IR 05000259/2018440: Difference between revisions

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| number = ML18051A745
| number = ML18051A745
| issue date = 02/20/2018
| issue date = 02/20/2018
| title = Browns Ferry Nuclear Plant, Units 1, 2 & 3 - U.S. Nuclear Regulatory Commission Inspection Procedure 95001 Supplemental Inspection Report 05000259/2018440, 05000260/2018440 and 05000296/2018440 and Closed Regulatory Performance Meeting
| title = U.S. Nuclear Regulatory Commission Inspection Procedure 95001 Supplemental Inspection Report 05000259/2018440, 05000260/2018440 and 05000296/2018440 and Closed Regulatory Performance Meeting
| author name = Desai B
| author name = Desai B
| author affiliation = NRC/RGN-II/DRS/EB
| author affiliation = NRC/RGN-II/DRS/EB
| 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 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ary 20, 2018
[[Issue date::February 20, 2018]]


Mr. Joseph Vice President, Nuclear Regulatory Affairs and Support Services Licensing Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37402-2801
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION PROCEDURE 95001 SUPPLEMENTAL INSPECTION REPORT 05000259/2018440, 05000260/2018440 AND 05000296/2018440 AND CLOSED REGULATORY PERFORMANCE MEETING


SUBJECT: BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION PROCEDURE 95001 SUPPLEMENTAL INSPECTION REPORT 05000259/2018440, 05000260/2018440 AND 05000296/2018440 AND CLOSED REGULATORY PERFORMANCE MEETING
==Dear Mr. Shea:==
On February 02, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, at your Browns Ferry Nuclear Plant, Units 1, 2, and 3, and discussed the results of this inspection with Mr. S. Bono and other members of your staff. The results of this inspection are documented in the enclosed report.


==Dear Mr. Shea:==
In accordance with the NRC Reactor Oversight Process Action Matrix, this supplemental inspection was performed to follow-up on a greater than green finding with low to moderate safety significance which was issued in the second quarter of 2017. This issue was previously documented and assessed in NRC Inspection Report 05000259, 260, 296/2017406.
On February 02, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," at your Browns Ferry Nuclear Plant, Units 1, 2, and 3, and discussed the results of this inspection with Mr. S. Bono and other members of your staff. The results of this inspection are documented in the enclosed report. In accordance with the NRC Reactor Oversight Process Action Matrix, this supplemental inspection was performed to follow-up on a greater than green finding with low to moderate safety significance which was issued in the second quarter of 2017. This issue was previously documented and assessed in NRC Inspection Report 05000259, 260, 296/2017406. The NRC was informed on November 17, 2017 of your staff's readiness for this inspection.
 
The NRC was informed on November 17, 2017 of your staffs readiness for this inspection.


The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the risk-significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes. Based on the results of this inspection, the NRC has concluded that you have adequately completed a root cause analysis of the issue, and have identified appropriate corrective actions to prevent recurrence of the issue. No findings were identified concerning the root cause evaluation and corrective actions. The NRC has determined that inspection objectives stated above have been met. As a result, the violation is considered closed. Therefore in accordance with IMC 0305, "Operating Reactor Assessment Program," the performance issue shall not be considered in the Action Matrix after the end of the first quarter 2018.
The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the risk-significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.


This letter will be made available for public inspection and copying at https://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding." However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publicly available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response "Security-Related Information-Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).
Based on the results of this inspection, the NRC has concluded that you have adequately completed a root cause analysis of the issue, and have identified appropriate corrective actions to prevent recurrence of the issue. No findings were identified concerning the root cause evaluation and corrective actions. The NRC has determined that inspection objectives stated above have been met. As a result, the violation is considered closed. Therefore in accordance with IMC 0305, Operating Reactor Assessment Program, the performance issue shall not be considered in the Action Matrix after the end of the first quarter 2018.


Sincerely,/RA/ Binoy Desai, Chief Plant Support Branch Division of Reactor Safety
This letter will be made available for public inspection and copying at https://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.


Docket Nos: 50-259, 50-260 and 50-296 License Nos: DPR-33, DPR-52 and DPR-68
However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publicly available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).


===Enclosure:===
Sincerely,
NRC IR 05000259/2018440, 260/2018440 and 296/2018440  
/RA/
Binoy Desai, Chief Plant Support Branch Division of Reactor Safety Docket Nos: 50-259, 50-260 and 50-296 License Nos: DPR-33, DPR-52 and DPR-68 Enclosure:
NRC IR 05000259/2018440, 260/2018440 and 296/2018440 w/Attachment: Supplemental Information (OUO)
cc: (See page 3) cc:
Mr. F. E. Marcussen Director, Nuclear Security Tennessee Valley Authority 1101 Market Street, LP 1A Chattanooga, TN 37402-2801 Mr. R. Dawson, Jr.


===w/Attachment:===
Senior Manager, Site Security Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 PAB 2G-BFN Athens, AL 35609 Mr. D. Lang Hughes General Manager, Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 NAB 1A-BFN Decatur, AL 35609 Mr. Glen E. Pry Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 POB 2C-BFN Decatur, AL 35609 Mr. James A. Kent Director, Plant Support Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 NAB 1A-BFN Decatur, AL 35609 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS/PSB RII:DRS/PSB RII:DRS/PSB RII:DRP/BR6 RII:DRS/PSB SIGNATURE JPT JDG4 BBD ADM2 BBD NAME  J. Tornow D. Golden B. Desai A. Masters B. Desai DATE  2/ 20 /2018 2/ 14 /2018 2/14 /2018 2/ 20 /2018 2/ 20 /2018 E-MAIL COPY YES NO YES NO YES NO YES NO YES NO
Supplemental Information (OUO) cc: (See page 3)
}}
}}

Latest revision as of 19:57, 21 October 2019

U.S. Nuclear Regulatory Commission Inspection Procedure 95001 Supplemental Inspection Report 05000259/2018440, 05000260/2018440 and 05000296/2018440 and Closed Regulatory Performance Meeting
ML18051A745
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/20/2018
From: Binoy Desai
NRC/RGN-II/DRS/EB
To: James Shea
Tennessee Valley Authority
References
IR 2018440
Download: ML18051A745 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ary 20, 2018

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION PROCEDURE 95001 SUPPLEMENTAL INSPECTION REPORT 05000259/2018440, 05000260/2018440 AND 05000296/2018440 AND CLOSED REGULATORY PERFORMANCE MEETING

Dear Mr. Shea:

On February 02, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, at your Browns Ferry Nuclear Plant, Units 1, 2, and 3, and discussed the results of this inspection with Mr. S. Bono and other members of your staff. The results of this inspection are documented in the enclosed report.

In accordance with the NRC Reactor Oversight Process Action Matrix, this supplemental inspection was performed to follow-up on a greater than green finding with low to moderate safety significance which was issued in the second quarter of 2017. This issue was previously documented and assessed in NRC Inspection Report 05000259, 260, 296/2017406.

The NRC was informed on November 17, 2017 of your staffs readiness for this inspection.

The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the risk-significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.

Based on the results of this inspection, the NRC has concluded that you have adequately completed a root cause analysis of the issue, and have identified appropriate corrective actions to prevent recurrence of the issue. No findings were identified concerning the root cause evaluation and corrective actions. The NRC has determined that inspection objectives stated above have been met. As a result, the violation is considered closed. Therefore in accordance with IMC 0305, Operating Reactor Assessment Program, the performance issue shall not be considered in the Action Matrix after the end of the first quarter 2018.

This letter will be made available for public inspection and copying at https://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publicly available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).

Sincerely,

/RA/

Binoy Desai, Chief Plant Support Branch Division of Reactor Safety Docket Nos: 50-259, 50-260 and 50-296 License Nos: DPR-33, DPR-52 and DPR-68 Enclosure:

NRC IR 05000259/2018440, 260/2018440 and 296/2018440 w/Attachment: Supplemental Information (OUO)

cc: (See page 3) cc:

Mr. F. E. Marcussen Director, Nuclear Security Tennessee Valley Authority 1101 Market Street, LP 1A Chattanooga, TN 37402-2801 Mr. R. Dawson, Jr.

Senior Manager, Site Security Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 PAB 2G-BFN Athens, AL 35609 Mr. D. Lang Hughes General Manager, Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 NAB 1A-BFN Decatur, AL 35609 Mr. Glen E. Pry Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 POB 2C-BFN Decatur, AL 35609 Mr. James A. Kent Director, Plant Support Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 NAB 1A-BFN Decatur, AL 35609 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS/PSB RII:DRS/PSB RII:DRS/PSB RII:DRP/BR6 RII:DRS/PSB SIGNATURE JPT JDG4 BBD ADM2 BBD NAME J. Tornow D. Golden B. Desai A. Masters B. Desai DATE 2/ 20 /2018 2/ 14 /2018 2/14 /2018 2/ 20 /2018 2/ 20 /2018 E-MAIL COPY YES NO YES NO YES NO YES NO YES NO

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