ML12066A059
| ML12066A059 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/05/2012 |
| From: | McCree V M Region 2 Administrator |
| To: | Shea J W Tennessee Valley Authority |
| References | |
| IR-11-007 | |
| Download: ML12066A059 (6) | |
See also: IR 05000259/2011007
Text
March 5, 2012
Mr. Joseph Manager, Corp. Nuclear Licensing Programs Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801
SUBJECT: ANNUAL ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2011007)
Dear Mr. Shea:
On February 16, 2012, the NRC completed its end-of-cycle performance review of Browns Ferry Nuclear Plant, Units 1, 2, and 3. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2011 through December 31, 2011. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the plant performance at Browns Ferry Units 2 and 3, during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all Performance Indicators (PI) indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at these units. The NRC determined the plant performance at Browns Ferry Unit 1 during the most recent quarter was within the Multiple/Repetitive Degraded Cornerstone column (Column 4) of the NRC's ROP Action Matrix, beginning the fourth quarter 2010, based on the issuance of one finding classified as having a high safety significance (Red). This was detailed in Final Significance Determination Of A Red Finding, Notice Of Violation, And Assessment Follow-Up Letter (NRC Inspection Report No. 05000259/2011008) for Browns Ferry Nuclear Plant, dated May 9, 2011.
Consistent with NRC Manual Chapter 0305, the NRC will conduct Part 3 of a supplemental inspection in accordance with IP 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input," following written notification from you on your readiness to support this inspection. The Red finding is being held open past 4 quarters pending completion of Part 3, IP 95003. Based on a review of the inspection results, the NRC will provide further clarification regarding specific actions TVA will need to take following completion of Part 3 of IP 95003.
TVA 2 In its Annual Assessment Letter, dated March 4, 2011, (ML11063042), the NRC opened a SCCI in the Corrective Action Program component of the Problem Identification and Resolution cross-cutting area. Specifically, a cross-cutting theme was identified based on four Green inspection findings for the associated 12-month assessment period with documented cross-cutting aspects in the area of Problem Identification and Resolution, in the aspect of "appropriate and timely corrective actions" (P.1(d)). The NRC determined that an SCCI existed because the NRC had a concern with your staff's scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No. 05000259,260,296/2010005). Although you identified and implemented a range of actions to address the cross-cutting theme; these actions had not yet proven effective in substantially mitigating the cross-cutting theme, even though a reasonable duration of time has passed. In its Mid-Cycle Assessment Letter, dated August 29, 2011, (ML112411450), the NRC requested that this SCCI be addressed during your third party safety culture assessment which will be reviewed as part of the Independent NRC Safety Culture Assessment per IP 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input." This SCCI will continue to remain open pending completion of these assessments and until the NRC has reviewed your other actions to address this SCCI, based on the following: 1.) A comprehensive range of actions are identified in your Corrective Action Program that effectively demonstrate you will address the cross-cutting theme; 2.) No significant increase in the number of findings with the cross-cutting aspect of "appropriate and timely corrective actions" (P.1(d)) during the previous twelve month assessment period; and 3.) The NRC has an increased level of confidence in your ability to deal effectively with operational/equipment issues as related to the cross-cutting theme of "appropriate and timely corrective actions" (P.1(d)) during the previous six months assessment period. This letter is the third consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.
In its Annual Assessment Letter, dated March 3, 2010, (ML100620960), the NRC opened a SCCI in the Corrective Action Program component of the Problem Identification and Resolution cross-cutting area. Specifically, a cross-cutting theme was identified based on four Green inspection findings for the associated 12-month assessment period with documented cross-cutting aspects in the area of Problem Identification and Resolution, in the aspect of "thorough evaluation of identified problems" (P.1(c)). The NRC determined that an SCCI existed because the NRC had a concern with your staff's scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No. 05000259,260,296/2010005). Although you identified and implemented a range of actions to address the cross-cutting theme; these actions had not yet proven effective in substantially mitigating the cross-cutting theme, even though a reasonable duration of time has passed. In its Mid-Cycle Assessment Letter, dated August 29, 2011, (ML112411450), the NRC requested that this SCCI be addressed during your third party safety culture assessment which will be reviewed as part of the Independent NRC Safety Culture Assessment per IP 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input." This SCCI will continue to remain open pending completion of these assessments and until the NRC has reviewed your other actions to address this SCCI, based on the following: 1) An appropriate and comprehensive range of actions identified by the Corrective Action Program, which will effectively address the cross-cutting theme; 2) No significant increase in the number of findings with the cross-cutting aspect of "thorough evaluation of identified problems" (P.1(c)) during the previous twelve month assessment period; and 3) An increased level of confidence in your ability to deal effectively with operational and equipment issues as related to the cross-cutting theme of "thorough evaluation of identified problems" (P.1(c)) during the previous six month TVA 3 assessment period. This letter is the fifth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect. In addition to the reactor oversight process (ROP) baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: Inspection Procedure (IP) 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input"; Reactor operator licensing examinations; 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders; and TI 2515/182, "Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks.". The enclosed inspection plan lists the inspections scheduled through June 30, 2013. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter 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). If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.
Sincerely,/RA By Leonard D. Wert, Jr. For/ Victor M. McCree Regional Administrator Docket No.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68
Enclosure:
Browns Ferry Inspection/Activity Plan cc w/encl: (See page 5)
TVA 3 assessment period. This letter is the fifth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.
In addition to the reactor oversight process (ROP) baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: Inspection Procedure (IP) 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input." Reactor operator licensing examinations; 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders, and TI 2515/182, "Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks.".
The enclosed inspection plan lists the inspections scheduled through June 30, 2013. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter 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). If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.
Sincerely,/RA By Leonard D. Wert, Jr. For/ Victor M. McCree Regional Administrator Docket No.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68
Enclosure:
Browns Ferry Inspection/Activity Plan cc w/encl: (See page 5) X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE ADAMS: XYes ACCESSION NUMBER:__ ML12066A059 _______________________ X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP RII:DRP RII:ORA RII:ORA SIGNATURE /RA By EGuthrie./ /RA By EGuthrie/ /RA/ /RA/ /RA By LWert/ NAME CKontz EGuthrie RCroteau LWert VMcCree DATE 2/28/2012 2/28/2012 2/28/2012 3/5/2012 3/5/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRP\PERIODIC ASSESSMENTS & REPORTS\EOC & MID-CYCLE\2011\END-OF-CYCLE\INPUT\RPB6\EOC LETTERS - FINAL\ANNUAL ASSESSMENT EOC CYCLE LETTER BFN 2011 (CRK) FINAL REV.DOCX 4 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 Manager, Corporate Nuclear Licensing - BFN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution T. A. Hess Tennessee Valley Authority Electronic Mail Distribution Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Donald E. Williamson State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611-6970 5 Letter to Joseph from Victor M. McCree dated March 5, 2012
SUBJECT: ANNUAL ASSESSMENT LETTER FOR THE BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2011007) Distribution w/encl: C. Evans, RII EICS (Part 72 Only) L. Douglas, RII EICS (Linda Douglas)
OE Mail (email address if applicable) RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource