|
|
| (7 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML14114A563 | | | number = ML14114A563 |
| | issue date = 09/10/2014 | | | issue date = 09/10/2014 |
| | title = Oyster Creek Nuclear Generating Station - Request for Additional Information Regarding License Amendment Request Related to Reactor Building Vital Area Access Control (TAC No. MF3295) | | | title = Request for Additional Information Regarding License Amendment Request Related to Reactor Building Vital Area Access Control |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000219 | | | docket = 05000219 |
| | license number = | | | license number = |
| | contact person = Lamb J G, NRR/DORL/LPLI-2 | | | contact person = Lamb J, NRR/DORL/LPLI-2 |
| | case reference number = TAC MF3295 | | | case reference number = TAC MF3295 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:OFFICIAL USE ONLY SECURITY RELATED INFORMATION Mr. Michael J. Pacilio UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| OYSTER CREEK NUCLEAR GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295) | | OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295) |
|
| |
|
| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML 13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access for certain portions of the reactor building at OCNGS. The attachment to the letter dated December 19, 2013, contained Safeguards Information and has been withheld from public disclosure. In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives, and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 1 0 CFR 73.55. The NRC staff is currently reviewing the submittal and is enclosing a request for additional information (RAI) to support its review. A draft of these questions was previously sent to Mr. Richard Gropp of your staff on August 12, 2014, with an opportunity to have a teleconference to ensure that Exelon understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Enclosure 2 transmitted herewith contains Security-Related Information. When separated from Enclosure 2, this document is decontrolled. OFFICIAL USE ONLY SECURITY RELATED INFORMATION OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacillo A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAI by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 1 0 CFR 2.1 08, "Denial of application for failure to supply information." If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. Docket No. 50-219 | | |
| | By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access for certain portions of the reactor building at OCNGS. The attachment to the letter dated December 19, 2013, contained Safeguards Information and has been withheld from public disclosure. |
| | In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives, and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. |
| | The NRC staff is currently reviewing the submittal and is enclosing a request for additional information (RAI) to support its review. A draft of these questions was previously sent to Mr. |
| | Richard Gropp of your staff on August 12, 2014, with an opportunity to have a teleconference to ensure that Exelon understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. |
| | Enclosure 2 transmitted herewith contains Security-Related Information. When separated from Enclosure 2, this document is decontrolled. |
| | OFFICIAL USE ONLY SECURITY RELATED INFORMATION |
| | |
| | OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacillo A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAI by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 10 CFR 2.1 08, "Denial of application for failure to supply information." |
| | If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. |
| | Sincerely, |
| | . Lamb, Senior Project Manager PI Licensing Branch 1-2 Di |
| | * ion of Operating Reactor Licensing 0 1ce of Nuclear Reactor Regulation Docket No. 50-219 |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
| 1. Request for Additional Information 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv Sincerely, . Lamb, Senior Project Manager PI Licensing Branch 1-2 Di | | : 1. Request for Additional Information |
| * ion of Operating Reactor Licensing 0 1ce of Nuclear Reactor Regulation OFFICIAL USE ONLY SECURITY RELATED INFORMATION OFFICIAL US& ONLY SECURITY R&LAT&D INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING THE REACTOR BUILDING VITAL AREA ACCESS CONTROL OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 Security-related information has been redacted from this document. Redacted information is identified by blank space enclosed within double brackets as shown here [[ ]]. By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML 13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90 to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access at OCNGS. The enclosure to the letter contained Safeguards Information and has been withheld from public disclosure. In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. The NRC staff is currently reviewing the submittal and has determined that the additional information requested below is needed to support its review. REGULA TORY BASIS The regulations in 10 CFR 73.55(e)(9)(i), state that "[v]ital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans." The regulations in 10 CFR 73.55(e)(9)(ii) state that "[t]he licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking Enclosure 1 OFFICIAL USE ONLY SECURITY REbATED INFORMATION OFFICIAl USE! ONlY Si!CURITY Ri!bATE!D INFORMATION devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section." The regulation in 10 CFR 73.55(e)(9)(iii) states that, "[u]noccupied vital areas must