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{{#Wiki_filter: | {{#Wiki_filter:July 30, 2010 | ||
==SUBJECT:== | ==SUBJECT:== | ||
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In addition to the routine Reactor Oversight Process (ROP) baseline inspections for all three units, the inspectors have continued to apply the Augmented Inspection Plan (AIP) on Unit 1 as delineated in NRC letters dated May 16, 2007, December 6, 2007, and May 21, 2008. The Unit 1 AIP was conducted to compensate for the lack of valid data for certain Performance Indicators (PI). These additional augmented baseline inspections were only considered to be an interim substitute for the invalid Unit 1 PIs until complete and accurate PI data was developed and declared valid. However, following the second quarter of 2010, all Unit 1 PIs will now have sufficient past data and operating experience to be considered valid, and thereby end the need for any further augmented inspections. Consequently, beginning with the third quarter of 2010, the AIP is considered closed and all Unit 1 PIs, including the Mitigating Systems Performance Index PIs, will be reported, assessed, and inspected, in accordance with Inspection Manual Chapter (0305), Operating Reactor Assessment Program, and IMC 2515, Light Water Reactor Inspection Program - Operations Phase. | In addition to the routine Reactor Oversight Process (ROP) baseline inspections for all three units, the inspectors have continued to apply the Augmented Inspection Plan (AIP) on Unit 1 as delineated in NRC letters dated May 16, 2007, December 6, 2007, and May 21, 2008. The Unit 1 AIP was conducted to compensate for the lack of valid data for certain Performance Indicators (PI). These additional augmented baseline inspections were only considered to be an interim substitute for the invalid Unit 1 PIs until complete and accurate PI data was developed and declared valid. However, following the second quarter of 2010, all Unit 1 PIs will now have sufficient past data and operating experience to be considered valid, and thereby end the need for any further augmented inspections. Consequently, beginning with the third quarter of 2010, the AIP is considered closed and all Unit 1 PIs, including the Mitigating Systems Performance Index PIs, will be reported, assessed, and inspected, in accordance with Inspection Manual Chapter (0305), Operating Reactor Assessment Program, and IMC 2515, Light Water Reactor Inspection Program - Operations Phase. | ||
TVA | TVA | ||
Based on the results of this inspection, the NRC has determined that two Severity Level IV violations of NRC requirements occurred. The NRC has also identified two additional findings that were evaluated under the risk significance determination process as having a very low safety significance (Green). The NRC has determined that violations of NRC requirements are associated with these findings. Additionally, a licensee-identified violation, which was determined to be of very low safety significance, is listed in this report. However, because of the very low safety significance and categorization as Severity Level IV, and because they were entered into your corrective action program, the NRC is treating these as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you wish to contest these non-cited violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: | |||
Document Control Desk, Washington DC 20555-001; with copies to the Regional Administrator Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Browns Ferry Nuclear Plant. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Browns Ferry Nuclear Plant. | Document Control Desk, Washington DC 20555-001; with copies to the Regional Administrator Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Browns Ferry Nuclear Plant. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Browns Ferry Nuclear Plant. | ||
| Line 38: | Line 40: | ||
Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Eugene F. Guthrie, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-259, 50-260, 50-296, 72-052 License Nos.: DPR-33, DPR-52, DPR-68 Enclosure: Inspection Report 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002 w/Attachment: Supplemental Information cc w/encl. (See page 3) | |||
Eugene F. Guthrie, Chief | |||
Reactor Projects Branch 6 | |||
Division of Reactor Projects | |||
Docket Nos.: 50-259, 50-260, 50-296, 72-052 License Nos.: DPR-33, DPR-52, DPR-68 | |||
Enclosure: Inspection Report 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002 | |||
w/Attachment: Supplemental Information | |||
cc w/encl. (See page 3) | |||
_________________________ | _________________________ | ||
OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:DRP RII:DRP SIGNATURE Via email Via email Via emai Via telecon CRK /RA/ EFG /RA/ | OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:DRP RII:DRP SIGNATURE Via email Via email Via emai Via telecon CRK /RA/ | ||
NAME | EFG /RA/ | ||
NAME CStancil KKorth TRoss HGepford CKontz EGuthrie DATE 07/30/2010 07/30/2010 07/30/2010 07/30/2010 07/30/2010 07/30/2010 E-MAIL COPY? | |||
YES NO YES NO YES NO YES NO YES NO YES NO | |||
TVA | TVA | ||
cc w/encl: | |||
Mr. K. J. Polson Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution | |||
