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| | number = ML070030463 | | | number = ML070030463 |
| | issue date = 01/16/2007 | | | issue date = 01/16/2007 |
| | title = Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Susquehanna Steam Electric Station, Units 1 and 2 (TAC Nos. MD3021 and MD3022) | | | title = Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Susquehanna Steam Electric Station, Units 1 and 2 |
| | author name = Mullins A | | | author name = Mullins A |
| | author affiliation = NRC/NRR/ADRO/DLR/REBB | | | author affiliation = NRC/NRR/ADRO/DLR/REBB |
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| =Text= | | =Text= |
| {{#Wiki_filter:January 16, 2007Mr. Britt T. MckinneySr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 | | {{#Wiki_filter:January 16, 2007 Mr. Britt T. Mckinney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVEREACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022) | | REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022) |
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| ==Dear Mr. McKinney:== | | ==Dear Mr. McKinney:== |
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| The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident MitigationAlternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staff's requests for additional information.We request that you provide your responses to these questions within 90 days of the date ofthis letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov | | The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident Mitigation Alternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staffs requests for additional information. |
| .Sincerely, /RA/Alicia Mullins, Project ManagerEnvironmental Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388
| | We request that you provide your responses to these questions within 90 days of the date of this letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Alicia Mullins, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedcc w/encl: See next page January 16, 2007Mr. Britt T. MckinneySr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 | | |
| | As stated cc w/encl: See next page |
| | |
| | January 16, 2007 Mr. Britt T. Mckinney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVEREACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022) | | REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022) |
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| ==Dear Mr. McKinney:== | | ==Dear Mr. McKinney:== |
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| The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident MitigationAlternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staff's requests for additional information.We request that you provide your responses to these questions within 90 days of the date ofthis letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov | | The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident Mitigation Alternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staffs requests for additional information. |
| .Sincerely, /RA/Alicia Mullins, Project ManagerEnvironmental Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388
| | We request that you provide your responses to these questions within 90 days of the date of this letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Alicia Mullins, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedcc w/encl: See next page DISTRIBUTION: See next page
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| Adams Accession No. ML070030463OFFICELA:DLRPM:DLR:REBBPM:DLR:REBBBC:DLR:REBBNAMEI. KingJ.DavisA.MullinsR.Franovich DATE01/5/07 01/8/0701/16/0701/16/07 OFFICIAL RECORD COPY Letter to B. McKinney from A. Mullins Dated January 16, 2007 | | As stated cc w/encl: See next page DISTRIBUTION: See next page Adams Accession No. ML070030463 OFFICE LA:DLR PM:DLR:REBB PM:DLR:REBB BC:DLR:REBB NAME I. King J.Davis A.Mullins R.Franovich DATE 01/5/07 01/8/07 01/16/07 01/16/07 OFFICIAL RECORD COPY |
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| | Letter to B. McKinney from A. Mullins Dated January 16, 2007 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENTMITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022)DISTRIBUTION | | REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022) |
| :HARD COPYA. MullinsB. Palla E-MAILP.T. Kuo (RidsNrrDlr)M. Rubin (RidsNrrDraApla)
| | DISTRIBUTION: |
| | HARD COPY A. Mullins B. Palla E-MAIL P.T. Kuo (RidsNrrDlr) |
| | M. Rubin (RidsNrrDraApla) |
| R. Franovich (RidsNrrDlrRebb) | | R. Franovich (RidsNrrDlrRebb) |
| E. Benner (RidsNrrDlrReba) | | E. Benner (RidsNrrDlrReba) |
| B. Palla PMNS BRidsNrrAdro RidsNrrDlrRebb RidsNrrDlrReba RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsOgcMailRoom RidsOpaMail RidsOcaMailCenter A. Mullins J. Davis S. Lopas R. Schaaf F. Monette (fmonette@anl.gov) | | B. Palla PMNS BRidsNrrAdro RidsNrrDlrRebb RidsNrrDlrReba RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsOgcMailRoom RidsOpaMail RidsOcaMailCenter A. Mullins J. Davis S. Lopas R. Schaaf F. Monette (fmonette@anl.gov) |
| R. Guzman Y. Diaz Sanabria E. Gettys A. Blamey, SRI Region 1 N. Sheehan, OPA Region 1 Samuel Lee, EDO Contact, Region I A. Blamey (ajb3@nrc.gov) | | R. Guzman Y. Diaz Sanabria E. Gettys A. Blamey, SRI Region 1 N. Sheehan, OPA Region 1 Samuel Lee, EDO Contact, Region I A. Blamey (ajb3@nrc.gov) |
| C. Colleli R. K. Wild | | C. Colleli R. K. Wild J. Storch |
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| | Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives for the Susquehanna Steam Electric Station, Units 1 and 2 |
| | : 1. Provide the following information regarding the Susquehanna Steam Electric Station (SSES) |
| | Probabilistic Risk Assessment (PRA) model used for the Severe Accident Mitigation Alternatives (SAMA) analysis: |
| | : a. Provide a summary of the major Level 1 and 2 PRA versions and their core damage frequency (CDFs) from the Individual Plant Examination (IPE) to the present, including the version reviewed by the Boiling Water Reactor Owners Group (BWROG), and the version used for risk-informed submittals such as inservice inspection and allowed outage time extension for offsite power. Also, indicate the major changes to each version from the prior version (including the changes from pre-Extended Power Uprate (EPU) to post-EPU models) and the major reasons for changes in the CDF. |
