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| {{#Wiki_filter:August 27, 2007LICENSEE:PPL Susquehanna, LLCFACILITY:Susquehanna Steam Electric Station, Units 1 and 2 | | {{#Wiki_filter:August 27, 2007 LICENSEE: PPL Susquehanna, LLC FACILITY: Susquehanna Steam Electric Station, Units 1 and 2 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007,BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATIONThe U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPLSusquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the staff's draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's D-RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of theD-RAIs discussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary./RA/Evelyn Gettys, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388 | | OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items. |
| | The applicant had an opportunity to comment on this summary. |
| | /RA/ |
| | Evelyn Gettys, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. List of Participants | | : 1. List of Participants |
| : 2. List of Draft Requests for Additional Informationcc w/encls: See next page | | : 2. List of Draft Requests for Additional Information cc w/encls: See next page |
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| ML072330167 OFFICEPM:RLRA:DLRLA:DLRBC:RLRA:DLRNAMEEGettysSFigueroaLLundDATE08/22/0708/22/0708/27/07 TELEPHONE CONFERENCE CALLSUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSJULY 26, 2007PARTICIPANTSAFFILIATIONSEvelyn GettysU.S. Nuclear Regulatory Commission (NRC)George ThomasNRC David JengNRC Duane FilchnerPPL Susquehanna, LLC Ross GardnerPPL Susquehanna, LLC DRAFT REQUESTS FOR ADDITIONAL INFORMATIONSUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2LICENSE RENEWAL APPLICATIONJuly 26, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPLSusquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station (SSES), Units 1 and 2 license renewal application (LRA). D-RAI 2.4-1The first sentence in the fourth paragraph of the LRA Section 2.4 "Scoping and ScreeningResults: Structures" states that "The major structures in the scope of license renewal are the: ...". Per Title 10 of the Code of Federal Regulations, Part 54.4 (10 CFR 54.4), all structuresthat perform an intended function stated in 10 CFR 54.4(a) are required to be included within the scope of license renewal and not just the major structures. Please confirm that the in-scope structures and structure categories listed in Section 2.4 is all inclusive. Please clarify the language used in that section of the LRA, "The major structures in the scope ...". Pleaseinclude any remaining structures that may be within the scope of license renewal and provide corresponding scoping, screening and aging management review (AMR) results information relevant to the LRA.Discussion: The applicant will remove the term "major" and list the structures as discussed. They indicated that the question is clear. This D-RAI will be sent as a formal RAI. D-RAI 2.4.1-2Table 2.4-1 lists penetrations (mechanical and electrical, primary containment boundary) ascomponents subject to an AMR. This does not seem to include the penetrations through the Reactor Shield Wall with hinged doors or removable plugs that facilitate piping (feedwater, reactor recirculation, recirculation inlet, etc.) connections to the reactor vessel which would provide access for in-service inspection (see FSAR Section 3.8.3.1.3 and drawings C-1932 Sheets 3 & 5). Please confirm the inclusion or exclusion of these penetrations and theirdoors/plugs from the scope of license renewal (LR) and subject to an AMR. If they were not included as an oversight, please provide a description of their scoping, screening and AMR. If they are excluded from the scope of license renewal, please provide the technical basis for the exclusion.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. RAI 2.4.1-3Section 2.4.1 and Table 2.4-1 list Access Hatches (equipment hatch, personnel airlock,suppression chamber access hatches, and the control rod drive removal hatch) as Primary Containment components subject to an AMR. It is not explicitly clear from Table 2.4-1 and Table 2.4-10 if the flange double-gaskets, hatch locks, hinges and closure mechanisms thathelp prevent loss of sealing/leak-tightness for these listed hatches are included within the scope of LR and subject to an AMR. Please confirm the inclusion or exclusion of these components. | | ML072330167 OFFICE PM:RLRA:DLR LA:DLR BC:RLRA:DLR NAME EGettys SFigueroa LLund DATE 08/22/07 08/22/07 08/27/07 |