be locked and alarmed." Consistent with 10 CFR 73.55(r)(3), the licensee shall submit a technical basis for each proposed alternative measure. The basis must include an analysis or assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii). REQUEST FOR ADDITIONAL INFORMATION The following additional licensing basis information is needed to justify the need to apply 10 CFR 73.55(r) and to justify that the proposed alternative measures meet the performance requirements of 10 CFR 73.55(b). [[ OFFICIAl USE! ONlY SECURITY REbATED INFORMATION OFFICIAL US& ONLY SliCURITY RlilATiiD INFORMATION ]] OFFICIAL US& ONLY SECURITY REbATI5D INFORMATION OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacilio A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAJ by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 10 CFR 2.1 08, "Denial of application for failure to supply information." If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. Docket No. 50-219
| | : 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY SECURITY RELATED INFORMATION |
| | |
| | OFFICIAL US& ONLY SECURITY R&LAT&D INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING THE REACTOR BUILDING VITAL AREA ACCESS CONTROL OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 Security-related information has been redacted from this document. |
| | Redacted information is identified by blank space enclosed within double brackets as shown here (( )). |
| | By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90 to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access at OCNGS. The enclosure to the letter contained Safeguards Information and has been withheld from public disclosure. |
| | In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. The NRC staff is currently reviewing the submittal and has determined that the additional information requested below is needed to support its review. |
| | REGULA TORY BASIS The regulations in 10 CFR 73.55(e)(9)(i), state that "[v]ital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans." |
| | The regulations in 10 CFR 73.55(e)(9)(ii) state that "[t]he licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking Enclosure 1 OFFICIAL USE ONLY SECURITY REbATED INFORMATION |
|
| |
|
| ==Enclosures:==
| | OFFICIAl USE! ONlY Si!CURITY Ri!bATE!D INFORMATION devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section." |
| 1. Request for Additional Information 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv DISTRIBUTION: PUBLIC RidsAcrsAcnw&mMaiiCenter Resource RidsNrrPMOysterCreek Resource RidsNrrDpr Resource LPL 1-2 R/F ADAMS Accession No ML14114A563 Sincerely, IRA/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsRgn1 Mail Center Resource RMathew, NRR RidsNrrLAABaxter Resource RidsNrrDorllpl1-2 Resource *via email OFFICE NRR/LPL 1-2/PM N RR/LPL 1-2/LA NSIR/BC NRR/LPL 1-2/BC(A) NRR/LPL 1-2/PM Jlamb A Baxter* DHuyck* RSchaaf Jlamb NAME w/comment DATE 08/24/14 09/05/14 09/08/14 9/10/14 9/10/14 OFFICIAL RECORD COPY OFFICIAL USE ONLY SECURITY RELATED INFORMATION
| | The regulation in 10 CFR 73.55(e)(9)(iii) states that, "[u]noccupied vital areas must be locked and alarmed." |
| }} | | Consistent with 10 CFR 73.55(r)(3), the licensee shall submit a technical basis for each proposed alternative measure. The basis must include an analysis or assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii). |
| | REQUEST FOR ADDITIONAL INFORMATION The following additional licensing basis information is needed to justify the need to apply 10 CFR 73.55(r) and to justify that the proposed alternative measures meet the performance requirements of 10 CFR 73.55(b). |
| | (( |
| | OFFICIAl USE! ONlY SECURITY REbATED INFORMATION |
| | |
| | OFFICIAL US& ONLY SliCURITY RlilATiiD INFORMATION |
| | )) |
| | OFFICIAL US& ONLY SECURITY REbATI5D INFORMATION |
| | |
| | ML14114A563 *via email OFFICE NRR/LPL1-2/PM N RR/LPL 1-2/LA NSIR/BC NRR/LPL 1-2/BC(A) NRR/LPL 1-2/PM Jlamb A Baxter* DHuyck* RSchaaf Jlamb NAME w/comment DATE 08/24/14 09/05/14 09/08/14 9/10/14 9/10/14}} |
|
|---|
Category:Letter
MONTHYEARML24284A1972024-10-10010 October 2024
Cover Letter Oyster Creek, License Termination Plan Acceptance Review
ML24269A0462024-10-0404 October 2024
Cover Letter for Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Acceptance Review Request for Additional Information
ML24274A0822024-09-25025 September 2024
Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000219/20240022024-09-0505 September 2024
– NRC Inspection Report 05000219/2024002 and 07200015/2024001
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24214A0372024-08-0101 August 2024
License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements
ML24179A1842024-07-23023 July 2024
June 20, 2024, Clarification Call on Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
IR 05000219/20240012024-05-14014 May 2024
Decommissioning Intl, LLC Oyster Creek Nuclear Generating Station - NRC Inspection Report No. 05000219/2024001
ML24120A0412024-04-29029 April 2024
Annual Radioactive Environmental Operating Report for 2023
L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024
HDI Annual Occupational Radiation Exposure Data Reports - 2023
ML24120A0402024-04-29029 April 2024
Annual Radioactive Effluent Release Report for 2023
ML24094A2142024-04-19019 April 2024
Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan
ML24089A2492024-03-29029 March 2024
Reply to Notice of Violation EA-2024-024
L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)
ML24085A7902024-03-28028 March 2024
– Preapplication Readiness Assessment of the License Termination Plan
ML24081A2882024-03-21021 March 2024