| | : b. Provide the freeze date for the incorporation of design and/or procedure changes into the PRA. |
| | : c. Provide the CDF contribution due to station blackout (SBO) and anticipated transient without scram (ATWS). |
| | : d. Explain why loss of an AC bus is a very small (approximately 0.2 percent) contributor to the CDF. |
| | : e. The summary of the BWROG peer review overall assessment provided on pages E.2-14 and -15 describes a non-conservatism associated with SBO events. Identify the facts and observations (F&Os) associated with this non-conservatism and discuss their resolution. |
| | : f. Section E.2.3.2 of the Environmental Report (ER) describes a self assessment that considered the open Level B F&Os and concluded that the remaining items and gaps would not have a significant impact on the EPU application. Confirm that the same conclusion can be drawn concerning the impacts of the remaining items and gaps on the SAMA analysis. |
| | : g. Describe the current containment venting capability and procedural directions at SSES (hard pipe, via standby gas treatment system, etc.) and how it is modeled in the PRA. |
| | : 2. Provide the following information relative to the Level 2 analysis: |
| | : a. Provide a summary description of the current Level 2 model, including: the Level 1/Level 2 interface, the containment event tree (CET), the basis for quantification of CET nodes, the binning process used to assign end states to release categories, and the determination of release fractions for each release category. |
| | ENCLOSURE |
| | : b. Describe the steps taken to ensure the technical adequacy of the Level 2 revisions subsequent to the BWROG peer review. |
| | : 3. Provide the following information with regard to the treatment and inclusion of external events in the SAMA analysis: |
| | : a. The individual plant examination of external events (IPEEE) fire analysis utilized the IPE internal events models to assess system performance. Indicate whether the original IPE models or the revised IPE models were utilized. |
| | : b. Based on a sensitivity study performed by PPL Susquehanna, LLC, the U.S. Nuclear Regulatory Commission concluded in the IPEEE safety evaluation report that the CDF for some fire contributors might be as much as three orders of magnitude higher than the revised values reported in the IPEEE. Discuss this issue and its potential impact on the ER assumption that the fire CDF is about equal to the internal events CDF. |
| | : 4. Provide the following information concerning the MACCS2 analyses: |
| | : a. Clarify whether separate ORIGEN calculations were performed for pre-EPU and post-EPU conditions and used to determine population doses for the respective cases. |
| | : b. Based on the March 31, 2006, license amendment request, the EPU power level would be approximately 13% above the current licensed power level. As such, the population dose for EPU conditions would be expected to be approximately 13% greater than for pre-EPU conditions. However, from Table E.3-4, the increase in dose for the dominant release categories (e.g., L2-1, L2-2, and L2-5) ranges from 4 to 11%. Explain this result. |
| | : 5. Provide the following with regard to the SAMA identification and screening process: |
| | : a. Tables E.5-1 and E.5-2 include a number of events that are described as preventative maintenance actions (i.e., 024-N-E-DSL-P, 024-I-A-DSL-P, and 024-II-B-DSL-P). Identify the specific structure, system, and components associated with these maintenance actions. |
| | : b. Section 5.1.5 includes a list of nine enhancements identified in the IPE. The seventh enhancement, revise guidance regarding reactor vessel control, is listed as not implemented and only provides the reasoning that the enhancement has been determined not to be required for safe operation of the plant. Provide a further description of the disposition of this enhancement, and any efforts made to identify SAMA candidates exist to address the associated risk contributors. |
| | : c. Section E.5.1.7.1 discusses the contribution to fire CDF from the dominant fire zones. |
| | Although two SAMAs from the internal events analysis were identified to address this risk, no SAMAs unique to the fire analysis were identified. For each fire zone, discuss the potential for SAMAs to address the unique cause of the fire risk, such as SAMAs to reduce the fire initiators, to improve fire detection or suppression, or to relocate components or cabling. |
| | : 6. Provide the following with regard to the Phase 2 cost-benefit evaluations: |
| | : a. For SAMA 3, Proceduralize Reactor Pressure Valve Depressurization When Fire Protection System Injection is the Only Makeup Source, indicate what failure events were included for the failure to provide late low pressure injection via the fire main. |
| | : b. For SAMA 8, Automatic Feedwater Runback for ATWS, the percent reduction in dose risk and offsite economic cost risk (OECR) is much smaller than the reduction in CDF. |
| | The reduction in CDF is almost entirely in the low/early release category, which has a very small contribution to dose-risk and OECR. One might expect the reduction in CDF due to ATWS to impact high or medium release categories. Explain this apparent discrepancy. |
| | : c. In the discussion of the costs for SAMA 8, it is implied that the cost estimate does not account for inflation. Clarify whether this cost estimate, or any other cost estimates, accounts for inflation. |
| | : d. For SAMA 12, Containment Venting After Core Damage, the analysis shows very little risk reduction. Since this SAMA would reduce the releases for all drywell overpressure failure sequences, a more significant reduction in risk would be expected. Explain the reasons for the small risk reduction for this SAMA. |
| | : 7. One of the Mark I plants considered in its SAMA identification process (Section E.5.1.4) identified the following SAMAs as potentially cost-beneficial: |
| | : a. Develop guidance/procedures for local, manual control of reactor core isolation cooling following loss of DC power. |
