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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] Category:Safety Evaluation
MONTHYEARML23257A1222023-09-19019 September 2023 Authorization and Safety Evaluation for Alternative Request for Valve 251130 ML23207A1762023-08-0101 August 2023 Authorization and Safety Evaluation for Relief Request 4RR-10 ML23073A0822023-03-30030 March 2023 Enclosure 2 - Draft Conforming Amendments - Susquehanna Steam Electric Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation- Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L ML23073A1072023-03-30030 March 2023 Enclosure 4 - Safety Evaluation Nonproprietary Susquehanna Steam Electric Station,Units 1,2 & Associated Independent Spent Fuel Storage Installation-Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L- ML23010A1082023-01-15015 January 2023 Issuance of Amendment No. 268 Change to Control Rod Technical Specifications ML22294A1502022-11-17017 November 2022 Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program ML22256A0542022-10-28028 October 2022 Issuance of Amendment Nos. 283 and 266 Change to Reactor Steam Dome Pressure--Low Instrument Function Allowable Value in Technical Specifications ML22200A0622022-08-30030 August 2022 Issuance of Amendment Nos. 282 and 265 Regarding Risk-Informed Completion Times in Technical Specifications ML22146A2072022-07-15015 July 2022 Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY - ML21229A1572021-11-0404 November 2021 Issuance of Amendment No. 263 Temporary Change to Unit 2 Technical Specification 3.8.7 to Allow Replacement of Unit 1 480 Volt Load Center Transformers ML21095A3042021-04-19019 April 2021 Relief Request 4RR-02 Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML20317A3142021-03-10010 March 2021 Issuance of Amendment Nos. 280 and 262 Revise Technical Specification 3.8.1, AC Sources-Operating, to Create a New Condition for an Inoperable Manual Synchronization Circuit ML20342A2372021-02-18018 February 2021 Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements ML20168B0042021-01-21021 January 2021 Issuance of Amendment Nos. 278 and 260 to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2019-LLA-0153) (Redacted) ML20297A5642020-12-22022 December 2020 Issuance of Amendment Nos. 277 and 259 Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML20199G7492020-10-0808 October 2020 Issuance of Amendment Nos. 276 and 258 Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis ML20028E8842020-02-10010 February 2020 Correction to Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of the Emergency Service Water System Piping ML19248A8442020-01-17017 January 2020 Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping ML19336D0642020-01-13013 January 2020 Issuance of Amendment Nos. 274 and 256 to Revise Shutdown Margin Definition to Address Advanced Fuel (TSTF-535, Revision 0) ML19155A2642019-07-16016 July 2019 Issuance of Amendment Nos. 273 and 255 Adoption of TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19154A0602019-06-24024 June 2019 Issuance of Amendment Nos. 272 and 254 Technical Specifications to Adopt TSTF-501, Revision 1, Relocated Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18302A3032019-01-0303 January 2019 SE Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order Ea-13-109 (CAC Nos. MF4364 and MF4365; EPID No. L-2014-JLD-0055 ML18284A4552018-11-0707 November 2018 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18222A2032018-09-26026 September 2018 Issuance of Amendment Nos. 271 and 253 Revising Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MG0269 and MG0270; EPID L-2017-LLA-0306) ML17187A2972017-07-28028 July 2017 Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Revising Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF9154 and MF9155) ML17067A4442017-03-27027 March 2017 Issuance of Amendments Secondary Containment Access Openings ML16320A0802016-11-30030 November 2016 NON-PROPRIETARY - Safety Evaluation by NRR Related to Indirect Transfer of Renewed Operating Licenses from Talen Energy Corporation to Riverstone Holdings, LLC for the Susquehanna Steam Electric Station, Units 1 and 2 ML16005A2342016-05-20020 May 2016 Issuance of Amendments Adoption of TSTF-425 ML16069A1992016-05-10010 May 2016 Relief Requests for the Third 10-Year Inservice Inspection Interval (CAC Nos. MF6302 Through MF6307) ML16062A2162016-03-28028 March 2016 Issuance of Amendments Emergency Action Level Scheme Change ML15267A3812015-11-0202 November 2015 Issuance of Amendments Approval of Cyber Security Plan Milestone 8 ML15243A1402015-09-30030 September 2015 Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits ML15098A4782015-04-28028 April 2015 Relief Requests 4RR-01: Use of a Risk-Informed Inservice Inspection Alternative for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF5097 and MF5098) 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) ML14141A0732014-06-0909 June 2014 Relief Requests for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF2705 Through MF2714) ML14122A1972014-05-22022 May 2014 Relief Requests for the Fourth 10-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2912 and MF2915) ML14111A0522014-05-14014 May 2014 Issuance of Amendments Regarding Change to Technical Specification Surveillance Requirement 3.5.1.12 ML14028A3952014-03-12012 March 2014 Request for Relief 3RR-20 from the Requirements of the American Society of Mechanical Engineers Section XI ML14036A2572014-02-26026 February 2014 Issuance of Amendment Change to Allow Only One Manual Trip System to Be Operable for the Residual Heat Removal Shutdown Cooling System in Modes 4 and 5 ML12160A1942012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML1211701292012-04-27027 April 2012 Correction to Issuance of Amendment ML12096A1582012-04-19019 April 2012 Issuance of Amendment Temporary Change to Unit 2 Technical Specifications 3.8.7 and 3.7.1 to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1, 4160 V Buses ML12062A1332012-03-0606 March 2012 ME7902 & ME7903-Approval of RR-2012-001 Use of Later Edition of the ASME OM Code for Check Valve Condition Monitoring Program ML12046A0462012-02-23023 February 2012 Relief Request No. 3RR-18, Regarding Relief from the Requirements of the ASME Code for Successive Inspections ML11292A1372011-11-17017 November 2011 ME5050 & ME5051-Issuance of Amendments to Renewed FOLs Changes to TS SR 3.4.3.1, Safety Relief Valve Tolerances from -3% to -5% ML11221A2712011-09-0808 September 2011 License Amendment, Issuance of Amendment Adoption of TSTF-514, Revision 3 ML11152A0092011-07-21021 July 2011 Issuance of Amendment Approval of the PPL Susquehanna, LLC Cyber Security Plan ML1035600052011-01-0404 January 2011 Approval of Relief Request RR-02, Revision 1, to Allow 6 Month Extension for SRV IST ML1015204312010-06-16016 June 2010 Request for Alternative No. RR-07 Main Steam Safety Relief Valve Test Interval Extension ML0935201522010-01-0707 January 2010 Relief Requests RR-07 and RR-08 from the Requirements of the OM Code Inservice Testing of Safety Relief Valves 2023-09-19
[Table view] |
Text
October 26, 2006Mr. Britt T. McKinneySr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - PROPOSEDREVISION TO EMERGENCY ACTION LEVELS (TAC NOS. MC9602 AND MC9603)
Dear Mr. McKinney:
By letter dated January 6, 2006, as supplemented by letter dated May 1, 2006, PPLSusquehanna, LLC, submitted proposed changes to the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2), Emergency Action Levels (EALs) for Nuclear Regulatory Commission (NRC) review and approval.The proposed changes revise the SSES 1 and 2 EAL entry conditions for EAL EU1 for theSSES 1 and 2 Independent Spent Fuel Storage Installation (ISFSI) to accomodate use of the approved Transnuclear 61BT dry storage canisters with both 5-year and 10-year cooling periods for spent fuel. This EAL is also revised to provide clarity for the radiological readingsthat may be indicative of damage to the ISFSI system. Based on its review, the NRC staff has concluded that the proposed SSES 1 and 2 EALchanges meet the standards of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.47(b) and the requirements of Appendix E to 10 CFR Part 50, and are therefore considered acceptable as evaluated in the enclosed safety evaluation. As agreed to by your staff, the SSES 1 and 2 EAL changes shall be implemented within 30 days from the issuance date of this letter. If you have any questions, please contact me at 301-415-1030.Sincerely,/RA/Richard V. Guzman, Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388
Enclosure:
Safety Evaluationcc w/encl: See next page October 26, 2006Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - PROPOSEDREVISION TO EMERGENCY ACTION LEVELS (TAC NOS. MC9602 AND MC9603)
Dear Mr. McKinney:
By letter dated January 6, 2006, as supplemented by letter dated May 1, 2006, PPLSusquehanna, LLC, submitted proposed changes to the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2), Emergency Action Levels (EALs) for Nuclear Regulatory Commission (NRC) review and approval.The proposed changes revise the SSES 1 and 2 EAL entry conditions for EAL EU1 for theSSES 1 and 2 Independent Spent Fuel Storage Installation (ISFSI) to accomodate use of the approved Transnuclear 61BT dry storage canisters with both 5-year and 10-year cooling periods for spent fuel. This EAL is also revised to provide clarity for the radiological readingsthat may be indicative of damage to the ISFSI system. Based on its review, the NRC staff has concluded that the proposed SSES 1 and 2 EALchanges meet the standards of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.47(b) and the requirements of Appendix E to 10 CFR Part 50, and are therefore considered acceptable as evaluated in the enclosed safety evaluation. As agreed to by your staff, the SSES 1 and 2 EAL changes shall be implemented within 30 days from the issuance date of this letter. If you have any questions, please contact me at 301-415-1030.Sincerely,/RA/Richard V. Guzman, Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388
Enclosure:
Safety Evaluationcc w/encl: See next pageDISTRIBUTIONPUBLICLPLI-1 RFRidsNrrDorlLpl1-1RidsNrrPmRGuzmanRidsNrrLaSlittleRidsOgcMailCenterDJohnsonEWeiss RidsAcrsAcnwMailCenter ACCESSION NO.: ML062960084
- Provided SE input. No substantive changes made.OFFICELPLI-1/PMLPLI-1/LANSIR/DPRLPLI-1/BCNAMERGuzmanSLittle EWeiss*RLaufer DATE10/26/0610/26/067/28/0610/26/06OFFICIAL RECORD COPY Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:Robert A. SacconeVice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467Terry L. HarpsterGeneral Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Rocco R. SgarroManager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Walter E. MorrisseySupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Michael H. CrowthersSupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Steven M. CookManager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467Luis A. RamosCommunity Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467Bryan A. Snapp, EsqAssoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179Supervisor - Document Control ServicesPPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Richard W. OsborneAllegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266Director, Bureau of Radiation ProtectionPennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4Berwick, PA 18603-0035Regional Administrator, Region 1U.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406Board of SupervisorsSalem Township P.O. Box 405 Berwick, PA 18603-0035Dr. Judith JohnsrudNational Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803 EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO THE PROPOSED EMERGENCY ACTION LEVELS FORPPL SUSQUEHANNA, LLCSUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2DOCKET NOS. 50-387 AND 50-38
81.0 INTRODUCTION
In its application dated January 6, 2006 (Agencywide Documents Access and ManagementSystem Accession No. ML060190489, as supplemented by letter dated May 1, 2006 (ML061290595), PPL Susquehanna, LLC (PPL, the licensee) requested a change to the emergency action levels (EALs) for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).The proposed changes revise the EAL entry conditions for EAL EU1 for the SSES 1 and 2Independent Spent Fuel Storage Installation (ISFSI) to accommodate use of the approved Transnuclear 61BT dry storage containers with both 5-year and 10-year cooling periods for spent fuel. This EAL is also revised to provide clarity for the radiological readings that may be indicative of damage to the ISFSI system.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance which the Nuclear Regulatory Commission (NRC)staff considered in its review of the application are as follows:2.1 Regulations Paragraph (a)(1) to Section 50.47, "Emergency plans," of Title 10 of the Code of FederalRegulations (10 CFR) Part 50 states in part, that no operating license for a nuclear powerreactor will be issued unless a finding is made by the NRC that the state of onsite and offsite emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Section 50.47 also establishes standards that must be met by the onsite and offsite emergency response plans for NRC staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. One of these standards, 50.47(b)(4), stipulates that emergency plans include a standard emergency classification and action level scheme.Section IV.B to Appendix E of 10 CFR Part 50, "Emergency Planning and Preparedness forProduction and Utilization Facilities," provides that emergency plans are to include EALs, which are to be used as criteria for determining the need for notification and participation of local and State agencies and which are to be used for determining when and what type of protective measures should be considered both onsite and offsite to protect public health and safety.
