ML111600598

Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection

ML111600598
Person / Time
Site:	Sequoyah
Issue date:	06/09/2011
From:	Hopper G Reactor Projects Branch 7
To:	Krich R Tennessee Valley Authority
References
Download: ML111600598 (9)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 June 9, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION

Dear Mr. Krich:

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 your Sequoyah Nuclear Plant during the weeks of August 1-5 and August 15-19, 2011. The inspection team will be led by Mr. Ryan Taylor, a Senior Project Inspector from the NRCs Region II office. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71152, Problem Identification and Resolution, issued on February 26, 2010.

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 9, 2011, Mr. Taylor confirmed with Mr. Rusty Proffitt of your staff, arrangements for the two-week onsite inspection.

The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than July 18, 2011. Contact Mr. Taylor 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.

TVA.

2 If additional documents are needed, they will be requested when identified. Prior to the onsite inspection, Mr. Taylor 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; access to licensee computers; working space; arrangements for site access; and other applicable information.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure 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. Taylor at (404) 997-4630.

Sincerely,

/RA/

George T. Hopper, Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79

Enclosure:

Information Request for Sequoyah Nuclear Plant Problem Identification &

Resolution Inspection cc w/encl: (See page 3)

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.

_ ML111600598 __

X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP RII:DRP SIGNATURE GTH1 for GTH1 NAME RTaylor GHopper DATE 06/09/2011 06/09/2011 E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO

TVA 3

cc w/encl:

M. D. Skaggs Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution K. Langdon Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution G. M. Cook Manager Licensing Sequoyah Nuclear Plant Electronic Mail Distribution Dan Green Manager, Corp. Nuclear Licensing - SQN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution County Mayor Hamilton County Hamilton County Courthouse 208 Courthouse 625 Georgia Avenue Chattanooga, TN 37402-2801 Tennessee Department of Environment &

Conservation Division of Radiological Health 401 Church Street Nashville, TN 37243 Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379-3624 Ann Harris 341 Swing Loop Rockwood, TN 37854

TVA 4

Letter to R. M. Krich from George T. Hopper dated June 9, 2011

SUBJECT:

SEQUOYAH NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION Distribution w/encl:

C. Evans, RII EICS L. Douglas, RII EICS OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMSequoyah Resource

Enclosure INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (AUGUST 1-5 AND August 15-19, 2011)

Note: Unless otherwise noted, the information requested below corresponds to documents generated since August 1, 2009. Please provide the requested documents in electronic format.

If the information is not available in electronic format, please contact the inspection team leader to coordinate other available methods to provide the information.

1.

Copies of the corporate and site level procedures and sub-tier procedures associated with the corrective action program. This should include procedures related to:

a) Corrective action process b) Cause evaluation c) Operating experience program d) Employee concerns program e) Self-assessment program f) Maintenance rule program and implementing procedures g) Operability determination process h) Degraded/non-conforming condition process (e.g., RIS 2005-20) i) System health process or equivalent equipment reliability improvement programs j) Preventive maintenance deferral and Condition Report (CR) extension process If any of the procedures requested above were revised after December 2008, please provide (or have available) copies of all revisions during the onsite inspection.

2.

List of top ten risk significant systems, top ten risk significant components for each one of the top ten risk significant systems, and top ten risk significant operator manual actions

3.

List of all CRs initiated including the following information for each CR:

a) CR number b) Brief, but complete problem description c) Priority or level d) Affected system e) Affected component f) Responsible plant department g) CR completion status If possible, provide this list in a format compatible with spreadsheet software (example shown below).

CR #

Problem Priority System Component Org Status CR2008 000001 A RHR Pump failed flow criteria per SR 5.0.5.4 2

RHR 2-RHR-PMP-A ENG Open

2 Enclosure

4.

