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TAC:MD8932, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action (Approved, Closed) |
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Category:Letter
MONTHYEARML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22118A6122022-04-28028 April 2022 Annual Radioactive Environmental Operating Report for 2021 ML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22069A3762022-03-10010 March 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML22032A0582022-03-0808 March 2022 EA-21-139; EA-150: Oyster Creek Nuclear Generating Station - NRC Investigation Report Nos.. 1-2021-002 & 1-2021-014 ML22060A2202022-03-0202 March 2022 NRC Office of Investigations Case No. 1-2021-009 ML22049B2452022-02-19019 February 2022 Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G IR 05000219/20214022022-01-26026 January 2022 EA-21-041: Confirmatory Order Related to Oyster Greek Nuclear Generating Station - NRC Investigation Report I-2020-007; NRC Inspection Report Nos. 05000219/2021402 & 07200015/2021401 ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22025A2182022-01-25025 January 2022 Late LLRW Shipments Investigation Report Pursuant to 10 CFR 20, Appendix G ML22021B5512022-01-21021 January 2022 Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML21349A5192021-12-15015 December 2021 Commitment Change Summary Report ML21285A1912021-11-30030 November 2021 Nrc'S Analysis of Holtec Decommissioning International'S Decommissioning Funding Status Report for Oyster Creek Nuclear Generating Station and Pilgrim Nuclear Power Station, Docket Nos 50-219 and 50-293 IR 05000219/20210032021-11-16016 November 2021 NRC Inspection Report No. 05000219/2021003 L-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021 Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades IR 05000219/20214042021-08-26026 August 2021 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200015/2021402 and Security Decommissioning Inspection Report 05000219/2021404 - (Public) 2024-01-09
[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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 28, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD DRIVE ROD NOTCH TESTING FREQUENCY LICENSE AMENDMENT REQUEST (TAC NO. MD8932)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated June 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620236), as supplemented by letter dated March 30, 2009 (ADAMS Accession No. ML090890777), Exelon Generation Company, LLC (Exelon), submitted a license amendment request. The proposed change would revise Surveillance Requirement 4.2.D to decrease the 'frequency of performing control rod drive rod notch testing from weekly to once per 31 days. The NRC staff has reviewed the request submitted by the licensee and has identified a need for additional information as set forth in the Enclosure.
The draft questions were sent via facsimile on August 4, 2009, to Mr. Frank Mascitelli, of your staff, to ensure that the questions were understandable, the regulatory basis for the question was clear, and to determine if the information was previously docketed. On August 17, 2009, Mr. Mascitelli indicated that Exelon would be able to respond by September 14, 2009. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108.
C. Pardee -2 If you have any questions, please contact me at (301) 415-2481.
Sincerely,
\
- ~'..u
G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Request for Additional Information cc: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST CONTROL ROD DRIVE ROD NOTCH TESTING FREQUENCY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 By letter to the Nuclear Regulatory Commission (NRC) dated June 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620236), as supplemented by letter dated March 30, 2009 (ADAMS Accession No. ML090890777), Exelon Generation Company, LLC (Exelon), submitted a license amendment request. The proposed change would revise Surveillance Requirement (SR) 4.2.0 to decrease the frequency of performing control rod drive rod notch testing from weekly to once per 31 days. The NRC staff has reviewed Exelon's submittal and determined that additional information, as described below, is needed to complete the review.
- 1. The model safety evaluation referenced in the license amendment request evaluates a reduction of the frequency for performing control rod notch testing for fully withdrawn control rods while the proposed change for Oyster Creek would decrease the frequency for both fully and partially withdrawn control rods. Please provide justification for why the decreased frequency of performing control rod notch testing in accordance with SR 4.2.0 for partially withdrawn control rods will adequately assure the necessary quality of the control rod system and its components. Additionally, please identify and discuss any differences in the frequency or method of performing scram time testing for fully and partially withdrawn control rods.
Enclosure
C. Pardee -2 If you have any questions, please contact me at (301) 415-2481.
Sincerely, Ira/
G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Request for Additional Information cc: Distribution via ListServ DISTRIBUTION:
PUBLIC LPLI-2 RlF RidsNrrPMGMillerResource RidsNrrLAABaxterResource RidsNrrDirsltsbResource RidsRgn1 MailCenterResource RidsNrrDorlLpl1-2Resource RGrover, NRR RidsOgcRpResource RidsAcrsAcnw_MailCTRResource ADAMS Accession Number' ML092320170 *via E-mail OFFICE LPL1-2/PM LPL1-2/LA ITSB/BC LPL 1-2/BC NAME GEMiller ABaxter RElliot* HChernoff DATE 8/25/09 8/25/09 07/31/09 8128109 OFFICIAL RECORD COPY