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| =Text= | | =Text= |
| {{#Wiki_filter:May 29, 2008 | | {{#Wiki_filter:May 29, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/ |
| | | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8253) | | OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8253) |
| | | The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008. |
| The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee | | The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document. |
| =s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008. | |
| | |
| The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document. | |
| | |
| The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | | The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. |
| Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. | | Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request. |
| | | Docket No. 50-219 |
| Docket No. 50-219 | |
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| ==Enclosure:== | | ==Enclosure:== |
| Draft RAI | | Draft RAI |
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| May 29, 2008 | | May 29, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/ |
| | | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD7261) | | OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD7261) |
| | | The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008. |
| The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee | | The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document. |
| =s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008. | |
| | |
| The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document. | |
| | |
| The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | | The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. |
| Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. | | Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request. |
| | | Docket No. 50-219 |
| Docket No. 50-219 | |
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| ==Attachment:== | | ==Attachment:== |
| Draft RAI | | Draft RAI DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 LPL I-2 Reading RidsNrrPMGMiller RidsNrrDorlDpr |
| | *Memorandum dated 5/27/2008, no significant changes ACCESSION NO.: ML081490485 OFFICE LPI-2/PM DCI/CVIB/BC NAME G. E. Miller M. Mitchell* |
| | DATE 5/29/08 5/27/08 OFFICIAL RECORD COPY |
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| DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 LPL I-2 Reading RidsNrrPMGMiller RidsNrrDorlDpr
| | DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE-TEMPERATURE LIMITS CURVES OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 By letter dated March 10, 2008, AmerGen Energy Company, LLC (Amergen) submitted an amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specifications regarding secondary containment operability requirements during refueling. |
| | The Nuclear Regulatory Commission staff has reviewed the information provided in support of the proposed amendment and finds that the following information is required to complete its review: |
| | : 1) To verify that Oyster Creek reactor pressure vessel (RPV) pressure-temperature (P-T) limits in the proposed Pressure-Temperature Limits Report (PTLR) are results of correctly implementing the methodology of SIR-05-044-A, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, the staff requests you: |
| | a) Provide an evaluation showing that you have performed analysis for the bottom head region and the non-beltline region in accordance with SIR-05-044-A and identify the portion of the proposed P-T limits (Figures 1 to 3 of the proposed PTLR are sufficient) that are limited by materials in these regions, b) Provide an evaluation for the small-diameter, drill-hole type instrument nozzle (e.g., water level nozzle) if it exists in your RPV beltline, c) Identify among the three methodologies (Page 2-13 of SIR-05-044-A) the one that you used to calculate thermal stress intensity factors for shell regions, d) Provide the temperature instrument uncertainty, the pressure instrument uncertainty, and the pressure head to account for the column of water in the RPV (Page 2-25 of SIR 044-A) so that the staff can assess the difference between the staffs calculated P-T limits and your proposed P-T limits, and e) Provide Reference 6.16 (a reference listed in the proposed PTLR), Revised Calculation of P-T Limit Curves for the Oyster Creek Generating Station, dated February 26, 2008, to supplement the above requested specific information. |
| | : 2) Page 7 of the PTLR mentioned that, With respect to operating conditions, stress distributions were developed for a thermal shock of 450º F, which represents the maximum thermal shock for the feedwater nozzle during normal operating conditions. The only guideline in SIR-05-044-A regarding the thermal stress intensity factorcalculation for the ENCLOSURE |
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| *Memorandum dated 5/27/2008, no significant changes ACCESSION NO.: ML081490485 OFFICE LPI-2/PM DCI/CVIB/BC NAME G. E. Miller M. Mitchell*
| | feedwater nozzle is that the stress distribution should be extracted from a finite element model using the limiting normal/upset transient. Provide information regarding whether your feedwater nozzle analysis is plant-specific and how the 450º F thermal shock transient was selected and determined to be bounding. |
| DATE 5/29/08 5/27/08 OFFICIAL RECORD COPY ENCLOSURE DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE-TEMPERATURE LIMITS CURVES OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
| |
| | |
| By letter dated March 10, 2008, AmerGen Energy Company, LLC (Amergen) submitted an amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specifications regarding secondary containment operability requirements during ref ueling.
| |
| | |
| The Nuclear Regulatory Commission staff has reviewed the information provided in support of the proposed amendment and finds that the following information is required to complete its review:
| |
| : 1) To verify that Oyster Creek reactor pressure vessel (RPV) pressure-temperature (P-T) limits in the proposed Pressure-Temperature Limits Report (PTLR) are results of correctly implementing the methodology of SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," the staff requests you:
| |
| a) Provide an evaluation showing that you have performed analysis for the bottom head region and the non-beltline region in accordance with SIR-05-044-A and identify the portion of the proposed P-T limits (Figures 1 to 3 of the proposed PTLR are sufficient) that are limited by materials in these regions, b) Provide an evaluation for the small-diameter, drill-hole type instrument nozzle (e.g., water level nozzle) if it exists in your RPV beltline, c) Identify among the three methodologies (Page 2-13 of SIR-05-044-A) the one that you used to calculate thermal stress intensity factors for shell regions, d) Provide the temperature instrument uncertainty, the pressure instrument uncertainty, and the pressure head to account for the column of water in the RPV (Page 2-25 of SIR 044-A) so that the staff can assess the difference between the staff's calculated P-T limits and your proposed P-T limits, and e) Provide Reference 6.16 (a reference listed in the proposed PTLR), "Revised Calculation of P-T Limit Curves for the Oyster Creek Generating Station," dated February 26, 2008, to supplement the above requested specific information.
| |
| : 2) Page 7 of the PTLR mentioned that, "With respect to operating conditions, stress distributions were developed for a thermal shock of 450º F, which represents the maximum thermal shock for the feedwater nozzle during normal operating conditions." The only guideline in SIR-05-044-A regarding the thermal stress intensity factorcalculation for the feedwater nozzle is that the stress distribution should be extracted from a finite element model using the limiting normal/upset transient. Provide information regarding whether your feedwater nozzle analysis is plant-specific and how the 450º F thermal shock transient was selected and determined to be bounding.
| |
| : 3) Pages 7 and 8 provided some additional information regarding the finite element modeling of the feedwater nozzle for evaluating P-T limits for non-beltline materials that were not in SIR-05-044-A. Please justify the following: | | : 3) Pages 7 and 8 provided some additional information regarding the finite element modeling of the feedwater nozzle for evaluating P-T limits for non-beltline materials that were not in SIR-05-044-A. Please justify the following: |
| a) Use of a conversion factor of 3.2 times the cylinder radius to model the sphere (upper head), and b) Use of material properties at 325º F to bound the 100º F condition.}} | | a) Use of a conversion factor of 3.2 times the cylinder radius to model the sphere (upper head), and b) Use of material properties at 325º F to bound the 100º F condition.}} |
Letter Sequence Draft RAI |
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Category:Memoranda
MONTHYEARML23324A4332024-01-23023 January 2024 10/16-17/2023 Summary of Routine NRC Site Visit at the Oyster Creek Nuclear Generating Station to Discuss License Termination Plans and Other Technical Topics ML20150A3252020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Oyster Creek ISFSI ML19295G4922019-10-24024 October 2019 Summary of the October 3, 2019, Public Meeting Near the Oyster Creek Nuclear Generating Station Regarding the Establishment and Operation of Community Advisory Boards ML18205A5502018-08-0606 August 2018 Memorandum to File - Public Feedback to 7/17/18 Public Meeting in Forked River, Nj, to Receive Public Comments on Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate ML18102A1072018-04-18018 April 2018 Annual Assessment Meeting Summary 2018 ML17151A2702017-05-31031 May 2017 Annual Assess Meeting Summary and Attendees ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17132A2242017-05-10010 May 2017 May 25, 2017, Oyster Creek Nuclear Generating Station Public Meeting Notice ML17075A0172017-03-16016 March 2017 Meeting Summary Memorandum - Regulatory Conference March 9, 2017 ML16221A6152016-08-19019 August 2016 Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC Regarding a Presubmittal Physical Security Plan Change for Decommissioning at the Oyster Creek Nuclear Generating Station ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16035A0362016-02-0505 February 2016 February 3, 2016, Summary of Closed Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Regarding Security Plan Change for the Oyster Creek Nuclear Generating Station ML16015A1402016-01-27027 January 2016 Forthcoming Closed Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding a Physical Security Plan Change for the Oyster Creek Nuclear Generating Station ML15239A4622015-08-28028 August 2015 54p PSP Rev 13 Close-out Letter 8-27-15 ML14220A5122014-09-0303 September 2014 Summary - Site Visit Regarding Physical Security License Amendment Request for Oyster Creek Nuclear Generating Station ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13199A5092013-09-18018 September 2013 Transmittal of Final Oyster Creek Nuclear Station Accident Sequence Precursor Analysis ML13240A2952013-09-10010 September 2013 Notice of Forthcoming Closed Meeting with the Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding a Pre-Submittal Physical Security License Amendment Request for Oyster Creek Nuclear Generating Station ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML1208602902012-03-26026 March 2012 Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML1118702612011-06-27027 June 2011 NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2) ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1109502212011-04-11011 April 2011 Electronic Transmission, Draft Request for Additional Information Regarding Review of Flaw Evaluation for Weld NG-E-007 ML1108402192011-04-0404 April 2011 Memorandum to File: Transcripts for 10 CFR 2.206 Petition Regarding Oyster Creek and Nine Mile Point, Unit No. 1 Peak Cladding Temperature and ECCS Performance ML1100502522011-02-0909 February 2011 Memo to Chairman Jaczko Fm R. W. Borchardt, EDO Initiatives for Improved Communication of Groundwater Incidents ML1035703292011-01-28028 January 2011 OMA Exemption, Fire Protection Input for Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability (Phase 1) ML1032105082010-11-16016 November 2010 Units 1 & 2 - Electronic Transmission, Draft Request for Additional Information Regarding Request to Implement Emergency Action Level Scheme Change to NEI 99-01, Revision 5 ML1030905672010-11-0505 November 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Modify Required Actions for Inoperability of an Emergency Diesel Generator ML1026004432010-09-17017 September 2010 Closeout of Bulletin 2007-1 Security Officer Attentiveness, ML1025305792010-09-10010 September 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Modify Required Actions for Inoperability of an Emergency Diesel Generator ML1023005762010-08-18018 August 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to a Licensee Controlled Document ML1016806172010-06-18018 June 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Allow Temporary Changes to Secondary Containment Boundary During Shutdown Conditions ML1006401882010-03-0505 March 2010 Charter for the Groundwater Contamination Task Force ML1006100122010-03-0303 March 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to a Licensee Controlled Document ML0935705822010-01-19019 January 2010 Forthcoming Meeting Notice with Exelon Generation Company, LLC, to Discuss Oyster Creek Nuclear Generating Station, License Amendment Request Regarding Secondary Containment Operability ML0933805322009-12-0404 December 2009 Electronic Transmission, Draft Request for Additional Information Regarding Requested Exemptions to Fire Protection Requirements in 10 CFR 50, Appendix R ML0929311432009-12-0101 December 2009 Request for Additional Information on Request for Exception from 10 CFR 50, Appendix R, Section Iii. G, Fire Protection of Safe Shutdown Capability (Phase 1 & 2) at Oyster Creek Nuclear Generating Station ML0932210302009-11-18018 November 2009 Electronic Transmission, Draft RAI Regarding Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray System ML0928103632009-10-0808 October 2009 Notice of Meeting with Exelon Generation Company, LLC, to Discuss Oyster Creek Nuclear Generating Station and Exelon Fleet Lessons-Learned on Buried Piping Issues ML0926801972009-09-29029 September 2009 Notice of Pre-application Meeting to Discuss Egc'S Plants to Submit Power Uprate Requests for Various Units in Its Reactor Fleet ML0925803412009-09-17017 September 2009 Revised Notice of Meeting with Exelon Generation Company, LLC, to Discuss Oyster Creek Nuclear Generating Station, License Amendment Request Regarding Secondary Containment Operability ML0925801582009-09-15015 September 2009 Audit Plan for Review of the Addendum 3-Dimensional Finite Element Analysis for the Oyster Creek Nuclear Generating Station Containment Drywell Shell ML0925705572009-09-14014 September 2009 Draft Request for Additional Information Regarding Secondary Containment Operability ML0925402362009-09-11011 September 2009 Draft Request for Additional Information Regarding Secondary Containment Operability ML0921202792009-08-0404 August 2009 Draft Request for Additional Information Regarding Control Rod Drive Rod Notch Testing Frequency 2024-01-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML21099A0442021-04-0808 April 2021 Enclosure - Request for Additional Information Related to Request for Approval of Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Only Emergency Plan Holtec Decommissioning International, LLC ML20335A3102020-11-30030 November 2020 RAI November 2020 Part 73 FOF Exemption Request ML20297A2382020-10-22022 October 2020 Fleet DQAP RAIs - Enclosure ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20134H8732020-05-12012 May 2020 E-mail - Request for Additional Information: Oyster Creek Request for Temporary Exemption from Part 73, Appendix B Requirements ML19263D2142019-09-20020 September 2019 Hdi PSDAR Environmental RAI Enclosure (002) ML19158A2772019-05-28028 May 2019 NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS ML19025A1172019-01-24024 January 2019 NRR E-mail Capture - for Your Action - RAI for Oyster Creek EP Exemption (Change to Adiabatic Heat-Up Calculation) ML18256A0022018-09-12012 September 2018 NRR E-mail Capture - for