| If they were not included as an oversight, please provide a description of their scoping and AMR. If they are excluded from the scope of LR, please provide the technical basis for the exclusionDiscussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. RAI 2.4.1-4Based on information provided in LRA Section 2.4.1 and Tables 2.4-1 and 2.4-10, it is not clearif all drywell pipe restraints/whip restraints are within the scope of LR. If they are not included as an oversight, please provide a description of their scoping and AMR. If they are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of LR, please provide the technical basis for the exclusion.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. RAI 2.4.10-1Sections 2.4.1 thru 2.4.9 state that the structural commodities for these respective structuresare addressed in the bulk commodities evaluation in Section 2.4.10. Table 2.4-10 lists the Bulk Commodities Components Subject to an AMR in categories based on the material of the component type. This table does not identify the specific structures addressed in Sections 2.4.1 thru 2.4.9 in which these individual component types are located. Please add a column to Table 2.4-10 listing the structure(s) in which each bulk commodity component type is located. | | |
| Clearly state if the intent of the Table is for every occurrence (all inclusive) of these component types in each of the applicable structures are in-scope and subject to an AMR. If not, specifically identify those cases which are in-scope and subject to an AMR and those that are not in-scope and excluded from an AMR with technical justification for exclusion. Please confirm and address if there is or is not any Lubrite sliding support bearings/surfaces in-scope and subject to an AMR and will need to be included in Table 2.4-10.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. | | TELEPHONE CONFERENCE CALL SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 26, 2007 PARTICIPANTS AFFILIATIONS Evelyn Gettys U.S. Nuclear Regulatory Commission (NRC) |
| | George Thomas NRC David Jeng NRC Duane Filchner PPL Susquehanna, LLC Ross Gardner PPL Susquehanna, LLC Enclosure 1 |
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| | DRAFT REQUESTS FOR ADDITIONAL INFORMATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION July 26, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station (SSES), Units 1 and 2 license renewal application (LRA). |
| | D-RAI 2.4-1 The first sentence in the fourth paragraph of the LRA Section 2.4 Scoping and Screening Results: Structures states that The major structures in the scope of license renewal are the: .... Per Title 10 of the Code of Federal Regulations, Part 54.4 (10 CFR 54.4), all structures that perform an intended function stated in 10 CFR 54.4(a) are required to be included within the scope of license renewal and not just the major structures. Please confirm that the in-scope structures and structure categories listed in Section 2.4 is all inclusive. Please clarify the language used in that section of the LRA, The major structures in the scope .... Please include any remaining structures that may be within the scope of license renewal and provide corresponding scoping, screening and aging management review (AMR) results information relevant to the LRA. |
| | Discussion: The applicant will remove the term major and list the structures as discussed. |
| | They indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
| | D-RAI 2.4.1-2 Table 2.4-1 lists penetrations (mechanical and electrical, primary containment boundary) as components subject to an AMR. This does not seem to include the penetrations through the Reactor Shield Wall with hinged doors or removable plugs that facilitate piping (feedwater, reactor recirculation, recirculation inlet, etc.) connections to the reactor vessel which would provide access for in-service inspection (see FSAR Section 3.8.3.1.3 and drawings C-1932 Sheets 3 & 5). Please confirm the inclusion or exclusion of these penetrations and their doors/plugs from the scope of license renewal (LR) and subject to an AMR. If they were not included as an oversight, please provide a description of their scoping, screening and AMR. If they are excluded from the scope of license renewal, please provide the technical basis for the exclusion. |
| | Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
| | RAI 2.4.1-3 Section 2.4.1 and Table 2.4-1 list Access Hatches (equipment hatch, personnel airlock, suppression chamber access hatches, and the control rod drive removal hatch) as Primary Containment components subject to an AMR. It is not explicitly clear from Table 2.4-1 and Enclosure 2 |
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| | Table 2.4-10 if the flange double-gaskets, hatch locks, hinges and closure mechanisms that help prevent loss of sealing/leak-tightness for these listed hatches are included within the scope of LR and subject to an AMR. Please confirm the inclusion or exclusion of these components. |
| | If they were not included as an oversight, please provide a description of their scoping and AMR. If they are excluded from the scope of LR, please provide the technical basis for the exclusion Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
| | RAI 2.4.1-4 Based on information provided in LRA Section 2.4.1 and Tables 2.4-1 and 2.4-10, it is not clear if all drywell pipe restraints/whip restraints are within the scope of LR. If they are not included as an oversight, please provide a description of their scoping and AMR. If they are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of LR, please provide the technical basis for the exclusion. |
| | Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
| | RAI 2.4.10-1 Sections 2.4.1 thru 2.4.9 state that the structural commodities for these respective structures are addressed in the bulk commodities evaluation in Section 2.4.10. Table 2.4-10 lists the Bulk Commodities Components Subject to an AMR in categories based on the material of the component type. This table does not identify the specific structures addressed in Sections 2.4.1 thru 2.4.9 in which these individual component types are located. Please add a column to Table 2.4-10 listing the structure(s) in which each bulk commodity component type is located. |
| | Clearly state if the intent of the Table is for every occurrence (all inclusive) of these component types in each of the applicable structures are in-scope and subject to an AMR. If not, specifically identify those cases which are in-scope and subject to an AMR and those that are not in-scope and excluded from an AMR with technical justification for exclusion. Please confirm and address if there is or is not any Lubrite sliding support bearings/surfaces in-scope and subject to an AMR and will need to be included in Table 2.4-10. |
| | Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
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| Letter to PPL Susquehanna, from E. Gettys, dated August 27, 2007 | | Letter to PPL Susquehanna, from E. Gettys, dated August 27, 2007 |
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| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007,BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATIONDISTRIBUTION | | OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION DISTRIBUTION: |
| :HARD COPY: DLR RFE-MAIL:PUBLICSSmith (srs3)
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| RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb | | SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes |
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| | YDiaz RGuzman BRogers EGettys |
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| YDiaz RGuzman BRogers EGettys Susquehanna Steam Electric Station, Units 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, Esq.Associate 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.
| | Susquehanna Steam Electric Station, Units 1 and 2 cc: |
| 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
| | Robert A. Saccone Bryan A. Snapp, Esq. |
| | Vice President - Nuclear Operations Associate General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Terry L. Harpster Supervisor - Document Control Services General Manager - Plant Support PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSA4 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 Steven M. Cook King of Prussia, PA 19406 Manager - Quality Assurance PPL Susquehanna, LLC Board of Supervisors 769 Salem Blvd., NUCSB2 Salem Township Berwick, PA 18603-0467 P.O. Box 405 Berwick, PA 18603-0035 Luis A. Ramos Community Relations Manager, Dr. Judith Johnsrud Susquehanna National Energy Committee PPL Susquehanna, LLC Sierra Club 634 Salem Blvd., SSO 443 Orlando Avenue Berwick, PA 18603-0467 State College, PA 16803 |
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| 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 Susquehanna Steam Electric Station, Units 1 and 2 cc:-2-Ms. Julie KeysNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708}}
| | Susquehanna Steam Electric Station, Units 1 and 2 cc: |
| | Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708}} |
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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:Meeting Summary
MONTHYEARML23228A1952023-08-21021 August 2023
Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative
ML23179A0012023-06-28028 June 2023
6/7/2023 - Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - Meeting Summary
ML22187A1462022-07-0606 July 2022
Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Meeting Summary
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09/26/2007 Summary of Telephone Conference Call Between the NRC and PPL Susquehanna, LLC Concerning Requests for Additional Information Pertaining to the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application
2023-08-21
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Text
August 27, 2007 LICENSEE: PPL Susquehanna, LLC FACILITY: Susquehanna Steam Electric Station, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Evelyn Gettys, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. List of Participants
- 2. List of Draft Requests for Additional Information cc w/encls: See next page
ML072330167 OFFICE PM:RLRA:DLR LA:DLR BC:RLRA:DLR NAME EGettys SFigueroa LLund DATE 08/22/07 08/22/07 08/27/07
TELEPHONE CONFERENCE CALL SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 26, 2007 PARTICIPANTS AFFILIATIONS Evelyn Gettys U.S. Nuclear Regulatory Commission (NRC)
George Thomas NRC David Jeng NRC Duane Filchner PPL Susquehanna, LLC Ross Gardner PPL Susquehanna, LLC Enclosure 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION July 26, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on July 26, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Susquehanna Steam Electric Station (SSES), Units 1 and 2 license renewal application (LRA).
D-RAI 2.4-1 The first sentence in the fourth paragraph of the LRA Section 2.4 Scoping and Screening Results: Structures states that The major structures in the scope of license renewal are the: .... Per Title 10 of the Code of Federal Regulations, Part 54.4 (10 CFR 54.4), all structures that perform an intended function stated in 10 CFR 54.4(a) are required to be included within the scope of license renewal and not just the major structures. Please confirm that the in-scope structures and structure categories listed in Section 2.4 is all inclusive. Please clarify the language used in that section of the LRA, The major structures in the scope .... Please include any remaining structures that may be within the scope of license renewal and provide corresponding scoping, screening and aging management review (AMR) results information relevant to the LRA.
Discussion: The applicant will remove the term major and list the structures as discussed.
They indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 2.4.1-2 Table 2.4-1 lists penetrations (mechanical and electrical, primary containment boundary) as components subject to an AMR. This does not seem to include the penetrations through the Reactor Shield Wall with hinged doors or removable plugs that facilitate piping (feedwater, reactor recirculation, recirculation inlet, etc.) connections to the reactor vessel which would provide access for in-service inspection (see FSAR Section 3.8.3.1.3 and drawings C-1932 Sheets 3 & 5). Please confirm the inclusion or exclusion of these penetrations and their doors/plugs from the scope of license renewal (LR) and subject to an AMR. If they were not included as an oversight, please provide a description of their scoping, screening and AMR. If they are excluded from the scope of license renewal, please provide the technical basis for the exclusion.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
RAI 2.4.1-3 Section 2.4.1 and Table 2.4-1 list Access Hatches (equipment hatch, personnel airlock, suppression chamber access hatches, and the control rod drive removal hatch) as Primary Containment components subject to an AMR. It is not explicitly clear from Table 2.4-1 and Enclosure 2
Table 2.4-10 if the flange double-gaskets, hatch locks, hinges and closure mechanisms that help prevent loss of sealing/leak-tightness for these listed hatches are included within the scope of LR and subject to an AMR. Please confirm the inclusion or exclusion of these components.
If they were not included as an oversight, please provide a description of their scoping and AMR. If they are excluded from the scope of LR, please provide the technical basis for the exclusion Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
RAI 2.4.1-4 Based on information provided in LRA Section 2.4.1 and Tables 2.4-1 and 2.4-10, it is not clear if all drywell pipe restraints/whip restraints are within the scope of LR. If they are not included as an oversight, please provide a description of their scoping and AMR. If they are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of LR, please provide the technical basis for the exclusion.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
RAI 2.4.10-1 Sections 2.4.1 thru 2.4.9 state that the structural commodities for these respective structures are addressed in the bulk commodities evaluation in Section 2.4.10. Table 2.4-10 lists the Bulk Commodities Components Subject to an AMR in categories based on the material of the component type. This table does not identify the specific structures addressed in Sections 2.4.1 thru 2.4.9 in which these individual component types are located. Please add a column to Table 2.4-10 listing the structure(s) in which each bulk commodity component type is located.
Clearly state if the intent of the Table is for every occurrence (all inclusive) of these component types in each of the applicable structures are in-scope and subject to an AMR. If not, specifically identify those cases which are in-scope and subject to an AMR and those that are not in-scope and excluded from an AMR with technical justification for exclusion. Please confirm and address if there is or is not any Lubrite sliding support bearings/surfaces in-scope and subject to an AMR and will need to be included in Table 2.4-10.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Letter to PPL Susquehanna, from E. Gettys, dated August 27, 2007
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 26, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC SSmith (srs3)
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Susquehanna Steam Electric Station, Units 1 and 2 cc:
Robert A. Saccone Bryan A. Snapp, Esq.
Vice President - Nuclear Operations Associate General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Terry L. Harpster Supervisor - Document Control Services General Manager - Plant Support PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSA4 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 Steven M. Cook King of Prussia, PA 19406 Manager - Quality Assurance PPL Susquehanna, LLC Board of Supervisors 769 Salem Blvd., NUCSB2 Salem Township Berwick, PA 18603-0467 P.O. Box 405 Berwick, PA 18603-0035 Luis A. Ramos Community Relations Manager, Dr. Judith Johnsrud Susquehanna National Energy Committee PPL Susquehanna, LLC Sierra Club 634 Salem Blvd., SSO 443 Orlando Avenue Berwick, PA 18603-0467 State College, PA 16803
Susquehanna Steam Electric Station, Units 1 and 2 cc:
Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708
