ML24354A209
| ML24354A209 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/19/2024 |
| From: | Komm D Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML24354A209 (1) | |
Text
10 CFR 50.55a Post Office Box 2000, Decatur, Alabama 35609-2000 December , 2024 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 NRC Docket No. 50-259
Subject:
American Society of Mechanical Engineers,Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 15 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI, Owners Activity Report for BFN, Unit 1, Cycle 15 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 Inservice 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 15 refueling outage, during the third inspection period of the Third 10 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 15 refueling outage ended on September 27, 2024. Accordingly, this submittal is due by December 26, 2024.
1\\14 TENNESSEE VALLEY AUTHORITY
U.S. Nuclear Regulatory Commission Page 2 December , 2024 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David Renn, Site Licensing Manager, at (256) 729-2636.
Respectfully, Daniel A. Komm Site Vice President
Enclosure:
American Society of Mechanical Engineers,Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 15 Operation cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC 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, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 1, Cycle 15 Operation See Enclosed
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number..,B,,_F,_N'-'-'U,,_1.,..,R-'-'-'15"-------------------------------------
Plant Browns Ferry Nuclear Plant. P.O. Box 2000, Decatur, AL 35609 Unit No. ___.___ Commercial service date August 1, 1974 Refueling Outage no Refueling Outage 15 l*f OJ)IIUCOOlo)
Current Inspection Interval Third_T...,e=n.,___,,Y..,,e"'a"'"r~ln""s"'p"'e"'ct.,.i"'o"'"n""l"'n"'te=rv..,,,.,a... 1 _________________________ _
(ISi, lna, ltd, ott,er}
Current Inspection Period ~T~h-"'ir=d-'-P~e=r-"io.,d,,__ ___________ --,--,----c---------------------
P*l 2r<i. J"']
2007 Edition, 2008 Addenda (ISi)
Edition and Addenda of Section XI applicable 10 lhe inspection plans =2=0~1=3~E=d=i=tio~n~ (C~ IS-I\\ _________________
~
0-TPP-ENG-376. Revision 0006, 02/07/2024 0-Tl-364, Revision 0026, 11/28/2023 Date and Revision of inspection plan 0-TPP-ENG-467. Revision 0002. 02/05/2024 Edition and Addenda of Section XI applicable to repairs and replacements,,f different than the inspection plan _ N=/A~--
Code Cases used for inspection and evaluation: N-508-4, N-532-5, N-586-1. N-613-2, N-716-1, N-747.
(d' appllca~ includll"IQ uises ITIOll-lfieo by Case,53.2 and laler,emlON~
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 requ,red by the ASME Code.Section XI; and (c) the repair/replacement activities and evaluations supporting the completion or __
..,U<-1..:.R.,_1,_,5<---
conform to the requirements of Section XI.
(reJueW'IQ outage number)
Signed ______________________ Date _______________ _
Owm-r o, Owners DtislQntt, TIUe CERTIFICATE OF INSERVICE INSPECTION I, the undersigned. holding a valid commission Issued by the Nahonal Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler lnspes;tion and Insurance Company of Hartford Connecticut have inspected the items described in this Owner'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 achvities and evaluation described in this repo urtherrn neither the Inspector nor his employer shall be liable in any manner for any personal injury or prope ama or a I s n kind ar'
- g fr m or cted with this Inspection.
N(S Nauon.al OoanJ Number and Enckw'se-ment Date __
l_-z_/,,__n_.-/,_1-_'-1...,~---
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U1R15 PI ant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no.
15 Current inspection interval 3rd Current inspection period 3rd Examination Category and Item Number F-A / F1.40C 8-D / 83.90 F-A I F1.40A TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Item Description Evaluation Description CR 1957166, NOi U1R15-R001 During ASME Section XI VT-3 of the RPV Stabilizer Supports, component RPV-ST AB-1-1 H was observed to have crack like indications.
These are previously identified indications and there was no observed change from the previous Vessel Support, RPV-STAB examination. There were no new indications observed.
