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| number = ML12248A296
| number = ML12248A296
| issue date = 09/04/2012
| issue date = 09/04/2012
| title = Browns Ferry 2012 Mid Cycle
| title = Mid Cycle
| author name = McCree V M
| author name = Mccree V
| author affiliation = NRC/RGN-II/ORA
| author affiliation = NRC/RGN-II/ORA
| addressee name = Shea J W
| addressee name = Shea J
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000259, 05000260, 05000296
| docket = 05000259, 05000260, 05000296
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 4, 2012  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 4, 2012 Mr. Joseph W. Shea Manager, Corp. Nuclear Licensing Programs Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801
 
Mr. Joseph W. Shea Manager, Corp. Nuclear Licensing Programs Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801  


==SUBJECT:==
==SUBJECT:==
MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)  
MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)


==Dear Mr. Shea:==
==Dear Mr. Shea:==


On August 16, 2012, the NRC completed its mid-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 July 1, 2011, through June 30, 2012. 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 assessment reflects the integration of the security cornerstone into the Reactor Oversight Process performance assessment program governed by IMC 0305, "Operating Reactor Assessment Program."
On August 16, 2012, the NRC completed its mid-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 July 1, 2011, through June 30, 2012. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This assessment reflects the integration of the security cornerstone into the Reactor Oversight Process performance assessment program governed by IMC 0305, Operating Reactor Assessment Program.
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 Reactor Oversight Process Action Matr ix, 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, (ML111290482)) for Browns Ferry Nuclear Plant, dated May 9, 2011.  
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 NRCs Reactor Oversight Process 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, (ML111290482)) for Browns Ferry Nuclear Plant, dated May 9, 2011.
Since the last performance assessment, Browns Ferry Unit 1 received one additional action matrix input for Mitigating System Performance Index, High Pressure Injection Systems (HPCI)
Performance Indicator, when it changed from Green to White. During this reporting period, 4 HPCI system failures were included. Unavailability also contributed to the performance indicator change due to HPCI steam admission valve leakage. The White performance indicator input does not change the current assessment of performance for Unit 1 because Unit 1 was already assessed to be in the Multiple/Repetitive Degraded Cornerstone column of the Reactor Oversight Process Action Matrix.
Consistent with NRC Manual Chapter 0305, the NRC will conduct Part 3 of a supplemental inspection in accordance with Inspection Procedure (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


Since the last performance assessment, Browns Ferry Unit 1 received one additional action matrix input for Mitigating System Performance Index, High Pressure Injection Systems (HPCI) Performance Indicator, when it changed from Green to White. During this reporting period, 4 HPCI system failures were included. Unavailability also contributed to the performance indicator change due to HPCI steam admission valve leakage. The White performance indicator input does not change the current assessment of performance for Unit 1 because Unit 1 was already assessed to be in the Multiple/Repetitive Degraded Cornerstone column of the Reactor Oversight Process Action Matrix.
J. Shea                                       2 regarding any specific actions the Tennesse Valley Authority will need to take following completion of Part 3 of IP 95003. Additionally, the NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Mitigating System Performance Index, High Pressure Injection Systems, for Unit 1.
Consistent with NRC Manual Chapter 0305, the NRC will conduct Part 3 of a supplemental inspection in accordance with Inspection Procedure (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 J. Shea 2 regarding any specific actions the Tennesse Valley Authority will need to take following completion of Part 3 of IP 95003. Additionally , the NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Mitigating System Performance Index, High Pressure Injection Systems, for Unit 1.  
Plant performance for Browns Ferry Units 2 and 3 for the most recent quarter was in the Regulatory Response Column (Column 2) of the NRCs Reactor Oversight Process Action Matrix. As detailed in Final Significance Determination Of A White Finding, Notice Of Violation, And Assessment Follow-Up Letter (NRC Inspection Reports 05000259,260,296/2012013, (ML12226A647)) for Browns Ferry Nuclear Plant, dated Aug 13, 2012, Units 2 and 3 were determined to be in the Regulatory Response Column beginning in the second quarter 2012.
 
Plant performance for Browns Ferry Units 2 and 3 for the most recent quarter was in the Regulatory Response Column (Column 2) of the NRC's Reactor Oversight Process Action Matrix. As detailed in Final Significance Determination Of A White Finding, Notice Of Violation, And Assessment Follow-Up Letter (NRC Inspection Reports 05000259,260,296/2012013, (ML12226A647)) for Browns Ferry Nuclear Plant, dated Aug 13, 2012, Units 2 and 3 were determined to be in the Regulatory Response Column beginning in the second quarter 2012.
As stated in this assessment, additional regulatory oversight actions will be implemented at your facility. We will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Finding.
As stated in this assessment, additional regulatory oversight actions will be implemented at your facility. We will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Finding.
Since the last performance assessment, Browns Ferry Unit 3 received one additional action matrix input for the Unplanned Scrams Performance Indicator, which changed from Green to White in May of 2012. Reactor scrams on September 28, 2011, May 22, May 24, 2012, and May 29, 2012, caused the Performance Indicator to change from Green to White. The White performance indicator input does not change the current assessment of performance for Unit 3 because Unit 3 was already assessed to be in the Regulatory Response column of the NRC's Action Matrix based on an input from a different Reactor Oversight Process cornerstone. The NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Unplanned Scrams Performance Indicator for Unit 3.  
Since the last performance assessment, Browns Ferry Unit 3 received one additional action matrix input for the Unplanned Scrams Performance Indicator, which changed from Green to White in May of 2012. Reactor scrams on September 28, 2011, May 22, May 24, 2012, and May 29, 2012, caused the Performance Indicator to change from Green to White. The White performance indicator input does not change the current assessment of performance for Unit 3 because Unit 3 was already assessed to be in the Regulatory Response column of the NRCs Action Matrix based on an input from a different Reactor Oversight Process cornerstone. The NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Unplanned Scrams Performance Indicator for Unit 3.
 
In its Annual Assessment Letter, dated March 4, 2011, (ML11063042), the NRC opened a Substantive Cross-Cutting Issue (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 staffs scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No.
In its Annual Assessment Letter, dated March 4, 2011, (ML11063042), the NRC opened a Substantive Cross-Cutting Issue (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 ML110400431). 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
05000259,260,296/2010005 ML110400431). 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 J. Shea 3  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 fourth 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 assessment period. This letter is the sixth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect. 
 
During this assessment, the NRC identified a cro ss-cutting theme in the Resources component of the Human Performance & Error Prevention cross-cutting area. Specifically, five Green inspection findings for the current 12-month assessment period, each with a documented cross-cutting aspect of "Complete Documentation and Component Labeling" (H.2.(c)) were identified.
The NRC determined that a SCCI did not exist because the NRC does not have a concern with your staff's scope of effort and progress in addressing the cross-cutting theme. This is based on TVA's proactive actions, which began in 2010, in addressing concerns associated with this Cross Cutting Aspect (CCA). Three of the five CCA's were assigned in the second quarter of 2012, which were the result of issues with the licensee's procurement and operations procedure processes that would not have been reasonably identified by the previous efforts to address this CCA. Each of the CCAs involved separate Reactor Oversight Process cornerstones. The NRC has concluded that it is reasonable to allow some amount of time for you to incorporate the new issues into your corrective action program. The NRC will evaluate the effectiveness of your corrective actions during the next assessment cycle and will continue to monitor your staff's effort and progress in addressing this theme.
J. Shea 4  The enclosed inspection plan lists the inspections scheduled through December 30, 2013. Routine inspections performed by resident inspectors are not included in the inspection plan. In addition to the baseline inspections, consistent with the Agency's actions related to Fukushima, the NRC will perform TI-187, "Inspection of Near-Term Task Force Recommendation 2.3 Flooding Walkdowns" and TI-188 Inspection of Near-Term Task Force Recommmendation 2.3 Seismic Walkdowns."  The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-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 di scuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
In addition to the baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include:  IP 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders; initial reactor operator licensing examinations; and TI 2515/182, "Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks." 
 
