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| | number = ML071020298 | | | number = ML071020298 |
| | issue date = 04/12/2007 | | | issue date = 04/12/2007 |
| | title = Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Health Physics Technical Review (TAC Nos. MD3309 and MD3310) | | | title = Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Health Physics Technical Review |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 |
| | addressee name = McKinney B T | | | addressee name = Mckinney B |
| | addressee affiliation = PPL Susquehanna, LLC | | | addressee affiliation = PPL Susquehanna, LLC |
| | docket = 05000387, 05000388 | | | docket = 05000387, 05000388 |
| | license number = NPF-012, NPF-022 | | | license number = NPF-012, NPF-022 |
| | contact person = Guzman R V, NRR/DORL, 415-1030 | | | contact person = Guzman R, NRR/DORL, 415-1030 |
| | case reference number = TAC MD3309, TAC MD3310 | | | case reference number = TAC MD3309, TAC MD3310 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:April 12, 2007Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 | | {{#Wiki_filter:April 12, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAMELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310) | | REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310) |
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| ==Dear Mr. McKinney:== | | ==Dear Mr. McKinney:== |
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| In reviewing your letter dated October 11, 2006, concerning the request to increase themaximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007.If you have any questions, please contact me at 301-415-1030.Sincerely,/RA/Richard V. Guzman, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388 | | In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007. |
| | If you have any questions, please contact me at 301-415-1030. |
| | Sincerely, |
| | /RA/ |
| | Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAIcc w/encl: See next page April 12, 2007Mr. Britt T. McKinneySr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
| | RAI cc w/encl: See next page |
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| | April 12, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAMELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310) | | REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310) |
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| ==Dear Mr. McKinney:== | | ==Dear Mr. McKinney:== |
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| In reviewing your letter dated October 11, 2006, concerning the request to increase themaximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007.If you have any questions, please contact me at 301-415-1030.Sincerely,/RA/Richard V. Guzman, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388 | | In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007. |
| | If you have any questions, please contact me at 301-415-1030. |
| | Sincerely, |
| | /RA/ |
| | Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAIcc w/encl: See next pageDISTRIBUTION
| | RAI cc w/encl: See next page DISTRIBUTION: |
| :PublicRidsOgcMailCenterRidsNrrPmRGuzmanRidsNrrIhpbBCCHinson LPLI-1 R/FRidsNrrDorlLpl1-1RidsAcrsAcnwMailCenterRidsNrrLaSLittleJQuichochoAccession Number:
| | Public RidsOgcMailCenter RidsNrrPmRGuzman RidsNrrIhpbBC CHinson LPLI-1 R/F RidsNrrDorlLpl1-1 RidsAcrsAcnwMailCenter RidsNrrLaSLittle JQuichocho Accession Number: |
| * RAI provided by memo. No substantive changes made.OFFICENRR/LPLI-1/PMNRR/LPLI-1/LANRR/IHPB/BCNRR/LPLI-1/BC(A)NAMERGuzmanSLittleTFrye*DPickett DATE4/12/074/12/073/13/074/12/07OFFICIAL RECORD COPY EnclosureREQUEST FOR ADDITIONAL INFORMATIONRELATING TO THEAPPLICATION FOR EXTENDED POWER UPRATE (EPU)SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2)PPL SUSQUEHANNA, LLCDOCKET NOS. 50-387 AND 50-388The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPLSusquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2. | | * RAI provided by memo. No substantive changes made. |
| The NRC staff has determined that additional information requested below will be needed to complete its review. 1.Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the fission products in the steam and in the reactor water (resulting from the proposed constant pressure power uprate (CPPU) is expected to be small and would be bounded by the current licensed thermal power (CLTP) design-basis values. Provide the expected percentage increase in the fission products in the steam and in the reactor water for the proposed CPPU at SSES 1 and 2.2.Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the activated corrosion product (ACP) production in the coolant (resulting from the proposed CPPU) is expected to be negligible. Section 8.5 (page 8-6) of your submittal states that non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase. Describe why the increase in ACPs in the coolant is expected to be negligible while the non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase. 3.Section 8.5 (page 8-6) of your submittal states that the Nitrogen-16 (N-16) dose rates from main steam lines and related equipment may increase up to 20% due to the combined effects of increased activation rates and reduced transit decay times. Verify that the expected increase in dose rates from N-16 does not create new radiation, or high radiation areas around condensate bearing systems/components in the turbine building. 4.Section 8.5 (page 8-7) of your submittal states that the CPPU may result in localized hotspots in areas outside feedwater heater rooms and near drywell penetrations. Provide more detailed information on the expected pre- and post-CPPU dose rates in these areas and describe what controls/changes will be implemented to maintain worker doses as low as is reasonably achievable (ALARA) and within the occupational dose limits of Title 10 of the Code of Federal Regulations (10 CFR) Part 20. 