ML22182A163
| ML22182A163 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/01/2022 |
| From: | Rasmussen M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML22182A163 (7) | |
Text
l TENNESSEE VALLEY AUTHORITY Post Office Box 2000, Decatur, Alabama 35609-2000 July 1, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296 10 CFR 50.55a
Subject:
American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 20 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 3, Cycle 20 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 3, Cycle 20 refueling outage, during the second inspection period of the Fourth 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 3, Cycle 20 refueling outage ended on April 4, 2022. Accordingly, this submittal is due by July 3, 2022.
U.S. Nuclear Regulatory Commission Page2 July 1, 2022 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact C. L. Vaughn, Site Licensing Manager, at (256) 729-2636.
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Matthew Rasmussen Site Vice President
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Enclosure:
American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 20 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 Unit3 American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 20 Operation See Enclosed
FORM OAR-1 OWNER'S ACTIVITY REPORT ReportNumber __ B
__ F
__ N"""""""U_.3 __ R=2=0 ________________________________ _
Plant Browns Ferry Nuclear Plant. P.O. Box 2000. Decatur, AL 35609 Unil No. ___ 3 ____ _ Commercial service date March 1, 1977 Refueling Outage no Ref uelinq Outage 20 1,1 opr,L-:able)
Current lnspedion Interval Fourth Ten Year lnspecljon Interval Current Inspection Period
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e...,ri=o=d _______________________________ _
C1!.I. 2nd. 3rd1 2007 Edition. 2008 Addenda (ISi)
Edition and Addenda of Section XI applicable to the inspection plans :;;:;2=0....
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C~IS.,._,_.I) _______________ _
0-TPP-ENG-376, Revision 0003, 01/21/2022 0-Tl-364, Revision 0023, 02115/2022 Date and RevisiOn of inspection plan 0-S1-4 6.G, Revision 001 O 03/04/2022 Edition and Addenda or Section XI applicable to repairs and replacements. if different than the inspection plan ___ N __ IA ___ _
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.
C*I 11ppl~. mtlud,ng tast'S model~ fly case IU,3:? 1111d l41Ct fl'~IOIIJ)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct: (b) lhe 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-=3...,R=2=0'----
conform to the requirements of Section XI.
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Signed&~*')<< (."o/ /tfrC Date __
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CERTIFICATE OF INSERVICE INSPECTION I, the undersigned. holding a vahd commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Companv of Hartford Connecllcut have inspected the items described in this Owner's Activity Report and stale 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 personal injury or property damage or a loss of any k" arising fro or conneded wilh this Inspection.
Date --~.:....,2,-..a3~/z=--z..-=---
FORM OAR--1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U3R20 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
20 Current inspection interval 4th Current inspection period
_2_n_d ____ _
TABLE 1 Examination Category and Item Number F-A / F1.20D ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Item Description Evaluation Description CR 1759027, NOi U3R20-001 A snubber was found with loose bolting on the on the concrete anchor bolts in plate PL 3/4X11X1' 1/2 11
- a gap of approximately 1/8" was observed between the nut and the base plate. The anchor High Pressure Coolant Injection bolts were observed to be secured into the System Snubber, 3-478455-629 concrete. Civil Engineering evaluated the condition identified and concluded that the snubber and *as-found' anchor bolts would still be able to perform its intended design function with the loose bolting. The bolting was tightened in accordance with design configuration and reexamined with no recordable indications.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U3R20 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
_2_0 __
Current inspection interval 4th Current inspection period 2nd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number During the GL 89-13 Raw Water Inspection on the 3A RHR Heat Exchanger (WO 121053378), the vertical welds between the partition plate and the shell were found to be corroded and cracked. The east side weld has a small crack approximately 3 11 long as measured from the top.
Approximately 95% of the weld is not cracked. No light can be seen through the crack on the east side.
The west side weld is cracked 2
Weld repair of partition approximately 80% down from 11/18/2021 121769737 plate vertical weld.
the top toward the bottom with the crack length approximately 18" downward from the top.
Holding a flashlight behind the west side, light can be seen in about 4" of the upper portion of the crack, estimated at 1/32" width.
CR 1655446 was written to document and correct the condition adverse to quality by repairs documented in WO 121769737. Condition was corrected and work was completed on 11/18/2021.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN U3R20 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
.....;;2;;._0 __
Current inspection interval 4th Current inspection period
_2_n~d ___ _
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 U3R20, Inspection of the Protective Coatings identified unsatisfactory locations on the moisture seal barrier {MSB) that could potentially permit moisture intrusion into the inaccessible areas beneath the barrier. The moisture seal barrier was excavated in these locations to make the steel containment vessel accessible and visually examined with no reportable conditions identified. The moisture seal barrier was repaired with examination of the repaired sections having no reportable conditions. A visual examination of the entire moisture seal barrier was completed with no recordable conditions identified.