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| | issue date = 02/20/2019 | | | issue date = 02/20/2019 |
| | title = American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report Cycle 12 Operation | | | title = American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report Cycle 12 Operation |
| | author name = Hughes D L | | | author name = Hughes D |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Tennessee Valley Authority , Post Office Box 2000 , Decatur , Alabama 35609-2000 February 20 , 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant , Unit 1 Renewed Facility Operating License No. DPR-33 NRG Docket No. 50-259 10 CFR 50.55 | | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 20, 2019 10 CFR 50.55 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRG Docket No. 50-259 |
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| ==Subject:== | | ==Subject:== |
| American Society of Mechanical Engineers Section XI, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs -Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME), Section XI, Owner's Activity Report for BFN , Unit 1, Cycle 12 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission , Section XI , Division 1. The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary , up to and including the BFN , Unit 1, Cycle 12 refueling outage , during the first inspection period of the Third 1 O Year Inspection Interval. | | American Society of Mechanical Engineers Section XI, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs - Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME), Section XI, Owner's Activity Report for BFN, Unit 1, Cycle 12 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission, Section XI , Division 1. |
| The applicable provisions of the ASME Code Case N-532-5 require that this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 1, Cycle 12 refueling outage ended on November 22, 2018. Accordingly , this submittal is due by February 20 , 2019. | | The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary, up to and including the BFN, Unit 1, Cycle 12 refueling outage, during the first inspection period of the Third 1O Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-5 require that this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 1, Cycle 12 refueling outage ended on November 22, 2018. Accordingly, this submittal is due by February 20, 2019. |
| U.S. Nuclear Regulatory Commission Page 2 February 20 , 2019 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal , please contact M. W. Oliver , Acting Nuclear Site Licensing Manager , at (256) 729-7874. D. L. Hughes Site V i ce President Enclos u re: American Society of Mechanical Engineers , Section XI , Third 10 Year Inspection Interval , lnservice Inspection, System Pressure Test, Containment Inspection , and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant , Unit 1 , Cycle 12 Operation cc (Enclosure) | | |
| : NRG Regional Administrator | | U.S. Nuclear Regulatory Commission Page 2 February 20, 2019 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact M. W. Oliver, Acting Nuclear Site Licensing Manager, at (256) 729-7874. |
| -Region II NRG Senior Resident Inspector | | R~~ |
| -Browns Ferry Nuclear Plant NRG Project Manager -Browns Ferry Nuclear Plant Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation See Enclosed FORM OAR-1 OWNER'S ACTIVITY REPORT Report Plant Browns Ferry Nuclear Plant P.O. Box 2000 Decatur AL 35609 Unit No.--~~--Commercial service date August 1 197 4 Refueling Outage no. ---~U~1~R~1~2~----(if applicable) Current Inspection Interval Third Ten Year Inspection Interval (1st , 2nd , 3rd, ot he r) Current Inspection Period (1 st, 2nd , 3rd) 2007 Edition , 2008 Addenda (ISi) Edition and Addenda of Section XI applicable to the inspection plans ~2=0~13~E~d~it~io~n__,,{~C~IS~IJ._) | | D. L. Hughes Site Vice President |
| -----------------~ | | |
| 0-TPP-ENG-376 , Revision 0000 , 09/06/2018 0-Tl-364 , Revision 0022 , 09/19/2018 Date and Revision of inspection plan 0-Sl-4.6.G Revision 0003 09/14/2018 Edition and Addenda of Section XI applicable to repairs/replacement activities , if different than the inspection plans _,_N.,,./Code Cases used for inspection and evaluation
| | ==Enclosure:== |