List of outstanding corrective actions including the following information for each action:

a) Corrective action number b) Corrective action type (e.g., corrective action to prevent recurrence, enhancement, maintenance rule evaluation, etc) c) Brief, but complete corrective action description d) Associated CR number e) Corrective action initiation date f) Number of extensions g) Corrective action due date h) Completion status If possible, provide this list in a format compatible with spreadsheet software (example shown below).

Corrective Action #

Type Description CR Initiation Date Extensions Due Date Status AI2008000 001 CAPR Revise Procedure NGK-003-4585 CR20080 00001 01/05/08 2

06/15/08 Awaiting CARB Review

5.

List of control room deficiencies with a brief description and corresponding CR and/or work order (WO) number

6.

List of operator workarounds and operator burdens with a brief description and corresponding CR number

7.

List of all currently extended or overdue CRs, sorted by initiation date, with the following information:

a) CR number b) Priority or Significance c) CR title and short description

8.

List of all CRs that have been voided, cancelled, or deleted. Please provide the following information for each CR:

a) CR number b) Brief, but complete problem description c) Reason voided, cancelled, or deleted

9.

List of all structures, systems, and components (SSCs) which were classified as (a)(1) in accordance with the Maintenance Rule since August 2009. Please include the following information for each system in (a)(1):

a) Date of classification in (a)(1)

3 Enclosure b) Reason for being placed in (a)(1) c) Planned actions and their status

10.

List of Maintenance Preventable Functional Failures (MPFF) of risk significant systems.

Please include actions completed and current status.

11.

List of corrective maintenance work orders. Please include the following information for each work order:

a) WO number b) Brief, but complete work description c) Affected system and components d) Date of initiation e) Date of completion (if completed)

If possible, provide this list in a format compatible with spreadsheet software (example shown below).

Work Order #

Description System Component Initiation Date Due Date Status WO01345 Replace breaker 2A-BKR-08-BB4 for 2A SI Pump.

SI 2A-SI-PMP, BKR-08-BB4 01/05/08 03/15/09 Closed

12.

Corrective action closeout packages, including CRs with description of corrective actions, for all NRC findings and Licensee identified violations. Please include a cross reference linking NRC Finding numbers and LIVs to appropriate CR numbers

13.

Corrective action closeout packages, including CRs with description of corrective actions, for all licensee event reports (LERs) issued. Please include a cross reference linking LER number to appropriate CR number.

14.

List of all NRC generic communications (e.g., Information Notices, Generic Letters, etc.)

and industry operating experience (OE) documents (e.g., Part 21 reports, vendor information letters, information from other sites, etc.) evaluated by the site for applicability to the station, regardless of the determination of applicability. Please include the reference number (e.g., CR number) for the documents that evaluated the aforementioned OE information.

15.

Copies of all quality assurance audits and/or assessments issued, including the last two audits/assessments of the corrective action program

16.

Copies of all department self-assessments

17.

Copy of the most recent integrated plant trend report, departmental trend report(s), and corrective action trend report, including any human performance and equipment reliability trends

4 Enclosure

18.

Copy of the latest Corrective Action Program statistics (if exists) such as the number of CRs initiated by department, human performance errors by department, and others as may be available

19.

Copies of any minutes of meetings by the offsite safety review boards/groups. In addition, please provide a list of routine meetings involving the CAP to be held while team is onsite

20.

List of CRs related to equipment aging issues in the top ten risk significant systems since August 2006 (e.g., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.;

environmental qualification). Please provide the following information for each CR:

a) CR number b) Priority c) CR problem description

21.

If performed, please provide any recent self-assessment of the site safety culture.

22.

Copies of corrective action program documents related to cross-cutting issues (human performance, problem identification and resolution, and safety conscious work environment) identified via trending, self-assessments, safety review committee or other oversight methods

23.

List of all root cause evaluations with a brief description

24.

Copy of Probabilistic Risk Assessment importance measures report, if available

25.

System Health Reports, system design basis documents, and system description information for the top ten risk significant systems