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| #REDIRECT [[IR 05000321/2021010]]
| | {{Adams |
| | | number = ML21013A411 |
| | | issue date = 01/13/2021 |
| | | title = Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010 |
| | | author name = Baptist J |
| | | author affiliation = NRC/RGN-II/DRS/EB1 |
| | | addressee name = Dean E |
| | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | | docket = 05000321, 05000366 |
| | | license number = DPR-057, NPF-005 |
| | | contact person = |
| | | case reference number = IR 2021010 |
| | | document type = Inspection Plan, Letter, Request for Additional Information (RAI) |
| | | page count = 5 |
| | }} |
| | See also: [[see also::IR 05000321/2021010]] |
| | |
| | =Text= |
| | {{#Wiki_filter:January 13, 2021 |
| | Mr. Edwin (Sonny) Dean |
| | Site Vice President |
| | Edwin I. Hatch Nuclear Plant |
| | Southern Nuclear Operating Company, Inc. |
| | 11028 Hatch Parkway North |
| | Baxley, GA 31513 |
| | SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES |
| | ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION |
| | INSPECTION REPORT 05000321/2021010 AND 05000366/2021010 |
| | Dear Mr. Dean: |
| | The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) |
| | Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your plant Hatch |
| | during the weeks of April 26, 2021 and May 10, 2021. Mr. Mark Schwieg, a 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, Design Bases Assurance Inspection |
| | (Teams), dated January 1, 2017 (ADAMS ML16340B000). |
| | 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, operating |
| | experience, and modifications. |
| | During a telephone conversation on January 11, 2021, with James Love 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 April 12, 2021 |
| | * Onsite weeks: Weeks of April 26 and May 10, 2021 |
| | 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. Mark Schwieg 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 will be needed |
| | on the plant-referenced simulator in order to facilitate the development of operator action-based |
| | scenarios. |
| | |
| | S. Dean 2 |
| | Starting on March 20, 2020, in response to the National Emergency declared by the President |
| | of the United States on the public health risks of the coronavirus (COVID-19), inspectors were |
| | directed to begin telework. In addition, regional baseline inspections were evaluated to |
| | determine if all or portion of the objectives and requirements stated in the IP could be performed |
| | remotely. If the inspections could be performed remotely, they were conducted per the |
| | applicable IP. In some cases, portions of an IP were completed remotely and on site. |
| | 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 April 12, 2021. Additional |
| | documents will be requested following the information-gathering visit. The inspectors 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 |
| | April 19, 2021, to support the inspection teams preparation week. During the information- |
| | gathering trip, Mr. Schwieg 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. Schwieg at 404-997-4631 or contact |
| | me at 404-997-4506. |
| | Sincerely, |
| | /RA/ |
| | James Baptist, Chief |
| | Engineering Branch 1 |
| | Division of Reactor Safety |
| | Docket Nos.: 50-321, 50-366 |
| | License Nos.: DPR-57 and NPF-5 |
| | Enclosure: |
| | Notification of Hatch, |
| | Design Bases Assurance Inspection (Teams) |
| | cc: Distribution via Listserv |
| | |
| | S. Dean 3 |
| | SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES |
| | ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION |
| | INSPECTION REPORT 05000321/2021010 AND 05000366/2021010 |
| | Dated January 13, 2021 |
| | DISTRIBUION: |
| | M. Schwieg, RII |
| | J. Baptist, RII |
| | RIDNrrPMHATCH |
| | RIDSNrrDRO Resource |
| | ADAMS ACCESION NUMBER: ML21013A411_ |
| | OFFICE RII:DRS RII:DRS |
| | NAME M. Schwieg J. Baptist |
| | DATE 01/13/2021 01/13/2021 |
| | E-MAIL COPY? YES NO YES NO |
| | OFFICIAL RECORD COPY |
| | |
| | INFORMATION REQUEST FOR HATCH |
| | DESIGN BASES ASSURANCE INSPECTION (TEAMS) |
| | 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 March 31, 2018, until present. |
| | 1. *List and brief description of permanent and field work completed plant modifications |
| | including permanent plant changes, design changes, set point changes, procedure |
| | changes, equivalency evaluations, suitability analyses, calculations, and commercial grade |
| | dedications. Include an index of systems (system numbers/designators and corresponding |
| | names), the safety classification for each modification, and type of modification. |
| | 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 |
| | 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 status as |
| | described in NRC Inspection Manual Chapter 0326, issued December 3, 2015 |
| | 10. *List and brief description of Operability Determinations and Functionality Assessments |
| | Enclosure |
| | |
| | 2 |
| | 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. List of motor operated valves and air operated valves in the valve program, and their |
| | associated design margin and risk ranking |
| | 23. Primary AC and DC calculations for safety-related buses |
| | 24. One-line diagram of electrical plant (Electronic only) |
| | 25. Index and legend for electrical plant one-line diagrams |
| | 26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic) |
| | 27. Index and legend for P&IDs |
| | 28. Index (procedure number, title, and current revision) of station Emergency Operating |
| | Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures |
| | 29. Copies of corrective action documents generated from previous CDBI |
| | 30. Copy of any self-assessments performed, and corrective action documents generated, in |
| | preparation for current DBAI |
| | 31. 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) |
| | }} |
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Hatch Nuclear Plant, Units 1 and 2 - NRC Inspection Report 05000321/2022006 and 05000366/2022006 NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23354A2032023-12-18018 December 2023 Document Request for Hatch Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-01 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23264A0142023-09-14014 September 2023 NRR E-mail Capture - (External_Sender) Draft Round-2 RAI - Hatch, Units 1 and 2, Revise TS 1.1-1 Modes LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23018A1872023-01-17017 January 2023 2023 HNP CGD Inspection Information Request ML22355A2082022-12-21021 December 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, Reactor Pressure Vessel 'Rpv Head Studs' LAR ML23026A2372022-11-16016 November 2022 2023001 Hatch RP RFI Final ML22208A1332022-07-26026 July 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-208 LAR ML22157A3542022-06-0606 June 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-505 LAR ML22140A1192022-05-20020 May 2022 NRR E-mail Capture - RAIs - Hatch, Units 1 and 2, TSTF-505 LAR ML22073A0842022-03-21021 March 2022 an NRC Fire Protection Team Inspection (NRC Inspection Report Nos. 05000321/2022011 and 05000366/2022011) and Request for Information ML22025A2142022-01-21021 January 2022 Plant Hatch 2022001 RP Baseline Inspection Information Request ML21265A3402021-09-22022 September 2021 NRR E-mail Capture - Request for Additional Information - Hatch, Unit 1, Emergency TS 3.7.2 LAR ML21111A3032021-04-21021 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21110A6842021-04-20020 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21013A4112021-01-13013 January 2021 Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010 ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20253A2732020-09-0909 September 2020 Requalification Program Inspection Hatch Nuclear Station ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests NL-19-1532, Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors2019-12-18018 December 2019 Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors ML19336A0142019-12-0101 December 2019 NRR E-mail Capture - RAI: Hatch Emergency TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LAR ML19280A0082019-10-0404 October 2019 NRR E-mail Capture - Request for Additional Information (RAI) - Hatch TSTF-51 LAR (L-2019-LLA-0091) ML19224C0552019-08-12012 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Degraded Voltage (L-2019-LLA-0108) ML19220A0362019-08-0808 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Adoption of NFPA 805, Request for Additional Information, EPID L-2018-LLA-0107 ML19164A2582019-06-13013 June 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19107A4962019-04-17017 April 2019 NRR E-mail Capture - Request for Additional Information - Hatch 1 & 2 Application to Adopt Title 10 of Code of Federal Regulations 50.69 RISK-INFORMED Categorization and Treatment of Structures, Systems and Components for Power Reactors ML19088A0092019-03-29029 March 2019 NRR E-mail Capture - Hatch 1 and 2 - LAR to Adopt NFPA 805 Fire Protection Standard, EPID L-2018-LLA-0107, Request for Additional Information ML19029B3402019-01-23023 January 2019 Southern Nuclear Operating Company, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 Draft Request for Additional Information for the License Amendment Requests to Adopt the Risk-Informed Provisions of Title 10 of the Code of Federal Regulat ML19016A3422019-01-10010 January 2019 U2 ISI 2019001 RFI - Bcc ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18085A0132018-03-0808 March 2018 Draft Request for Additional Information on Alternative RR-V-11, Proposed Extension to Main Steam Safety Relief Valve Testing Requirements ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17284A3542017-11-0707 November 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools ML17270A1402017-09-27027 September 2017 PIR Notification Letter 2017 ML17290A3172017-09-19019 September 2017 NRR E-mail Capture - Hatch 1 and 2 - Draft Request for Additional Information Request for Alternative No. HNP-ISI-ALT-05-05 ML17111A5792017-04-26026 April 2017 Request for Additional Information, Fourth 10-Year ISI Interval Relief Requests ML17110A2112017-04-24024 April 2017 Request for Additional Information ML16330A1282016-12-0505 December 2016 Request for Additional Information ML16307A1842016-11-0202 November 2016 Request for Additional Information (Non-Proprietary) ML16271A1692016-10-17017 October 2016 Request for Additional Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16205A0012016-07-22022 July 2016 Requalification Program Inspection - Plant Hatch ML16195A4002016-07-13013 July 2016 Request for Additional Information License Amendment Request to Revise Technical Specifications Regarding TSTF-500 ML16194A4282016-07-12012 July 2016 E-mail Draft Request for Additional Information for Technical Clarification ML16187A1222016-07-0101 July 2016 Notification of Inspection and Request for Information ML16111B3132016-04-20020 April 2016 Notification of Inspection and Request for Information ML16098A1442016-04-15015 April 2016 Request for Additional Information 2024-01-12
[Table view] |
See also: IR 05000321/2021010
Text
January 13, 2021
Mr. Edwin (Sonny) Dean
Site Vice President
Edwin I. Hatch Nuclear Plant
Southern Nuclear Operating Company, Inc.
11028 Hatch Parkway North
Baxley, GA 31513
SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES
ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
INSPECTION REPORT 05000321/2021010 AND 05000366/2021010
Dear Mr. Dean:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your plant Hatch
during the weeks of April 26, 2021 and May 10, 2021. Mr. Mark Schwieg, a 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, Design Bases Assurance Inspection
(Teams), dated January 1, 2017 (ADAMS ML16340B000).
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, operating
experience, and modifications.
During a telephone conversation on January 11, 2021, with James Love 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 April 12, 2021
- Onsite weeks: Weeks of April 26 and May 10, 2021
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. Mark Schwieg 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 will be needed
on the plant-referenced simulator in order to facilitate the development of operator action-based
scenarios.
S. Dean 2
Starting on March 20, 2020, in response to the National Emergency declared by the President
of the United States on the public health risks of the coronavirus (COVID-19), inspectors were
directed to begin telework. In addition, regional baseline inspections were evaluated to
determine if all or portion of the objectives and requirements stated in the IP could be performed
remotely. If the inspections could be performed remotely, they were conducted per the
applicable IP. In some cases, portions of an IP were completed remotely and on site.
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 April 12, 2021. Additional
documents will be requested following the information-gathering visit. The inspectors 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
April 19, 2021, to support the inspection teams preparation week. During the information-
gathering trip, Mr. Schwieg 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. Schwieg at 404-997-4631 or contact
me at 404-997-4506.
Sincerely,
/RA/
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-321, 50-366
License Nos.: DPR-57 and NPF-5
Enclosure:
Notification of Hatch,
Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv
S. Dean 3
SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES
ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
INSPECTION REPORT 05000321/2021010 AND 05000366/2021010
Dated January 13, 2021
DISTRIBUION:
M. Schwieg, RII
J. Baptist, RII
RIDNrrPMHATCH
RIDSNrrDRO Resource
ADAMS ACCESION NUMBER: ML21013A411_
OFFICE RII:DRS RII:DRS
NAME M. Schwieg J. Baptist
DATE 01/13/2021 01/13/2021
E-MAIL COPY? YES NO YES NO
OFFICIAL RECORD COPY
INFORMATION REQUEST FOR HATCH
DESIGN BASES ASSURANCE INSPECTION (TEAMS)
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 March 31, 2018, until present.
1. *List and brief description of permanent and field work completed plant modifications
including permanent plant changes, design changes, set point changes, procedure
changes, equivalency evaluations, suitability analyses, calculations, and commercial grade
dedications. Include an index of systems (system numbers/designators and corresponding
names), the safety classification for each modification, and type of modification.
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
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 status as
described in NRC Inspection Manual Chapter 0326, issued December 3, 2015
10. *List and brief description of Operability Determinations and Functionality Assessments
Enclosure
2
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. List of motor operated valves and air operated valves in the valve program, and their
associated design margin and risk ranking
23. Primary AC and DC calculations for safety-related buses
24. One-line diagram of electrical plant (Electronic only)
25. Index and legend for electrical plant one-line diagrams
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
27. Index and legend for P&IDs
28. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
29. Copies of corrective action documents generated from previous CDBI
30. Copy of any self-assessments performed, and corrective action documents generated, in
preparation for current DBAI
31. 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)