EALs are to be based on in-plant conditions and instrumentation, and also on onsite and offsite monitoring.Section IV.B of Appendix E also provides that initial EALs shall be discussed and agreed on by the applicant and State and local authorities, be approved by NRC, and be reviewed annually with State and local authorities. In addition,Section IV.B of Appendix E states in part, that an EAL revision must be approved by the NRC before implementation if it involves: (1) the changing from an EAL scheme based on NUREG-0654/FEMA-REP-1 to a scheme based on NUMARC/NESP-007 or Nuclear Energy Institute (NEI) 99-01; (2) the licensee is proposing an alternate method for complying with the regulations; or (3) the EAL revision has been evaluated by licensee as constituting a decrease in effectiveness.2.2 Guidance Revision 4 to Regulatory Guide (RG) 1.101, "Emergency Planning and Preparedness forNuclear Power Reactors," issued in July 2003 (ML032020276), endorses the guidance contained in NEI 99-01, "Methodology for Development of Emergency Action Levels," (Revision 4, January 2003), as acceptable to the NRC staff as an alternative method to that described in the following guidance for developing EALs required in Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4):Appendix 1 to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation ofRadiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" (November 1980), andNuclear Utilities Management Council (NUMARC) document, entitled NESP-007,"Methodology for Development of Emergency Action Levels" (Revision 2, January 1992).Regulatory Issue Summary (RIS) 2003-18, "Use of NEI 99-01, Methodology for Development ofEmergency Action Levels," dated October 8, 2003, (as well as supplements 1 and 2, dated July 13, 2004, and December 12, 2005, respectively), provides guidance for developing or changing a standard emergency classification and action level scheme. In addition, the RIS provides recommendations to assist licensees, consistent with Section IV.B to Appendix E of Part 50, in determining whether to seek prior NRC approval of deviations from the new guidance.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed PPL's regulatory and technical analyses in support of its proposedEAL changes, which are described in PPL's application dated January 6, 2006, as supplemented by letter dated May 1, 2006. Since the proposed revision to the SSES 1 and 2 EALs was evaluated by PPL to be a potential decrease in effectiveness, the proposed changes were submitted to the NRC for approval prior to implementation by PPL, as required under Section IV.B to Appendix E of Part 50 and 10 CFR 50.54(q). SSES 1 and 2 utilizes an EAL scheme based upon NEI 99-01, Revision 4, "Methodology forDevelopment of Emergency Action Levels," dated January 2003 (ML041470143). The current SSES EAL, EU1, was based upon utilization of the model 52B Dry Shielded canisters. The proposed changes to EAL EU1 are based upon utilization of the model 52B Dry Shielded canisters as well as the model 61BT Dry Shielded canisters. The 61BT Dry Shielded canisters comply with the conditions and requirements of the "Certificate of Compliance for Dry Spent Fuel Storage Casks" Number 1004, the Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel (NUH-003) and the PPL 72.212 evaluation and were approved for use at SSES under the provisions of 10 CFR Part 72.The calculated EAL entry condition for the current EAL EU1 is 1 Roentgen-per-hour (R/hour) at1 foot and is derived from calculations utilizing the model 52B canisters only. The model 61BT canister is designed to contain a larger number of fuel assemblies and can contain fuel cooled for a shorter period of time. The normal dose rate during transport of 5-year cooled fuel to the model 61BT canister approaches the current EAL value of 1 R/hour at 1 foot. This could lead to unnecessary emergency declarations as the expected dose rate value under accident conditions is approximately 5-7 R/hour at 1 foot. PPL performed a calculation (EC-RADN-1024) and determined that an EAL entry condition of 2 R/hour at 1 foot would bound the credible accident scenarios associated with storing fuel in the 52B and 61BT canisters. The proposed EAL entry conditions are above normal operation dose rates but less than the dose rates associated with an accident and are, therefore, considered acceptable.The current EAL does not specifically address dose rates near the surface of the roof "birdscreen" of a horizontal storage module. PPL proposes a new EAL entry condition incorporating a calculated value for dose rates 1 foot from the roof "bird screen." PPL's calculation, EC-RADN-1024, determined that a value of 4 R/hour at 1 foot from the roof "bird screen" would bound this event and is considered acceptable by the NRC staff.Clarification of the wording in SSES EAL EU1 was proposed to ensure focus was maintained onthe transfer cask used during materials transport and on the horizontal storage module which is used during storage post-transport. The unnecessary wording in EU1.1 that discussed the module, and in EU1.2 that discussed the transfer cask, was removed. This change is acceptable in that the intent of the EAL is maintained.
4.0 CONCLUSION
The NRC staff performed a review of the proposed changes to the SSES 1 and 2 EALs assubmitted under application dated January 6, 2006. Based on the application and the supplemental letter dated May 1, 2006, the NRC staff finds that the proposed SSES 1 and 2 EAL revision is consistent with the guidance of NEI 99-01, Revision 4. As such, the proposed SSES 1 and 2 EAL changes meet the requirements of 10 CFR 50.47(b) and Section IV.B of Appendix E to 10 CFR Part 50, do not result in a decrease in effectiveness of the emergency plan, and are therefore acceptable.Principal Contributor: D. Johnson Date: October 26, 2006