ML23171A913

Amse,Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report

ML23171A913
Person / Time
Site:	Browns Ferry
Issue date:	06/20/2023
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML23171A913 (1)

Text

TENNESSEE 1\14 VALLEY AUTHORITY Post Office Box 2000, Decatur, Alabama 35609-2000 June 20, 2023 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

American Society of Mechanical Engineers,Section XI, Fifth 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 2, Cycle 22 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 2, Cycle 22 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 2, Cycle 22 refueling outage, during the third inspection period of the Fifth 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 2, Cycle 22 refueling outage ended on March 22, 2023. Accordingly, this submittal is due by June 20, 2023.

U.S. Nuclear Regulatory Commission Page 2 June 20, 2023 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.

Respectfully, Manu Sivaraman Site Vice President

Enclosure:

American Society of Mechanical Engineers,Section XI, Fifth 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 2, Cycle 22 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 2 American Society of Mechanical Engineers,Section XI, Fifth 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 2, Cycle 22 Operation See Enclosed

FORM OAR~1 OWNER'S ACTIVITY REPORT Report Number --"8'-'-F...,_N,..,U"-'2'-'-R_,_,2 .,2~----- - - - - - - -- -- - -- - - - -- - - - - - -- - - - - - -- -

Plant Browns Ferry Nuclear Pl<1nl. P 0 . Box 2000 Decatur AL 35609 Unit No. - ---,-~2~-,-- Commercial service date March 1 1975 Refueling Outage no. --"'R~e~fl~ ' e"'li'-'n"'g_,O"-'u'-'-l'ag"'

" e"-"-2,._2_ _

(ir apph.:abliC!-)

Current Inspection Interval Fifth Ten Year inspection Interval

{ 151. 2M, 31C1 . mtier)

Current Inspection Period T~h~i~rd~P~e~ri=od~-------- -------::-c--:::-,-,-,----- - - - - -- - - - - - - --

p s,. 2nd, :!;, d) 2007 Edition, 2008 Addenda (ISi)

Edition and Addenda of Section XI applicable lo l11e inspection plans =2=0~13~E~d~it,~ *o~n~(C=IS~IL)- - - -- - - - - -- - - - - - - ~

O-TPP-ENG-376, Revision 0004, 11/18/2022 O-Tl-364, Revision 0025, 02/06/2023 Dale and Revision of inspection plan 0-TPP-E NG-467 Revision 0001 01/12/2023 Edition and Addenda of Section XI applicable lo repairs and replacements, if different than the inspection plan ~N=IA~- -

Code Cases used for inspection and evaluation: N-532-5 N-613-2 N-716-1 N-751 N-854 . and N-864 (1I apphc.able, 1nclud1r\Q Crl:!>C~ mQd1f;ed b)' Case N-S-32 anel la!Cr f C','1$kil'I~)

CERTIFICATE OF CONFORMANCE I certify that (a) lhe 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 re pair/rep lacement activities and evaluations supporting the completion of U2R22 conform to the requiremen ts of Section XL '""'""!l oota~c ou mner) s,,,.,f?~

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 lnspeclion and Insurance Company of Hartford Connecticut have inspected the items described in th is Owner s Activity Report and state that, to the best of my knowledge and belief, lhe Owner has performed all activities represented by this report in accordance wit h the requirements of Section XI.

By signing this certifica te neither the Inspector nor his emp loyer makes any warranty , expressed or implied , concerning the repai r/rep lacement activities and evalua tion described in this report . Furthermore, neither the Inspector nor his employer shal l be liable in any manner for any personal 1n1ury o(. roperty damage or a loss of any kind arising from or connected with this Inspection P/~7 , Comm issions f'Sf3. I ~q 71 L, N R...

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number - BFNU2R22 PI ant Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. 22 Current inspection interval 5th Current inspection period 3rd TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description F-A / F1 .30C Residual Heat Removal Service Water NOi U2R22-001 Variable Support, 2-4 7B450H0041 A variable spring support setting was found out of tolerance/ out of its load seeing range . It was determ ined that the as-found setting was within the allowable working range , and that the variable spring support wou ld have been able to perform its intended design function without any adverse effect. The spring was reset to within the design limit.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number PI ant

-BFNU2R22 Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. --

Current inspection interval 5th Current inspection period 3rd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Date Repair/Replacement Item Description Description of Work Class Completed Plan Number Replacement of BFN-2-FCV-068-0003 valve dra in li ne (3/4 ") leak .

Flaw was removed with the drain Through wall leak was 1 line and replaced with a 2" line. 3-14-2023 123498959 identified Design change was detailed in Eng ineering Change Paper (ECP) number BFN-23-018.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R22 PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. - -

Current inspection interval 5th 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.

Browns Ferry Unit 2 is currently in the Third IWE Inspection Interval , Second Period. During BFN U2R22, there were no degradation assessments of inaccessible areas as a result of conditions identified in accessible areas during performance of the ASME Section XI, Subsection IWE SCV Inspection Program.

Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)

E-A, Item E1.30 MSB-2-1 Mechanical During BFN 2R22, inspection of None None (Moisture Seal Damage Barrier) the drywell Moisture Seal Barrier identified unsatisfactory locations that cou ld potentially permit moisture intrusion into the inaccessible areas beneath the barrier. The MSB was excavated in these locations to make the steel containment vessel accessible and visually examined with no reportable conditions identified. Conditions were corrected by cleaning and replacing damaged areas of the MSB with no Repair/

Replacement Activity required .

The MSB was repaired with examination of the repaired sections having no reportable conditions. A post repair visual examination of the entire MSB was completed with no reportable conditions identified.