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Category:Inspection Report
MONTHYEARIR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 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 IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 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 IR 05000348/20230042024-02-0909 February 2024 Integrated Inspection Report 05000348/2023004 and 05000364/2023004 and Exercise of Enforcement Discretion IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 IR 05000348/20230112023-04-13013 April 2023 Biennial Problem Identification and Resolution Inspection Report 05000348/2023011 and 05000364/2023011 IR 05000348/20234012023-03-31031 March 2023 Security Baseline Inspection Report 05000348/2023401 and 05000364/2023401 IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 IR 05000348/20220112023-02-16016 February 2023 NRC Inspection Report 05000348/2022011 IR 05000348/20220902023-02-16016 February 2023 NRC Inspection Report 05000348/2022090 IR 05000348/20220042023-01-23023 January 2023 Integrated Inspection Report 05000348/2022004 and 05000364/2022004 ML22343A0382022-12-13013 December 2022 Notification of Joseph M. Farley Nuclear Plant Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20224042022-11-29029 November 2022 Security Baseline Inspection Report 05000348/2022404 and 05000364/2022404 IR 05000348/20224402022-11-0707 November 2022 Special Inspection Report 05000348/2022440 and 05000364/ 2022440 and Preliminary Greater than Green Finding and and Apparent Violation (Cover Letter) IR 05000348/20220032022-10-28028 October 2022 Integrated Inspection Report 05000348/2022003 and 05000364/2022003 IR 05000348/20220502022-09-30030 September 2022 Special Inspection Reactive Report 05000348/2022050 and Apparent Violation IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 IR 05000348/20220022022-08-12012 August 2022 Integrated Inspection Report 05000348/2022002 and 05000364/2022002 ML22214B8262022-08-0404 August 2022 Security Baseline Inspection Report 05000348/2022403 and 05000364/2022403 IR 05000348/20233012022-08-0101 August 2022 Notification of Licensed Operator Initial Examination 05000348/2023301 and 05000364/2023301 IR 05000348/20224022022-07-26026 July 2022 Security Baseline Inspection Report 05000348/2022402 and 05000364/2022402 IR 05000348/20224012022-05-0606 May 2022 Cyber Security Inspection Report 05000348/2022401 and 05000364/2022401 IR 05000348/20220012022-05-0404 May 2022 Integrated Inspection Report 05000348/2022001 and 05000364/2022001 IR 05000348/20220102022-03-22022 March 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000348/2022010 and 05000364/2022010 IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210042022-02-0808 February 2022 Integrated Inspection Report 05000348/2021004 and 05000364/2021004 IR 05000348/20210112021-12-13013 December 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000348/2021011 and 05000364/2021011 ML21347A4422021-12-13013 December 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000348/2022401; 05000364/2022401 IR 05000348/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000348/2021403 and 05000364/2021403 IR 05000348/20210032021-11-10010 November 2021 Integrated Inspection Report 05000348/2021003, 05000364/2021003, and 07200042/2021001 IR 05000348/20214022021-09-15015 September 2021 Security Baseline Inspection Report 05000348/2021402 and 05000364/2021402 IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) IR 05000348/20213012021-08-18018 August 2021 NRC Operator License Examination Report 05000348/2021301 and 05000364/2021301 IR 05000348/20210022021-07-30030 July 2021 Integrated Inspection Report 05000348/2021002 and 05000364/2021002 and Exercise of Enforcement Discretion 2024-09-10
[Table view] Category:Inspection Report Correspondence
MONTHYEARIR 05000348/20164052016-06-21021 June 2016 NRC Security Target Set Inspection Report 05000348/2016405 and 05000364/2016405: Cover Letter ML0811406982008-04-23023 April 2008 IR 05000348-08-301 and 05000364-08-301, on 04/17/2008, Reactor and Senior Reactor Operator Initial Examinations - Joseph M. Farley Nuclear Plant ML0734802412007-12-10010 December 2007 IR 05000348-08-006 & 05000364-08-006, on 02/26-28/2008 & 03/17-21/2008 and 03/31-04/04/2008, Southern Nuclear Operating Co. Inc Notification of Triennial Fire Protection Baseline Inspection IR 05000348/20075012007-10-12012 October 2007 IR 05000348-07-501, 05000364-07-501, on 09/10-14/2007, Joseph M. Farley Nuclear Plant, Baseline Inspection IR 05000348/20052042007-10-0303 October 2007 Letter to Mr. R. Johnson Joseph M. Farley Nuclear Plant, Units 1 and 2 - NRC Material Control and Accounting Program Inspection Report Nos. 5000348/2005204 and 05000364/2005204 IR 05000348/20070032007-07-30030 July 2007 IR 05000348-07-003 and 05000364-07-003, on 04/01/2007 - 06/30/2007, Joseph M. Farley Nuclear Plant, Units 1 & 2, Routine Integrated Report IR 05000348/20074012007-03-30030 March 2007 NRC Security Inspection Report 05000348/2007401 and 05000364/2007401 ML0633300552006-11-28028 November 2006 Notification of Inspection and Request for Information IR 05000348/20060072006-09-27027 September 2006 IR 05000348/2006007 and 05000364/2006007 - Safeguards Information Removed IR 05000348/20060062006-09-22022 September 2006 IR 05000348-06-006, IR 05000364-06-006, on 06/26 - 08/18/2006, Joseph M. Farley Nuclear Plant IR 05000348/20010072001-06-21021 June 2001 IR 05000348/2001007 and 05000364/2001007, Southern Nuclear Operating Company, Inc., Farley Nuclear Plant 2016-06-21
[Table view] 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-24-0259, 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 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 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 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 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-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 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-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 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-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 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 2024-09-05
[Table view] |
Text
ber 12, 2007
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000348/2007501 AND 05000364/2007501
Dear Mr. R. Johnson:
On September 14, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2.
The enclosed inspection report documents the inspection results, which were discussed on September 14, 2007, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety 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 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8
Enclosure:
NRC Inspection Report No. 05000348/2007501, 05000364/2007501w/Attachment:
Supplemental Information
REGION II==
Docket Nos: 50-348, 50-364 License Nos: NPF-2, NPF-8 Report Nos: 05000348/2007501, 05000364/2007501 Licensee: Southern Nuclear Operating Company Facility: J. M. Farley Nuclear Plant Location: Columbia, AL 36319 Dates: September 10 - 14, 2007 Inspector: L. Miller, Senior Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000348/2007501, 05000364/2007501;09/10-14/2007;Joseph M. Farley Nuclear Plant;
Baseline Inspection.
The report covered an announced inspection by one emergency preparedness inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
.
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP2 Alert and Notification System Evaluation
a. Inspection Scope
The inspector evaluated the adequacy of licensees methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, Alert and Notification System (ANS) Testing. The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, was also used as a reference.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis.
b. Findings
No findings of significance were identified.
1EP3 Emergency Response Organization (ERO) Staffing and Augmentation System
a. Inspection Scope
The inspector reviewed the licensees ERO augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection were reviewed to assess the effectiveness of corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, Emergency Response Organization (ERO) Augmentation Testing.
The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on an biennial basis.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes
a. Inspection Scope
The inspectors review of revisions to the emergency plan, implementing procedures and EAL changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q)reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The inspector reviewed Farley Emergency Plan Revisions 46, 47, and 48 and changes to the implementing procedures from September 2006 to September 2007.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standard (PS), 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUMARC/NESP-007, Methodology for Development of Emergency Action Levels, Revision 2, Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, and Regulatory Guide 1.101 were also used as references.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the EAL and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified.
1EP5 Correction of Emergency Preparedness Weaknesses
a. Inspection Scope
The inspector reviewed the corrective actions identified through the Emergency Preparedness (EP) program to determine the significance of the issues and to determine if repeat problems were occurring. The facilitys self-assessments and audits were reviewed to assess the licensees ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspector reviewed licensees self-assessments and audits to assess the completeness and effectiveness of all EP-related corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, Correction of Emergency Preparedness Weaknesses and Deficiencies. The applicable planning standard, 10 CFR 50.47(b)(14) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the correction of emergency preparedness weaknesses on an biennial basis.
Findings No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
The inspector sampled licensee submittals for the three performance indicators (PIs)listed below for units one and two. For each of the submittals reviewed, the inspector looked at the period from third quarter 2006 through the second quarter 2007. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Indicator Guideline, Revision 4, were used to verify the basis in reporting for each data element.
- Emergency Response Organization Drill/Exercise Performance (DEP)
- Emergency Response Organization Readiness (ERO)
- Alert and Notification System Reliability (ANS)
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspector also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.
The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. The applicable PI, 10 CFR 50.9 and NEI 99-02, Revision 4, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection satisfied three inspection samples for PI verification on an annual basis.
b. Findings
No findings of significance were identified.
4OA6 Meetings, including Exit
On September 14, 2007, the lead inspector presented the inspection results to you, and other members of your staff. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- R. Johnson, Vice President - Farley
- W. Bargeron, Plant Manager
- B. Moore, Site Support Manager
- R. Wells, Operations Manager
- J. Horn, Training Manager
- S. Chestnut, Engineering Support Manager
- C. Thornell, Maintenance Manager
- R. Bayne, Performance Improvement Supervisor
- W. Oldfield, Quality Assurance Supervisor
- R. Vanderbye, Emergency Preparedness Coordinator
LIST OF DOCUMENTS REVIEWED