IR 05000259/2012011: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES ber 29, 2012 | ||
==SUBJECT:== | |||
BROWNS FERRY UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000259/2012011 | |||
==Dear Mr. Shea:== | ==Dear Mr. Shea:== | ||
On November 1, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at your Browns Ferry Nuclear Station, Unit 1. The enclosed report documents the inspection results, which were discussed on November 1, 2012, with members of your staff. | On November 1, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at your Browns Ferry Nuclear Station, Unit 1. The enclosed report documents the inspection results, which were discussed on November 1, 2012, with members of your staff. | ||
The inspection examined activities conducted under your license as they relate to safety and compliance with the | 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. | ||
Based on the results of this inspection, no findings were identified. | Based on the results of this inspection, no findings were identified. | ||
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Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety | Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-259 License Nos. DPR-33 | ||
Docket Nos. 50-259 License Nos. DPR-33 | |||
===Enclosure:=== | ===Enclosure:=== | ||
NRC Inspection Report 05000259/2012011 | NRC Inspection Report 05000259/2012011 w/Attachment: Supplemental Information | ||
REGION II== | |||
Docket Nos: 50-259 License Nos: DPR-33 Report No: 05000259/2012011 Licensee: Tennessee Valley Authority Facility: Browns Ferry, Unit 1 Location: Athens, AL 35611 Dates: October 29 - November 1, 2012 Inspectors: Cecil Fletcher, Senior Reactor Inspector Michael Coursey, Reactor Inspector Approved by: Steven J. Vias, Branch Chief Engineering Branch 3 Division of Reactor Safety Enclosure | |||
=SUMMARY OF FINDINGS= | |||
IR 05000259/2012011; October 29 - November 1, 2012; Browns Ferry Nuclear Station Unit 1; | |||
Post-Approval Site Inspection for License Renewal. | |||
The report covers an inspection conducted by regional inspectors in accordance with Nuclear Regulatory Commission (NRC) Manual Chapter 2516 and NRC Inspection Procedure 71003, | |||
Post-Approval Site Inspection for License Renewal. | Post-Approval Site Inspection for License Renewal. | ||
Based on the sample selected for review, the inspectors determined that commitments, license conditions, and regulatory requirements associated with the renewed facility operating license were either being met, or where commitment actions had not been completed, that the licensee had administrative controls in place to ensure completion before the period of extended operation. | Based on the sample selected for review, the inspectors determined that commitments, license conditions, and regulatory requirements associated with the renewed facility operating license were either being met, or where commitment actions had not been completed, that the licensee had administrative controls in place to ensure completion before the period of extended operation. | ||
The | The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006. | ||
===NRC-Identified and Self-Revealing Findings=== | ===NRC-Identified and Self-Revealing Findings=== | ||
None | None | ||
=== | ===Licensee-Identified Violations=== | ||
None | None | ||
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The inspectors reviewed a sample of license renewal activities scheduled for the Unit 1 fall 2012 refueling outage, which was the last outage prior to the period of extended operation (PEO). The inspectors selected this refueling outage because it would present the best opportunity to observe and review the majority of the one-time inspections associated with license renewal commitments. The objective of the inspection was to maximize observations of the actual implementation of license renewal activities before the beginning of the PEO (December 31, 2013), and verify that the licensee completed the necessary actions to: | The inspectors reviewed a sample of license renewal activities scheduled for the Unit 1 fall 2012 refueling outage, which was the last outage prior to the period of extended operation (PEO). The inspectors selected this refueling outage because it would present the best opportunity to observe and review the majority of the one-time inspections associated with license renewal commitments. The objective of the inspection was to maximize observations of the actual implementation of license renewal activities before the beginning of the PEO (December 31, 2013), and verify that the licensee completed the necessary actions to: | ||
: (a) comply with the conditions stipulated in the renewed facility operating license; | : (a) comply with the conditions stipulated in the renewed facility operating license; | ||
: (b) meet the license renewal commitments described in NUREG-1843, | : (b) meet the license renewal commitments described in NUREG-1843, Safety Evaluation Report (SER) Related to the License Renewal of the Browns Ferry Nuclear Plant (BFN), Units 1, 2,and 3; and | ||
: (c) meet the future activities, including Aging Management Programs (AMPs), described in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d). | : (c) meet the future activities, including Aging Management Programs (AMPs), described in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d). | ||
The inspectors performed a walk-down of the Unit 1 Drywell on the 561 | The inspectors performed a walk-down of the Unit 1 Drywell on the 561, 584, and 604 level to assess general conditions of civil engineering structures and components with regards to age related issues. | ||
The inspectors reviewed supporting documents; conducted interviews with licensee staff; observed in-process outage activities; and performed visual inspection of structures, systems, and components (SSCs) including those not accessible during power operation. The commitment items and AMPs selected for the inspection sample are summarized below based on their description in Appendix A of the License Renewal Application (LRA). The specific inspection activities conducted for each AMP are also described below. Specific documents reviewed are listed in the report attachment. | The inspectors reviewed supporting documents; conducted interviews with licensee staff; observed in-process outage activities; and performed visual inspection of structures, systems, and components (SSCs) including those not accessible during power operation. The commitment items and AMPs selected for the inspection sample are summarized below based on their description in Appendix A of the License Renewal Application (LRA). The specific inspection activities conducted for each AMP are also described below. Specific documents reviewed are listed in the report attachment. | ||
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===.2 License Renewal Commitment Changes=== | ===.2 License Renewal Commitment Changes=== | ||
The inspectors reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, | The inspectors reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, Guidelines for Managing NRC Commitment Changes, for the following commitment changes: | ||
changes: | |||
* NCO 040006070, Underground Piping and Tanks Integrity Program | * NCO 040006070, Underground Piping and Tanks Integrity Program | ||
* NCO 0400006083, Inspection of Overhead Heavy Load and Light Load Handling Systems Program | * NCO 0400006083, Inspection of Overhead Heavy Load and Light Load Handling Systems Program The inspectors verified that the licensee properly evaluated, reported, and approved, where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59. | ||
The inspectors verified that the licensee properly evaluated, reported, and approved, where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59. | |||
The inspectors did not identify any examples where commitment changes were not consistent with the guidance in NEI 99-04. The review of remaining license renewal commitment changes is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003, scheduled to be performed in 2013. | The inspectors did not identify any examples where commitment changes were not consistent with the guidance in NEI 99-04. The review of remaining license renewal commitment changes is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003, scheduled to be performed in 2013. | ||
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===.3 Newly-Identified SSCs=== | ===.3 Newly-Identified SSCs=== | ||
This inspection requirement will be | This inspection requirement will be completed during the Phase 2 implementation of inspection procedure 71003. | ||
===.4 Description of AMPs and Time-Limited Aging Analysis (TLAA) in the UFSAR=== | ===.4 Description of AMPs and Time-Limited Aging Analysis (TLAA) in the UFSAR=== | ||
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On November 1, 2012, the inspectors presented the inspection results to Mr. K. Polson, Site Vice President, and other members of the licensee staff. The inspectors confirmed that none of the potential report input discussed was considered proprietary. | On November 1, 2012, the inspectors presented the inspection results to Mr. K. Polson, Site Vice President, and other members of the licensee staff. The inspectors confirmed that none of the potential report input discussed was considered proprietary. | ||
ATTACHMENT: | ATTACHMENT: | ||
=SUPPLEMENTAL INFORMATION= | =SUPPLEMENTAL INFORMATION= | ||
Line 141: | Line 130: | ||
===Licensee Personnel=== | ===Licensee Personnel=== | ||
: | : | ||
: [[contact::T. Rogers]], License Renewal Engineer | : [[contact::T. Rogers]], License Renewal Engineer | ||
: [[contact::J. Davenport]], | : [[contact::J. Davenport]], Licensing Engineer | ||
: [[contact::J. Emens]], Licensing Manager | : [[contact::J. Emens]], Licensing Manager | ||
NRC: | NRC: | ||
: [[contact::D. Dumbacher]], Senior Resident Inspector | : [[contact::D. Dumbacher]], Senior Resident Inspector | ||
: [[contact::L. Pressley]], Resident Inspector | : [[contact::L. Pressley]], Resident Inspector | ||
: [[contact::C. Stancil]], Resident Inspector | : [[contact::C. Stancil]], Resident Inspector | ||
==LIST OF REPORT ITEMS== | ==LIST OF REPORT ITEMS== | ||
===Opened=== | ===Opened=== | ||
None | |||
None | |||
===Opened and Closed=== | ===Opened and Closed=== | ||
None | None | ||
===Closed=== | ===Closed=== | ||
None | |||
None | |||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} |
Latest revision as of 20:21, 11 November 2019
ML12335A228 | |
Person / Time | |
---|---|
Site: | Browns Ferry ![]() |
Issue date: | 11/29/2012 |
From: | Vias S NRC/RGN-II/DRS/EB3 |
To: | James Shea Tennessee Valley Authority |
References | |
IR-12-011 | |
Download: ML12335A228 (13) | |
Text
UNITED STATES ber 29, 2012
SUBJECT:
BROWNS FERRY UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000259/2012011
Dear Mr. Shea:
On November 1, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at your Browns Ferry Nuclear Station, Unit 1. The enclosed report documents the inspection results, which were discussed on November 1, 2012, with 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.