| : N-508-4 N-532-5 N-613-2 N-648-1 N-702 N-716-1 and N-751 (if applicable , including cases modified by Case N-532 and later rev i sions) CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code , Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of conform to the requirements of Section XI. (refuel in g outage number) Signed ; * /J 4----es;t> ~rs O esignee. Titl e CERTIFICATE OF INSERVICE INSPECTION I , the undersigned , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in this Owne r's Activity Report and state that , to the best of my knowledge and belief , the Owner has performed all activities represented by this report in accordance with the requirements of Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty , expressed or implied , concerning the repair/r eplacement activities and evaluation described in this report. Furthermore , neither the Inspector nor his employer shall be liable in an y manner for any pers~Aju roperty age or a loss of any kind arising from or connected with this Inspection. Date __ 2--</,_,_(-=--+--1/~f '5 ___ _
| | American Society of Mechanical Engineers, Section XI , Third 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation cc (Enclosure): NRG Regional Administrator - Region II NRG Senior Resident Inspector - Browns Ferry Nuclear Plant NRG Project Manager - Browns Ferry Nuclear Plant |
| FORM OAR-1 O W NER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 -----------------
| | |
| --------------PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. 1 2 ----Current inspection interval 3rd -----Current inspection period 1st -------TABLE 1 ITEMS WITH FLA W S OR RELEV A NT CONDITIONS THAT REQUIRE EVALUATIO N S FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Variable spring as-found (Acceptance by Evaluation) F-A , Item F1 .20C setting found out of range. The condition was evaluated i n accordance Acceptance range is 2078 with IWF-3122.3. S i nce the spr i ng support was lbs , +/-54 (2024 lbs to determ i ned to still be ab l e to perfo r m i ts des i gn 2132 lbs). As-found function , corrective measures were perfo r med setting 2350 lbs. [NOi to restore the support to its orig i na l des i gn U1R12-001) condition per IWF-3122.3 (b). WO 11 9973691 reset the load setting of the spri n g to the des i g n range specifications. Therefore , no add i t i ona l or preservice exams are app li cab l e. The spr in g support was then reinspec t ed to ve rif y th e sett i ngs. E-A , Item E1 .11 Gouge in Drywell liner. EVALUATED ACCEPTABLE
| | Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation See Enclosed |
| [NOi U1 R12-002] (No Corrective Measures Requ i red.) An indication cons i sting of mechanical damage 1/32" in depth , 3/8" in w i dth , and 7/16" i n l engt h was identified on the stee l conta i nment vesse l (Drywell) liner. The remaining wall th i ckness was 0.73" in the area of mechan i ca l damage. The wall thickness was below the accepta n ce cr i teria without C i v i l Design Eng i nee ri ng evaluation of 0.75". C i v i l Eng i nee r ing determined that the rema i n i ng th i ckness o f 0. 73" i s greater than the allowed 10% reduct i o n of wall thickness (0.675"), thus it i s acceptable for continued operation. Per IWE-3122.3 (b) the area will be reexamined in acco r dance w i th IWE-2420.
| | |
| FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 -----------------------------
| | FORM OAR-1 OWNER'S ACTIVITY REPORT Report N u m b e r ~ B ~ F ~ N ~ U ~ 1 ~ R ~ 1 ~ 2 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - |
| PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. 12 ----Current inspection interval 3rd -----Current inspection period 1st ------TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of I Date Repair/Replacement Class Work Completed Plan Number I NONE NONE FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 -----------------------------------
| | Plant Browns Ferry Nuclear Plant P.O. Box 2000 Decatur AL 35609 Unit No . - - ~ ~ - - Commercial service date August 1 1974 Refueling Outage no. ---~U~1~R~1~2~---- |
| PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. 12 -----Current inspection interval 3rd ------Current inspection period 1st --------Summary of IWE Indications for U1R12 The summary table below is provided in accordance with the requirements of 10 CFR 50. 55a(b )(2)(i x)(A). Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)
| | (if applicable) |
| E-A , Item E1 .30 Moisture Seal Areas of EVALUATED ACCEPTABLE None None Barrier Separation. None of the areas penetrated the full MSB-1-1 [NOi U1R12-depth of the seal , seal adhesion was 003] good in all locations , and there was no seal failure. The affected portions of the seal identified for repair were excavated and drywell liner below the seal was VT-1 examined. No evidence of moisture intrusion or damage to the liner indicative of moisture intrusion was observed demonstrating no seal failure occurred. The MSB was then re-poured in these areas and re-examined.}} | | Current Inspection Interval Third Ten Year Inspection Interval (1st, 2nd , 3rd, other) |