This condition was evaluated and was found to be bounded by the evaluation documented in CR 1220533 which concluded that the condition was acceptable and no further evaluation was required.
CR 1957619, NOi U1R15-R002 During U 1 R 15 examination of N4A nozzle to vessel weld, 21 indications were recorded that had been identified during prior examinations. These indications had previously failed IWB-3500 Feedwater Nozzle, N4A Nozzle to Acceptance Criteria but had been found Shell acceptable by an IWB-3600 Analytical Evaluation.
A new IWB-3600 Analytical Evaluation was performed to consider the findings from the latest examination. The evaluation concluded that the allowable fracture toughness was not exceeded for normal or emergency conditions at the end of service life, and therefore, acceptable for continued service per IWB-3600.
CR 1958491, NOi U1R15-R003 During VT-3 examination of Inner Radius Lateral Support 15, two of eight bolts were identified to lack full thread engagement. The bolts were Torus Inner Radius Lateral Support noted to be tight and unable to be turned by hand.
- 15 The condition was evaluated and found to be acceptable for continued service since the condition did not adversely affect the capability of the support to sustain all design basis loads. A workorder has been created to correct the condition at a later time.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U1R15 PI ant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no.
15 Current inspection interval 3rd Current inspection period 3rd Examination Category and Item Number Item Description Evaluation Description CR 1958495, NOi U1R15-R004 During VT-3 examination of Inner Radius Lateral Support 16, it was identified that one of eight bolts F-A/ F1.40A Torus Inner Radius Lateral Support was missing the bolt head. The condition was
- 16 evaluated and found to be acceptable for continue service since the condition did not adversely affect the capability of the support to sustain all design basis loads. A workorder has been created to correct the condition at a later time.
CR 1959639, NOi U 1 R 15-R005 The MSB was examined during a Coatings Program examination and there were adhesion breaches noted at multiple locations. The affected areas of the MSB were excavated and prepared for restoration. After the MSB was excavated, the Steel Containment Vessel (SCV) below the MSB was examined for degradation. Examiners documented minor scattered pitting throughout :;;
1/16" in depth. The general condition was considered acceptable.
E-A/E1.11 Drywell Liner Surface beneath Moisture Seal Barrier (MSB)
There was one pit at Marker 143 that measured up to 3/32" deep and there was new general corrosion noted at Markers 89-91 and 141-144 on the liner plate to first weld interface. The pit at Marker 143 was documented as acceptable. At Marker 89-91 and 141-144, UT thickness readings were taken and it was confirmed the liner thickness was acceptable. It was concluded that the SCV below the MSB remained acceptable for continued service as there is no evidence of damage or degradation requiring further evaluation or Repair/ Replacement Activity required.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U1R15 PI ant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no.
15 Current inspection interval 3rd Current inspection period 3rd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number N/A N/A N/A N/A N/A
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U1R15 PI ant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no.
15 Current inspection interval 3rd Current inspection period 3rd REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program 10 CFR 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV)
Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.
During BFN U1R15, the MSB was examined during a Coatings Program examination and there were adhesion breaches noted at multiple locations. The affected areas of the MSB were excavated and prepared for restoration. After the MSB was excavated, the Steel Containment Vessel (SCV) below the MSB was examined for degradation. Examiners documented minor scattered pitting throughout s; 1/16" in depth. The general condition was considered similar and typical to previous outages.
There was one pit at Marker 143 that measured up to 3/32" deep and there was new general corrosion noted at Markers 89-91 and 141-144 on the liner plate to first weld interface. The pit at Marker 143 was documented acceptable since calculation CDQ099997014 concluded that a 1/8" approximate reduction in plate thickness was allowed at this location. At Marker 89-91 and 141-144, UT thickness readings were taken and it was confirmed the liner thickness was greater than t-min 0.83" (all locations greater than 1" thick). It was concluded that the SCV below the MSB remained acceptable for continued service as there is no evidence of damage or degradation requiring further evaluation or Repair/ Replacement Activity required.