Table of Contents | Mr. J. J. Randich General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution | ||
Mr. F. R. Godwin Manager, Site Licensing & Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution | |||
Mr. E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902 | |||
James L. McNees, CHP Director, Office of Radiation Control Alabama State Dept. of Public Health P.O. Box 303017 Montgomery, AL 36130-3017 | |||
Chairman, Limestone County Commission 310 West Washington Street Athens, AL 35611 | |||
TVA | |||
Letter to R. from Eugene F. Guthrie dated July 30, 2010 | |||
SUBJECT: | |||
BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002 | |||
Distribution w/encl: | |||
C. Evans, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource | |||
Enclosure Table of Contents | |||
=SUMMARY OF FINDINGS= | =SUMMARY OF FINDINGS= | ||
| Line 58: | Line 94: | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
{{a|1R01}} | {{a|1R01}} | ||
==1R01 Adverse Weather Protection 1R04 Equipment Alignment 1R05 Fire Protection== | |||
==1R05 Fire Protection | {{a|1R07}} | ||
{{a| | |||
==1R07 Heat Sink Performance 1R11 Licensed Operator Requalification 1R12 Maintenance Effectiveness== | |||
{{a|1R13}} | {{a|1R13}} | ||
==1R13 Maintenance Risk Assessments and Emergent Work Control 1R15 Operability Evaluations== | |||
{{a|1R18}} | {{a|1R18}} | ||
==1R18 Plant Modifications 1R19 Post Maintenance Testing 1R20 Refueling and Other Outage Activities== | |||
==1R20 Refueling and Other Outage Activities | {{a|1R22}} | ||
1R22 Surveillance Testing | ==1R22 Surveillance Testing EMERGENCY PREPAREDNESS 1EP2 Alert Notification System Evaluation== | ||
1EP3 Emergency Preparedness Organization Staffing and Augmentation 1EP4 Emergency Action Level and Emergency Plan Changes 1EP5 Correction of Emergency Preparedness Weaknesses | |||
==RADIATION SAFETY== | ==RADIATION SAFETY== | ||
{{a|2RS5}} | {{a|2RS5}} | ||
==2RS5 Radiation Monitoring Instrumentation== | ==2RS5 Radiation Monitoring Instrumentation== | ||
{{a|2RS6}} | |||
==2RS6 Radioactive Gaseous and Liquid Effluent Treatment== | ==2RS6 Radioactive Gaseous and Liquid Effluent Treatment== | ||
{{a|2RS7}} | |||
==2RS7 Radiological Environmental Monitoring Program== | ==2RS7 Radiological Environmental Monitoring Program== | ||
{{a|2RS8}} | |||
==2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling,== | ==2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling,== | ||
Storage and Transportation | |||
==OTHER ACTIVITIES== | ==OTHER ACTIVITIES== | ||
{{a|4OA1}} | {{a|4OA1}} | ||
==4OA1 Performance Indicator (PI) Verification== | ==4OA1 Performance Indicator (PI) Verification== | ||
{{a|4OA2}} | |||
==4OA2 Identification and Resolution of Problems== | ==4OA2 Identification and Resolution of Problems== | ||
{{a|4OA3}} | |||
==4OA3 Event Follow-up== | ==4OA3 Event Follow-up== | ||
{{a|4OA5}} | |||
==4OA5 Other Activities== | ==4OA5 Other Activities== | ||
{{a|4OA6}} | |||
==4OA6 Meetings, Including Exit== | ==4OA6 Meetings, Including Exit== | ||
{{a|4OA7}} | |||
==4OA7 Licensee-identified Violations== | ==4OA7 Licensee-identified Violations== | ||
ATTACHMENT: | |||
=SUPPLEMENTAL INFORMATION= | =SUPPLEMENTAL INFORMATION= | ||
==KEY POINTS OF CONTACT== | ==KEY POINTS OF CONTACT== | ||
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ||
==LIST OF DOCUMENTS REVIEWED== | |||
}} | }} | ||
Latest revision as of 03:42, 14 January 2025
| ML102110467 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/30/2010 |
| From: | Eugene Guthrie Reactor Projects Region 2 Branch 6 |
| To: | Krich R Tennessee Valley Authority |
| References | |
| IR-10-003 | |
| Download: ML102110467 (66) | |
Text
July 30, 2010
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002
Dear Mr. Krich:
On June 30, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Browns Ferry Nuclear Plant, Units 1, 2, and 3. The enclosed inspection report documents the inspection results which were discussed, on July 9, 2010, with Mr. Keith Polson and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
In addition to the routine Reactor Oversight Process (ROP) baseline inspections for all three units, the inspectors have continued to apply the Augmented Inspection Plan (AIP) on Unit 1 as delineated in NRC letters dated May 16, 2007, December 6, 2007, and May 21, 2008. The Unit 1 AIP was conducted to compensate for the lack of valid data for certain Performance Indicators (PI). These additional augmented baseline inspections were only considered to be an interim substitute for the invalid Unit 1 PIs until complete and accurate PI data was developed and declared valid. However, following the second quarter of 2010, all Unit 1 PIs will now have sufficient past data and operating experience to be considered valid, and thereby end the need for any further augmented inspections. Consequently, beginning with the third quarter of 2010, the AIP is considered closed and all Unit 1 PIs, including the Mitigating Systems Performance Index PIs, will be reported, assessed, and inspected, in accordance with Inspection Manual Chapter (0305), Operating Reactor Assessment Program, and IMC 2515, Light Water Reactor Inspection Program - Operations Phase.