5.Section 8.5 (page 8-7) of your submittal states that radiation surveys of selected areas will be conducted as part of the CPPU startup and test plan to identify areas that may require changes in radiation shielding or zone designation. Provide a listing of these selected areas where you will conduct radiation surveys following the proposed CPPU implementation and describe your criteria for selecting these areas.6.Section 8.5 (page 8-7) of your submittal lists several strategies to control shutdown doserates. On the basis of experience gained from other boiling-water reactors (BWRs) which have implemented power uprates of similar magnitude to the one planned at SSES 1 and 2, and in light of the various strategies that you use to control shutdown dose rates at SSES 1 and 2, describe what impact you expect the proposed power uprate will have on the annual collective doses at SSES 1 and 2. Provide an estimate of the occupational dose that will result from the plant modifications that will be needed to support the implementation of the proposed power uprate.7.Explain the rational behind applying a scaling factor of 1.5 to the vital area CLTP doses to account for CPPU changes in power level (Section 8.5, page 8-8 and Table 8-1).8.Section 8.6 (page 8-9) of your submittal states that the highest estimated dose to a critical offsite location due to radiation shine from turbine building components for CPPU is approximately 4 milli-roentgen equivalent man (mrem) per year. Provide your basis for this estimate and provide your reasoning why a 500% increase in N-16 steam activity (resulting from implementation of hydrogen water chemistry at SSES 1 and 2) would not result in any increase in this estimated dose.9.Discuss any effects that the storage of the higher irradiated (due to the increased core flux) spent fuel assemblies in the spent fuel pool (SFP) may have on dose rates in accessible areas adjacent to the sides or bottom of the SFP. Discuss any plans that you may have (such as shuffling of spent fuel assemblies in the SFP so that the older assemblies are located at the perimeter of the SFP) to minimize the effects of the storage of the higher irradiated spent fuel assemblies in the SFP on dose rates in areas surrounding the SFP.10.For the each of the four vital areas listed under "Vital Missions" in Table 8-1, provide the estimated vital area post-accident dose rates which were used to determine the vital area mission dose. Provide mark-ups of plant layout maps showing the access routes to all vital areas listed in Table 8-1.11.Section 8.6 of your submittal states that the transport and storage of radioactive materials pathway is the major source of offsite dose, contributing approximately 12.2 mrem of the estimated 13.6 mrem/year to the limiting dose receptor location subject to the limits of 40 CFR 190 (25 mrem/year from effluents and external shine). | | OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/IHPB/BC NRR/LPLI-1/BC(A) |
| | NAME RGuzman SLittle TFrye* DPickett DATE 4/12/07 4/12/07 3/13/07 4/12/07 OFFICIAL RECORD COPY |
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| | REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU) |
| | SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) |
| | PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2. |
| | The NRC staff has determined that additional information requested below will be needed to complete its review. |
| | : 1. Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the fission products in the steam and in the reactor water (resulting from the proposed constant pressure power uprate (CPPU) is expected to be small and would be bounded by the current licensed thermal power (CLTP) design-basis values. Provide the expected percentage increase in the fission products in the steam and in the reactor water for the proposed CPPU at SSES 1 and 2. |
| | : 2. Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the activated corrosion product (ACP) production in the coolant (resulting from the proposed CPPU) is expected to be negligible. Section 8.5 (page 8-6) of your submittal states that non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase. Describe why the increase in ACPs in the coolant is expected to be negligible while the non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase. |
| | : 3. Section 8.5 (page 8-6) of your submittal states that the Nitrogen-16 (N-16) dose rates from main steam lines and related equipment may increase up to 20% due to the combined effects of increased activation rates and reduced transit decay times. Verify that the expected increase in dose rates from N-16 does not create new radiation, or high radiation areas around condensate bearing systems/components in the turbine building. |
| | : 4. Section 8.5 (page 8-7) of your submittal states that the CPPU may result in localized hot spots in areas outside feedwater heater rooms and near drywell penetrations. Provide more detailed information on the expected pre- and post-CPPU dose rates in these areas and describe what controls/changes will be implemented to maintain worker doses as low as is reasonably achievable (ALARA) and within the occupational dose limits of Title 10 of the Code of Federal Regulations (10 CFR) Part 20. |
| | Enclosure |
| | : 5. Section 8.5 (page 8-7) of your submittal states that radiation surveys of selected areas will be conducted as part of the CPPU startup and test plan to identify areas that may require changes in radiation shielding or zone designation. Provide a listing of these selected areas where you will conduct radiation surveys following the proposed CPPU implementation and describe your criteria for selecting these areas. |
| | : 6. Section 8.5 (page 8-7) of your submittal lists several strategies to control shutdown dose rates. On the basis of experience gained from other boiling-water reactors (BWRs) which have implemented power uprates of similar magnitude to the one planned at SSES 1 and 2, and in light of the various strategies that you use to control shutdown dose rates at SSES 1 and 2, describe what impact you expect the proposed power uprate will have on the annual collective doses at SSES 1 and 2. Provide an estimate of the occupational dose that will result from the plant modifications that will be needed to support the implementation of the proposed power uprate. |
