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Category:Inspection Plan
MONTHYEARIR 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 ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML24037A1362024-02-0606 February 2024 RP DLR Feb. 2024 ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML23335A0112023-12-0101 December 2023 IP 95001 Inspection Notification and Request for Information (EA-23-080) ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) 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 ML22347A0882022-12-13013 December 2022 Final Farley Pi_R Initial RFI (2023) 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 ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22101A2862022-04-0101 April 2022 RQ Inspection Corporate Notification Letter 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 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) ML20302A0002020-10-28028 October 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20175A1992020-06-23023 June 2020 Emergency Preparedness Program Inspection Request for Information ML20094H5182020-04-0303 April 2020 Plant Reference Simulator Inspection Request for Information IR 05000348/20190062020-03-0303 March 2020 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000348/2019006 and 05000364/2019006 ML19274D2092019-09-23023 September 2019 ISI Request for Information IR 05000348/20190052019-08-28028 August 2019 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Reports 05000348/2019005 and 05000364/2019005 ML19100A0072019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000348/20190132019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000364/20180062019-03-0404 March 2019 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000346 and 05000364/2018006 ML19063B8902019-03-0404 March 2019 ISI Sgisi 2019002 RFI - Bcc ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18360A2312018-12-21021 December 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000348/20180052018-08-23023 August 2018 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Reports 05000348/2018005 and 05000364/2018005 ML18094A7822018-04-0303 April 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2018011 and 05000364/2018011 ML18059A1532018-02-28028 February 2018 EOC Assessment Letter ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML18053A0942018-02-22022 February 2018 Baseline In-Service Inspection Initial Information Request ISI 2018002 Rpc IR 05000348/20170052017-08-28028 August 2017 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2, NRC Report 05000348/2017005 and 05000364/2017005 ML17156A1032017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000348/20160062017-03-0101 March 2017 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2016006 and 05000364/2016006) IR 05000348/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Report 05000348/2016005 and 05000364/2016005 ML16244A3102016-08-29029 August 2016 Notification of Inspection and Request for Information ML16062A1522016-03-0202 March 2016 Final Annual Assessment Letter ML15260A9022015-09-17017 September 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2015005 and 05000364/2015005) ML14245A1752014-09-0202 September 2014 Mid-cycle Ltr 2014 ML14121A5042014-05-0101 May 2014 Notification of Triennial Fire Protection Baseline Inspection and Request for Information IR 050000348-14-009 and 05000364-14-009 ML14063A1442014-03-0404 March 2014 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 IR 05000348/20140012014-03-0404 March 2014 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2014001 and 05000364/2014001) ML13354B9722013-12-20020 December 2013 Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 ML13253A3662013-09-10010 September 2013 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML13246A1102013-09-0303 September 2013 Mid-Cycle Assessment Letter ML13070A4622013-03-0808 March 2013 Notification of Inspection and Request for Information IR 05000348/20120012013-03-0404 March 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2012001 and 364/2012001) 2024-08-26
[Table view] Category:Letter
MONTHYEARIR 05000348/20240032024-11-13013 November 2024 Integrated Inspection Report 05000348/2024003, 05000364/2024003 and 07200042/2024001 IR 05000348/20244032024-11-13013 November 2024 – Security Baseline Inspection Report 05000348/2024403 & 05000364/2024403 NL-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-24-0340, 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-24-0230, 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 2024-09-05
[Table view] |
Text
Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT-NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Jamie Coleman:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a problem identification and resolution (PI&R) inspection at Joseph M. Farley Nuclear Plant during the weeks of October 711, 2024, and October 28 -
November 1, 2024. The inspection team will be led by Mr. Christian Scott, a Senior Project Engineer from the NRCs Region II office. This inspection will be conducted in accordance with the baseline inspection procedure, 71152, Problem Identification and Resolution, issued January 1, 2024.
The biennial PI&R inspection and assessment of the licensees Corrective Action Program (CAP) complements and expands upon the resident baseline inspections of routine daily screening of all corrective action program issues, quarterly focused issue reviews, and semiannual trend PI&R reviews.
On June 26, 2024, Mr. Scott confirmed with Mr. Gene Surber, Licensing Manager, the details and expectations for the two weeks of the inspection.
The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than September 23, 2024. Contact Mr. Scott with any questions concerning the requested information. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. If additional documents are needed, they will be requested when identified.
Prior to the inspection, Mr. Scott will discuss, with your staff, the following inspection support administrative details: availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; method of tracking inspector requests during the inspection; and other applicable information.
July 2, 2024
J. Coleman 2
The NRC inspection team requests that your staff be prepared to support these efforts.
Additionally, the inspection team is open to any suggestions regarding communications and coordination such that the overall effort from both the NRC inspection team and Joseph M.
Farley Nuclear Plant support staff may be the most efficient while also prioritizing public health and safety.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs 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 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).
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Scott at (404) 997-4403.
Sincerely, Alan Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 05000348 and 05000364 License No. NPF2, NPF8
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant Problem Identification and Resolution Inspections cc: Distribution via ListServ PAPERWORK REDUCTION ACT STATEMENT This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
Signed by Blamey, Alan on 07/02/24
ML24184A045 X
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DRP RII/DRP NAME C. Scott A. Blamey DATE 7/02/24 7/02/24
Enclosure INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (October 711, 2024, and October 28-November 1, 2024)
This inspection will cover the period from March 3, 2023, through November 1, 2024. All requested information is limited to this period or to the date of this request unless otherwise specified. To the extent possible, the requested information should be provided electronically in word-searchable Adobe PDF (preferred) or Microsoft Office format. If you determine that any information requested is sensitive, the specific handling of this information should be discussed in advance between the NRC inspectors and Farley Nuclear Plant representatives assigned to the Problem Identification and Resolution Inspection to ensure appropriate handling.
All requested documents should be provided electronically (e.g., Certrecs IMS) where possible.
If an online inspection management system is used to provide the requested information, please ensure that all uploaded documents are searchable by title and/or identification number (for example, Condition Report (CR) 1234567).
Lists of documents (summary lists) should be provided in Microsoft Excel or a similar sortable format. Please be prepared to provide any significant updates to this information on September 23, 2024, and as new information becomes available throughout the inspection. As used in this request, corrective action documents refers to corrective action types/products as defined in your corrective action program procedures (e.g., Corrective Action Reports (CARs),
Technical Evaluations (TEs) used to track CAP Corrective Actions to Preclude Repetition (CAPR), Corrective Actions (CA), Effectiveness Reviews (EFFRs), and Work Orders (WOs) to implement a corrective actions condition report.
1.
Document Lists Note: For these summary lists, please include, if applicable, the document/reference number, the type (i.e., TE, CAPR, CAR, WO, etc.) document title, long-text description of the issue, affected system, initiation date, current status, due date, priority/severity level, responsible organization/department, and associated condition report.
a.
Summary list of all corrective action documents related to significant conditions adverse to quality that were opened, closed, or evaluated during the period.
b.
Summary list of all corrective action documents related to conditions adverse to quality that were opened or closed during the period.
c.
Summary list of all CRs related to non-conditions adverse to quality that were opened or closed during the period.
d.
Summary list of all apparent cause evaluations (or equivalent causal determinations) performed during the period.
e.
Summary list of all conditions adverse to regulatory compliance (CARC) (as defined in your CAP procedure NMP-GM002001) identified during the period.
f.
Summary list of all corrective maintenance WOs and modifications (if not included as part of request item 1.a) for safety-related structures, systems, and components (SSCs) and any work considered high risk. Include the WO/modification number, brief description, affected system, date of initiation, date of completion (if completed),
and associated CR (if applicable).
g.
Summary list of all CRs that have been canceled during the period. Provide the CR number, brief problem description, and reason canceling.
h.
Summary list of all currently open corrective action documents associated with
Enclosure conditions first identified prior to the beginning of the inspection period.
i.
Summary list of all corrective action documents that were upgraded or downgraded in priority/significance during the period (these may be limited to those downgraded from, or upgraded to, apparent cause level or higher).
j.
Summary list of all corrective action documents initiated during the period that identify an adverse or potentially adverse trend in (1) safety-related or risk-significant equipment performance and (2) in any aspect of the plants safety culture.
k.
Summary lists of operator workarounds, operator burdens, temporary modifications, and control room deficiencies (1) currently open and (2) that were evaluated and/or closed during the period; this should include the date that each item was opened and/or closed. Include corresponding condition report and/or WO number.
l.
Summary list of all prompt operability determinations or other engineering evaluations to provide reasonable assurance of operability; if fewer than approximately 20, provide full documents and attachments.
m.
Summary list of plant safety issues raised or addressed by the Employee Concerns Program (or equivalent) (sensitive information should be made available by appropriate means after discussion with the team lead).
n.
Summary list of all SSCs which were classified as (a)(1) in accordance with the Maintenance Rule during the period. Include date of classification in (a)(1), reason for being placed in (a)(1), and planned actions and their status.
o.
Summary list of all Maintenance Preventable Functional Failures (MPFF). Include identification number, brief description, associated system, actions completed, and status.
p.