Based on the results of this inspection, no findings were identified.
In accordance with 10 CFR 2.390 of the NRC's "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 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).
Sincerely,
/RA/
Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-259 License Nos. DPR-33
Enclosure:
NRC Inspection Report 05000259/2012011 w/Attachment: Supplemental Information
REGION II==
Docket Nos: 50-259 License Nos: DPR-33 Report No: 05000259/2012011 Licensee: Tennessee Valley Authority Facility: Browns Ferry, Unit 1 Location: Athens, AL 35611 Dates: October 29 - November 1, 2012 Inspectors: Cecil Fletcher, Senior Reactor Inspector Michael Coursey, Reactor Inspector Approved by: Steven J. Vias, Branch Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000259/2012011; October 29 - November 1, 2012; Browns Ferry Nuclear Station Unit 1;
Post-Approval Site Inspection for License Renewal.
The report covers an inspection conducted by regional inspectors in accordance with Nuclear Regulatory Commission (NRC) Manual Chapter 2516 and NRC Inspection Procedure 71003,
Post-Approval Site Inspection for License Renewal.
Based on the sample selected for review, the inspectors determined that commitments, license conditions, and regulatory requirements associated with the renewed facility operating license were either being met, or where commitment actions had not been completed, that the licensee had administrative controls in place to ensure completion before the period of extended operation.
The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.
NRC-Identified and Self-Revealing Findings
None
Licensee-Identified Violations
None
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities: Post-Approval Site Inspection for License Renewal (Phase 1)
.1 Implementation of License Conditions and Commitments, including Aging Management
Programs
a. Inspection Scope
The inspectors reviewed a sample of license renewal activities scheduled for the Unit 1 fall 2012 refueling outage, which was the last outage prior to the period of extended operation (PEO). The inspectors selected this refueling outage because it would present the best opportunity to observe and review the majority of the one-time inspections associated with license renewal commitments. The objective of the inspection was to maximize observations of the actual implementation of license renewal activities before the beginning of the PEO (December 31, 2013), and verify that the licensee completed the necessary actions to:
- (a) comply with the conditions stipulated in the renewed facility operating license;
- (b) meet the license renewal commitments described in NUREG-1843, Safety Evaluation Report (SER) Related to the License Renewal of the Browns Ferry Nuclear Plant (BFN), Units 1, 2,and 3; and
- (c) meet the future activities, including Aging Management Programs (AMPs), described in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d).
The inspectors performed a walk-down of the Unit 1 Drywell on the 561, 584, and 604 level to assess general conditions of civil engineering structures and components with regards to age related issues.
The inspectors reviewed supporting documents; conducted interviews with licensee staff; observed in-process outage activities; and performed visual inspection of structures, systems, and components (SSCs) including those not accessible during power operation. The commitment items and AMPs selected for the inspection sample are summarized below based on their description in Appendix A of the License Renewal Application (LRA). The specific inspection activities conducted for each AMP are also described below. Specific documents reviewed are listed in the report attachment.
BFN One-Time Inspection Program: The One-Time Inspection Program at BFN is a new program described in the BFN UFSAR (section O.1.26) as a program which includes measures to verify that unacceptable degradation is not occurring: thereby validating the effectiveness of existing programs or confirming that there is no need to manage aging related degradation for the period of extended operation. The One-Time inspection Program is to be completed prior to entering the PEO. The elements of the One-Time Inspection Program include:
- (a) Determination of the sample size based on an assessment of materials of fabrication, environment, plausible aging effects, and operating experience.
- (b) Identification of the inspection locations in structures or components based on the aging effect.
- (c) Determination of the examination technique, including acceptance criteria that would be effective in detecting the age related effect for which the component is examined. Non-destructive techniques will generally be used.
- (d) Evaluation of the need for follow up examinations to monitor the progression of any aging degradation. When one-time inspections fail to meet the established acceptance criteria, the corrective action program will be used to schedule, trace, and trend the appropriate corrective actions and follow up inspections.
The inspectors observed/reviewed inspection activities, reviewed licensing basis documents, AMP administrative procedures, and implementing inspection and test procedures to verify that the program was developed as described in the LRA and corresponding SER. The inspectors also discussed the process used to select the inspection samples under this AMP and the criteria to be used for scope expansion with licensee personnel. The inspectors reviewed the examination reports listed below to verify that the implementation of the program was in accordance with the established procedures and consistent with the program attributes described in the licensing basis documents for the following activities:
- WO 112772844, License Renewal One-Time RW2-UT Inspections Sys 074 Piping
- Work Order (WO) 112763854, License Renewal One-Time RW3/TW3 Inspection of the heat exchanger plates for BFN-1-HEX-068-0001AA
- WO 113273618, Contingency, License Renewal One-Time RW2 inspection of piping between 1-TV-071-0528 & 1-SHV-071-0527
- WO 113680358, License Renewal One-Time RW2 Inspection BFN-1-CKV-077-0652 Bus Inspection Program: The Bus Inspection Program is described in section O.2.2 of the BFN UFSAR as a program that will provide reasonable assurance that the intended functions of isolated and non-segregated phase busses will be maintained consistent with the current licensing basis through the PEO. This program will manage non-segregated phase bus insulation exposed to adverse localized environments caused by heat in the presence of oxygen and loosening of fastening hardware associated with isolated and non-segregated phase bus due to cyclic loading resulting from thermal expansion and contraction of the bus. The program will also include inspection of the bus enclosure. This program will manage all portions of the isolated and non-segregated phase bus, within the scope of license renewal associated with the unit station service transformers, main transformers, and common station service transformers.
The inspectors performed a walkdown and observed the licensee perform inspections on the Main Transformer Bus in the switchyard and in the Auxiliary Building associated with WO 113221054, Inspection and Cleaning of the Switchyard Bus, Unit 1 between the Main 500 KV Transformers.
.2 License Renewal Commitment Changes
The inspectors reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, Guidelines for Managing NRC Commitment Changes, for the following commitment changes:
- NCO 040006070, Underground Piping and Tanks Integrity Program
- NCO 0400006083, Inspection of Overhead Heavy Load and Light Load Handling Systems Program The inspectors verified that the licensee properly evaluated, reported, and approved, where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59.
The inspectors did not identify any examples where commitment changes were not consistent with the guidance in NEI 99-04. The review of remaining license renewal commitment changes is scheduled to be completed during the Phase 2 implementation of inspection procedure 71003, scheduled to be performed in 2013.
.3 Newly-Identified SSCs
This inspection requirement will be completed during the Phase 2 implementation of inspection procedure 71003.
.4 Description of AMPs and Time-Limited Aging Analysis (TLAA) in the UFSAR
Supplement The review of the description of AMPs and TLAAs in the UFSAR supplement submitted pursuant 10 CFR 54.21(d) will be completed during the Phase 2 implementation of inspection procedure 71003.
b. Findings and Observations
No findings were identified. The inspectors determined that the licensee met the license renewal commitments, license conditions, and applicable regulatory requirements for the inspection samples selected for review. The inspectors determined that the overall implementation of AMP activities reviewed during the Unit 1 fall 2012 refueling outage was consistent with the license renewal commitments. The inspectors also determined that the licensee had administrative controls in place to ensure completion of pending actions scheduled both prior and during the PEO.
4OA6 Management Meetings
.1 Exit Meeting Summary
On November 1, 2012, the inspectors presented the inspection results to Mr. K. Polson, Site Vice President, and other members of the licensee staff. The inspectors confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- T. Rogers, License Renewal Engineer
- J. Davenport, Licensing Engineer
- J. Emens, Licensing Manager
NRC:
- D. Dumbacher, Senior Resident Inspector
- L. Pressley, Resident Inspector
- C. Stancil, Resident Inspector
LIST OF REPORT ITEMS
Opened
None
Opened and Closed
None
Closed
None