| | Current Inspection Period ~F~ir=st~P~e~r~io~d~--------------,---,----,-,-------------------- |
| | (1st, 2nd , 3rd) 2007 Edition, 2008 Addenda (ISi) |
| | Edition and Addenda of Section XI applicable to the inspection plans ~2=0~13~E~d~it~io~n__,,{~C~IS~IJ._)- - - - - - - - - - - - - - - - - ~ |
| | 0-TPP-ENG-376, Revision 0000, 09/06/2018 0-Tl-364, Revision 0022, 09/19/2018 Date and Revision of inspection plan 0-Sl-4.6.G Revision 0003 09/14/2018 Edition and Addenda of Section XI applicable to repairs/replacement activities, if different than the inspection plans _,_N.,,./A'-'---- |
| | Code Cases used for inspection and evaluation: N-508-4 N-532-5 N-613-2 N-648-1 N-702 N-716-1 and N-751 (if applicable , including cases modified by Case N-532 and later revisions) |
| | CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI ; and (c) the repair/replacement activities and evaluations supporting the completion of --~U~1~R~1~2~--- |
| | conform to the requirements of Section XI. (refueling outage number) |
| | Signed ; * /J4---- |
| | es;t> ~ r s Oesignee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in this Owne r's Activity Report and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI. |
| | By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied , concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pers~Aju roperty age or a loss of any kind arising from or connected with this Inspection . |
| | Date _ _ 2--</,_,_(-=--+-- |
| | 1/~ f '5____ |
| | |
| | FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. - 12- - - |
| | Current inspection interval 3rd Current inspection period -1st TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Variable spring as-found (Acceptance by Evaluation) |
| | F-A, Item F1 .20C setting found out of range . The condition was evaluated in accordance Acceptance range is 2078 with IWF-3122.3. Since the spring support was lbs, +/- 54 (2024 lbs to determined to still be able to perform its design 2132 lbs). As-found function , corrective measures were performed setting 2350 lbs. [NOi to restore the support to its orig ina l design U1R12-001) condition per IWF-3122.3 (b). WO 11 9973691 reset the load setting of the spring to the design range specifications. Therefore, no add itional or preservice exams are applicable. The spring support was then reinspected to ve rify th e settings. |
| | E-A, Item E1 .11 Gouge in Drywell liner. EVALUATED ACCEPTABLE |
| | [NOi U1 R12-002] (No Corrective Measures Requ ired .) |
| | An indication cons isting of mechanical damage 1/32" in depth , 3/8" in width , and 7/16" in length was identified on the steel conta inment vessel (Drywell) liner. The remaining wall th ickness was 0.73" in the area of mechanica l damage. |
| | The wall thickness was below the acceptance criteria without Civil Design Eng ineeri ng evaluation of 0.75". Civil Engineering determined that the remaining th ickness of 0.73" is greater than the allowed 10% reduction of wall thickness (0.675"), thus it is acceptable for continued operation . Per IWE-3122.3 (b) the area will be reexamined in accordance with IWE-2420. |
| | |
| | FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. - - |
| | Current inspection interval 3rd Current inspection period -1st TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Description of Date Repair/Replacement Item Description Class Work I Completed Plan Number I |
| | NONE NONE |
| | |
| | FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. -12 ---- |
| | Current inspection interval 3rd |
| | ------ Current inspection period 1st Summary of IWE Indications for U1R12 The summary table below is provided in accordance with the requirements of 10 CFR 50.55a(b )(2)(ix)(A) . |
| | Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation) |
| | E-A, Item E1 .30 Moisture Seal Areas of EVALUATED ACCEPTABLE None None Barrier Separation . None of the areas penetrated the full MSB-1-1 [NOi U1R12- depth of the seal , seal adhesion was 003] good in all locations, and there was no seal failure . The affected portions of the seal identified for repair were excavated and drywell liner below the seal was VT-1 examined . No evidence of moisture intrusion or damage to the liner indicative of moisture intrusion was observed demonstrating no seal failure occurred . The MSB was then re-poured in these areas and re-examined .}} |
|
|---|
Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24176A1132024-06-23023 June 2024
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2024-06-23
[Table view]
