ML13052A371

Inspection Procedure 95003 Information Request

ML13052A371
Person / Time
Site:	Browns Ferry
Issue date:	02/21/2013
From:	Eugene Guthrie Division Reactor Projects II
To:	James Shea Tennessee Valley Authority
References
Download: ML13052A371 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 February 21, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801

SUBJECT:

INSPECTION PROCEDURE 95003 INFORMATION REQUEST

Dear Mr. Shea:

The purpose of this letter is to request information to support the upcoming 95003 inspection.

The inspection will be conducted in accordance with Inspection Procedure 95003, Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input.

The current schedule for the inspection is as follows:

• March 18 Site Orientation at Browns Ferry

• May 13 On-site Inspection at Browns Ferry Per previous discussions with your staff, you are requested to post the requested documentation on the IMS website and provide each team member a user identification and unique password. As team members are identified, we will provide you with the necessary information in order for you to setup account access. This documentation will be available for each team member to review and download if necessary. Please make the electronic version of this information available as soon as practical, but no later than March 18, 2013. In addition, we will be providing you a second request for information around March 29, 2013. This request will ask for additional focused items for inspection. This information should be available to the team by April 19, 2013, in the same manner as the initial request. Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection please contact me at (404) 997-4662.

Sincerely,

/RA/

Eugene F. Guthrie, Chief Special Project, Browns Ferry Division of Reactor Projects Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68

_________________________ X SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRP RII:DRP RIII:DRS SIGNATURE CRK /RA/ EFG /RA/ Via email NAME CKontz EGuthrie RSkokowski DATE 02/20/2103 02/21/2013 02/21/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Inspection 95003 Documentation Request For each of the following, provide an electronic copy on the IMS website. Requests for corrective action program documents should include data from the traditional sources (as well as systems outside the corrective action program (training deficiency lists, etc.))

95003 Preparation Materials

1. Procedures, Assessments, RCA, PERs, and reports used for generation of the Integrated Improvement Plan.

2. Integrated Improvement Plan, and implementing procedures.

3. Performance Metrics and basis, and implementing procedures.

4. Safety Culture Assessment process procedures, basis documents, and policy statement.

5. Follow-up actions to issues identified during the Part I, Part II, and PI&R inspection.

Audit and Assessment Reports (include copies of documents associated with audit findings and assessments)

6. Since January 2010, a copy of all external audits and assessments.

7. Since January 2010, a summary listing of all internal audits and assessments (Area assessed, date performed, responsible organization, conclusions, and recommendations).

8. Since January 2010, a copy of all Quality Assurance Department audit reports.

9. Since January 2010, a summary of all Quality Assurance Department assessment reports (Area assessed, date performed, responsible organization, conclusions, and recommendations).

10. Since January 2010, a summary of bench marking activities (date, subject, lessons learned, and CAP document number).

11. Since 2000, audits and assessments of suppliers QA programs.

12. Corrective Action Program (CAP) Crosscutting Area.

13. Since January 2008, a summary listing of all root analyses (date opened, problem description, root and contributing causes, date evaluation was completed, date final corrective action was performed, and the effectiveness review).

14. Since 2000, copies of Offsite Nuclear Oversight Committee meeting minutes.

15. Since 2010, a cross reference of LERs to corrective action program (LER number, CAP document number, event date, and summary description).

16. Since 2010, a summary listing of all processes and performance metrics used to track backlogs at the station.

17. List of root cause analysis qualified personnel by department.

18. Since January 2010, summary of site wide and departmental performance measures and metrics.

19. Since January 2010, summary of all CAP documents documenting a potential or actual adverse trend.

20. Since 2003, summary of generic communications received and processed (NRC communications, vendor recommendations, etc.).

21. Since September 1, 2009, Key Performance Indicator Reports, Equipment Reliability Index Reports and any associated Equipment Reliability Bubble Charts.

Enclosure

2

22. Since January 1, 2009, Critical Component Failure Trend Evaluation Reports.

23. Since January 1, 2010, Safety Cultural Assessment Reports, and any associated Improvement Plans and related PERs.

Procedures - include a consolidated index of procedures for reference

24. Complete and up-to-date copy of reference materials provided for NRC initial licensing operating test preparations and review (Items included in this package that are duplicated below only need to be submitted once).

25. Corrective Action Program procedures, instructions, and charters (CAP processes, root cause analysis, apparent cause analysis, oversight functions, trending, etc.).

26. Procedure change process procedure.

27. Summary listing of all open procedure change requests, including maintenance instructions, sorted by organization and date of request.

28. UFSAR

29. Technical Specifications, (hard copy to be available in team room).

30. Technical Requirements Manual, (hard copy to be available in team room).

31. Policies and procedures on nuclear safety (including corporate).

32. Industry operating experience program procedures.

33. Instructions for developing and implementing performance measures and metrics.

34. Change management procedures.

35. Communication procedures.

36. Decision making process procedures.

37. Procedures for raising concerns.

38. Departmental conduct of operations, maintenance, engineering, security, etc. procedures.

39. Safety impact/risk assessment review procedures.

40. Policies and procedures on harassment and intimidation.

41. Employee discipline procedures.

42. Assessment and audit procedures.

43. Design control procedures.

44. Design modification procedures.

45. Control of design basis procedures.

46. Control of overtime procedures.

47. Procedures for simulator fidelity.

48. Work control procedures (planning, scheduling, outage, and implementing).

49. Pre-job brief and shift brief procedures.

50. Procedures and policies involving procedural compliance.

51. Policies and procedures for supervisory and management oversight of work.

52. Equipment Qualification and Commercial Parts Dedication procedures.

53. Governing procedures for local leak rate testing, containment leak rate testing, code welding, and motor operated valve, air operated valve, and check valve testing, include the IST and MOV program basis documents.

54. Employee Concerns Program Procedures.

55. Policies and procedures associated with assessing equipment reliability and maintenance quality and/or effectiveness (rework).

56. Procedures related to operability determinations.

Enclosure

3 Engineering Documents

57. Since Jan 2010, summary listing (including a short description) of all temporary modifications, permanent, minor, and maintenance modifications. This should include modifications that were cancelled, completed, or remain open.

58. Since Jan 2010, summary listing (including a short description) of all temporary modifications, permanent, minor, and maintenance modifications. This should include modifications that were cancelled, completed, or remain open.

Documents in support of critical safety element review ( Vertical Slice Review)

59. For all systems required to support the function of containment heat removal, including;

a. Ultimate Heat Sink and the raw water closed cooling water systems that support the Emergency Diesel Generators;

b. EDGs and their other support systems;

c. Residual Heat Removal System

i. Suppression Pool heat removal; ii. Containment Spray;

d. Core Spray;

e. Condensate Storage Tank and systems needed for its swapover mode to the Suppression Pool and emergency refill; For each of the above provide the following:

o System health reports since January 1, 2010.

o System recovery plan actions and associated PERs.

o Electrical and mechanical system drawings.

Other Documents

60. List of Operability determinations completed since January 1, 2012.

61. List of PERs initiated since December 1, 2012.

62. Current station organizational chart, including special groups in place for the 95003 inspection.

63. Current site rooster or telephone listing.

64. Any Safety Conscience Work Environment/Safety Culture Training material used since January 2012.

65. Minutes from Employee Review Boards or any other disciplinary screening boards.

66. List of routine meetings including their times and locations for the month of May 2013.

67. List of issues reviewed against Browns Ferry 95003 Inspection Preparation Criterion 1, with a summary of the review results.

Enclosure