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| | number = ML17026A284 | | | number = ML17026A284 |
| | issue date = 01/23/2017 | | | issue date = 01/23/2017 |
| | title = Joseph M. Farley Nuclear Plant - Emergency Preparedness Inspection and Request for Information | | | title = Emergency Preparedness Inspection and Request for Information |
| | author name = Bonser B R | | | author name = Bonser B R |
| | author affiliation = NRC/RGN-II/DRS/PSB1 | | | author affiliation = NRC/RGN-II/DRS/PSB1 |
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Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-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 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 ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time 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-24-0230, 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-24-0234, 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-24-0143, 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 05000348/LER-2024-002-01, 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) 05000348/LER-2024-001, 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 05000364/LER-2024-002, 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 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 January 23, 2017
Ms. Cheryl Gayheart Vice President Nuclear Plant Site
Southern Nuclear Operating Company, Inc.
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - EMERGENCY PREPAREDNESS INSPECTION AND REQUEST FOR INFORMATION
Dear Ms. Gayheart:
From April 10-14, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a baseline Emergency Preparedness program inspection at the Joseph M. Farley Nuclear Plant. The inspection will evaluate activities in the Emergency Preparedness cornerstone using NRC Inspection Procedures (IPs) 71114.02, Alert and Notification System Evaluation; 71114.03, Emergency Response Organization Staffing and Augmentation System; 71114.04, Emergency Action Level and Emergency Plan Changes; 71114.05, Maintenance of Emergency Preparedness; and Emergency Preparedness sections of 71151 Performance Indicator Verification.
Experience has shown that this inspection is resource-intens ive for both the NRC inspectors and your staff. To minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. It is important that all of these documents are up-to-date, and complete, to minimize the number of additional documents requested during the preparation, and/or the onsite portions of the inspection.
We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Mr. David Simmons (334-814-4618) of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Steven Sanchez at 404-997-4418 (steven.sanchez@nrc.gov
), or the Chief, Plant Support Branch 1, Brian Bonser at 404-997-4653.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public inspections, exemptions, requests for withholding," of the NRC's "Agency Rules of Practice and Procedure," 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)
C. Gayheart 2 component of NRC's Agencywide Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA: Wade T. Loo for/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety
Docket Nos. 50-348 and 50-364 License Nos. NPF-2 and NPF-8
Enclosure:
Document Request List
cc: Distribution via Listserv
SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS/PSB1 RII:DRS/PSB1 RII:DRS/PSB1 SIGNATURE JDH9 WTL FOR SPS WTL FOR BRB1 NAME J. Hickman S. Sanchez B. Bonser DATE 1/19/2017 1/23/2017 1/23/2017 E-MAIL COPY YES NO YES NO YES NO Enclosure Document Request List Inspection Dates: April 10-14, 2017 Inspection Procedures (IPs): 71114.02 Alert and Notification System Evaluation 71114.03 Emergency Response Organization Staffing and Augmentation System 71114.04 Emergency Action Level and Emergency Plan Changes 71114.05 Maintenance of Emergency Preparedness 71151 Performance Indicator Verification Note: This is a list of the documents to be provided to the inspectors. The current version of these documents is expected unless specified otherwise. About 3 weeks prior to the inspection, provide, as a minimum, an electronic version of the Emergency Plan (E-Plan), 10 CFR 50.54(q) evaluation/screening packages of changed Emergency Action Level (EAL), E-Plan, and EP implementing procedures, and Corrective Action Program (CAP) entries relating to EP, for the 2-year inspection period (including those written by Corporate). The preferred file format is
Word or searchable ".pdf" files on CDROM. [Note that the inspectors cannot accept data provided on USB or "flash" drives due to NRC IT security policies.] Please organize the information as it is arranged below (e.g., a folder labeled "Miscellaneous"). It is not the intent that large or burdensome data be scanned for this purpose (e.g., Performance Indicator documents). This data will be inspected using original documentation. Material can be
provided prior to the inspection to the NRC Region II Office (ATTN: Steven Sanchez), 245 Peachtree Center Avenue, NE, Suite 1200, Atlanta, GA 30303-1257. If there are questions regarding the documents requested, please do not hesitate to contact the lead inspector. 71114.02 Alert and Notification System Evaluation Federal Emergency Management Agency (FEMA) approved Alert and Notification System (ANS) report and any currently associated correspondence ANS testing procedure ANS equipment technical manual ANS equipment testing results (raw data) for the 2-year inspection period ANS equipment maintenance records for the 2-year inspection period Changes to the ANS system, implementing procedures, testing procedures, and the maintenance program including any supporting FEMA approval letters for the past 2 years Information provided to the public inside the 10-mile plume exposure pathway CAP entries related to the ANS for the 2-year inspection period (including those written by Corporate) 71114.03 Emergency Response Organization Staffing and Augmentation System Current Emergency Response Organization (ERO) roster ERO Duty Roster in-effect during the week of the inspection (can be provided upon arrival) ERO and augmentation implementing procedures and changes made over the past 2 years NUREG 0654 Table B1 site equivalent ERO training program procedure Emergency Preparedness (EP) staff training program and qualification records ERO augmentation testing results for the 2-year inspection period CAP entries related to ERO staffing and augmentation for the 2-year inspection period (including those written by Corporate)
2 71114.04 Emergency Action Level and Emergency Plan Changes Governing document for 10 CFR 50.54(q) evaluation process 10 CFR 50.54(q) evaluator training program and qualification records 10 CFR 50.54(q) evaluation/screening packages of changed Emergency Action Level (EAL), E-Plan, and EP implementing procedures (including corporate procedures) Current and immediately previous revisions of EAL, E-Plan, and EP procedures (electronic version of current E-Plan requested about 3 weeks before inspection) CAP entries related to EAL and E-Plan changes since the last NRC EP inspection (including those written by Corporate) 71114.05 Maintenance of Emergency Preparedness Governing documents for the assessment process All EP program assessments, not including INPO performed assessments, for the 2-year inspection period 10 CFR 50.54(t) audits, audit checklists, and subsequent State/local correspondence for the 2-year inspection period Drill and exercise critiques for the 2-year inspection period Critiques of actual events resulting in implementation of the E-Plan over the past 2 years Governing documents for 10 CFR 50.54(q) evaluation process Emergency Response Facility (ERF) activation procedures, including backup and alternate facilities Completed maintenance records and availability-tracking information for equipment important to EP (e.g., Heating and Ventilation system in ERFs and Radiation Monitors called out in EALs, etc.) for the 2-year inspection period Last Evacuation Time Estimates Analysis and annual review documentation CAP governing procedures CAP entries relating to EP (abbreviated format, i.e., identifier and brief description only) for the 2-year inspection period with the risk-significant related entries separated (including those written by Corporate)
71151 Performance Indicator Verification Governing document for the performance indicator (PI) process Drill and Exercise Performance (DEP), ERO, and ANS PI data submitted since the last NRC EP inspection (hard copies can be provided upon arrival) DEP documentation and evaluations since the last NRC EP inspection CAP entries related to PIs, that is DEP, ERO training and participation, and ANS since the last NRC EP inspection (including those written by Corporate)
Miscellaneous Procedures and Records Safety Evaluation Report approved E-Plan and EALs Corporate and Departmental processes or procedures for EP staff Matrix of Drill Types performed and accounted for during the 8-year cycle Lead Inspector Contact Information: Steven Sanchez 404-997-4418 steven.sanchez@nrc.gov