IR 05000324/2022010

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Notification of Brunswick Steam Electric Plant, Units 1 & 2 - Design Bases Assurance Inspection - U.S. Nuclear Regulatory Inspection Report 05000324/2022010 and 05000325/2022010
ML22018A184
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/18/2022
From: James Baptist
Division of Reactor Safety II
To: Krakuszeski J
Duke Energy Progress
References
IR 2022010
Download: ML22018A184 (4)


Text

January 18, 2022

SUBJECT:

NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2 DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000324/2022010 AND 05000325/2022010

Dear Mr. Krakuszeski:

The purpose of this letter is to notify you that the U.S. Nucle ar Regulatory Commission (NRC)

Region II staff will conduct a Design Bases Assurance Inspectio n (DBAI) at your Brunswick Steam Electric Plant Units 1 & 2 during the weeks of April 25 a nd May 9, 2022.

Mr. Paul Carman, a Senior Reactor Inspector from the NRCs Regi on II office, will lead the inspection team. The inspection will be conducted in accordanc e with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated D ecember 8, 2016 (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 t o support proper system operation. The inspection will also include a review of select ed operator actions, operating experience, and modifications.

During a telephone conversation on January 12, 2022, with Mr. T om Sherrill we confirmed arrangements for an information-gathering site visit and the tw o-week onsite inspection. The schedule is as follows:

  • Information-gathering visit: April 4, 2022
  • Onsite weeks: Weeks of April 25 and May 9, 2022

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. Andy Rosebrook, a Region II Senior Risk Analyst, will suppo rt Mr. Carman during the information-gathering visit to review probabilistic risk assess ment 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 deve lopment 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 Offi ce by Friday, March 25, 2022. Additional documents will be requested following the informatio n-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional informatio n will be needed in the Region II office by Friday, April 15, 2022, to support the inspection tea ms preparation week. During the information-gathering trip, Mr. Carman will also discuss the fo llowing 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 info rmation.

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, Exem ptions, 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. Car man at 404-997-4471 or contact me at 404-997-4506.

Sincerely,

/RA/

James Baptist, Chief Engi neering Branch 1 DivisionofReactorSafety

Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71

Enclosure:

Information Request for Brunswick Steam Electric Plant, Units 1 & 2 Design Bases Assurance Inspection (Teams)

cc w/ encl: Distribution via LISTSERV INFORMATION REQUEST FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2 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 bel ow, identified with an asterisk (*),

should have a date range from January 1, 2019, until present.

1. *List and brief description of permanent and field work completed plant modifications including permanent plant changes, design changes, set point ch anges, procedure changes, equivalency evaluations, suitability analyses, calcula tions, and commercial grade dedications. Include an index of systems (system numbers/desig nators and corresponding names), the safety classification for each modification, and ty pe 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 descript ion of each action

6. *List of components with low-design margins (i.e., pumps clo sest 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 perfor med

8. *List and brief description of common-cause component failur es that have occurred

9. List and brief description of equipment currently in degrade d or nonconforming status as described in NRC Inspection Manual Chapter 0326, issued Septemb er 30, 2019

10. *List and brief description of Operability Determinations a nd Functionality Assessments

Enclosure

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 Reliabil ity 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 dat es 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 o r suitability analyses, commercial grade dedications, post-modifications testing, 10 CFR 50.59 screenings and evaluat ions, and UFSAR updates

22. List of motor operated valves and air operated valves in th e 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-rela ted systems (Electronic)

27. Index and legend for P&IDs

28. Index (procedure number, title, and current revision) of st ation Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Resp onse Procedures

29. Copies of corrective action documents generated from previo us CDBI

30. Copy of any self-assessment s performed, and corrective acti on 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-ma il address)