ML20176A365
| ML20176A365 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/24/2020 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML20176A365 (7) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 24, 2020 10 CFR 50.55a 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
Subject:
American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 19 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 3, Cycle 19 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 3, Cycle 19 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 19 refueling outage ended on March 26, 2020. Accordingly, this submittal is due by June 24, 2020.
uID
U.S. Nuclear Regulatory Commission Page 2 June 24, 2020 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Site Licensing Manager, at (256) 729-2636.
Respectfully, S. M. Bono Site Vice President
Enclosure:
American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 19 Operation cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant p
y, S M B
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 American Society of Mechanical Engineers,Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 19 Operation See Enclosed
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number~B=F~N~U=3=R~1=9 __________________________________ _
Plant Browns Ferry Nuclear Plant. P.O. Box 2000, Decatur, AL 35609 Unit No. --~3~--
(it applicable)
Commercial service date March 1 1977 Refueling Outage no. Refueling Outage 19 Current Inspection Interval Fourth Ten Year Inspection Interval (1st. 2nd. 3rd. other)
Current Inspection Period zS=e=c=o~nd~P~e=ri=o=d------------.,....---------------------
(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=l=S~I)~---------------~
O-TPP-ENG-376, Revision 0001, 10/03/2019 0-Tl-364, Revision 0022, 09/19/2018 Date and Revision of inspection plan 0-SI-4.6.G Revision 0005 02/27/2020 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan __,_N,,.,/A..._ __
Code Cases used for inspection and evaluation: N-508-4, N-513-3, N-526, N-532-5, N-586-1, N-613-2, N-648-1, N-702, N-716-1, N-735, N-747, and N-751 (if applicable, indudlng 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~3=R~1~9~--
I.
(refueling outage number)
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 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 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 loss of any kind arisin m or connected with this Inspection.
~ /1 "'7/ l.DZ.()
Date ___________ _
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R19 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
19 Current inspection interval 4th Current inspection period 2nd Examination Category and Item Number F-A / F1.30D F-A / F1.30D F-A/ F1.10D F-A / F1.10C TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Item Description Evaluation Description CR 1589844, NOi U3R19-001 A mechanical snubber was found with loose Main Steam System Mechanical bolting on the riser clamp. Civil Engineering evaluated the conditions identified and concluded Snubber, 3-47B401-24 that the snubber would still be able to perform its intended design function with the loose bolting.
The bolting was tightened in accordance with design configuration.
CR 1589851, NOi U3R19-002 A mechanical snubber was found with loose Main Steam System Mechanical bolting on the riser clamp. Civil Engineering evaluated the conditions identified and concluded Snubber, 3-47B401-21 that the snubber would still be able to perform its intended design function with the loose bolting.
The bolting was tightened in accordance with design configuration.
CR 1590623, NOi U3R 19-003 Feedwater System Hydraulic Snubber, A hydraulic snubber was found with a missing 3-47B415-21 cotter pin at the clevis plate. The associated clevis pin was still in place allowing the support to provide its intended design function. A new cotter pin was installed per design configuration.
CR 1592392, NOi U3R 19-004 A variable support was found to have a missing load plate making it unable to verify the support settings. Measurements to determine spring Residual Heat Removal System position were taken using reference points and Variable Support, 3-478452-3044 provided to Civil Engineering. Civil Engineering evaluated the conditions identified, found that the spring was outside of the specified range, and concluded that the variable support could still perform its intended design function. The spring can load plate was reset per Civil Engineering instructions.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R19 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
19 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 None None None None None
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R19 PI ant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no. 19 Current inspection interval 4th Current inspection period 2nd 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 U3R19, the moisture seal barrier (MSB) of the SCV was identified to have conditions requiring examination of inaccessible areas beneath the barrier. The inaccessible areas of the SCV beneath the MSB were determined to be acceptable by visual examination. These conditions were identified and resolved under NOi U3R19-006.
No corrective actions are required.