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| {{Adams | | {{Adams |
| | number = ML12193A563 | | | number = ML12024A011 |
| | issue date = 08/16/2012 | | | issue date = 01/30/2012 |
| | title = IR 05000352-12-202 & 05000353-12-202, 07/05/2012, Limerick Generating Station - Security | | | title = IR 05000352-12-201, 05000353-12-201; January 9, 2012 Through January 11, 2012, Limerick Generating Station, Units 1 and 2; Target Set Inspection. Cover Letter |
| | author name = Johnson R C | | | author name = West G |
| | author affiliation = NRC/NSIR/DSO/DDSO/SPEB | | | author affiliation = NRC/NSIR/DSO |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000352, 05000353 | | | docket = 05000352, 05000353 |
| | license number = NPF-039, NPF-085 | | | license number = NPF-039, NPF-085 |
| | contact person = | | | contact person = |
| | document report number = IR-12-202 | | | document report number = IR-12-201 |
| | | package number = ML12024A010 |
| | document type = Letter | | | document type = Letter |
| | page count = 3 | | | page count = 2 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:ary 30, 2012 |
| [[Issue date::August 16, 2012]]
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| Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road.
| | ==SUBJECT:== |
| | LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000352/2012201 AND 05000353/2012201 |
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| Warrenville, IL 60555
| | ==Dear Mr. Pacilio:== |
| | On January 11, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at the Limerick Generating Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on January 11, 2012, with Mr. B. Maguire, Site Vice President, and other members of your staff. |
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| SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000352/2012202 AND 05000353/2012202
| | The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| ==Dear Mr. Pacilio:==
| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| On July 5, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Limerick Generating Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed via telephone on July 5, 2012, with Mr. Thomas Dougherty, Vice President, Limerick Generating Station and other members of your staff. The inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. No findings were identified during this inspection. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, the material enclosed herewith contains Safeguards Information as defined by 10 CFR 73.21 and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if security-related information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information- withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
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| | Based on the results of this inspection, no findings of significance were identified. |
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| Sincerely,/RA by Kenneth Brooks for/ Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 05000352, 05000353 License Nos. NPF-39, NPF-85 Nonpublic
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's |
| | "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection. |
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| ===Enclosure:===
| | In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Security-Related Information - Withhold Under 10 CFR 2.390 and follow the instructions for withholding in 10 CFR 2.390(b)(1). |
| Inspection Report 05000352/2012202 and 05000353/2012202
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| ===w/Attachments:===
| | Sincerely, |
| Supplemental Information cc w/encl: K. Kemper, Limerick Generating Station cc w/o encl: M. Jesse, Exelon | | /RA/ |
| | Garmon West, Chief Security Training and Support Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-352; 50-353 License Nos. NPF-39; NPF-85 Enclosure: Inspection Report 05000352/2012201 and 05000353/2012201 w/Attachments: |
| | Supplemental Information |
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Category:Letter
MONTHYEARML24303A0902024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000352/20240122024-10-17017 October 2024 Commercial Grade Dedication Inspection Report 05000352/2024012 and 05000353/2024012 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24274A2372024-10-0707 October 2024 – Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications ML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A0032024-09-27027 September 2024 Generation Station, Units 1 and 2 – Regulatory Audit Plan Supporting Review of the Component Interface Module System of the Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) (Redacted) ML24243A0482024-09-19019 September 2024 Generation Station, Unit Nos. 1 and 2 - Schedule Update for License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24215A4042024-09-18018 September 2024 Request for Withholding Information from Public Disclosure IR 05000352/20244202024-09-16016 September 2024 – Security Baseline Inspection Report 05000352/2024420 and 05000353/2024420 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds IR 05000352/20250102024-09-10010 September 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000352/2025010 and 05000353/2025010 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000352/20230022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000352/2023002 and 05000353/2023002 IR 05000352/20240052024-08-29029 August 2024 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2024005 and 05000353/2024005) ML24241A1952024-08-28028 August 2024 License Amendment Request for Modification to Technical Specification 3.6.1.2 and Main Steam Isolation Valve Leakage Rate Requirements ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24163A3902024-08-14014 August 2024 Request for Withholding Information from Public Disclosure IR 05000352/20240022024-08-12012 August 2024 Integrated Inspection Report 05000352/2024002 and 05000353/2024002 ML24220A2392024-08-12012 August 2024 Correction to Technical Specification Page 3/4 3-11 in Amendment No. 225 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for 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 ML24204A0712024-07-29029 July 2024 Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature ML24208A1592024-07-25025 July 2024 Regulatory Audit Plan Supporting Review of the System Development Portion of Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24201A1662024-07-19019 July 2024 Response to Request for Additional Information for License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam L ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24180A1572024-06-28028 June 2024 Request to Return and Replace WEC Documents (EQ-EV-386-GLIM, EQ-QR- 433-GLIM, and APP-GW-GLR-611), to Meet 10CFR2.390 Request to Withdraw from Public Disclosure Requirements ML24170A7702024-06-20020 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing(Epid L-2024-LLA-0079) LTR 05000352/LER-2024-003, Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK1232024-06-18018 June 2024 Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK123 ML24166A1142024-06-14014 June 2024 Response to Requests for Additional Information (RAIs 15 Through 23) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24165A2642024-06-13013 June 2024 License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam Line Tunnel Temperature TS 3/4.7.9 05000352/LER-2024-001, Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit2024-06-10010 June 2024 Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit 05000352/LER-2024-002, Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker2024-06-10010 June 2024 Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker ML24151A2012024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24151A2882024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24150A0242024-05-29029 May 2024 Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information ML24149A2112024-05-28028 May 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000352/20243022024-05-20020 May 2024 Revised Initial Operator Licensing Examination Report 05000352/2024302 and 05000353/2024302 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000352/20240012024-05-0707 May 2024 Integrated Inspection Report 05000352/2024001 and 05000353/2024001 ML24124A0432024-05-0303 May 2024 Response to Requests for Additional Information (RAIs 9 Through 14) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 ML24114A3222024-04-23023 April 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) - Pivot to Unit ML24109A0702024-04-18018 April 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFRC50.52 ATWS Rule to Support the Digital Modernization Project Installation . ML24093A0912024-04-17017 April 2024 Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24106A1832024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases 2024-09-06
[Table view] |
Text
ary 30, 2012
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000352/2012201 AND 05000353/2012201
Dear Mr. Pacilio:
On January 11, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at the Limerick Generating Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on January 11, 2012, with Mr. B. Maguire, Site Vice President, and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's
"Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Security-Related Information - Withhold Under 10 CFR 2.390 and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely,
/RA/
Garmon West, Chief Security Training and Support Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-352; 50-353 License Nos. NPF-39; NPF-85 Enclosure: Inspection Report 05000352/2012201 and 05000353/2012201 w/Attachments:
Supplemental Information