| | : 7. Explain the rational behind applying a scaling factor of 1.5 to the vital area CLTP doses to account for CPPU changes in power level (Section 8.5, page 8-8 and Table 8-1). |
| | : 8. Section 8.6 (page 8-9) of your submittal states that the highest estimated dose to a critical offsite location due to radiation shine from turbine building components for CPPU is approximately 4 milli-roentgen equivalent man (mrem) per year. Provide your basis for this estimate and provide your reasoning why a 500% increase in N-16 steam activity (resulting from implementation of hydrogen water chemistry at SSES 1 and 2) would not result in any increase in this estimated dose. |
| | : 9. Discuss any effects that the storage of the higher irradiated (due to the increased core flux) spent fuel assemblies in the spent fuel pool (SFP) may have on dose rates in accessible areas adjacent to the sides or bottom of the SFP. Discuss any plans that you may have (such as shuffling of spent fuel assemblies in the SFP so that the older assemblies are located at the perimeter of the SFP) to minimize the effects of the storage of the higher irradiated spent fuel assemblies in the SFP on dose rates in areas surrounding the SFP. |
| | : 10. For the each of the four vital areas listed under Vital Missions in Table 8-1, provide the estimated vital area post-accident dose rates which were used to determine the vital area mission dose. Provide mark-ups of plant layout maps showing the access routes to all vital areas listed in Table 8-1. |
| | : 11. Section 8.6 of your submittal states that the transport and storage of radioactive materials pathway is the major source of offsite dose, contributing approximately 12.2 mrem of the estimated 13.6 mrem/year to the limiting dose receptor location subject to the limits of 40 CFR 190 (25 mrem/year from effluents and external shine). |
| Provide a breakdown for the estimated dose contributions from the other dose pathways (liquid radioactive effluents, gaseous radioactive effluents, and gamma radiation shine from the plant turbines) that make up this 13.6 mrem/year estimate. | | Provide a breakdown for the estimated dose contributions from the other dose pathways (liquid radioactive effluents, gaseous radioactive effluents, and gamma radiation shine from the plant turbines) that make up this 13.6 mrem/year estimate. |
| Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:Robert A. SacconeVice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467Terry L. HarpsterGeneral Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Rocco R. SgarroManager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Supervisor -Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Michael H. CrowthersSupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Steven M. CookManager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467Luis A. RamosCommunity Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467Bryan A. Snapp, EsqAssoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179Supervisor - Document Control ServicesPPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Richard W. OsborneAllegheny Electric Cooperative, Inc.
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| 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
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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, Unit Nos. 1 and 2 cc: |
| | Robert A. Saccone Bryan A. Snapp, Esq Vice President - Nuclear Operations Assoc. 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 Supervisor - Pennsylvania Department of Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC Rachel Carson State Office Building 769 Salem Blvd., NUCSA4 P.O. Box 8469 Berwick, PA 18603-0467 Harrisburg, PA 17105-8469 Michael H. Crowthers Senior Resident Inspector Supervising Engineer U.S. Nuclear Regulatory Commission Nuclear Regulatory Affairs P.O. Box 35, NUCSA4 PPL Susquehanna, LLC Berwick, PA 18603-0035 Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Steven M. Cook 475 Allendale Road Manager - Quality Assurance King of Prussia, PA 19406 PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Board of Supervisors Berwick, PA 18603-0467 Salem Township P.O. Box 405 Luis A. Ramos Berwick, PA 18603-0035 Community Relations Manager, Susquehanna Dr. Judith Johnsrud PPL Susquehanna, LLC National Energy Committee 634 Salem Blvd., SSO Sierra Club Berwick, PA 18603-0467 443 Orlando Avenue State College, PA 16803}} |
Letter Sequence RAI |
|---|
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML071620334, ML073320383, ML073390289, ML073390306, ML081000038, PLA-6187, Response for Additional Information Requested in Regard to Proposed License Amendment No. 285, Constant Pressure Power Uprate Environmental, PLA-6255, Proposed License Amendments 285 and 253, Constant Pressure Power Uprate Application Regarding Steam Dryer Flow Effects Verbal and Confirmatory Requests for Additional Information Responses, PLA-6266, Proposed License Amendment No. 285 for Unit 1, License No. NPF-14 & Proposed License Amendment No. 253 for Unit 2, License No. NPF-22, Extended Power Uprate Application Regarding Change to Technical Specification SR 3.7.1 - RHRSW and UHS, PLA-6370, License Renewal Application, Amendment to Section 4.2.2, PLA-6633, Providing Notice That the License Conditions 2.C.(36)(a)3, 2.C.(36(b)7 & 2.C.(36)(f) Have Been Met, PLA-6876, Th Rio Steam Dryer Visual Inspection Report, PLA-7047, Th Rio Steam Dryer Visual Inspection Report
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MONTHYEARML0716203342006-01-24024 January 2006
GE Ne 0000-0038-8052 Susq-EPU-T506-MSLHiFlo-Calc-2006, Revision 0, Instrument Limits Calculation, PPL Susquehanna, LLC Susquehanna Steam Electric Station Units 1 and 2, Main Steam Line High Flow MSIV Isolation.
Project stage: Other
ML0632500922006-11-21021 November 2006
Extended Power Uprate Acceptance Review
Project stage: Acceptance Review
PLA-6138, Proposed License Amendments 285 & 253, Constant Pressure Power Uprate - Supplement2006-12-0404 December 2006
Proposed License Amendments 285 & 253, Constant Pressure Power Uprate - Supplement
Project stage: Supplement
ML0710400302006-12-12012 December 2006
Pennsylvania Fish and Boat Commission Threatened and Endangered Species
Project stage: Request
PLA-6146, Proposed License Amendment No. 285 for Unit 1 Operating License No. NPF-14 and Proposed License Amendment No. 253 for Unit 2 Operating License No. NPF-22 Re Constant Pressure Power Uprate -Supplement2006-12-26026 December 2006
Proposed License Amendment No. 285 for Unit 1 Operating License No. NPF-14 and Proposed License Amendment No. 253 for Unit 2 Operating License No. NPF-22 Re Constant Pressure Power Uprate -Supplement
Project stage: Supplement
ML0700800322007-01-0505 January 2007
Extended Power Uprate (EPU) Acceptance Review Results
Project stage: Acceptance Review
ML0703201532007-02-0808 February 2007
PPL Susquehanna, LLC - Request for Withholding of Proprietary Information from Public Disclosure for Susquehanna Steam Electric Station, Units 1 and 2
Project stage: Withholding Request Acceptance
ML0703201762007-02-0808 February 2007
PPL Susquehanna, LLC - Request for Withholding of Proprietary Information from Public Disclosure for Susquehanna Steam Electric Station, Units 1 and 2
Project stage: Withholding Request Acceptance
PLA-6155, Proposed License Amendment Nos. 285 and 253, Constant Pressure Power Uprate Supplement2007-02-13013 February 2007
Proposed License Amendment Nos. 285 and 253, Constant Pressure Power Uprate Supplement
Project stage: Supplement
ML0704301392007-03-0101 March 2007
PPL Susquehanna, LLC-Request for Withholding Information from Public Disclosure for Susquehanna Steam Electric Station, Units 1 and 2 (TAC Nos. MD3309 and MD3310)
Project stage: Withholding Request Acceptance
PLA-6163, Proposed License Amendment Re Constant Pressure Power Uprate - Supplement2007-03-14014 March 2007
Proposed License Amendment Re Constant Pressure Power Uprate - Supplement
Project stage: Supplement
ML0707304972007-03-15015 March 2007
Request for Additional Information - Extended Power Uprated Application Regarding Turbine Generator Review
Project stage: RAI
ML0707303892007-03-19019 March 2007
Request for Additional Information (RAI) - Susquehanna, Units 1 and 2 - Extended Power Uprate Application
Project stage: RAI
ML0707305682007-03-20020 March 2007
(SSES 1 and 2), Request for Additional Information (RAI) - Extended Power Uprate Application Regarding Steam Dryer and Flow Effects
Project stage: RAI
PLA-6172, Proposed License Amendment for Constant Pressure Power Uprate - Supplement PLA-61722007-03-22022 March 2007
Proposed License Amendment for Constant Pressure Power Uprate - Supplement PLA-6172
Project stage: Supplement
ML0708608662007-03-29029 March 2007
RAI, Extended Power Uprate Application; Vessels and Internals Technical Review (TAC Nos. MD3309 and Md3310)
Project stage: RAI
ML0710001412007-04-10010 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Piping and Nondestructive Examination Technical Review
Project stage: RAI
ML0710001262007-04-12012 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Operator Licensing and Human Performance Technical Review (TAC Nos. MD3309 and MD3310)
Project stage: RAI
ML0710300402007-04-12012 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Electrical Engineering Technical Review (TAC Nos. MD3309 and MD3310)
Project stage: RAI
ML0710300312007-04-12012 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Materials and Chemical Engineering Technical Review
Project stage: RAI
ML0710202982007-04-12012 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Health Physics Technical Review
Project stage: RAI
ML0710400322007-04-12012 April 2007
Pennsylvania Fish and Boat Commission Threatened and Endangered Species
Project stage: Request
ML0710400252007-04-12012 April 2007
Pennsylvania Efacts
Project stage: Request
ML0710400222007-04-12012 April 2007
PA Dcnr Wild Resource Conservation Program - Regal Fritillary
Project stage: Request
ML0710400262007-04-12012 April 2007
EPA Envirofacts
Project stage: Request
PLA-6174, Constant Pressure Power Uprate - PLA-61742007-04-13013 April 2007
Constant Pressure Power Uprate - PLA-6174
Project stage: Request
ML0710203152007-04-16016 April 2007
(SSES 1 and 2), Request for Additional Information (Rai), - Extended Power Uprate Application Balance-of-Plant Physics Technical Review
Project stage: RAI
ML0710601352007-04-18018 April 2007
Request for Additional Information, Extended Power Uprate Application Safety-Related Pumps and Valves and Mechanical Equipment Environmental Qualification
Project stage: RAI
PLA-6187, Response for Additional Information Requested in Regard to Proposed License Amendment No. 285, Constant Pressure Power Uprate Environmental2007-04-23023 April 2007
Response for Additional Information Requested in Regard to Proposed License Amendment No. 285, Constant Pressure Power Uprate Environmental
Project stage: Other
PLA-6186, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Extended Power Uprate Application Vessels and Internals Technical Review Request for Additional Information Responses2007-04-26026 April 2007
Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Extended Power Uprate Application Vessels and Internals Technical Review Request for Additional Information Responses
Project stage: Request
ML0711600672007-04-27027 April 2007
Request for Additional Information (RAI) Extended Power Uprate Application Probabilistic Risk Assessment Licensing Review
Project stage: RAI
ML0711504712007-04-27027 April 2007
Request for Additional Information (Rai), Extended Power Uprate Application Containment and Ventilation Technical Review
Project stage: RAI
ML0711403432007-04-27027 April 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2) - Extended Power Uprate Application Instrumentation and Controls Technical Review
Project stage: RAI
ML0711604062007-04-30030 April 2007
Request for Additional Information (Rai), Extended Power Uprate Application Vessels and Internals Integrity Technical Review
Project stage: RAI
ML0710900722007-04-30030 April 2007
Request for Additional Information (Rai), Extended Power Uprate Application Mechanical and Civil Engineering Technical Review
Project stage: RAI
PLA-6191, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Piping and Nondestructive Examination Technical Review Request for Additional Information Responses2007-05-0303 May 2007
Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Piping and Nondestructive Examination Technical Review Request for Additional Information Responses
Project stage: Request
PLA-6194, Proposed License Amendments 285 and 253, Extended Power Uprate Application Health Physics Technical Review, Request for Additional Information Responses2007-05-0909 May 2007
Proposed License Amendments 285 and 253, Extended Power Uprate Application Health Physics Technical Review, Request for Additional Information Responses
Project stage: Request
PLA-6195, Extended Power Uprate Application Electrical Engineering Technical Review Request for Additional Information Responses2007-05-0909 May 2007
Extended Power Uprate Application Electrical Engineering Technical Review Request for Additional Information Responses
Project stage: Request
ML0712906522007-05-14014 May 2007
Request for Additional Information (RAI) - Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2) - Extended Power Uprate Application Reactor Systems Technical Review
Project stage: RAI
PLA-6198, Proposed License Amendments 285 and 253, Extended Power Uprate Application Balance-of-Plant Safety Systems Request for Additional Information Responses2007-05-14014 May 2007
Proposed License Amendments 285 and 253, Extended Power Uprate Application Balance-of-Plant Safety Systems Request for Additional Information Responses
Project stage: Request
PLA-6210, Extended Power Uprate Application Vessels and Internals Integrity Technical Review Request for Additional Information Responses2007-05-21021 May 2007
Extended Power Uprate Application Vessels and Internals Integrity Technical Review Request for Additional Information Responses
Project stage: Request
PLA-6196, Proposed License Amendments 285 and 253, Extended Power Uprate Application Safety Related Pumps and Valves and Mechanical Equipment Environmental Qualification Review Request for Additional Information Responses2007-06-0101 June 2007
Proposed License Amendments 285 and 253, Extended Power Uprate Application Safety Related Pumps and Valves and Mechanical Equipment Environmental Qualification Review Request for Additional Information Responses
Project stage: Request
PLA-6200, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Mechanical and Civil Engineering Technical Review Request for Additional Information Responses2007-06-0101 June 2007
Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Mechanical and Civil Engineering Technical Review Request for Additional Information Responses
Project stage: Request
PLA-6204, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Instrumentation and Controls Technical Review Request for Additional Information Responses2007-06-0101 June 2007
Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Instrumentation and Controls Technical Review Request for Additional Information Responses
Project stage: Request
PLA-6212, Extended Power Uprate Application Materials and Chemical Engineering Technical Review Request for Additional Information Responses2007-06-0101 June 2007
Extended Power Uprate Application Materials and Chemical Engineering Technical Review Request for Additional Information Responses
Project stage: Request
PLA-6203, Proposed License Amendment Extended Power Uprate Application Containment and Ventilation Technical Review Request for Additional Information Responses, PLA-62032007-06-0404 June 2007
Proposed License Amendment Extended Power Uprate Application Containment and Ventilation Technical Review Request for Additional Information Responses, PLA-6203
Project stage: Request
PLA-6225, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Supplement to Request for Additional Information Responses2007-06-0808 June 2007
Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Supplement to Request for Additional Information Responses
Project stage: Supplement
PLA-6231, Proposed License Amendment No. 285 for Unit 1 and Proposed License Amendment No. 253 for Unit 2, Extended Power Uprate Application Electrical Engineering Technical Review Request for Additional Information Response Supplement, PLA-62312007-06-20020 June 2007
Proposed License Amendment No. 285 for Unit 1 and Proposed License Amendment No. 253 for Unit 2, Extended Power Uprate Application Electrical Engineering Technical Review Request for Additional Information Response Supplement, PLA-6231
Project stage: Supplement
PLA-6230, Proposed License Amendment for Units 1 and 2, Extended Power Uprate Application & Supplement to Request for Additional Information Responses2007-06-27027 June 2007
Proposed License Amendment for Units 1 and 2, Extended Power Uprate Application & Supplement to Request for Additional Information Responses
Project stage: Supplement
PLA-6232, Proposed License Amendments 285 & 253, Extended Power Uprate Application Supplement to Operator Licensing & Human Performance, Health Physics & Piping and Nondestructive Examination Request for Additional Information Responses2007-06-27027 June 2007
Proposed License Amendments 285 & 253, Extended Power Uprate Application Supplement to Operator Licensing & Human Performance, Health Physics & Piping and Nondestructive Examination Request for Additional Information Responses
Project stage: Supplement
2007-04-12
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000387/20245012024-11-13013 November 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000387/2024501 and 05000388/2024501
IR 05000387/20240102024-11-13013 November 2024
Biennial Problem Identification and Resolution Inspection Report 05000387/2024010 and 05000388/2024010
IR 05000387/20240032024-11-12012 November 2024
Integrated Inspection Report 05000387/2024003 and 05000388/2024003
PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-81352024-11-0101 November 2024
Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135
ML24289A1252024-10-22022 October 2024
– Authorized Alternative to Requirements of the ASME OM Code
PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024
Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145
ML24291A1562024-10-16016 October 2024
Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645
PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024
Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310
PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024
Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141
PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024
Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142
ML24260A2312024-09-17017 September 2024
Senior Reactor and Reactor Operator Initial License Examinations
05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024
B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
ML24233A2192024-09-0303 September 2024
– Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
IR 05000387/20240052024-08-29029 August 2024
Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005)
05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024
Manual Reactor Scram Due to Degraded Main Condenser Vacuum
05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024
Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear
IR 05000387/20240022024-08-12012 August 2024
Integrated Inspection Report 05000387/2024002 and 05000388/2024002
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024
23rd Refueling Outage Owners Activity Report (PLA-8117)
ML24197A0982024-07-15015 July 2024
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010
ML24127A2262024-05-29029 May 2024
Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563
PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024
Response to Request for Confirmation of Information Regarding Relief Request 1RR06
PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024
Annual Radiological Environmental Operating Report (PLA-8122)
PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024
Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)
05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024
Main Steam Isolation Valve Leakage
IR 05000387/20240012024-05-13013 May 2024
Integrated Inspection Report 05000387/2024001 and 05000388/2024001
IR 05000387/20244042024-05-0707 May 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404
PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024
Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094
PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024
2023 Annual Radiological Environmental Operating Report (PLA-8095)
PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024
Re 2023 Annual Report of Radiation Exposure
ML24082A1372024-04-22022 April 2024
Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes
PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024
Annual Environmental Operating Report (Nonradiological) PLA-8102
PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024
Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)
PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024
Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112
PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024
Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)
PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024
Property Insurance Program (PLA-8100)
PLA-8098, Annual Financial Report (PLA-8098)2024-04-0101 April 2024
Annual Financial Report (PLA-8098)
PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024
Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)
PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024
Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance
ML24067A2512024-03-19019 March 2024
Authorized Alternative to Requirements of the ASME Code
ML24044A2532024-03-14014 March 2024
Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting))
IR 05000387/20240112024-02-29029 February 2024
Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011
IR 05000387/20230062024-02-28028 February 2024
Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006)
ML24039A1882024-02-27027 February 2024
Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods
ML24037A3072024-02-22022 February 2024
Summary of Regulatory Audit in Support of Relief Request 5RR-02
PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024
Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)
IR 05000387/20230042024-02-0707 February 2024
Integrated Inspection Report 05000387/2023004 and 05000388/2023004
05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024
Manual Reactor Scram Due to Degraded Main Condenser Vacuum
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24150A3362024-05-29029 May 2024
Request for Confirmation of Information Relief Request 1RR06 (Proposed Alternative) Susquehanna Nuclear, LLC Susquehanna Steam Electric Station (Susquehanna), Unit 1 Docket No. 50-387
IR 05000387/20244042024-05-0707 May 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404
ML24102A1252024-04-10010 April 2024
Request for Additional Information for Susquehanna, Unit 1 Alternative Request 4RR-11
ML23334A1502023-11-30030 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
IR 05000387/20224042022-05-26026 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
IR 05000387/20220132022-02-10010 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
ML19319A0092019-11-14014 November 2019
NRR E-mail Capture - Draft RAI for SSES Units 1 and 2 LAR to Replace ESW Piping
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
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
ML15230A0462015-08-17017 August 2015
Draft RAIs SSES EAL Scheme Change LAR in Accordance with NEI 99-01 Rev 6
ML15229A2092015-08-17017 August 2015
SSES Draft Request for Additional Information Licensee Request to Adopt TSTF-425
ML15229A2002015-08-17017 August 2015
E-mail from J. Whited to J. Jennings SSES Draft TSTF-425 RAIs
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)
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
ML15128A5162015-05-0808 May 2015
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
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
ML14346A1022014-12-12012 December 2014
Draft License Transfer Revised 2nd RAIs
ML14346A1002014-12-12012 December 2014
E-mail from J. Whited to R. Sgarro Susquehanna Steam Electric Station Draft License Transfer Revised 2nd RAIs
ML14342A8132014-12-0808 December 2014
SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses
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
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
2024-05-07
[Table view] |
Text
April 12, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310)
Dear Mr. McKinney:
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
RAI cc w/encl: See next page
April 12, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: HEALTH PHYSICS TECHNICAL REVIEW (TAC NOS. MD3309 AND MD3310)
Dear Mr. McKinney:
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 5, 2007. As agreed to by your staff, we request you respond by May 9, 2007.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
Public RidsOgcMailCenter RidsNrrPmRGuzman RidsNrrIhpbBC CHinson LPLI-1 R/F RidsNrrDorlLpl1-1 RidsAcrsAcnwMailCenter RidsNrrLaSLittle JQuichocho Accession Number:
- RAI provided by memo. No substantive changes made.
OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/IHPB/BC NRR/LPLI-1/BC(A)
NAME RGuzman SLittle TFrye* DPickett DATE 4/12/07 4/12/07 3/13/07 4/12/07 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU)
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2)
PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2.
The NRC staff has determined that additional information requested below will be needed to complete its review.
- 1. Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the fission products in the steam and in the reactor water (resulting from the proposed constant pressure power uprate (CPPU) is expected to be small and would be bounded by the current licensed thermal power (CLTP) design-basis values. Provide the expected percentage increase in the fission products in the steam and in the reactor water for the proposed CPPU at SSES 1 and 2.
- 2. Section 8.4.2 (page 8-5) of your submittal states that the magnitude of any increase in the activated corrosion product (ACP) production in the coolant (resulting from the proposed CPPU) is expected to be negligible. Section 8.5 (page 8-6) of your submittal states that non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase. Describe why the increase in ACPs in the coolant is expected to be negligible while the non-coolant activation (corrosion) products are expected to increase in proportion to the thermal power increase.
- 3. Section 8.5 (page 8-6) of your submittal states that the Nitrogen-16 (N-16) dose rates from main steam lines and related equipment may increase up to 20% due to the combined effects of increased activation rates and reduced transit decay times. Verify that the expected increase in dose rates from N-16 does not create new radiation, or high radiation areas around condensate bearing systems/components in the turbine building.
- 4. Section 8.5 (page 8-7) of your submittal states that the CPPU may result in localized hot spots in areas outside feedwater heater rooms and near drywell penetrations. Provide more detailed information on the expected pre- and post-CPPU dose rates in these areas and describe what controls/changes will be implemented to maintain worker doses as low as is reasonably achievable (ALARA) and within the occupational dose limits of Title 10 of the Code of Federal Regulations (10 CFR) Part 20.
Enclosure
- 5. Section 8.5 (page 8-7) of your submittal states that radiation surveys of selected areas will be conducted as part of the CPPU startup and test plan to identify areas that may require changes in radiation shielding or zone designation. Provide a listing of these selected areas where you will conduct radiation surveys following the proposed CPPU implementation and describe your criteria for selecting these areas.
- 6. Section 8.5 (page 8-7) of your submittal lists several strategies to control shutdown dose rates. On the basis of experience gained from other boiling-water reactors (BWRs) which have implemented power uprates of similar magnitude to the one planned at SSES 1 and 2, and in light of the various strategies that you use to control shutdown dose rates at SSES 1 and 2, describe what impact you expect the proposed power uprate will have on the annual collective doses at SSES 1 and 2. Provide an estimate of the occupational dose that will result from the plant modifications that will be needed to support the implementation of the proposed power uprate.
- 7. Explain the rational behind applying a scaling factor of 1.5 to the vital area CLTP doses to account for CPPU changes in power level (Section 8.5, page 8-8 and Table 8-1).
- 8. Section 8.6 (page 8-9) of your submittal states that the highest estimated dose to a critical offsite location due to radiation shine from turbine building components for CPPU is approximately 4 milli-roentgen equivalent man (mrem) per year. Provide your basis for this estimate and provide your reasoning why a 500% increase in N-16 steam activity (resulting from implementation of hydrogen water chemistry at SSES 1 and 2) would not result in any increase in this estimated dose.
- 9. Discuss any effects that the storage of the higher irradiated (due to the increased core flux) spent fuel assemblies in the spent fuel pool (SFP) may have on dose rates in accessible areas adjacent to the sides or bottom of the SFP. Discuss any plans that you may have (such as shuffling of spent fuel assemblies in the SFP so that the older assemblies are located at the perimeter of the SFP) to minimize the effects of the storage of the higher irradiated spent fuel assemblies in the SFP on dose rates in areas surrounding the SFP.
- 10. For the each of the four vital areas listed under Vital Missions in Table 8-1, provide the estimated vital area post-accident dose rates which were used to determine the vital area mission dose. Provide mark-ups of plant layout maps showing the access routes to all vital areas listed in Table 8-1.
- 11. Section 8.6 of your submittal states that the transport and storage of radioactive materials pathway is the major source of offsite dose, contributing approximately 12.2 mrem of the estimated 13.6 mrem/year to the limiting dose receptor location subject to the limits of 40 CFR 190 (25 mrem/year from effluents and external shine).
Provide a breakdown for the estimated dose contributions from the other dose pathways (liquid radioactive effluents, gaseous radioactive effluents, and gamma radiation shine from the plant turbines) that make up this 13.6 mrem/year estimate.
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Robert A. Saccone Bryan A. Snapp, Esq Vice President - Nuclear Operations Assoc. 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 Supervisor - Pennsylvania Department of Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC Rachel Carson State Office Building 769 Salem Blvd., NUCSA4 P.O. Box 8469 Berwick, PA 18603-0467 Harrisburg, PA 17105-8469 Michael H. Crowthers Senior Resident Inspector Supervising Engineer U.S. Nuclear Regulatory Commission Nuclear Regulatory Affairs P.O. Box 35, NUCSA4 PPL Susquehanna, LLC Berwick, PA 18603-0035 Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Steven M. Cook 475 Allendale Road Manager - Quality Assurance King of Prussia, PA 19406 PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Board of Supervisors Berwick, PA 18603-0467 Salem Township P.O. Box 405 Luis A. Ramos Berwick, PA 18603-0035 Community Relations Manager, Susquehanna Dr. Judith Johnsrud PPL Susquehanna, LLC National Energy Committee 634 Salem Blvd., SSO Sierra Club Berwick, PA 18603-0467 443 Orlando Avenue State College, PA 16803