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).  
J. Shea                                        3 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 fourth 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 staffs 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 assessment period. This letter is the sixth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.
During this assessment, the NRC identified a cross-cutting theme in the Resources component of the Human Performance & Error Prevention cross-cutting area. Specifically, five Green inspection findings for the current 12-month assessment period, each with a documented cross-cutting aspect of Complete Documentation and Component Labeling (H.2.(c)) were identified.
The NRC determined that a SCCI did not exist because the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. This is based on TVAs proactive actions, which began in 2010, in addressing concerns associated with this Cross Cutting Aspect (CCA). Three of the five CCAs were assigned in the second quarter of 2012, which were the result of issues with the licensees procurement and operations procedure processes that would not have been reasonably identified by the previous efforts to address this CCA. Each of the CCAs involved separate Reactor Oversight Process cornerstones. The NRC has concluded that it is reasonable to allow some amount of time for you to incorporate the new issues into your corrective action program. The NRC will evaluate the effectiveness of your corrective actions during the next assessment cycle and will continue to monitor your staffs effort and progress in addressing this theme.


J. Shea                                        4 The enclosed inspection plan lists the inspections scheduled through December 30, 2013.
Routine inspections performed by resident inspectors are not included in the inspection plan. In addition to the baseline inspections, consistent with the Agencys actions related to Fukushima, the NRC will perform TI-187, Inspection of Near-Term Task Force Recommendation 2.3 Flooding Walkdowns and TI-188 Inspection of Near-Term Task Force Recommmendation 2.3 Seismic Walkdowns. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-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. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
In addition to the baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: IP 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders; initial reactor operator licensing examinations; and TI 2515/182, Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks.
In accordance with 10 CFR 2.390 of the NRCs 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).
Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.
Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.
Sincerely, /RA/   Victor M. McCree Regional Administrator Docket No.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68  
Sincerely,
                                                /RA/
Victor M. McCree Regional Administrator Docket No.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68


==Enclosure:==
==Enclosure:==
Browns Ferry Inspection/Activity Plan (09/01/2012 - 12/31/2013)  
Browns Ferry Inspection/Activity Plan (09/01/2012 - 12/31/2013) cc w/encl: (See page 5)
 
cc w/encl: (See page 5)  
 
__
_______________________  X  SUNSI REVIEW COMPLETE OF FICE RII:DRP RII:DRP RII:DRP RII:ORA RII:ORA  SIGNATURE /RA By EGuthrie/ /RA/
/RA/ /RA/ /RA/  NAME CKontz EGuthrie RCroteau LWert VMcCree  DATE 8/27/2012 8/27/2012 8/28/2012 8/31/2012 9/4/2012  E-MAIL COPY?    YES NO      YES NO    YES N O  YES NO  YES NO  YES NO  YES NO J. Shea 5  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 James 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 Edward 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  
__ ML12248A296 _______________________                      X SUNSI REVIEW COMPLETE OFFICE            RII:DRP          RII:DRP        RII:DRP        RII:ORA          RII:ORA SIGNATURE        /RA By EGuthrie/  /RA/            /RA/            /RA/            /RA/
NAME              CKontz            EGuthrie        RCroteau        LWert            VMcCree DATE                  8/27/2012        8/27/2012      8/28/2012        8/31/2012        9/4/2012 E-MAIL COPY?        YES        NO    YES        NO  YES          NO YES          NO  YES        NO YES      NO  YES NO J. Shea                                5 cc w/encl:                              James L. McNees, CHP K. J. Polson                            Director Site Vice President                      Office of Radiation Control Browns Ferry Nuclear Plant              Alabama Dept. of Public Health Tennessee Valley Authority              P. O. Box 303017 Electronic Mail Distribution            Montgomery, AL 36130-3017 C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution James 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 Edward 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


J. Shea 6 Letter to Joseph W. Shea from Victor M. McCree dated September 4, 2012  
J. Shea                                   6 Letter to Joseph W. Shea from Victor M. McCree dated September 4, 2012


==SUBJECT:==
==SUBJECT:==
MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)  
MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)
Distribution w/encl:
C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource INPO ROP Reports


Distribution w/encl
Page 1 of 2                                                                                  Browns Ferry 09/04/2012      08:15:05                                                            Inspection / Activity Plan Report 22 09/01/2012 - 12/31/2013 Unit          Planned Dates                                                                                                                        No. of Staff Number          Start        End      Inspection Activity                                                            Title                        on Site 95001        - WHITE VIOLATION FOR SSI TRAINING                                                                    1 1, 2, 3      10/08/2012    10/08/2012      IP 95001              Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area OL RQ        - REQUAL INSPECTION                                                                                  2 1, 2, 3      10/08/2012    10/12/2012      IP 7111111B            Licensed Operator Requalification Program TI-188        - TI-188 P2 - NTTF 2.3 - SEISMIC WALKDOWNS                                                            1 1, 2, 3      10/17/2012    10/19/2012      IP 2515/188            Inspection of Near-Term Task Force Recommendation 2.3 Seismic Walkdowns EB3 ISI      - UNIT 1 INSERVICE INSPECTION                                                                        1 1            10/29/2012    11/02/2012      IP 7111108G            Inservice Inspection Activities - BWR EB3 LR        - UNIT 1 POST APPROVAL LR - PHASE 1                                                                  2 1            10/29/2012    11/02/2012      IP 71003              Post-Approval Site Inspection for License Renewal CDBI          - COMPONENT DESIGN BASES INSPECTION                                                                  10 1, 2, 3      01/07/2013    01/11/2013      IP 7111121            Component Design Bases Inspection 1, 2, 3      01/28/2013    02/01/2013      IP 7111121            Component Design Bases Inspection 1, 2, 3      02/11/2013    02/15/2013      IP 7111121            Component Design Bases Inspection 1, 2, 3      02/25/2013    03/01/2013      IP 7111121            Component Design Bases Inspection ISI          - UNIT 2 INSERVICE INSPECTION                                                                        1 2        03/25/2013    03/29/2013      IP 7111108G            Inservice Inspection Activities - BWR LR71003      - UNIT 2 POST APPROVAL LR PHASE 1                                                                    2 2        04/01/2013    04/05/2013      IP 71003              Post-Approval Site Inspection for License Renewal PSB1-RP      - RP OCCUPATIONAL BASELINE                                                                            2 1, 2, 3      04/01/2013    04/05/2013      IP 71124.01            Radiological Hazard Assessment and Exposure Controls 1, 2, 3      04/01/2013    04/05/2013      IP 71124.02            Occupational ALARA Planning and Controls 1, 2, 3      04/01/2013    04/05/2013      IP 71124.03            In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3      04/01/2013    04/05/2013      IP 71124.04            Occupational Dose Assessment 1, 2, 3      04/01/2013    04/05/2013      IP 71124.05            Radiation Monitoring Instrumentation 1, 2, 3      04/01/2013    04/05/2013      IP 71151              Performance Indicator Verification PSB1-RP      - RP OCCUPATIONAL BASELINE WEEK 2                                                                    3 1, 2, 3      04/15/2013    04/19/2013      IP 71124.01            Radiological Hazard Assessment and Exposure Controls 1, 2, 3      04/15/2013    04/19/2013      IP 71124.02            Occupational ALARA Planning and Controls 1, 2, 3      04/15/2013    04/19/2013      IP 71124.03            In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3      04/15/2013    04/19/2013      IP 71124.04            Occupational Dose Assessment 1, 2, 3      04/15/2013    04/19/2013      IP 71124.05            Radiation Monitoring Instrumentation 1, 2, 3      04/15/2013    04/19/2013      IP 71151              Performance Indicator Verification This report does not include INPO and OUTAGE activities.                                                                                      Enclosure This report shows only on-site and announced inspection procedures.
: C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS


PUBLIC RidsNrrPMBrownsFerry Resource INPO ROP Reports Browns Ferry Inspection / Activity Plan 09/01/2012
Page 2 of 2                                                                                   Browns Ferry 09/04/2012       08:15:05                                                             Inspection / Activity Plan Report 22 09/01/2012 - 12/31/2013 Unit         Planned Dates                                                                                                                                        No. of Staff Number          Start         End       Inspection Activity                                                               Title                                       on Site OL EXAM       - INITIAL EXAM PREP                                                                                                   3 1           05/06/2013   05/10/2013       V23394               BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES LR71003       - UNIT 1 POST APPROVAL LR PHASE 2                                                                                     5 1           05/06/2013   05/10/2013     IP 71003               Post-Approval Site Inspection for License Renewal 1           05/20/2013   05/24/2013     IP 71003               Post-Approval Site Inspection for License Renewal TI-182       - TI-182 BURIED PIPING/TANK - PHASE 1                                                                                  1 1, 2, 3     05/13/2013   05/17/2013     IP 2515/182             Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping EP           - EMERGENCY PREPAREDNESS EXERCISE                                                                                     1 1, 2, 3     06/03/2013   06/07/2013     IP 7111401             Exercise Evaluation 1, 2, 3     06/03/2013   06/07/2013     IP 71151               Performance Indicator Verification OL EXAM       - INITIAL EXAM - WEEK 1                                                                                               3 1           06/03/2013   06/07/2013       V23394               BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES OL EXAM       - INITIAL EXAM - WEEK 2                                                                                               3 1           06/10/2013   06/14/2013       V23394               BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES BF TFPI       - BF - TRIENNIAL FIRE PROTECTION INSP                                                                                 4 1, 2, 3     10/01/2013   10/03/2013     IP 7111105T             Fire Protection [Triennial]
-12/31/2013 Unit Number Page 1 of 2 09/04/2012 08:15:05 Report 22 No. of Staff on Site Planned Dates Start          End Inspection Activity Title 1 95001-WHITE VIOLATION FOR SSI TRAINING 1, 2, 3 10/08/2012 10/08/2012 IP 95001 Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area 2 OL RQ-REQUAL INSPECTION 1, 2, 3 10/08/2012 10/12/2012 IP 7111111B Licensed Operator Requalification Program 1 TI-188-TI-188 P2 - NTTF 2.3 - SEISMIC WALKDOWNS 1, 2, 3 10/17/2012 10/19/2012 IP 2515/188 Inspection of Near-Term Task Force Recommendation 2.3 Seismic Walkdowns 1 EB3 ISI-UNIT 1 INSERVICE INSPECTION 1    10/29/2012 11/02/2012 IP 7111108G Inservice Inspection Activities - BWR 2 EB3 LR-UNIT 1 POST APPROVAL LR - PHASE 1 1    10/29/2012 11/02/2012 IP 71003 Post-Approval Site Inspection for License Renewal 10 CDBI-COMPONENT DESIGN BASES INSPECTION 1, 2, 3 01/07/2013 01/11/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 01/28/2013 02/01/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 02/11/2013 02/15/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 02/25/2013 03/01/2013 IP 7111121 Component Design Bases Inspection 1 ISI-UNIT 2 INSERVICE INSPECTION 2  03/25/2013 03/29/2013 IP 7111108G Inservice Inspection Activities - BWR 2 LR71003-UNIT 2 POST APPROVAL LR PHASE 1 2  04/01/2013 04/05/2013 IP 71003 Post-Approval Site Inspection for License Renewal 2 PSB1-RP-RP OCCUPATIONAL BASELINE 1, 2, 3 04/01/2013 04/05/2013 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2, 3 04/01/2013 04/05/2013 IP 71124.02 Occupational ALARA Planning and Controls 1, 2, 3 04/01/2013 04/05/2013 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3 04/01/2013 04/05/2013 IP 71124.04 Occupational Dose Assessment 1, 2, 3 04/01/2013 04/05/2013 IP 71124.05 Radiation Monitoring Instrumentation 1, 2, 3 04/01/2013 04/05/2013 IP 71151 Performance Indicator Verification 3 PSB1-RP-RP OCCUPATIONAL BASELINE WEEK 2 1, 2, 3 04/15/2013 04/19/2013 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2, 3 04/15/2013 04/19/2013 IP 71124.02 Occupational ALARA Planning and Controls 1, 2, 3 04/15/2013 04/19/2013 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3 04/15/2013 04/19/2013 IP 71124.04 Occupational Dose Assessment 1, 2, 3 04/15/2013 04/19/2013 IP 71124.05 Radiation Monitoring Instrumentation 1, 2, 3 04/15/2013 04/19/2013 IP 71151 Performance Indicator Verification This report does not include INPO and OUTAGE activities.
1, 2, 3     10/21/2013   10/25/2013     IP 7111105T             Fire Protection [Triennial]
This report shows only on-site and announced inspection procedures.
1, 2, 3     11/04/2013   11/08/2013     IP 7111105T             Fire Protection [Triennial]
Browns Ferry Inspection / Activity Plan 09/01/2012
Comments:
-12/31/2013 Unit Number Page 2 of 2 09/04/2012 08:15:05 Report 22 No. of Staff on Site Planned Dates Start           End Inspection Activity Title 3 OL EXAM-INITIAL EXAM PREP 1     05/06/2013 05/10/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES 5 LR71003-UNIT 1 POST APPROVAL LR PHASE 2 1     05/06/2013 05/10/2013 IP 71003 Post-Approval Site Inspection for License Renewal 1     05/20/2013 05/24/2013 IP 71003 Post-Approval Site Inspection for License Renewal 1 TI-182-TI-182 BURIED PIPING/TANK - PHASE 1 1, 2, 3 05/13/2013 05/17/2013 IP 2515/182 Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping 1 EP-EMERGENCY PREPAREDNESS EXERCISE 1, 2, 3 06/03/2013 06/07/2013 IP 7111401 Exercise Evaluation 1, 2, 3 06/03/2013 06/07/2013 IP 71151 Performance Indicator Verification 3 OL EXAM-INITIAL EXAM - WEEK 1 1     06/03/2013 06/07/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES 3 OL EXAM-INITIAL EXAM - WEEK 2 1     06/10/2013 06/14/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES 4 BF TFPI-BF - TRIENNIAL FIRE PROTECTION INSP 1, 2, 3 10/01/2013 10/03/2013 IP 7111105T Fire Protection [Triennial]
This report does not include INPO and OUTAGE activities.                                                                                                       Enclosure This report shows only on-site and announced inspection procedures.}}
1, 2, 3 10/21/2013 10/25/2013 IP 7111105T Fire Protection [Triennial]
1, 2, 3 11/04/2013 11/08/2013 IP 7111105T Fire Protection [Triennial]
Comments: This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.}}

