial of the
proposed action. Denial of the exemption would result in no change in the current environmental impact.
Agencies and Persons Consulted: This exemption request was discussed with Mr. Brad Fuller of the Pennsylvania Department of Environmental Protection Bureau of Radiation Protection on March 6, 2006. He stated that the State had no comments on the technical aspects of the exemption. The NRC staff has determined that a consultation under Section 7 of the Endangered Species Act is not required because the proposed action will not affect listed species or critical habitat. The NRC staff has also determined that the proposed action is not a type of activity having the potential to cause effects on historic properties. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act.
Conclusion:
The staff has reviewed the exemption request submitted by PPL. Allowing loading of Framatome 9x9-2 fuel assemblies in the NUHOMS 61BT DSC would have no significant impact on the environment.
FINDING OF NO SIGNIFICANT IMPACT The environmental impacts of the proposed action have been reviewed in accordance with the requirements set forth in 10 CFR Part 51. Based upon the foregoing Environmental Assessment, the Commission finds that the proposed action of granting the exemption from specific provisions of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7), and 10 CFR 72.214, to allow PPL to load of Framatome ANP 9x9-2 fuel assemblies in the NUHOMS 61BT DSC, subject to conditions, will not significantly impact the quality of the human environment. Accordingly, the Commission has determined that an environmental impact statement for the proposed exemption is not warranted.
In accordance with 10 CFR 2.390 of NRCs Rules of Practice, final NRC records and documents regarding this proposed action are publically available in the records component of NRCs Agencywide Documents Access and Management System (ADAMS). The request for exemption dated January 31, 2006, and March 6, 2006, was docketed under 10 CFR Part 72, Docket No. 72-28. These documents may be inspected at NRCs Public Electronic Reading Room at http://www.nrc.gov/reading-rm/adams.html. These documents may also be viewed electronically on the public computers located at the NRCs Public Document Room (PDR),
O1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or (301) 415-4737, or by e-mail to pdr@nrc.gov Dated at Rockville, Maryland, this 31st day of March, 2006.
FOR THE NUCLEAR REGULATORY COMMISSION.
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
10 CFR 72.214, to allow PPL to load of Framatome ANP 9x9-2 fuel assemblies in the NUHOMS 61BT DSC, subject to conditions, will not significantly impact the quality of the human environment. Accordingly, the Commission has determined that an environmental impact statement for the proposed exemption is not warranted.
In accordance with 10 CFR 2.390 of NRCs Rules of Practice, final NRC records and documents regarding this proposed action are publically available in the records component of NRCs Agencywide Documents Access and Management System (ADAMS). The request for exemption dated January 31, 2006, and March 6, 2006, was docketed under 10 CFR Part 72, Docket No. 72-28. These documents may be inspected at NRCs Public Electronic Reading Room at http://www.nrc.gov/reading-rm/adams.html. These documents may also be viewed electronically on the public computers located at the NRCs Public Document Room (PDR),
O1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or (301) 415-4737, or by e-mail to pdr@nrc.gov Dated at Rockville, Maryland, this 31st day of March, 2006.
FOR THE NUCLEAR REGULATORY COMMISSION.
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
- See previous concurrence OFC SFPO SFPO E OGC E SFPO SFPO NAME JSebrosky EZiegler STreby (NLO) RNelson WRuland DATE 3/29/06 3/3/06 3/22/2006 3/24/2006 03/29/06 OFFICIAL RECORD COPY