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05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024
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05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024
Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure
ML24299A2632024-10-25025 October 2024
Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075
ML24289A1232024-10-24024 October 2024
Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24308A0042024-10-16016 October 2024
Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County
CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024
Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1
ML24270A2162024-09-27027 September 2024
Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075
ML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24263A2952024-09-19019 September 2024
Site Emergency Plan Implementing Procedure Revision
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000260/20240902024-09-17017 September 2024
NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1
CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024
Cycle 16 Reload Analysis Report
ML24255A8862024-09-10010 September 2024
Core Operating Limits Report for Cycle 16 Operation, Revision 0
IR 05000259/20244042024-09-0303 September 2024
Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter
ML24239A3332024-09-0303 September 2024
Full Audit Plan
IR 05000259/20240052024-08-26026 August 2024
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005
ML24225A1682024-08-16016 August 2024
– Notification of Inspection and Request
ML24219A0272024-08-0606 August 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000259/20244022024-08-0606 August 2024
Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402
IR 05000259/20240022024-08-0202 August 2024
Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
ML24183A4142024-07-10010 July 2024
– License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296)
05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024
Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024
Inoperability of Unit 3 Diesel Generator Due to Relay Failure
ML24184A1142024-07-0202 July 2024
Site Emergency Plan Implementing Procedure Revision
ML24183A3842024-07-0101 July 2024
Registration of Use of Cask to Store Spent Fuel (MPC-364, -365)
ML24179A0282024-06-26026 June 2024
Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a)
05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024
Reactor Scram Due to Generator Step-Up Transformer Failure
ML24175A0042024-06-23023 June 2024
Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System
ML24176A1132024-06-23023 June 2024
American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24155A0042024-06-18018 June 2024
Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47)
ML24158A5312024-06-0606 June 2024
Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363)
ML24071A0292024-06-0505 June 2024
Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter
ML24068A2612024-06-0505 June 2024
SLRA Fluence Methodology Report - Proprietary Determination Letter
ML24151A6322024-05-30030 May 2024
Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report
IR 05000259/20244032024-05-22022 May 2024
– Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403
05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024
High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24136A0702024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
IR 05000259/20240012024-05-14014 May 2024
Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
2024-09-03
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Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 20, 2019 10 CFR 50.55 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRG Docket No. 50-259
Subject:
American Society of Mechanical EngineersSection XI, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs - Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI, Owner's Activity Report for BFN, Unit 1, Cycle 12 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission,Section XI , Division 1.
The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary, up to and including the BFN, Unit 1, Cycle 12 refueling outage, during the first inspection period of the Third 1O Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-5 require that this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 1, Cycle 12 refueling outage ended on November 22, 2018. Accordingly, this submittal is due by February 20, 2019.
U.S. Nuclear Regulatory Commission Page 2 February 20, 2019 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact M. W. Oliver, Acting Nuclear Site Licensing Manager, at (256) 729-7874.