| | : b. Procedures to control containment venting to avoid adverse impacts on emergency core cooling system. |
| | These SAMAs would appear to be applicable to SSES but are not among the Phase 2 SAMAs for SSES. Provide a brief statement regarding the applicability/feasibility of these alternatives for SSES, and a further evaluation (similar to those evaluations provided in the ER) if the alternative could be potentially cost-beneficial at SSES. |
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| J. Storch Request for Additional InformationRegarding the Analysis of Severe Accident Mitigation Alternativesfor the Susquehanna Steam Electric Station, Units 1 and 21.Provide the following information regarding the Susquehanna Steam Electric Station (SSES)Probabilistic Risk Assessment (PRA) model used for the Severe Accident Mitigation Alternatives (SAMA) analysis:a.Provide a summary of the major Level 1 and 2 PRA versions and their core damagefrequency (CDFs) from the Individual Plant Examination (IPE) to the present, including the version reviewed by the Boiling Water Reactor Owners Group (BWROG), and the version used for risk-informed submittals such as inservice inspection and allowed outage time extension for offsite power. Also, indicate the major changes to each version from the prior version (including the changes from pre-Extended Power Uprate (EPU) to post-EPU models) and the major reasons for changes in the CDF.b.Provide the freeze date for the incorporation of design and/or procedure changes intothe PRA.c.Provide the CDF contribution due to station blackout (SBO) and anticipatedtransient without scram (ATWS).d.Explain why loss of an AC bus is a very small (approximately 0.2 percent)contributor to the CDF.e.The summary of the BWROG peer review overall assessment provided on pagesE.2-14 and -15 describes a non-conservatism associated with SBO events. Identify the facts and observations (F&Os) associated with this non-conservatism and discuss their resolution.f.Section E.2.3.2 of the Environmental Report (ER) describes a self assessment thatconsidered the open Level B F&Os and concluded that the remaining items and gaps would not have a significant impact on the EPU application. Confirm that the same conclusion can be drawn concerning the impacts of the remaining items and gaps on the SAMA analysis.g.Describe the current containment venting capability and procedural directions at SSES(hard pipe, via standby gas treatment system, etc.) and how it is modeled in the PRA.2.Provide the following information relative to the Level 2 analysis:a.Provide a summary description of the current Level 2 model, including: the Level1/Level 2 interface, the containment event tree (CET), the basis for quantification of CET nodes, the binning process used to assign end states to release categories, and the determination of release fractions for each release category.ENCLOSURE b.Describe the steps taken to ensure the technical adequacy of the Level 2 revisionssubsequent to the BWROG peer review.3.Provide the following information with regard to the treatment and inclusion of external eventsin the SAMA analysis:a.The individual plant examination of external events (IPEEE) fire analysis utilized the IPEinternal events models to assess system performance. Indicate whether the original IPE models or the revised IPE models were utilized.b.Based on a sensitivity study performed by PPL Susquehanna, LLC, the U.S. NuclearRegulatory Commission concluded in the IPEEE safety evaluation report that the CDF for some fire contributors might be as much as three orders of magnitude higher than the revised values reported in the IPEEE. Discuss this issue and its potential impact on the ER assumption that the fire CDF is about equal to the internal events CDF.4.Provide the following information concerning the MACCS2 analyses:a.Clarify whether separate ORIGEN calculations were performed for pre-EPU andpost-EPU conditions and used to determine population doses for the respective cases.b.Based on the March 31, 2006, license amendment request, the EPU power level wouldbe approximately 13% above the current licensed power level. As such, the population dose for EPU conditions would be expected to be approximately 13% greater than for pre-EPU conditions. However, from Table E.3-4, the increase in dose for the dominant release categories (e.g., L2-1, L2-2, and L2-5) ranges from 4 to 11%. Explain this result. 5.Provide the following with regard to the SAMA identification and screening process:a.Tables E.5-1 and E.5-2 include a number of events that are described aspreventative maintenance actions (i.e., 024-N-E-DSL-P, 024-I-A-DSL-P, and 024-II-B-DSL-P). Identify the specific structure, system, and components associated with these maintenance actions.b.Section 5.1.5 includes a list of nine enhancements identified in the IPE. The seventhenhancement, revise guidance regarding reactor vessel control, is listed as "not implemented" and only provides the reasoning that the enhancement has been determined not to be required for safe operation of the plant. Provide a further description of the disposition of this enhancement, and any efforts made to identify SAMA candidates exist to address the associated risk contributors.c.Section E.5.1.7.1 discusses the contribution to fire CDF from the dominant fire zones. Although two SAMAs from the internal events analysis were identified to address this risk, no SAMAs unique to the fire analysis were identified. For each fire zone, discuss the potential for SAMAs to address the unique cause of the fire risk, such as SAMAs to reduce the fire initiators, to improve fire detection or suppression, or to relocate components or cabling. 6.Provide the following with regard to the Phase 2 cost-benefit evaluations:a.For SAMA 3, Proceduralize Reactor Pressure Valve Depressurization When FireProtection System Injection is the Only Makeup Source, indicate what failure events were included for the failure to provide late low pressure injection via the fire main.b.For SAMA 8, Automatic Feedwater Runback for ATWS, the percent reduction in doserisk and offsite economic cost risk (OECR) is much smaller than the reduction in CDF.
| | Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc: |
| The reduction in CDF is almost entirely in the low/early release category, which has a very small contribution to dose-risk and OECR. One might expect the reduction in CDF due to ATWS to impact high or medium release categories. Explain this apparent discrepancy.c.In the discussion of the costs for SAMA 8, it is implied that the cost estimate does notaccount for inflation. Clarify whether this cost estimate, or any other cost estimates, accounts for inflation.d.For SAMA 12, Containment Venting After Core Damage, the analysis shows very littlerisk reduction. Since this SAMA would reduce the releases for all drywell overpressure failure sequences, a more significant reduction in risk would be expected. Explain the reasons for the small risk reduction for this SAMA.7.One of the Mark I plants considered in it's SAMA identification process (Section E.5.1.4)identified the following SAMAs as potentially cost-beneficial:a.Develop guidance/procedures for local, manual control of reactor core isolation coolingfollowing loss of DC power.b.Procedures to control containment venting to avoid adverse impacts on emergencycore cooling system.These SAMAs would appear to be applicable to SSES but are not among the Phase 2 SAMAsfor SSES. Provide a brief statement regarding the applicability/feasibility of these alternatives for SSES, and a further evaluation (similar to those evaluations provided in the ER) if the alternative could be potentially cost-beneficial at SSES.
| | Robert A. Saccone Luis A. Ramos Vice President - Nuclear Operations Community Relations Manager, PPL Susquehanna, LLC Susquehanna 769 Salem Blvd., NUCSB3 PPL Susquehanna, LLC Berwick, PA 18603-0467 634 Salem Blvd., SSO Berwick, PA 18603-0467 Aloysius J. Wrape, III General Manager - Performance Bryan A. Snapp, Esq. |
| Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467Aloysius J. Wrape, IIIGeneral Manager - Performance Improvement and Oversight PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Terry 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. | | Improvement and Oversight Associate General Counsel PPL Susquehanna, LLC PPL Services Corporation Two North Ninth Street, GENPL4 Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 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. |
| 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
| | 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 |
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| 475 Allendale Road King of Prussia, PA 19406Board of SupervisorsSalem Township P.O. Box 405 Berwick, PA 18603-0035 Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:-2-Dr. Judith JohnsrudNational Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803Mr. James RossNuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, D.C. 20006-3708}}
| | Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc: |
| | Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803 Mr. James Ross Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, D.C. 20006-3708 |
| | }} |
Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement
Results
Other: ML062960009, ML063040075, ML063050355, ML063050363, ML063050370, ML063050590, ML063050595, ML063050608, ML063100474, ML063470607, ML070320537, ML070320542, ML070320564, ML070320567, ML070320592, ML070320601, ML070320605, ML070320657, ML070320662, ML070320667, ML070320671, ML070320676, ML070320680, ML070320719, ML070320721, ML070320728, ML070320733, ML070320740, ML070320745, ML070320756, ML070320784, ML070320787, ML070320791, ML070320802, ML070320803, ML070320806, ML070570480, ML070590453, ML070590456, ML070610479, ML070710153, ML070710154, ML070710155, ML070710159, ML070710161, ML070720347, ML070800414, ML070800420, ML070800423, ML070800434... further results
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Project stage: Other
ML0802303262005-10-12012 October 2005
Centers for Disease Control & Prevention, Legionellosis: Legionnaires' Disease (Ld) and Pontiac Fever.
Project stage: Other
ML0802303172005-12-0606 December 2005
Pennsylvania Department of Environmental Protection, Standards for Cleanup, Reuse of Hazleton Mine Reclamation Project
Project stage: Other
ML0802303342005-12-31031 December 2005
River Basin Commission, Susquehanna River Basin Commission Gis Program., Excerpt, Middle Susquehanna Subbasin.
