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| | number = ML17060A353 | | | number = ML17060A353 |
| | issue date = 03/10/2017 | | | issue date = 03/10/2017 |
| | title = Joseph M. Farley Nuclear Plant - NRC Security Inspection Report 05000348/2017201 and 05000364/2017201 | | | title = NRC Security Inspection Report 05000348/2017201 and 05000364/2017201 |
| | author name = Johnson R C | | | author name = Johnson R |
| | author affiliation = NRC/NSIR/DSO/DDSO/SPEB | | | author affiliation = NRC/NSIR/DSO/DDSO/SPEB |
| | addressee name = Madison D | | | addressee name = Madison D |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:rch 10, 2017 |
| [[Issue date::March 10, 2017]]
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| Mr. Dennis Madison Site Vice President Southern Nuclear Operating Company, Inc.
| | ==SUBJECT:== |
| | | JOSEPH M. FARLEY NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000348/2017201 AND 05000364/2017201 |
| Joseph M. Farley Nuclear Plant
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| 7388 North State Highway 95
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| Columbia, AL 36319
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| SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000348/2017201 AND 05000364/2017201 | |
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| ==Dear Mr. Madison:== | | ==Dear Mr. Madison:== |
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| The NRC inspectors did not identify any findings or violations of more than minor significance. | | The NRC inspectors did not identify any findings or violations of more than minor significance. |
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| This letter will be available for public inspection at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Request for Withholding." | | This letter will be available for public inspection at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Request for Withholding. |
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| The enclosed report contains Safeguards Information as defined by 10 CFR 73.21, "Protection of Safeguards Information: Performance Requirements," and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended.
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| Therefore, the material enclosed report will not be made publicly available. If you choose to provide a response that contains Safeguards Information, please provide the level of protection described in 10 CFR 73.21. Otherwise, if you choose to provide a response that contains Security-Related Information, 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).
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| The enclosure transmitted herewith contains Safeguards Information. When separated from the enclosure
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| , this transmittal document is decontrolled. In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
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| Sincerely,/RA/
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| Robert C. Johnson, Chief
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| Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response
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| Docket Nos. 50-348, 50-364
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| License Nos. NPF-2, NPF-8 Nonpublic
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| ===Enclosure:===
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| Inspection Report 05000348/2017201 and 05000364/2017201
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| ===w/Attachment:===
| | The enclosed report contains Safeguards Information as defined by 10 CFR 73.21, Protection of Safeguards Information: Performance Requirements, and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. |
| Supplemental Information
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| cc w/o enclosure: Danny Bost, Executive Vice President and Chief Nuclear Officer Lyle Brian Askren, Site Security Manager
| | Therefore, the material enclosed report will not be made publicly available. If you choose to provide a response that contains Safeguards Information, please provide the level of protection described in 10 CFR 73.21. Otherwise, if you choose to provide a response that contains Security-Related Information, 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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| ML17060A353 Entire Report: SUNSI Review Complete By: Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: MD 3.4 Non-Public A.3 Cover Letter Only: SUNSI Review Complete By: Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: SUNSI Review Complete OFFICE NSIR/DSO/SPEB NSIR/DSO/SPEB NSIR/DSO/SPEB RII NSIR/DSO.SPEB NAME D. Hostetter J. Clark J. Berry B. Desai C. Johnson SIGNATURE DGolden via email DATE 2 / 23 /2017 2 / 27 /2017 3 / 1 /2017 03/02 /2017 03/ 10 /2017 | | Sincerely, |
| | /RA/ |
| | Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8 Nonpublic Enclosure: Inspection Report 05000348/2017201 and 05000364/2017201 w/Attachment: Supplemental Information cc w/o enclosure: Danny Bost, Executive Vice President and Chief Nuclear Officer Lyle Brian Askren, Site Security Manager ML17060A353 Entire Report: Non-Sensitive Publicly Available Keyword: |
| | SUNSI Review Complete Sensitive Non-Publicly Available MD 3.4 Non-Public A.3 By: |
| | Cover Letter Only: Non-Sensitive Publicly Available Keyword: |
| | SUNSI Review Complete Sensitive Non-Publicly Available SUNSI Review Complete By: |
| | OFFICE NSIR/DSO/SPEB NSIR/DSO/SPEB NSIR/DSO/SPEB RII NSIR/DSO.SPEB NAME D. Hostetter J. Clark J. Berry B. Desai C. Johnson SIGNATURE DGolden via email DATE 2 / 23 /2017 2 / 27 /2017 3 / 1 /2017 03/02 /2017 03/ 10 /2017 |
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Category:Letter
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 IR 05000348/20230062024-02-28028 February 2024 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2023006 and 05000364/2023006 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers 2024-09-05
[Table view] |
Text
rch 10, 2017
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000348/2017201 AND 05000364/2017201
Dear Mr. Madison:
On February 23, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2. NRC inspectors discussed results of this inspection with Mr. Lyle Brian Askren, Site Security Manager, and other members of your staff. The results of this inspection are documented in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
This letter will be available for public inspection at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Request for Withholding.
The enclosed report contains Safeguards Information as defined by 10 CFR 73.21, Protection of Safeguards Information: Performance Requirements, and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended.
Therefore, the material enclosed report will not be made publicly available. If you choose to provide a response that contains Safeguards Information, please provide the level of protection described in 10 CFR 73.21. Otherwise, if you choose to provide a response that contains Security-Related Information, 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.
Sincerely,
/RA/
Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8 Nonpublic Enclosure: Inspection Report 05000348/2017201 and 05000364/2017201 w/Attachment: Supplemental Information cc w/o enclosure: Danny Bost, Executive Vice President and Chief Nuclear Officer Lyle Brian Askren, Site Security Manager ML17060A353 Entire Report: Non-Sensitive Publicly Available Keyword:
SUNSI Review Complete Sensitive Non-Publicly Available MD 3.4 Non-Public A.3 By:
Cover Letter Only: Non-Sensitive Publicly Available Keyword:
SUNSI Review Complete Sensitive Non-Publicly Available SUNSI Review Complete By:
OFFICE NSIR/DSO/SPEB NSIR/DSO/SPEB NSIR/DSO/SPEB RII NSIR/DSO.SPEB NAME D. Hostetter J. Clark J. Berry B. Desai C. Johnson SIGNATURE DGolden via email DATE 2 / 23 /2017 2 / 27 /2017 3 / 1 /2017 03/02 /2017 03/ 10 /2017