Request Preliminary Review and Feedback on Chapter 6 of the Draft License Termination Plan
ML24046A1242024-02-29029 February 2024
– NRC Inspection Report 05000219/2023003
ML24033A3272024-02-0202 February 2024
Request Preliminary Review and Feedback on Chapter 5 of the Draft License Termination Plan
ML23342A1162024-01-0909 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
L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023
HDI Annual Occupational Radiation Exposure Data Reports - 2022
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-23-003, 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
2024-09-05
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24284A2032024-10-16016 October 2024
Enclosure 2 Revised Pending Request for Additional Information
ML24284A1962024-10-16016 October 2024
Enclosure 1 Revised Request for Supplemental Information
ML24269A0462024-10-0404 October 2024
Cover Letter for Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Acceptance Review Request for Additional Information
ML24269A0492024-10-0404 October 2024
Enclosure 1, Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Request for Supplemental Information
ML21099A0442021-04-0808 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
ML14252A7032014-09-17017 September 2014
Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate and Annual Decommissioning Funding Status Reports
ML14246A5182014-09-17017 September 2014
Request for Additional Information Regarding the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief
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)
ML12056A0512012-03-12012 March 2012
Enclosure 5 - Recommendation 9.3: Emergency Preparedness
ML12056A0492012-03-12012 March 2012
Enclosure 3 - Recommendation 2.3: Seismic
ML12056A0472012-03-12012 March 2012
Enclosure 1 - Recommendation 2.1: Seismic
ML12056A0482012-03-12012 March 2012
Enclosure 2 - Recommendation 2.1: Flooding
ML12056A0502012-03-12012 March 2012
Enclosure 4 - Recommendation 2.3: Flooding
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)
2024-10-04
[Table view] |
Text
OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295)
Dear Mr. Pacilio:
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access for certain portions of the reactor building at OCNGS. The attachment to the letter dated December 19, 2013, contained Safeguards Information and has been withheld from public disclosure.
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives, and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55.
The NRC staff is currently reviewing the submittal and is enclosing a request for additional information (RAI) to support its review. A draft of these questions was previously sent to Mr.
Richard Gropp of your staff on August 12, 2014, with an opportunity to have a teleconference to ensure that Exelon understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed.
Enclosure 2 transmitted herewith contains Security-Related Information. When separated from Enclosure 2, this document is decontrolled.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacillo A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAI by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 10 CFR 2.1 08, "Denial of application for failure to supply information."
If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov.
Sincerely,
. Lamb, Senior Project Manager PI Licensing Branch 1-2 Di
- ion of Operating Reactor Licensing 0 1ce of Nuclear Reactor Regulation Docket No. 50-219
Enclosures:
- 1. Request for Additional Information
- 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL US& ONLY SECURITY R&LAT&D INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING THE REACTOR BUILDING VITAL AREA ACCESS CONTROL OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 Security-related information has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets as shown here (( )).
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90 to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access at OCNGS. The enclosure to the letter contained Safeguards Information and has been withheld from public disclosure.
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. The NRC staff is currently reviewing the submittal and has determined that the additional information requested below is needed to support its review.
REGULA TORY BASIS The regulations in 10 CFR 73.55(e)(9)(i), state that "[v]ital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans."
The regulations in 10 CFR 73.55(e)(9)(ii) state that "[t]he licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking Enclosure 1 OFFICIAL USE ONLY SECURITY REbATED INFORMATION
OFFICIAl USE! ONlY Si!CURITY Ri!bATE!D INFORMATION devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section."
The regulation in 10 CFR 73.55(e)(9)(iii) states that, "[u]noccupied vital areas must be locked and alarmed."
Consistent with 10 CFR 73.55(r)(3), the licensee shall submit a technical basis for each proposed alternative measure. The basis must include an analysis or assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii).
REQUEST FOR ADDITIONAL INFORMATION The following additional licensing basis information is needed to justify the need to apply 10 CFR 73.55(r) and to justify that the proposed alternative measures meet the performance requirements of 10 CFR 73.55(b).
((
OFFICIAl USE! ONlY SECURITY REbATED INFORMATION
OFFICIAL US& ONLY SliCURITY RlilATiiD INFORMATION
))
OFFICIAL US& ONLY SECURITY REbATI5D INFORMATION
ML14114A563 *via email OFFICE NRR/LPL1-2/PM N RR/LPL 1-2/LA NSIR/BC NRR/LPL 1-2/BC(A) NRR/LPL 1-2/PM Jlamb A Baxter* DHuyck* RSchaaf Jlamb NAME w/comment DATE 08/24/14 09/05/14 09/08/14 9/10/14 9/10/14