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| | number = ML14028A240 | | | number = ML14028A240 |
| | issue date = 02/18/2014 | | | issue date = 02/18/2014 |
| | title = R.E. Ginna Nuclear Power Plant - Review of the Changes to the Licensee'S Physical Security Plan and Safeguards Contingency Plan (TAC No. MF1132) | | | title = Review of the Changes to the Licensee'S Physical Security Plan and Safeguards Contingency Plan |
| | author name = Thadani M C | | | author name = Thadani M |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Pacher J E | | | addressee name = Pacher J |
| | addressee affiliation = R. E. Ginna Nuclear Power Plant, LLC | | | addressee affiliation = R. E. Ginna Nuclear Power Plant, LLC |
| | docket = 05000244 | | | docket = 05000244 |
| | license number = | | | license number = |
| | contact person = Thadani M C | | | contact person = Thadani M |
| | case reference number = TAC MF1132 | | | case reference number = TAC MF1132 |
| | document type = Letter, Safety Evaluation | | | document type = Letter, Safety Evaluation |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF1132 | | | project = TAC:MF1132 |
| | stage = Other | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Febeuary 18, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Febeuary 18, 2014 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| R.E. GINNA NUCLEAR POWER PLANT-REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132) | | R.E. GINNA NUCLEAR POWER PLANT- REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132) |
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| ==Dear Mr. Pacher:== | | ==Dear Mr. Pacher:== |
| By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML 13050A51 0), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (1 0 CFR) 50.54(p)(2). The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC BOO "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans. Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54{p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions. The effectiveness of the implementation of this revision is subject to future NRC review and inspection. Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue. Docket No. 50-244 | | |
| | By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (1 0 CFR) 50.54(p)(2). |
| | The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC BOO "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans. |
| | Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54{p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions. |
| | The effectiveness of the implementation of this revision is subject to future NRC review and inspection. |
| | Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue. |
| | Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 |
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| ==Enclosures:== | | ==Enclosures:== |
| Safety Evaluation cc w/encl: Distribution via Listserv Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR SECURITY AND INCIDENTRESPONSE CHANGES TO SECURITY PLAN CONSTELLATION ENERGY NUCLEAR GROUP R. E. GINNA NUCLEAR POWER PLANT DOCKET NO 50-244
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| ==1.0 INTRODUCTION== | | Safety Evaluation cc w/encl: Distribution via Listserv |
| By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML 13050A51 0), Constellation Energy Nuclear Group, submitted the R. E. Ginna Nuclear Power Plant's (Ginna's) Physical Security Plan (PSP}, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2). This revision was performed to better delineate the required number of security personnel used at Ginna to effectively implement the protective strategy as described in the PSP. The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes to the PSP consistent with the applicable requirements of 1 0 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident response (NSIR) Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)" and the NRC endorsed Nuclear Energy Institute (NEI) guidance 03-12, Revision 7, template for security plans, as appropriate. The review was required to better delineate the number of personnel required at Ginna and to verify that the changes made did not reduce the effectiveness of the plans. | | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR SECURITY AND INCIDENTRESPONSE CHANGES TO SECURITY PLAN CONSTELLATION ENERGY NUCLEAR GROUP R. E. GINNA NUCLEAR POWER PLANT DOCKET NO 50-244 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R. E. Ginna Nuclear Power Plant's (Ginna's) Physical Security Plan (PSP}, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2). This revision was performed to better delineate the required number of security personnel used at Ginna to effectively implement the protective strategy as described in the PSP. |
| | The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes to the PSP consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident response (NSIR) |
| | Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)" and the NRC endorsed Nuclear Energy Institute (NEI) guidance 03-12, Revision 7, template for security plans, as appropriate. The review was required to better delineate the number of personnel required at Ginna and to verify that the changes made did not reduce the effectiveness of the plans. |
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| | ==2.0 REGULATORY EVALUATION== |