Project stage: Other
ML0623501472006-08-15015 August 2006
Monthly Operating Reports
Project stage: Request
ML0626201572006-09-13013 September 2006
Application for Renewed Operating Licenses
Project stage: Request
ML0626904702006-09-14014 September 2006
August 2006 Monthly Operating Report for Susquehanna Steam Electric Station, Units 1 and 2
Project stage: Request
ML0703206572006-10-0303 October 2006
Email from Allison Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703208032006-10-0303 October 2006
Email from Nash Regarding Consultation Letters on American Shad in the Susquehanna River
Project stage: Other
ML0703206012006-10-0505 October 2006
E-mail from Metz Regarding the Susquehanna Steam Electric Station Data Assessment
Project stage: Other
ML0703206052006-10-0505 October 2006
Email from Moret Regarding the Susquehanna Steam Electric Station Category 1 & 2 Issues
Project stage: Other
ML0703207982006-10-0505 October 2006
Email from Klementowicz Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Acceptance Review
ML0703206672006-10-0606 October 2006
E-mail from O'Rourke Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703206802006-10-0606 October 2006
Email from Avci Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703208002006-10-0606 October 2006
Email from Davis Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Acceptance Review
ML0703205672006-10-0707 October 2006
E-mail from Vinikour Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703205922006-10-0909 October 2006
E-mail from Monette Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703206622006-10-0909 October 2006
E-Mail from Lazaro Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703206762006-10-0909 October 2006
E-mail from Lagory Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703208022006-10-0909 October 2006
Email from Monette to Mullins Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0703205642006-10-0909 October 2006
Email from Wescott Regarding the Environmental Report (Er) Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
PLA-0061, September 2006 Monthly Operating Report for Susquehanna Steam Electric Station Units 1 and 22006-10-13013 October 2006
September 2006 Monthly Operating Report for Susquehanna Steam Electric Station Units 1 and 2
Project stage: Request
ML0703208062006-10-16016 October 2006
Acceptance Review Checklist from Mullins Regarding the Susquehanna Steam Electric Station Environmental Report
Project stage: Other
ML0629600792006-10-24024 October 2006
Maintenance of Reference Materials at the Mill Memorial Library, Related to the Review of the Susquehanna Steam Electric Station License Renewal Application
Project stage: Approval
ML0629600602006-10-26026 October 2006
Maintenance of Reference Materials at the Berwick Public Library, Related to the Review of the Susquehanna Steam Electric Station License Renewal Application
Project stage: Approval
ML0703206712006-10-31031 October 2006
E-mail from Quinn Regarding the Environmental Report Acceptance Review on the Susquehanna Steam Electric Station Application Review
Project stage: Other
ML0629600492006-11-0101 November 2006
50 Mile Vicinity Map
Project stage: Request
ML0629600092006-11-0101 November 2006
License Renewal Application Review (Shpo No. 05-1588-079-A)
Project stage: Other
PLA-6133, Acceptability and Sufficiency for Docketing - Application for Renewed Operating Licenses Numbers NPF-14 and NPF-222006-11-0202 November 2006
Acceptability and Sufficiency for Docketing - Application for Renewed Operating Licenses Numbers NPF-14 and NPF-22
Project stage: Request
ML0703207842006-11-0606 November 2006
Email from Franovich Regarding Questions on Consultation Letters
Project stage: Other
ML0630503632006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Oneida Nation Wisconsin
Project stage: Other
ML0630503552006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Eastern Shawnee Tribe Oklahoma
Project stage: Other
ML0630505952006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Shawnee Tribe
Project stage: Other
ML0630505902006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Onondaga Nation - Gonyea
Project stage: Other
ML0630506082006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Mohican Nation
Project stage: Other
ML0630503702006-11-14014 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Shawnee Tribe Oklahoma
Project stage: Other
ML0633302792006-11-15015 November 2006
(Units 1 & 2) Afternoon Public Meeting
Project stage: Meeting
ML0633302812006-11-15015 November 2006
Transcript of Susquehanna Steam Electric Station (Units 1 and 2) Evening Public Meeting on November 15, 2006, Pages 1-46
Project stage: Meeting
ML0632401502006-11-15015 November 2006
11/15/06 Environmental Scoping Meeting Slide Handouts
Project stage: Request
ML0630400752006-11-15015 November 2006
Request for Comments Concerning the Susquehanna Steam Electric Station, Units 1 and 2, License Renewal Application Review. Letter to Tonawanda Band of Seneca
Project stage: Other
2006-10-24
[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]
Category:Request for Additional Information (RAI)
MONTHYEARML23334A1502023-11-30030 November 2023
NRC Request for Additional Information Re. Susquehanna Relief Request RR-02
ML23277A0412023-10-0505 October 2023
Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information
ML23013A2082023-01-13013 January 2023
Request for Additional Information
ML22146A1022022-05-26026 May 2022
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000387/2022404 and 05000388/2022404
ML22146A0742022-05-25025 May 2022
NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request
ML22111A3132022-04-21021 April 2022
NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request