Summary list of CRs related to equipment aging issues identified during the period (e.g., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.; environmental qualification). Provide CR number, brief problem description, priority/severity level, associated system, and status.
q.
Summary list of training deficiencies, requests for training improvements, and simulator deficiencies for the period.
2.
Full Documents with Attachments a.
All root cause determinations/evaluations completed during the period; include a list of any planned or in progress.
b.
Quality Assurance Program audits and/or assessments performed during the period, including the last two audits/assessments of the corrective action program.
c.
Functional area/department self-assessments and non-NRC third-party assessments (e.g., peer assessments performed as part of routine or focused station self-and independent assessment activities; do not include Institute of Nuclear Power Operations (INPO) assessments) that were performed or completed during the period; include a list of those that are currently in progress.
d.
Any assessments of the safety conscious work environment (SCWE) at Farley Nuclear Plant including any safety culture survey results; if none performed during the inspection period, provide the most recent.
e.
Corrective action program documents related to cross-cutting issues (human performance, problem identification and resolution, and SCWE) identified via trending, self-assessments, safety review committee or other oversight methods.
Enclosure f.
Corrective action documents generated during the period associated with the following:
i.
NRC findings and/or violations issued to Farley Nuclear Plant ii.
Licensee Event Reports issued by Farley Nuclear Plant Please provide a crosswalk or key tying corrective action documents to specific findings or violations.
g.
Corrective action documents generated for the following:
i.
NRC Information Notices, Bulletins, and Generic Letters issued or evaluated during the period ii.
Part 21 reports issued or evaluated during the period iii.
Vendor safety information letters (or equivalent) issued or evaluated during the period iv.
Other external events and/or operating experience evaluated for applicability during the period h.
Corrective action documents generated for the following:
i.
Adverse trends in equipment, processes, procedures, or programs that were evaluated during the period.
ii.
Action items generated or addressed by offsite review committees during the period.
3.
Logs and Reports Note: For item 3.c-3.d, if there is no log or report maintained separate from the corrective action program, please provide a summary list of corrective action program items for the category described.
a.
If already compiled, copy of departmental trend reports, and corrective action trend reports, including any human performance and equipment reliability trends.
b.
If not included as part of request item 3.a, a copy the latest corrective action program statistics such as the number of CRs initiated by department, human performance errors by department, and others as may be available.
c.
Radiation protection event logs during the period.
d.
Security event logs and security incidents during the period (sensitive information should be made available during the teams first weekdo not provide electronically)-Handling of this item will need additional discussion.
e.
Employee Concerns Program (or equivalent) logs (sensitive information should be made available during the teams first week of inspectiondo not provide electronically).
f.
System health reports, system design basis documents, maintenance rule functions and status, and system description information for the top ten risk-significant systems.
4.
Procedures Note: For these procedures, include all revisions that were in effect at any time during the period.
a.
Corrective action program procedures, to include initiation and evaluation procedures,
Enclosure operability determination procedures, cause evaluation procedures, and any other procedures that implement the corrective action program at the plant, including applicable corporate procedures b.
QA self-assessment and audits program procedures c.
Operability determination and functionality assessment procedures d.
Employee Concerns Program (or equivalent) procedures e.
Procedures that implement/maintain a SCWE f.
Conduct of Operations procedure (or equivalent) and any other procedures or policies governing control room conduct, operator burdens and workarounds, etc.
g.
Maintenance rule procedures and any procedures implementing any portion of the maintenance rule at the station h.
Operating experience program procedures and any other procedures or guidance documents that describe the sites use of operating experience information i.
Procedures associated with the 10 CFR Part 21 program j.
System health process or equivalent equipment reliability improvement program procedures k.
Preventive maintenance deferral process 5.
Other a.
List of risk-significant components and systems, ranked by risk worth; if the list uses system designators, provide a list of the associated equipment/system names.
b.
List of top ten risk-significant operator manual actions.
c.
Organization charts for plant staff and long-term/permanent contractors.
d.
Electronic copies of the Updated Final Safety Analysis Report (or equivalent),
technical specifications, and technical specification bases.
e.
For each day the team is inspecting, provide the following:
i.
Planned work/maintenance schedule for the station ii.
Schedule of management, maintenance rule, correction action related, or corrective action review meetings (e.g. operations focus meetings, condition report screening meetings, Corrective Action Review Boards, Management Review Meetings, challenge meetings for cause evaluations, etc.)
iii.
Agendas and materials for these meetings Note: Please provide the items listed in 5.e on a daily basis.
Additionally, please note that system or areas for increased inspection focus will be identified following receipt of this initial information request, and additional documentation may be requested.