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| | Pursuant to 10 CFR 50.54(p)(2), the licensee may make changes to the plans without prior Commission approval if the changes do not decrease the safeguards effectiveness of the security plans. The licensee must submit a report to the NRC containing the description of each change, within two months after changes are made. |
| | The NRC staff reviewed the licensee's submittal to determine whether the licensee properly concluded that changes did not decrease the safeguards effectiveness of the Commission-approved security plans. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | The NRC staff compared the licensee's changes with the previous revision of the licensee's security plans and reviewed the submittal against applicable requirements of 10 CFR Part 73 as well as the guidance contained within the NSIR Procedure LIC 800 "Security Review Procedure Enclosure |
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| | for 10 CFR 50.54(p)(2)," and the NRC endorsed NEI 03-12, Revision 7, template for security plans, as appropriate. |
| | In reviewing the changes to the security plans, the NRC staff noted the following: (1) Within the summary of changes the licensee identified an administrative change to Section 18 of the PSP for the purpose of clarifying the configuration of the security response organization; and (2) The information provided in the plans did not address the changes at an adequate level of detail to demonstrate that the change did not represent a decrease in the safeguards effectiveness of the security plans. |
| | The NRC staff determined that additional information was necessary to complete its review. On April23, 2013, the NRC staff sent a Request for Additional Information (RAI) to the licensee. |
| | On May 23, 2013, the licensee responded to the RAI. |
| | The NRC staff reviewed the licensee's response, and concluded that the licensee's response to the RAI adequately addressed the item of NRC staff's concern. Accordingly, based on the additional information, the NRC staff concluded that the licensee's explanations were acceptable, and the NRC staff's review was closed. |
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| ==2.0 REGULATORY EVALUATION== | | ==4.0 CONCLUSION== |
| Pursuant to 10 CFR 50.54(p)(2), the licensee may make changes to the plans without prior Commission approval if the changes do not decrease the safeguards effectiveness of the security plans. The licensee must submit a report to the NRC containing the description of each change, within two months after changes are made. The NRC staff reviewed the licensee's submittal to determine whether the licensee properly concluded that changes did not decrease the safeguards effectiveness of the approved security plans.
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| ==3.0 TECHNICAL EVALUATION==
| | The NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p). |
| The NRC staff compared the licensee's changes with the previous revision of the licensee's security plans and reviewed the submittal against applicable requirements of 10 CFR Part 73 as well as the guidance contained within the NSIR Procedure LIC 800 "Security Review Procedure Enclosure for 10 CFR 50.54(p)(2)," and the NRC endorsed NEI 03-12, Revision 7, template for security plans, as appropriate. In reviewing the changes to the security plans, the NRC staff noted the following: (1) Within the summary of changes the licensee identified an administrative change to Section 18 of the PSP for the purpose of clarifying the configuration of the security response organization; and (2) The information provided in the plans did not address the changes at an adequate level of detail to demonstrate that the change did not represent a decrease in the safeguards effectiveness of the security plans. The NRC staff determined that additional information was necessary to complete its review. On April23, 2013, the NRC staff sent a Request for Additional Information (RAI) to the licensee. On May 23, 2013, the licensee responded to the RAI. The NRC staff reviewed the licensee's response, and concluded that the licensee's response to the RAI adequately addressed the item of NRC staff's concern. Accordingly, based on the additional information, the NRC staff concluded that the licensee's explanations were acceptable, and the NRC staff's review was closed. | | The NRC staff also concluded that the licensee properly demonstrated that the reported changes did not result in a decrease in safeguards effectiveness of their security plans, and no further regulatory actions were needed. |
| | The NRC staff notes that the effectiveness of the implementation of this revision is subject to future NRC review and inspection when required. |
| | Principal Contributor: R. Costa Dated: February 18, 2014 |
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| ==4.0 CONCLUSION==
| | February 18, 2014 Mr. Joseph E. Pacher Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519 |
| The NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p). The NRC staff also concluded that the licensee properly demonstrated that the reported changes did not result in a decrease in safeguards effectiveness of their security plans, and no further regulatory actions were needed. The NRC staff notes that the effectiveness of the implementation of this revision is subject to future NRC review and inspection when required. Principal Contributor: R. Costa Dated: February 18, 2014 February 18, 2014 Mr. Joseph E. Pacher Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
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| ==SUBJECT:== | | ==SUBJECT:== |
| R.E. GINNA NUCLEAR POWER PLANT-REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132) | | R.E. GINNA NUCLEAR POWER PLANT- REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132) |
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| ==Dear Mr. Pacher:== | | ==Dear Mr. Pacher:== |
| By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML 13050A51 0), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2). The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans. Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions. The effectiveness of the implementation of this revision is subject to future NRC review and inspection. Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue. Docket No. 50-244 | | |
| | By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2). |
| | The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans. |
| | Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions. |
| | The effectiveness of the implementation of this revision is subject to future NRC review and inspection. |
| | Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue. |
| | Sincerely, Ira/ |
| | Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrLAKGoldstein JFrost NSIR RidsNrrDoriLpl1-1 RidsAcrsAcnw_MaiiCTR RCosta NSIR ADAMS ACCESSION NO ML 14028A240 " OFFICE LPL1-1/PM LPL1-1/LA NAME MThadani KGoldstein DATE 02/06/14 02/06/14 Sincerely, Ira/ Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrPMREGinna RidsNrrDoriDpr DGordon NSIR NSIRIDSP/BC RFelts* 7/17/2013 LPL 1-1 Reading File RidsRgn 1 MaiiCenter s E input at ML 13169A060 LPL 1-1/BC LPL 1-1/PM BBeasley MThadani 02/14/14 02/18/14 OFFICIAL RECORD COPY | | |
| }} | | Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrDoriLpl1-1 RidsNrrPMREGinna LPL 1-1 Reading File RidsNrrLAKGoldstein RidsAcrsAcnw_MaiiCTR RidsNrrDoriDpr RidsRgn 1MaiiCenter JFrost NSIR RCosta NSIR DGordon NSIR ADAMS ACCESSION NO " ML14028A240 s E input at ML13169A060 OFFICE LPL1-1/PM LPL1-1/LA NSIRIDSP/BC LPL 1-1/BC LPL 1-1/PM NAME MThadani KGoldstein RFelts* BBeasley MThadani DATE 02/06/14 02/06/14 7/17/2013 02/14/14 02/18/14 OFFICIAL RECORD COPY}} |
Letter Sequence Approval |
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Results
Other: L-14-028, August 2014 Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049), L-14-031, August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), ML13254A279, ML13338A663, ML13338A664, ML14069A180, ML15289A526, RS-15-057, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-15-058, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-15-117, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-15-207, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-16-029, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-16-032, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
|
MONTHYEARML13066A1722013-02-28028 February 2013
R. E. Ginna, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation
Project stage: Request
ML13073A1552013-03-0808 March 2013
Supplement to Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation
Project stage: Supplement
ML13154A3992013-06-0505 June 2013
Request for Additional Information - Nine Mile Point Nuclear Station Units 1 and 2 Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Project stage: RAI
ML13197A2202013-07-0505 July 2013
Response to Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Project stage: Response to RAI
ML13254A2792013-08-27027 August 2013
Six-Month Status Report in Response to 03/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Project stage: Other
ML13281A2052013-11-15015 November 2013
Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation
Project stage: Acceptance Review
ML13338A6632013-12-11011 December 2013
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129
Project stage: Other
ML13338A6642013-12-11011 December 2013
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130
Project stage: Other
ML13225A5842013-12-19019 December 2013
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
Project stage: Acceptance Review
ML14028A2402014-02-18018 February 2014
Review of the Changes to the Licensee'S Physical Security Plan and Safeguards Contingency Plan
Project stage: Approval
ML14069A1802014-02-24024 February 2014
February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
Project stage: Other
L-14-031, August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-26026 August 2014
August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
Project stage: Other
L-14-028, August 2014 Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049)2014-08-26026 August 2014
August 2014 Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049)
Project stage: Other
RS-15-057, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-19019 February 2015
February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
Project stage: Other
RS-15-058, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-19019 February 2015
February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
Project stage: Other
ML15110A0262015-04-28028 April 2015
Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051
Project stage: Acceptance Review
RS-15-117, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-06-0808 June 2015
Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
Project stage: Other
RS-15-207, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-08-28028 August 2015
Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
Project stage: Other
ML15289A5262015-10-20020 October 2015
Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049
Project stage: Other
RS-16-029, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016
Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
Project stage: Other
RS-16-032, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-02-26026 February 2016
Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
Project stage: Other
2014-02-18
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Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000244/2024010
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
IR 05000244/20240012024-04-24024 April 2024
LLC - Integrated Inspection Report 05000244/2024001
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24101A0432024-04-10010 April 2024
2024 10 CFR 50.46 Annual Report
IR 05000244/20240112024-04-10010 April 2024
LLC - Fire Protection Team Inspection Report 05000244/2024011
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24088A2042024-03-28028 March 2024
R. E. Ginna Nuclear Power Plant - Response to NRC Request for Additional Information Regarding Relief Request Associated with Inservice Testing of ‘B’ Auxiliary Feedwater Pump
ML24110A0122024-03-28028 March 2024
2023 Report of Individual Monitoring for R.E. Ginna Nuclear Power Plant LLC, License DPR-18
05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam2024-03-0707 March 2024
Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam
IR 05000244/20230062024-02-28028 February 2024
Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC, (Report 05000244/2023006)
IR 05000244/20230042024-02-0505 February 2024
LLC - Integrated Inspection Report 05000244/2023004
ML24026A0112024-01-26026 January 2024
R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of ‘B’ Auxiliary Feedwater Pump
IR 05000244/20230102023-12-19019 December 2023
LLC - Age-Related Degradation Inspection Report 05000244/2023010
ML23348A0992023-12-15015 December 2023
R. E. Ginna Nuclear Power Plant – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23347A0092023-12-13013 December 2023
Annual Commitment Change Notification
ML23346A0142023-12-12012 December 2023
LLC - Senior Reactor and Reactor Operator Initial License Examinations
05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level2023-12-11011 December 2023
Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level
ML23341A1252023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
ML23321A1392023-11-17017 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
05000244/LER-2023-002, Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure2023-11-0808 November 2023
Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure.
IR 05000244/20230032023-10-25025 October 2023
LLC - Integrated Inspection Report 05000244/2023003
ML23292A0282023-10-19019 October 2023
LLC - Notification of Conduct of a Fire Protection Team Inspection
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
ML23258A1382023-09-18018 September 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010
IR 05000244/20230052023-08-31031 August 2023
Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005)
2024-09-25
[Table view]
Category:Safety Evaluation
MONTHYEARML24170A3852024-07-16016 July 2024
R. E. Ginna Nuclear Power Plant - Alternative Associated with Inservice Testing of B Auxiliary Feedwater Pump - PR-03
ML23158A1952023-08-30030 August 2023
R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications
ML23191A0592023-07-21021 July 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23073A3682023-03-16016 March 2023
Authorization and Safety Evaluation for Proposed Alternative I6R-10, Revision 0 Related to the Steam Generators,
ML22364A0242023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
ML23005A1762023-02-23023 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes
ML23005A1222023-02-22022 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
ML22293B8052022-11-30030 November 2022
Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits
ML22094A1072022-06-22022 June 2022
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 151 Adopt 10 CFR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22119A0942022-06-21021 June 2022
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML22090A0862022-04-29029 April 2022
Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position
ML21347A0382022-01-13013 January 2022
Issuance of Amendments to Revise Reactor Coolant Leakage Requirements
ML21277A2482021-11-16016 November 2021
Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version)
ML21250A3822021-09-29029 September 2021
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request I6R-06 Alternate Inspection for Reactor Vessel Internals
ML21246A1062021-09-22022 September 2021
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval
ML21230A2062021-09-0303 September 2021
Proposed Alternative to Use ASME OM Code Case OMN-28
ML21216A2202021-08-0505 August 2021
Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting
ML21175A0012021-07-27027 July 2021
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 145 Regarding Technical Specifications Change to Make a One-Time Exception to the Steam Generator Tube Inspection Requirements
ML21166A1682021-06-25025 June 2021
ML20353A1262021-03-11011 March 2021