ML22041A1562022-02-10010 February 2022
Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000387/2022013 and 05000388/2022013
ML21316A1242021-11-18018 November 2021
Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications
ML20056E4392020-02-21021 February 2020
Ti 2515/194 Inspection Documentation Request
ML20010D2012020-01-0909 January 2020
Request for Additional Information Related to Request to Allow Application of Framatome Analysis Methodologies Necessary to Support a Planned Transition to Atrium 11 Fuel Under Maximum
ML19319B1922019-11-14014 November 2019
NRR E-mail Capture - RAI for Susquehanna, 1 and 2 License Amendment Request - Replace the Emergency Service Water System and Residual Heat Removal Service Water System
ML19319A0092019-11-14014 November 2019
NRR E-mail Capture - Draft RAI for SSES Units 1 and 2 LAR to Replace ESW Piping
ML19128A0232019-05-0707 May 2019
Request for Additional Information: Susquehanna Steam Electric Station, Units 1 and 2 License Amendment Request for ESW Piping Replacement
ML18352B1832018-12-13013 December 2018
Enclosurequest for Additional Information (Letter to K. Cimorelli Request for Additional Information Regarding Susquehanna Nuclear, Llc'S Decommissioning Funding Plan Update for Susquehanna Steam Electric Station Independent Spent Fuel Stor
ML17180A2002017-07-0707 July 2017
Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits
ML17059D2142017-03-0606 March 2017
Susquehanna Steam Electric Station - Supplemental Information Needed for Acceptance of Requested Licensing Action Re: License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage Frequency Limits
ML16251A0652016-09-0909 September 2016
Susquehanna Steam Electric Station, Unit 2 - RAI Regarding Temporary Change of Unit 2, Technical Specifications 3.7.1 & 3.8.7 to Allow Replacement of Unit 1, 480 Volt Engineered Safeguard System Load Center Transformers(CAC No. MF7298)
ML16245A2052016-09-0101 September 2016
Draft Request for Additional Information Replacement of Load Center Transformers
ML16243A0952016-08-30030 August 2016
Draft Request for Additional Information Application for Approval of Indirect Transfer of Control of Licenses
ML16060A2302016-03-24024 March 2016
Acceptance of Requested Licensing Action License Amendment Request for Temporary Change of Unit 2 Technical Specifications 3.71 and 3.87 to Allow Replacement of Unit 1 480V Ess Load Center Transformers
ML15316A5632015-11-13013 November 2015
Request for Additional Information Regarding Proposed Relief Requests for the Third 10-Year Inservice Inspection Interval(Cac Nos. MF6302 Through MF6307)
ML15292A1782015-10-15015 October 2015
TSTF-425 LAR Draft 3rd RAIs
ML15230A0802015-08-26026 August 2015
Request for Additional Information Regarding License Amendment Request to Adopt NEI 99-01, Revision 6, EAL Scheme Change
ML15209A9742015-08-24024 August 2015
Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425
ML15229A2002015-08-17017 August 2015
E-mail from J. Whited to J. Jennings SSES Draft TSTF-425 RAIs
ML15229A2092015-08-17017 August 2015
SSES Draft Request for Additional Information Licensee Request to Adopt TSTF-425
ML15230A0462015-08-17017 August 2015
Draft RAIs SSES EAL Scheme Change LAR in Accordance with NEI 99-01 Rev 6
ML15183A3502015-07-0202 July 2015
SSES Relief Requests 3RR-19, 3RR-20, and 3RR-21 Draft Identified Information Insufficiencies (TAC Nos. MF6302 Through MF6307)
ML15103A3962015-05-22022 May 2015
Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 (TAC Nos. MF5151 and MF5152)
ML15128A5162015-05-0808 May 2015
SSES Draft Request for Additional Information LAR for Implementation of TSTF-425
ML15128A5092015-05-0808 May 2015
E-mail from J. Whited to D. Filchner SSES Draft Request for Additional Information LAR for Implementation of TSTF-425
ML15008A4702015-01-30030 January 2015
Request for Additional Information Request to Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits.
ML15016A2742015-01-16016 January 2015
Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980)
ML15016A2722015-01-16016 January 2015
E-mail from J. Whited to D. Filchner Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980)
ML14343A9842015-01-0808 January 2015
Request for Additional Information Relief Request 4RR-01
ML14345A2412014-12-16016 December 2014
Request for Additional Information Request for Order Approving Indirect Transfer of Control and Conforming License Amendments
ML14346A1022014-12-12012 December 2014
Draft License Transfer Revised 2nd RAIs
ML14346A4022014-12-12012 December 2014
Draft RAIs Relief Request 4RR-01
ML14346A4012014-12-12012 December 2014
E-mail from J. Whited to D. Filchner Susquehanna Steam Electric Station Draft RAIs Relief Request 4RR-01
ML14346A1002014-12-12012 December 2014
E-mail from J. Whited to R. Sgarro Susquehanna Steam Electric Station Draft License Transfer Revised 2nd RAIs
ML14342A8082014-12-0808 December 2014
E-mail from J. Whited to R. Sgarro (PPL) SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses
ML14342A8132014-12-0808 December 2014
SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses
ML14233A2772014-08-27027 August 2014
Request for Additional Information License Amendment Request to Change the Low Pressure Safety Limit
ML14233A3392014-08-21021 August 2014
Draft RAIs for Susquehanna Steam Electric Station Units 1 and 2 License Amendment Request for Changes to the Low Pressure Safety Limits
ML13298A7582014-03-0707 March 2014
Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage (TAC ME9607 and ME960)
ML13298A7812014-03-0707 March 2014
Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirement 3.8.1.19 to Increase Diesel Generator Minimum Steady State Frequency (TACs ME9609.