Latest revision as of 13:23, 6 February 2020

Mid Cycle
ML12248A296
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 09/04/2012
From: Mccree V
Region 2 Administrator
To: James Shea
Tennessee Valley Authority
References
Download: ML12248A296 (9)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 4, 2012 Mr. Joseph W. Shea Manager, Corp. Nuclear Licensing Programs Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)

Dear Mr. Shea:

On August 16, 2012, the NRC completed its mid-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 July 1, 2011, through June 30, 2012. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This assessment reflects the integration of the security cornerstone into the Reactor Oversight Process performance assessment program governed by IMC 0305, Operating Reactor Assessment Program.

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 NRCs Reactor Oversight Process 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, (ML111290482)) for Browns Ferry Nuclear Plant, dated May 9, 2011.

Since the last performance assessment, Browns Ferry Unit 1 received one additional action matrix input for Mitigating System Performance Index, High Pressure Injection Systems (HPCI)

Performance Indicator, when it changed from Green to White. During this reporting period, 4 HPCI system failures were included. Unavailability also contributed to the performance indicator change due to HPCI steam admission valve leakage. The White performance indicator input does not change the current assessment of performance for Unit 1 because Unit 1 was already assessed to be in the Multiple/Repetitive Degraded Cornerstone column of the Reactor Oversight Process Action Matrix.

Consistent with NRC Manual Chapter 0305, the NRC will conduct Part 3 of a supplemental inspection in accordance with Inspection Procedure (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

J. Shea 2 regarding any specific actions the Tennesse Valley Authority will need to take following completion of Part 3 of IP 95003. Additionally, the NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Mitigating System Performance Index, High Pressure Injection Systems, for Unit 1.

Plant performance for Browns Ferry Units 2 and 3 for the most recent quarter was in the Regulatory Response Column (Column 2) of the NRCs Reactor Oversight Process Action Matrix. As detailed in Final Significance Determination Of A White Finding, Notice Of Violation, And Assessment Follow-Up Letter (NRC Inspection Reports 05000259,260,296/2012013, (ML12226A647)) for Browns Ferry Nuclear Plant, dated Aug 13, 2012, Units 2 and 3 were determined to be in the Regulatory Response Column beginning in the second quarter 2012.