R~~
D. L. Hughes Site Vice President
Enclosure:
American Society of Mechanical Engineers,Section XI , Third 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation cc (Enclosure): NRG Regional Administrator - Region II NRG Senior Resident Inspector - Browns Ferry Nuclear Plant NRG Project Manager - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 American Society of Mechanical Engineers,Section XI, Third 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 12 Operation See Enclosed
FORM OAR-1 OWNER'S ACTIVITY REPORT Report N u m b e r ~ B ~ F ~ N ~ U ~ 1 ~ R ~ 1 ~ 2 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Plant Browns Ferry Nuclear Plant P.O. Box 2000 Decatur AL 35609 Unit No . - - ~ ~ - - Commercial service date August 1 1974 Refueling Outage no. ---~U~1~R~1~2~----
(if applicable)
Current Inspection Interval Third Ten Year Inspection Interval (1st, 2nd , 3rd, other)
Current Inspection Period ~F~ir=st~P~e~r~io~d~--------------,---,----,-,--------------------
(1st, 2nd , 3rd) 2007 Edition, 2008 Addenda (ISi)
Edition and Addenda of Section XI applicable to the inspection plans ~2=0~13~E~d~it~io~n__,,{~C~IS~IJ._)- - - - - - - - - - - - - - - - - ~
0-TPP-ENG-376, Revision 0000, 09/06/2018 0-Tl-364, Revision 0022, 09/19/2018 Date and Revision of inspection plan 0-Sl-4.6.G Revision 0003 09/14/2018 Edition and Addenda of Section XI applicable to repairs/replacement activities, if different than the inspection plans _,_N.,,./A'-'----
Code Cases used for inspection and evaluation: N-508-4 N-532-5 N-613-2 N-648-1 N-702 N-716-1 and N-751 (if applicable , including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI ; and (c) the repair/replacement activities and evaluations supporting the completion of --~U~1~R~1~2~---
conform to the requirements of Section XI. (refueling outage number)
Signed ; * /J4----
es;t> ~ r s Oesignee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in this Owne r's Activity Report and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied , concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pers~Aju roperty age or a loss of any kind arising from or connected with this Inspection .
Date _ _ 2--</,_,_(-=--+--
1/~ f '5____
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. - 12- - -
Current inspection interval 3rd Current inspection period -1st TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Variable spring as-found (Acceptance by Evaluation)
F-A, Item F1 .20C setting found out of range . The condition was evaluated in accordance Acceptance range is 2078 with IWF-3122.3. Since the spring support was lbs, +/- 54 (2024 lbs to determined to still be able to perform its design 2132 lbs). As-found function , corrective measures were performed setting 2350 lbs. [NOi to restore the support to its orig ina l design U1R12-001) condition per IWF-3122.3 (b). WO 11 9973691 reset the load setting of the spring to the design range specifications. Therefore, no add itional or preservice exams are applicable. The spring support was then reinspected to ve rify th e settings.
E-A, Item E1 .11 Gouge in Drywell liner. EVALUATED ACCEPTABLE
[NOi U1 R12-002] (No Corrective Measures Requ ired .)
An indication cons isting of mechanical damage 1/32" in depth , 3/8" in width , and 7/16" in length was identified on the steel conta inment vessel (Drywell) liner. The remaining wall th ickness was 0.73" in the area of mechanica l damage.
The wall thickness was below the acceptance criteria without Civil Design Eng ineeri ng evaluation of 0.75". Civil Engineering determined that the remaining th ickness of 0.73" is greater than the allowed 10% reduction of wall thickness (0.675"), thus it is acceptable for continued operation . Per IWE-3122.3 (b) the area will be reexamined in accordance with IWE-2420.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. - -
Current inspection interval 3rd Current inspection period -1st TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Description of Date Repair/Replacement Item Description Class Work I Completed Plan Number I
NONE NONE
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1R12 PI ant Browns Ferry Unit No. 1 Commercial service date 08/01/1974 Refueling outage no. -12 ----
Current inspection interval 3rd
Current inspection period 1st Summary of IWE Indications for U1R12 The summary table below is provided in accordance with the requirements of 10 CFR 50.55a(b )(2)(ix)(A) .
Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)
E-A, Item E1 .30 Moisture Seal Areas of EVALUATED ACCEPTABLE None None Barrier Separation . None of the areas penetrated the full MSB-1-1 [NOi U1R12- depth of the seal , seal adhesion was 003] good in all locations, and there was no seal failure . The affected portions of the seal identified for repair were excavated and drywell liner below the seal was VT-1 examined . No evidence of moisture intrusion or damage to the liner indicative of moisture intrusion was observed demonstrating no seal failure occurred . The MSB was then re-poured in these areas and re-examined .