ML14013A1502014-01-31031 January 2014
Request for Additional Information Regarding Relief Requests for the Fourth 10-Year Inservice Testing Interval
ML14024A4752014-01-24024 January 2014
Draft 4th IST RRs 1RR05 RAIs
ML13338A4422013-12-19019 December 2013
Request for Additional Information Regarding Relief Requests for the Fourth Ten-Year Inservice Inspection Interval
ML13312A9142013-12-18018 December 2013
Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements 3.5.1.12
2023-11-30
[Table view] |
Text
January 16, 2007 Mr. Britt T. Mckinney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022)
Dear Mr. McKinney:
The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident Mitigation Alternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staffs requests for additional information.
We request that you provide your responses to these questions within 90 days of the date of this letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov.
Sincerely,
/RA/
Alicia Mullins, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
As stated cc w/encl: See next page
January 16, 2007 Mr. Britt T. Mckinney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022)
Dear Mr. McKinney:
The U.S. Nuclear Regulatory Commission staff has reviewed the Severe Accident Mitigation Alternatives analysis submitted by PPL Susquehanna, LLC, in support of its application for license renewal for the Susquehanna Steam Electric Station, and has identified areas where additional information is needed to complete its review. Enclosed are the staffs requests for additional information.
We request that you provide your responses to these questions within 90 days of the date of this letter to support the license renewal review schedule. If you have any questions, please contact me at 301-415-1224 or via email at axm7@nrc.gov.
Sincerely,
/RA/
Alicia Mullins, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: See next page Adams Accession No. ML070030463 OFFICE LA:DLR PM:DLR:REBB PM:DLR:REBB BC:DLR:REBB NAME I. King J.Davis A.Mullins R.Franovich DATE 01/5/07 01/8/07 01/16/07 01/16/07 OFFICIAL RECORD COPY
Letter to B. McKinney from A. Mullins Dated January 16, 2007
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MD3021 AND MD3022)
DISTRIBUTION:
HARD COPY A. Mullins B. Palla E-MAIL P.T. Kuo (RidsNrrDlr)
M. Rubin (RidsNrrDraApla)
R. Franovich (RidsNrrDlrRebb)
E. Benner (RidsNrrDlrReba)
B. Palla PMNS BRidsNrrAdro RidsNrrDlrRebb RidsNrrDlrReba RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsOgcMailRoom RidsOpaMail RidsOcaMailCenter A. Mullins J. Davis S. Lopas R. Schaaf F. Monette (fmonette@anl.gov)
R. Guzman Y. Diaz Sanabria E. Gettys A. Blamey, SRI Region 1 N. Sheehan, OPA Region 1 Samuel Lee, EDO Contact, Region I A. Blamey (ajb3@nrc.gov)
C. Colleli R. K. Wild J. Storch
Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives for the Susquehanna Steam Electric Station, Units 1 and 2
- 1. Provide the following information regarding the Susquehanna Steam Electric Station (SSES)
Probabilistic Risk Assessment (PRA) model used for the Severe Accident Mitigation Alternatives (SAMA) analysis:
- a. Provide a summary of the major Level 1 and 2 PRA versions and their core damage frequency (CDFs) from the Individual Plant Examination (IPE) to the present, including the version reviewed by the Boiling Water Reactor Owners Group (BWROG), and the version used for risk-informed submittals such as inservice inspection and allowed outage time extension for offsite power. Also, indicate the major changes to each version from the prior version (including the changes from pre-Extended Power Uprate (EPU) to post-EPU models) and the major reasons for changes in the CDF.
- b. Provide the freeze date for the incorporation of design and/or procedure changes into the PRA.
- c. Provide the CDF contribution due to station blackout (SBO) and anticipated transient without scram (ATWS).
- d. Explain why loss of an AC bus is a very small (approximately 0.2 percent) contributor to the CDF.
- e. The summary of the BWROG peer review overall assessment provided on pages E.2-14 and -15 describes a non-conservatism associated with SBO events. Identify the facts and observations (F&Os) associated with this non-conservatism and discuss their resolution.
- f. Section E.2.3.2 of the Environmental Report (ER) describes a self assessment that considered the open Level B F&Os and concluded that the remaining items and gaps would not have a significant impact on the EPU application. Confirm that the same conclusion can be drawn concerning the impacts of the remaining items and gaps on the SAMA analysis.
- g. Describe the current containment venting capability and procedural directions at SSES (hard pipe, via standby gas treatment system, etc.) and how it is modeled in the PRA.
- 2. Provide the following information relative to the Level 2 analysis:
- a. Provide a summary description of the current Level 2 model, including: the Level 1/Level 2 interface, the containment event tree (CET), the basis for quantification of CET nodes, the binning process used to assign end states to release categories, and the determination of release fractions for each release category.
ENCLOSURE
- b. Describe the steps taken to ensure the technical adequacy of the Level 2 revisions subsequent to the BWROG peer review.
- 3. Provide the following information with regard to the treatment and inclusion of external events in the SAMA analysis:
- a. The individual plant examination of external events (IPEEE) fire analysis utilized the IPE internal events models to assess system performance. Indicate whether the original IPE models or the revised IPE models were utilized.
- b. Based on a sensitivity study performed by PPL Susquehanna, LLC, the U.S. Nuclear Regulatory Commission concluded in the IPEEE safety evaluation report that the CDF for some fire contributors might be as much as three orders of magnitude higher than the revised values reported in the IPEEE. Discuss this issue and its potential impact on the ER assumption that the fire CDF is about equal to the internal events CDF.
- 4. Provide the following information concerning the MACCS2 analyses:
- a. Clarify whether separate ORIGEN calculations were performed for pre-EPU and post-EPU conditions and used to determine population doses for the respective cases.
- b. Based on the March 31, 2006, license amendment request, the EPU power level would be approximately 13% above the current licensed power level. As such, the population dose for EPU conditions would be expected to be approximately 13% greater than for pre-EPU conditions. However, from Table E.3-4, the increase in dose for the dominant release categories (e.g., L2-1, L2-2, and L2-5) ranges from 4 to 11%. Explain this result.
- 5. Provide the following with regard to the SAMA identification and screening process:
- a. Tables E.5-1 and E.5-2 include a number of events that are described as preventative maintenance actions (i.e., 024-N-E-DSL-P, 024-I-A-DSL-P, and 024-II-B-DSL-P). Identify the specific structure, system, and components associated with these maintenance actions.
- b. Section 5.1.5 includes a list of nine enhancements identified in the IPE. The seventh enhancement, revise guidance regarding reactor vessel control, is listed as not implemented and only provides the reasoning that the enhancement has been determined not to be required for safe operation of the plant. Provide a further description of the disposition of this enhancement, and any efforts made to identify SAMA candidates exist to address the associated risk contributors.
- c. Section E.5.1.7.1 discusses the contribution to fire CDF from the dominant fire zones.
Although two SAMAs from the internal events analysis were identified to address this risk, no SAMAs unique to the fire analysis were identified. For each fire zone, discuss the potential for SAMAs to address the unique cause of the fire risk, such as SAMAs to reduce the fire initiators, to improve fire detection or suppression, or to relocate components or cabling.
- 6. Provide the following with regard to the Phase 2 cost-benefit evaluations:
- a. For SAMA 3, Proceduralize Reactor Pressure Valve Depressurization When Fire Protection System Injection is the Only Makeup Source, indicate what failure events were included for the failure to provide late low pressure injection via the fire main.
- b. For SAMA 8, Automatic Feedwater Runback for ATWS, the percent reduction in dose risk and offsite economic cost risk (OECR) is much smaller than the reduction in CDF.
The reduction in CDF is almost entirely in the low/early release category, which has a very small contribution to dose-risk and OECR. One might expect the reduction in CDF due to ATWS to impact high or medium release categories. Explain this apparent discrepancy.
- c. In the discussion of the costs for SAMA 8, it is implied that the cost estimate does not account for inflation. Clarify whether this cost estimate, or any other cost estimates, accounts for inflation.
- d. For SAMA 12, Containment Venting After Core Damage, the analysis shows very little risk reduction. Since this SAMA would reduce the releases for all drywell overpressure failure sequences, a more significant reduction in risk would be expected. Explain the reasons for the small risk reduction for this SAMA.
- 7. One of the Mark I plants considered in its SAMA identification process (Section E.5.1.4) identified the following SAMAs as potentially cost-beneficial:
- a. Develop guidance/procedures for local, manual control of reactor core isolation cooling following loss of DC power.
- b. Procedures to control containment venting to avoid adverse impacts on emergency core cooling system.
These SAMAs would appear to be applicable to SSES but are not among the Phase 2 SAMAs for SSES. Provide a brief statement regarding the applicability/feasibility of these alternatives for SSES, and a further evaluation (similar to those evaluations provided in the ER) if the alternative could be potentially cost-beneficial at SSES.
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Robert A. Saccone Luis A. Ramos Vice President - Nuclear Operations Community Relations Manager, PPL Susquehanna, LLC Susquehanna 769 Salem Blvd., NUCSB3 PPL Susquehanna, LLC Berwick, PA 18603-0467 634 Salem Blvd., SSO Berwick, PA 18603-0467 Aloysius J. Wrape, III General Manager - Performance Bryan A. Snapp, Esq.
Improvement and Oversight Associate General Counsel PPL Susquehanna, LLC PPL Services Corporation Two North Ninth Street, GENPL4 Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 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
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803 Mr. James Ross Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, D.C. 20006-3708
