ML112411393
| ML112411393 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/29/2011 |
| From: | Eugene Guthrie Division of Reactor Safety II |
| To: | Krich R Tennessee Valley Authority |
| References | |
| Download: ML112411393 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 August 29, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR PART 1 OF NRC SUPPLEMENTAL 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 supplemental inspection at your Browns Ferry Nuclear Plant beginning on September 12, 2011. The inspection team will be led by Bob Orlikowski, a Project Engineer from the NRCs Region III office. This 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, Experience has shown that these inspections are extremely resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a list of documents required for the inspection.
The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than September 6, 2011. Contact Mr. Orlikowski 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.
In accordance with 10 CFR 2.790 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
TVA 2
Thank you for your cooperation in this matter. If there are any questions about the material requested, or the inspection in general, please do not hesitate to call or e-mail Mr. Orlikowski at 630-829-9753 or Robert.orlikowski@nrc.gov. You may also contact Mr. Craig Kontz at 404-997-4715 or Craig.Kontz@nrc.gov.
Sincerely,
/RA/
Eugene F. Guthrie, Chief Special Projects Branch Division of Reactor Projects Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68
Enclosure:
As stated 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.
______ML112411393___________
X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP RIII:DRP SIGNATURE CRK /RA/
EFG /RA/
Via email NAME CKontz EGuthrie ROrlikowski DATE 08/29/2011 08/29/2011 05/25/2011 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO
TVA 3
cc w/encl:
K. J. Polson Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution J. E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution T. C. Matthews Manager, Corporate Nuclear Licensing -
BFN Tennessee Valley Authority Electronic Mail Distribution State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017
TVA 4
Letter to R. M. Krich from Eugene F. Guthrie dated August 29, 2011
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR PART 1 OF NRC SUPPLEMENTAL INSPECTION Distribution w/encl:
C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
Enclosure Requested Information for Part 1 of Browns Ferry 95003 Inspection Note: Unless otherwise noted, the information requested below corresponds to documents generated for the past two years. Please provide the requested documents in electronic format (on a compact disc if possible). 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: 1) corrective action process; 2) operating experience program; 3) self-assessment program; 4) maintenance rule program and implementing procedures; 5) operability determination process; 6) Degraded/non-conforming condition process (e.g., RIS 2005-20); 7) System Health process or equivalent equipment reliability improvement programs; 8) Operational Decision Making (ODMI) process.
- 2. Browns Ferry Nuclear Plants Procedure Control Procedure, including the following:
NPG-SPP-01.1, Administration of Standard Programs and Processes (SPPs); Standard Department Procedures (SDPs); and Business Practices (BPs)
NPG-SPP-01.2, Administration of Site Technical Procedures
- 3. The following TVA Surveillance Procedures:
1-SR-3.3.3.1.4(H II) 1-SR-3.6.1.3.5
- 4. List of all pumps and valves included in Browns Ferry Nuclear Plants In-service Testing (IST) Program and the GL 89-10 program.
- 5. Browns Ferry Nuclear Plants general IST, Surveillance Testing, and Post-Maintenance Testing implementation procedures. (Note: The general IST implementing procedures are sometimes quite large. Please contact the NRC if there are issues in obtaining copies to transmit)
- 6. Specific Plant/Vendor information on valve 1-FCV-74-66, including:
Technical Manuals Drawings/Diagrams Applicable Operating Experience IST/Surveillance Testing/Post Maintenance Testing (PMT) Results (for previous 2 years)
- 7. A copy of all Corrective Action Program (CAP) reports (PERs and SRs) generated that pertain to IST/PMT for pumps and valves in Browns Ferrys IST program. This list should be sorted by the following systems:
2 Enclosure
- 8. A list (Title and date) of all CAP PERs and SRs generated in the previous 5 years. This list should be sorted by the following systems:
- 9. A list of the corrective action and preventative maintenance backlog work items for the following systems:
- 10. A list of all pump/valve IST testing scheduled to occur between September 12, 2011, and September 23, 2011.
- 12. Piping and Instrument Drawings (P&IDs) for all ECCS systems as well as RCIC, RHRSW, and EECW (Note: Only include the primary or main P&ID that shows the system as a whole)
- 13. Documentation (to include any Corrective Action Program documents, Engineering Evaluations, Testing Results) pertaining to the following issues:
RHR Service Water valves (1/2/3-FCV-23-34, 40, 46, and 52) separation in 2008 Unit 2 HPCI testable Check Valve (1-FCV-73-45) was in the open position with Satisfactory IST testing and deficient valve indications relied on for IST LPCI/RHR Loop 1 outboard Injection valve (1-FCV-74-52) failure to re-open on August 2, 2011, after multiple cycles during RHR logic functional testing.
- 14. For the following list of valves:
FCV-71-34 FCV-73-50 FCV-74-53 FCV-74-67 FCV-23-34 FCV-23-40 FCV-23-46 FCV-23-52 FCV-67-48 FCV-67-49 FCV-67-50 FCV-67-51 1FCV-002-0170 1 FCV-002-0171 2 FCV-002-0162 2 FCV-002-0163 3FCV-002-0166 3 FCV-002-0167 FCV-74-46 FCV-23-57 FCV-74-100 FCV-74-101 FCV-75-53 FCV-75-51 FCV-75-25 FCV-75-23
3 Enclosure Please provide the following information:
A list of open and closed work orders (by title and date only) for all work performed on each valve. This list shall include activities for the past five years.
List of Issue Reports/Condition Reports related to any deficiencies for each valve over the past 5 years Results of any diagnostic testing (VOTES, MOVATS, etc.) performed over the past 5 years Documents requested to be available as printed copies on-site during the inspection:
Updated Final Safety Analysis Report Technical Specifications The QA manual Copy of Tennessee Valley Authority and/or Browns Ferry Nuclear Plants Inservice Testing, Surveillance Testing, and Post Maintenance Testing Implementing Procedures The latest organization chart and phone listing Copy of ASME Code to Which Browns Ferry is Committed Copy of Plant P&IDs Documentation of the technical review/justification for plant pumps and valves for inclusion in the IST program