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation
ML21039A6362021-02-17017 February 2021
R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885
ML21028A6732021-02-0303 February 2021
Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011
ML20287A1302020-11-0505 November 2020
Review of Quality Assurance Program Changes
ML20269A2002020-09-30030 September 2020
Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117
ML20167A0072020-09-11011 September 2020
R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues
ML20232A1712020-09-0101 September 2020
Request to Use Alternative Code Case OMN-26
ML20141L6362020-07-10010 July 2020
Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2
ML20134H9402020-07-0808 July 2020
Issuance of Amendments Revising the High Radiation Area Administrative Controls
ML20090D2912020-06-0202 June 2020
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0071). Supersedes ML20056D559
ML20113F0412020-04-30030 April 2020
Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19)
ML20021A0702020-04-0606 April 2020
Issuance of Amendments to Delete License Conditions for Decommissioning Trusts
ML20057E0912020-04-0303 April 2020
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method
ML20056D5592020-03-13013 March 2020
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval
ML20055F8862020-03-13013 March 2020
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-01 for the Sixth 10-Year Inservice Inspection Interval
ML19325D8242019-12-23023 December 2019
R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency
ML19318E0802019-12-0202 December 2019
R. E. Ginna Nuclear Power Plant - Safety Evaluation of Alternative Request SR-1 Related to Snubber Program Aligned with Sixth 10-Year Inservice Testing Interval Program
ML19252A2462019-10-29029 October 2019
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements
ML19269C5342019-09-27027 September 2019
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
ML19205A4532019-08-0505 August 2019
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program
ML19205A3532019-08-0505 August 2019
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives GR-01, VR-01, and VR-02 for the Sixth 10-Year Inservice Testing Program (EPID L-2018-LLR-0382; EPID L-2018-LLR-0383)
ML19192A2442019-07-18018 July 2019
Proposed Alternative to Use ASME Code Cases N-878 and N-880
ML19100A0042019-04-22022 April 2019
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request ISI-18 Regarding Fifth 10-Year Inservice Inspection Program Interval
ML18309A3012018-11-15015 November 2018
R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements
ML18213A3692018-11-13013 November 2018
Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation
ML18295A6302018-10-31031 October 2018
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF 547, Clarification of Rod Position Requirements
ML18214A1762018-08-31031 August 2018
Issuance of Amendment No. 130, Revise Technical Specification Surveillance Requirement 3.8.4.3, DC (Direct Current) Sources - Modes 1, 2, 3, and 4
ML18206A2822018-08-0202 August 2018
Issuance of Amendments to Relocate the Staff Qualification Requirements
ML18190A4722018-07-12012 July 2018
R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253)
ML18137A6142018-06-26026 June 2018
Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes
2024-07-16
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Febeuary 18, 2014
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT- REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132)
Dear Mr. Pacher:
By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (1 0 CFR) 50.54(p)(2).
The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC BOO "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans.
Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54{p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions.
The effectiveness of the implementation of this revision is subject to future NRC review and inspection.
Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue.
Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR SECURITY AND INCIDENTRESPONSE CHANGES TO SECURITY PLAN CONSTELLATION ENERGY NUCLEAR GROUP R. E. GINNA NUCLEAR POWER PLANT DOCKET NO 50-244
1.0 INTRODUCTION
By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R. E. Ginna Nuclear Power Plant's (Ginna's) Physical Security Plan (PSP}, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2). This revision was performed to better delineate the required number of security personnel used at Ginna to effectively implement the protective strategy as described in the PSP.
The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes to the PSP consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident response (NSIR)
Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)" and the NRC endorsed Nuclear Energy Institute (NEI) guidance 03-12, Revision 7, template for security plans, as appropriate. The review was required to better delineate the number of personnel required at Ginna and to verify that the changes made did not reduce the effectiveness of the plans.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.54(p)(2), the licensee may make changes to the plans without prior Commission approval if the changes do not decrease the safeguards effectiveness of the security plans. The licensee must submit a report to the NRC containing the description of each change, within two months after changes are made.
The NRC staff reviewed the licensee's submittal to determine whether the licensee properly concluded that changes did not decrease the safeguards effectiveness of the Commission-approved security plans.
3.0 TECHNICAL EVALUATION
The NRC staff compared the licensee's changes with the previous revision of the licensee's security plans and reviewed the submittal against applicable requirements of 10 CFR Part 73 as well as the guidance contained within the NSIR Procedure LIC 800 "Security Review Procedure Enclosure
for 10 CFR 50.54(p)(2)," and the NRC endorsed NEI 03-12, Revision 7, template for security plans, as appropriate.
In reviewing the changes to the security plans, the NRC staff noted the following: (1) Within the summary of changes the licensee identified an administrative change to Section 18 of the PSP for the purpose of clarifying the configuration of the security response organization; and (2) The information provided in the plans did not address the changes at an adequate level of detail to demonstrate that the change did not represent a decrease in the safeguards effectiveness of the security plans.
The NRC staff determined that additional information was necessary to complete its review. On April23, 2013, the NRC staff sent a Request for Additional Information (RAI) to the licensee.
On May 23, 2013, the licensee responded to the RAI.
The NRC staff reviewed the licensee's response, and concluded that the licensee's response to the RAI adequately addressed the item of NRC staff's concern. Accordingly, based on the additional information, the NRC staff concluded that the licensee's explanations were acceptable, and the NRC staff's review was closed.
4.0 CONCLUSION
The NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p).
The NRC staff also concluded that the licensee properly demonstrated that the reported changes did not result in a decrease in safeguards effectiveness of their security plans, and no further regulatory actions were needed.
The NRC staff notes that the effectiveness of the implementation of this revision is subject to future NRC review and inspection when required.
Principal Contributor: R. Costa Dated: February 18, 2014
February 18, 2014 Mr. Joseph E. Pacher Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT- REVIEW OF THE CHANGES TO THE LICENSEE'S PHYSICAL SECURITY PLAN AND SAFEGUARDS CONTINGENCY PLAN (TAC NO. MF1132)
Dear Mr. Pacher:
By letter dated February 14, 2013 (Agencywide Documents Access and Management System Accession No. ML13050A510), Constellation Energy Nuclear Group, submitted the R.E. Ginna Nuclear Power Plant's Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(p)(2).
The Nuclear Regulatory Commission (NRC) staff conducted the review of the licensee's changes consistent with the applicable requirements of 10 CFR Part 73 as well as the guidance contained within the Office of Nuclear Security and Incident Response Procedure LIC 800 "Security Review Procedure for 10 CFR 50.54(p)(2)," and the NRC endorsed Nuclear Energy Institute's (NEI) guidance 03-12, Revision 7, template for security plans.
Based on its review, the NRC staff concluded that the reported changes were implemented consistent with the provisions of 10 CFR 50.54(p), the licensee properly concluded that the reported changes did not result in a decrease in safeguards effectiveness of the security plans and the NRC staff recommends no further regulatory actions.
The effectiveness of the implementation of this revision is subject to future NRC review and inspection.
Please contact me at (301) 415-1476, or email Mohan.Thadani@nrc.gov, if you have any questions on this issue.
Sincerely, Ira/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDoriLpl1-1 RidsNrrPMREGinna LPL 1-1 Reading File RidsNrrLAKGoldstein RidsAcrsAcnw_MaiiCTR RidsNrrDoriDpr RidsRgn 1MaiiCenter JFrost NSIR RCosta NSIR DGordon NSIR ADAMS ACCESSION NO " ML14028A240 s E input at ML13169A060 OFFICE LPL1-1/PM LPL1-1/LA NSIRIDSP/BC LPL 1-1/BC LPL 1-1/PM NAME MThadani KGoldstein RFelts* BBeasley MThadani DATE 02/06/14 02/06/14 7/17/2013 02/14/14 02/18/14 OFFICIAL RECORD COPY
