|
---|
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 – 95002 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 05000348/20220012022-05-0404 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 IR 05000348/20224012021-12-13013 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 IR 05000348/20210122021-07-19019 July 2021 Triennial Fire Protection Team Inspection (FPTI) Report 05000348/2021012 and 05000364/2021012 2024-09-10
[Table view] 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-24-0340, 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 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 05000348/20240052024-08-26026 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 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 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 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
[Table view] |
See also: IR 05000348/2023010
Text
Mr. Delson Erb
Site Vice President
Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant
7388 North State Highway 95
Columbia, AL 36319-0470
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPREHENSIVE
ENGINEERING TEAM INSPECTION (CETI) BASELINE INSPECTION REPORT
05000348/2023010 AND 05000364/2023010
Dear Mr. Erb:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your
Joseph M. Farley Nuclear Plant during the weeks of April 3 and 17, 2023. Mr. Theo Fanelli, a
senior reactor inspector from the NRCs Region II office, will lead the inspection team. The
inspection will be conducted in accordance with Inspection Procedure 71111.21M,
Comprehensive Engineering Team Inspection (CETI), effective date January 1, 2023. This is a
new procedure that was issued on October 7, 2022.
The inspection will evaluate the capability of components that have been modified and risk-
significant/low-margin components to function as designed and to support proper system
operation. The inspection will also include a review of selected operator actions, and operating
experience, and modifications.
During a Teams meeting Ms. Mandy Ludlam, licensing Engineer, we confirmed arrangements
for an information-gathering site visit and the two-week onsite inspection. The schedule is as
follows:
Information-gathering visit: Week of March 13, 2023
Onsite weeks: Weeks of April 3 and 17, 2023
The purpose of the information-gathering visit is to meet with members of your staff to identify
components that have been modified, risk-significant components, and operator actions.
Information and documentation needed to support the inspection will also be identified.
Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Fanelli during the
information-gathering visit to review probabilistic risk assessment data and identify components
to be examined during the inspection. Additionally, during the onsite weeks, time may be
needed on the plant-referenced simulator to facilitate the development of operator action-based
scenarios.
The enclosure lists documents that will be needed prior to the information-gathering visit.
Please provide the referenced information to the Region II Office by Friday, February 27, 2023.
Additional documents will be requested following the information-gathering visit. The inspectors December 13, 2022
D. Erb 2
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information will be needed in the Region II
office by Friday, March 24, 2023, to support the inspection teams preparation week. During the
information-gathering trip, Mr. Fanelli will also discuss the following inspection support
administrative details: (1) availability of knowledgeable plant engineering and licensing
personnel to serve as points of contact during the inspection; (2) method of tracking inspector
requests during the inspection; (3) licensee computer access; (4) working space;
(5) arrangements for site access; and (6) other applicable information.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Thank you for your cooperation in this matter. If you have any questions, regarding the
information requested or the inspection, please contact Mr. Fanelli at 404-997-4433 or contact
me at 404-997-4506.
Sincerely,
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 05000348 AND 05000364
License No. NPF-2 and NPF-8
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant Comprehensive Engineering Team
Inspection
cc w/ encl: Distribution via LISTSERV
Signed by Baptist, James
on 12/13/22
ML22343A038
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE RII/DRS RII/DRS
NAME T. Fanelli J. Baptist
DATE 12/09/22 12/13/22
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT COMPREHENSIVE
ENGINEERING TEAM INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2020, until present.
1. *List of modifications to systems, structures or components (SSCs) that are permanent
and field work completed. (For the purpose of this inspection, modifications include
permanent: plant changes, design changes, calculation changes, procedure changes, and
set point changes.)
The list should contain the number of the modification, a short description, affected system
and unit. If multiple categories/stages of modifications exist, provide a description of the
types relative to the coding scheme in your transmittal. Additionally, the list should be
categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by
a screening or 10 CFR 50.59 evaluation. A query report return-field-set might look like:
Identifier Unit System1 Description Type2 Status3 QA Condition4 50.595
1 e.g. If systems are provided with some type of number or acronym designation,
define the systems designation on a separate list or document
2 e.g. Engineering Design/Document Change, Design Change Notice, Test,
Experiment, etc.
3 e.g. Closed, Returned to Operation, Void, Partially Completed, Released for
Installation, Phase 1 Completed, etc.
4 e.g. Safety Related or Non-Safety Related
5 e.g. Screened Out or Full 10 CFR 50.59 Evaluation
2. From your most recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
c. A list of the top 500 LERF contributors
3. From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
reliability worksheets for these items
5. List of time-critical operator actions with a brief description of each action
6. *List of components with low-design margins (i.e., pumps closest to the design limit for flow
or pressure, diesel generator close to design-required output, heat exchangers close to
rated design heat removal, and motor-operated valve risk-margin rankings, etc.) and
associated evaluations or calculations
7. *List and brief description of Root Cause Evaluations performed
Enclosure
8. *List and brief description of common-cause component failures that have occurred
9. List and brief description of equipment currently in degraded or nonconforming condition
10. *List and brief description of Operability Determinations and Functionality Assessments
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
12. *List of equipment on the sites Station Equipment Reliability Issues List, including a
description of the reason(s) why each component is on that list, and summaries (if
available) of your plans to address the issue(s) along with dates added or removed from
the issues list
13. List of current operator work arounds/burdens
14. Copy of Updated Final Safety Analysis Report
15. Copy of Technical Specification(s)
16. Copy of Technical Specifications Bases
17. Copy of Technical Requirements Manual(s)
18. Copy of the Quality Assurance Program Manual
19. Copy of Corrective Action Program Procedure(s)
20. Copy of Operability Determination Procedure(s)
21. Copy of procedures addressing the following: Modifications, design changes, set point
changes, equivalency evaluations or suitability analyses, commercial grade dedications,
post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
22. Copy of procedures addressing the following: loss of service water system or ultimate heat
sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,
and inspection requirements for service water system and UHS
23. Response to Generic Letter 89-13 including any regulatory commitments made
24. List of heat exchangers or equipment cooled by service water directly or indirectly. Include
the risk ranking for each listed heat exchanger.
25. List of motor operated valves and air operated valves in the valve program, and their
associated design margin and risk ranking
26. Primary AC and DC calculations for safety-related buses
27. One-line diagram of electrical plant (Electronic only)
28. Index and legend for electrical plant one-line diagrams
29. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
30. Index and legend for P&IDs
31. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
2
32. Copies of corrective action documents generated from previous design bases assurance
inspections
33. Copy of any self-assessments performed, and corrective action documents generated, in
preparation for current comprehensive engineering team inspection
34. Contact information for a person to discuss PSA information prior to and during the
information-gathering trip (Name, title, phone number, and e-mail address)
3