As stated in this assessment, additional regulatory oversight actions will be implemented at your facility. We will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Finding.

Since the last performance assessment, Browns Ferry Unit 3 received one additional action matrix input for the Unplanned Scrams Performance Indicator, which changed from Green to White in May of 2012. Reactor scrams on September 28, 2011, May 22, May 24, 2012, and May 29, 2012, caused the Performance Indicator to change from Green to White. The White performance indicator input does not change the current assessment of performance for Unit 3 because Unit 3 was already assessed to be in the Regulatory Response column of the NRCs Action Matrix based on an input from a different Reactor Oversight Process cornerstone. The NRC will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Unplanned Scrams Performance Indicator for Unit 3.

In its Annual Assessment Letter, dated March 4, 2011, (ML11063042), the NRC opened a Substantive Cross-Cutting Issue (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 staffs scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No.

05000259,260,296/2010005 ML110400431). 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

J. Shea 3 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 fourth 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 staffs 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 assessment period. This letter is the sixth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.

During this assessment, the NRC identified a cross-cutting theme in the Resources component of the Human Performance & Error Prevention cross-cutting area. Specifically, five Green inspection findings for the current 12-month assessment period, each with a documented cross-cutting aspect of Complete Documentation and Component Labeling (H.2.(c)) were identified.

The NRC determined that a SCCI did not exist because the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. This is based on TVAs proactive actions, which began in 2010, in addressing concerns associated with this Cross Cutting Aspect (CCA). Three of the five CCAs were assigned in the second quarter of 2012, which were the result of issues with the licensees procurement and operations procedure processes that would not have been reasonably identified by the previous efforts to address this CCA. Each of the CCAs involved separate Reactor Oversight Process cornerstones. The NRC has concluded that it is reasonable to allow some amount of time for you to incorporate the new issues into your corrective action program. The NRC will evaluate the effectiveness of your corrective actions during the next assessment cycle and will continue to monitor your staffs effort and progress in addressing this theme.

J. Shea 4 The enclosed inspection plan lists the inspections scheduled through December 30, 2013.

Routine inspections performed by resident inspectors are not included in the inspection plan. In addition to the baseline inspections, consistent with the Agencys actions related to Fukushima, the NRC will perform TI-187, Inspection of Near-Term Task Force Recommendation 2.3 Flooding Walkdowns and TI-188 Inspection of Near-Term Task Force Recommmendation 2.3 Seismic Walkdowns. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-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. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.

In addition to the baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: IP 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders; initial reactor operator licensing examinations; and TI 2515/182, Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks.

In accordance with 10 CFR 2.390 of the NRCs 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).

Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

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 (09/01/2012 - 12/31/2013) cc w/encl: (See page 5)

__ ML12248A296 _______________________ X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP RII:DRP RII:ORA RII:ORA SIGNATURE /RA By EGuthrie/ /RA/ /RA/ /RA/ /RA/

NAME CKontz EGuthrie RCroteau LWert VMcCree DATE 8/27/2012 8/27/2012 8/28/2012 8/31/2012 9/4/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO J. Shea 5 cc w/encl: James L. McNees, CHP K. J. Polson Director Site Vice President Office of Radiation Control Browns Ferry Nuclear Plant Alabama Dept. of Public Health Tennessee Valley Authority P. O. Box 303017 Electronic Mail Distribution Montgomery, AL 36130-3017 C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution James 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 Edward 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

J. Shea 6 Letter to Joseph W. Shea from Victor M. McCree dated September 4, 2012

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012006)

Distribution w/encl:

C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource INPO ROP Reports

Page 1 of 2 Browns Ferry 09/04/2012 08:15:05 Inspection / Activity Plan Report 22 09/01/2012 - 12/31/2013 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 95001 - WHITE VIOLATION FOR SSI TRAINING 1 1, 2, 3 10/08/2012 10/08/2012 IP 95001 Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area OL RQ - REQUAL INSPECTION 2 1, 2, 3 10/08/2012 10/12/2012 IP 7111111B Licensed Operator Requalification Program TI-188 - TI-188 P2 - NTTF 2.3 - SEISMIC WALKDOWNS 1 1, 2, 3 10/17/2012 10/19/2012 IP 2515/188 Inspection of Near-Term Task Force Recommendation 2.3 Seismic Walkdowns EB3 ISI - UNIT 1 INSERVICE INSPECTION 1 1 10/29/2012 11/02/2012 IP 7111108G Inservice Inspection Activities - BWR EB3 LR - UNIT 1 POST APPROVAL LR - PHASE 1 2 1 10/29/2012 11/02/2012 IP 71003 Post-Approval Site Inspection for License Renewal CDBI - COMPONENT DESIGN BASES INSPECTION 10 1, 2, 3 01/07/2013 01/11/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 01/28/2013 02/01/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 02/11/2013 02/15/2013 IP 7111121 Component Design Bases Inspection 1, 2, 3 02/25/2013 03/01/2013 IP 7111121 Component Design Bases Inspection ISI - UNIT 2 INSERVICE INSPECTION 1 2 03/25/2013 03/29/2013 IP 7111108G Inservice Inspection Activities - BWR LR71003 - UNIT 2 POST APPROVAL LR PHASE 1 2 2 04/01/2013 04/05/2013 IP 71003 Post-Approval Site Inspection for License Renewal PSB1-RP - RP OCCUPATIONAL BASELINE 2 1, 2, 3 04/01/2013 04/05/2013 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2, 3 04/01/2013 04/05/2013 IP 71124.02 Occupational ALARA Planning and Controls 1, 2, 3 04/01/2013 04/05/2013 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3 04/01/2013 04/05/2013 IP 71124.04 Occupational Dose Assessment 1, 2, 3 04/01/2013 04/05/2013 IP 71124.05 Radiation Monitoring Instrumentation 1, 2, 3 04/01/2013 04/05/2013 IP 71151 Performance Indicator Verification PSB1-RP - RP OCCUPATIONAL BASELINE WEEK 2 3 1, 2, 3 04/15/2013 04/19/2013 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2, 3 04/15/2013 04/19/2013 IP 71124.02 Occupational ALARA Planning and Controls 1, 2, 3 04/15/2013 04/19/2013 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1, 2, 3 04/15/2013 04/19/2013 IP 71124.04 Occupational Dose Assessment 1, 2, 3 04/15/2013 04/19/2013 IP 71124.05 Radiation Monitoring Instrumentation 1, 2, 3 04/15/2013 04/19/2013 IP 71151 Performance Indicator Verification This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures.

Page 2 of 2 Browns Ferry 09/04/2012 08:15:05 Inspection / Activity Plan Report 22 09/01/2012 - 12/31/2013 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site OL EXAM - INITIAL EXAM PREP 3 1 05/06/2013 05/10/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES LR71003 - UNIT 1 POST APPROVAL LR PHASE 2 5 1 05/06/2013 05/10/2013 IP 71003 Post-Approval Site Inspection for License Renewal 1 05/20/2013 05/24/2013 IP 71003 Post-Approval Site Inspection for License Renewal TI-182 - TI-182 BURIED PIPING/TANK - PHASE 1 1 1, 2, 3 05/13/2013 05/17/2013 IP 2515/182 Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping EP - EMERGENCY PREPAREDNESS EXERCISE 1 1, 2, 3 06/03/2013 06/07/2013 IP 7111401 Exercise Evaluation 1, 2, 3 06/03/2013 06/07/2013 IP 71151 Performance Indicator Verification OL EXAM - INITIAL EXAM - WEEK 1 3 1 06/03/2013 06/07/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES OL EXAM - INITIAL EXAM - WEEK 2 3 1 06/10/2013 06/14/2013 V23394 BROWNS FERRY/JUNE 2013 INITIAL EXAM AT POWER FACILITIES BF TFPI - BF - TRIENNIAL FIRE PROTECTION INSP 4 1, 2, 3 10/01/2013 10/03/2013 IP 7111105T Fire Protection [Triennial]

1, 2, 3 10/21/2013 10/25/2013 IP 7111105T Fire Protection [Triennial]

1, 2, 3 11/04/2013 11/08/2013 IP 7111105T Fire Protection [Triennial]

Comments:

This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures.

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