Your Action: RAIs for Oyster Creek Post Shutdown Decommissioning Activities Report (PSDAR) ML18135A0732018-05-15015 May 2018 NRR E-mail Capture - RAIs - Oyster Creek - Request Approval of the Decommissioning Quality Assurance Program ML18068A6582018-03-0909 March 2018 NRR E-mail Capture - RAIs - Oyster Creek Defueled TS LAR ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18024B0642018-01-24024 January 2018 NRR E-mail Capture - for Your Action - RAI for Oyster Creek Permanently Defueled EP and EAL Scheme LAR (CAC No. MG0160; EPID: L-2017-LLA-0307) ML18012A0782018-01-12012 January 2018 NRR E-mail Capture - for Your Review - Draft RAI for Oyster Creek Permanently Defueled EP and EAL Scheme LAR (CAC No. MG0160; EPID: L-2017-LLA-0307) ML18003A4122018-01-0303 January 2018 NRR E-mail Capture - for Your Action - RAI - Oyster Creek BWRVIP LAR (CAC No. MG0180; EPID No. L-LLA-2017-0304) ML17320A6372017-11-16016 November 2017 NRR E-mail Capture - Oyster Creek Nuclear Generating Station - Request for Additional Information Regarding License Amendment Request for Emergency Plan Exemption (CAC No. MG0153; EPID L-2017-LLE-0020) ML17319A9422017-11-15015 November 2017 NRR E-mail Capture - Oyster Creek Nuclear Generating Station - Request for Additional Information Regarding License Amendment Request for Emergency Plan Exemption (CAC No. MG0153; EPID L-2017-LLE-0020) ML17208A7472017-09-14014 September 2017 Request for Additional Information, License Amendment Request to Revise the Site Emergency Plan for On-Shift and Emergency Response Organization Staffing for Permanently Defueled Condition ML17136A3852017-05-12012 May 2017 NRR E-mail Capture - (External_Sender) Oyster Creek Response to NRC Flood MSA Audit Review Questions ML17038A5152017-02-0303 February 2017 NRR E-mail Capture - (External_Sender) Oyster Creek Nuclear Generating Station Response to Environmental Questions Regarding the Mitigating Strategies Final Integrated Plan and SPF Instrumentation Compliance Letter ML16244A3112016-10-0707 October 2016 Request for Additional Information Regarding License Amendment Request for Technical Specifications Section 6.0, Administrative Controls for Permanently Defueled Condition ML16125A2452016-05-16016 May 2016 Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program ML16060A1722016-03-0707 March 2016 Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate and Spent Fuel Management Program ML16056A0012016-02-24024 February 2016 NRR E-mail Capture - Request for Additional Information - Oyster Creek Security Plan - Revision 14 ML17144A3702015-05-0606 May 2015 NRC Email J. Hughey( NRC) to Dave Distel (Exelon)- Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109, Dated May 6, 2015 ML15005A0692015-01-0606 January 2015 Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief ML14246A5182014-09-17017 September 2014 Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief ML14252A7032014-09-17017 September 2014 Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate and Annual Decommissioning Funding Status Reports ML14247A5862014-09-16016 September 2014 Request for Additional Information Regarding License Amendment Request to Revise Snubber Surveillance Requirements (Tac No. MF4124) ML14114A5632014-09-10010 September 2014 Request for Additional Information Regarding License Amendment Request Related to Reactor Building Vital Area Access Control ML14220A0272014-08-27027 August 2014 Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML14083A1602014-03-31031 March 2014 Request for Additional Information Regarding Bulletin 2012-01, Design Vulnerability in Electric Power System ML13351A3142013-12-20020 December 2013 Request for Additional Information Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power System. ML13268A0312013-11-0808 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13227A3042013-08-28028 August 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13196A3382013-07-15015 July 2013 2013 Decommissioning Fund Report RAI ML12229A4332012-09-0606 September 2012 Request for Additional Information Regarding Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 12 (TAC No. D91660) ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12032A1872012-02-21021 February 2012 Request for Additional Information Related to the Response to License Renewal Commitment No. 10 Regarding Thermal Aging Irradiation Embrittlement of Cast Austenitic Stainless Steel ML12025A2542012-01-23023 January 2012 Request for Additional Information - License Renewal Commitment Regarding Thermal Aging and Neutron Irradiation Embrittlement of CASS Materials ML1200603242012-01-19019 January 2012 Fleet, RAI, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-789 (N-789) ML1131200572011-11-22022 November 2011 Fleet - Bulletin 2011 01, Mitigating Strategies Request for Additional Information Regarding 60-Day Response ML1123604472011-08-24024 August 2011 E-mail, Miller to Loomis, Oyster Creek Flaw Evaluation Draft RAI Questions ML1120910012011-07-22022 July 2011 Generation Station - Licensed Operator Request for Additional Information ML1116805642011-07-0707 July 2011 Fleet, Request for Additional Information, 2011 Report on Status of Decommissioning Funding for Reactors 2021-04-08
[Table view] |
Text
May 29, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8253)
The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008.
The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document.
The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-219
Enclosure:
Draft RAI
May 29, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD7261)
The attached draft request for information (RAI) was transmitted on May 28, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated March 10, 2008.
The proposed amendment would revise the Oyster Creek Technical Specifications by relocating the reactor vessel pressure-temperature limit curves to a licensee-controlled document.
The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-219
Attachment:
Draft RAI DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 LPL I-2 Reading RidsNrrPMGMiller RidsNrrDorlDpr
- Memorandum dated 5/27/2008, no significant changes ACCESSION NO.: ML081490485 OFFICE LPI-2/PM DCI/CVIB/BC NAME G. E. Miller M. Mitchell*
DATE 5/29/08 5/27/08 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE-TEMPERATURE LIMITS CURVES OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 By letter dated March 10, 2008, AmerGen Energy Company, LLC (Amergen) submitted an amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specifications regarding secondary containment operability requirements during refueling.
The Nuclear Regulatory Commission staff has reviewed the information provided in support of the proposed amendment and finds that the following information is required to complete its review:
- 1) To verify that Oyster Creek reactor pressure vessel (RPV) pressure-temperature (P-T) limits in the proposed Pressure-Temperature Limits Report (PTLR) are results of correctly implementing the methodology of SIR-05-044-A, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, the staff requests you:
a) Provide an evaluation showing that you have performed analysis for the bottom head region and the non-beltline region in accordance with SIR-05-044-A and identify the portion of the proposed P-T limits (Figures 1 to 3 of the proposed PTLR are sufficient) that are limited by materials in these regions, b) Provide an evaluation for the small-diameter, drill-hole type instrument nozzle (e.g., water level nozzle) if it exists in your RPV beltline, c) Identify among the three methodologies (Page 2-13 of SIR-05-044-A) the one that you used to calculate thermal stress intensity factors for shell regions, d) Provide the temperature instrument uncertainty, the pressure instrument uncertainty, and the pressure head to account for the column of water in the RPV (Page 2-25 of SIR 044-A) so that the staff can assess the difference between the staffs calculated P-T limits and your proposed P-T limits, and e) Provide Reference 6.16 (a reference listed in the proposed PTLR), Revised Calculation of P-T Limit Curves for the Oyster Creek Generating Station, dated February 26, 2008, to supplement the above requested specific information.
- 2) Page 7 of the PTLR mentioned that, With respect to operating conditions, stress distributions were developed for a thermal shock of 450º F, which represents the maximum thermal shock for the feedwater nozzle during normal operating conditions. The only guideline in SIR-05-044-A regarding the thermal stress intensity factorcalculation for the ENCLOSURE
feedwater nozzle is that the stress distribution should be extracted from a finite element model using the limiting normal/upset transient. Provide information regarding whether your feedwater nozzle analysis is plant-specific and how the 450º F thermal shock transient was selected and determined to be bounding.
- 3) Pages 7 and 8 provided some additional information regarding the finite element modeling of the feedwater nozzle for evaluating P-T limits for non-beltline materials that were not in SIR-05-044-A. Please justify the following:
a) Use of a conversion factor of 3.2 times the cylinder radius to model the sphere (upper head), and b) Use of material properties at 325º F to bound the 100º F condition.