Based on the results of this inspection, the NRC has determined that two Severity Level IV violations of NRC requirements occurred. The NRC has also identified two additional findings that were evaluated under the risk significance determination process as having a very low safety significance (Green). The NRC has determined that violations of NRC requirements are associated with these findings. Additionally, a licensee-identified violation, which was determined to be of very low safety significance, is listed in this report. However, because of the very low safety significance and categorization as Severity Level IV, and because they were entered into your corrective action program, the NRC is treating these as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you wish to contest these non-cited violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.:
Document Control Desk, Washington DC 20555-001; with copies to the Regional Administrator Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Browns Ferry Nuclear Plant. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Browns Ferry Nuclear Plant.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs 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).
Sincerely,
/RA/
Eugene F. Guthrie, Chief
Reactor Projects Branch 6
Division of Reactor Projects
Docket Nos.: 50-259, 50-260, 50-296,72-052 License Nos.: DPR-33, DPR-52, DPR-68
Enclosure: Inspection Report 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002
w/Attachment: Supplemental Information
cc w/encl. (See page 3)
_________________________
OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:DRP RII:DRP SIGNATURE Via email Via email Via emai Via telecon CRK /RA/
EFG /RA/
NAME CStancil KKorth TRoss HGepford CKontz EGuthrie DATE 07/30/2010 07/30/2010 07/30/2010 07/30/2010 07/30/2010 07/30/2010 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO
cc w/encl:
Mr. K. J. Polson Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
Mr. J. J. Randich General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
Mr. F. R. Godwin Manager, Site Licensing & Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
Mr. E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902
James L. McNees, CHP Director, Office of Radiation Control Alabama State Dept. of Public Health P.O. Box 303017 Montgomery, AL 36130-3017
Chairman, Limestone County Commission 310 West Washington Street Athens, AL 35611
Letter to R. from Eugene F. Guthrie dated July 30, 2010
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2010003, 05000260/2010003, 05000296/2010003, 05000259/2010501, 05000260/2010501, 05000296/2010501, AND 07200052/2010002
Distribution w/encl:
C. Evans, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
Enclosure Table of Contents
SUMMARY OF FINDINGS
REPORT DETAILS
REACTOR SAFETY
1R01 Adverse Weather Protection 1R04 Equipment Alignment 1R05 Fire Protection
1R07 Heat Sink Performance 1R11 Licensed Operator Requalification 1R12 Maintenance Effectiveness
1R13 Maintenance Risk Assessments and Emergent Work Control 1R15 Operability Evaluations
1R18 Plant Modifications 1R19 Post Maintenance Testing 1R20 Refueling and Other Outage Activities
1R22 Surveillance Testing EMERGENCY PREPAREDNESS 1EP2 Alert Notification System Evaluation
1EP3 Emergency Preparedness Organization Staffing and Augmentation 1EP4 Emergency Action Level and Emergency Plan Changes 1EP5 Correction of Emergency Preparedness Weaknesses
RADIATION SAFETY
2RS5 Radiation Monitoring Instrumentation
2RS6 Radioactive Gaseous and Liquid Effluent Treatment
2RS7 Radiological Environmental Monitoring Program
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling,
Storage and Transportation
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
4OA2 Identification and Resolution of Problems
4OA3 Event Follow-up
4OA5 Other Activities
4OA6 Meetings, Including Exit
4OA7 Licensee-identified Violations
ATTACHMENT: