ML19070A024

Cycle 22 Refueling Outage -90-Day Inservice Inspection Summary Report

ML19070A024
Person / Time
Site:	Sequoyah
Issue date:	03/08/2019
From:	Rasmussen M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML19070A024 (6)

Text

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 March 8, 2019 10CFR50.4 10 CFR 50.55a ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Unit 2Cycle 22 Refueling Outage Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Article IWA-6240 and Code Case N-532-5, the Tennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 2, Inservice Inspection (ISI)

Summary Report within 90 days from completion of the Unit 2Cycle 22 Refueling Outage (U2C22). The U2R22 refueling outage ended on December 8, 2018. Accordingly this report is required to be submitted by March 8, 2019.

The Enclosure tothis letter contains the Owner's Activity Report, a list of items with flaws or relevant conditions that required evaluation for continued service (Table 1), an abstract of repair and replacement activities required for continued service due to a flaw or relevant condition (Table 2), and the evaluation ofacceptability of inaccessible areas ofthe steel containment vessel in accordance with 10 CFR 50.55a(b)(2)(ix)(A).

There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mr. Jonathan Johnson, Site Licensinq Manaqer at (423)843-8129.

Respectfully, Matthew Rasmussen Site Vice President Sequoyah Nuclear Plant printed on recycled paper

ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 2 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT UNIT 2 CYCLE 22 REFUELING OUTAGE E-1

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R22 Plant SEQUOYAH NUCLEAR PLANT , P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Unit No . 2 Commercial service date June 1, 1982 Refueling outage no . 22 (if applicable)

Current inspection interval Fourth Inspection Interval Current inspection period First Inspection Period of the Fourth Interval (1", 2"', 3")

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition , 2008 Addenda Date and revision of inspection August 28, 2018 PI-DXl-000-114.4 Revision 1 plans Edition and Addenda of Section XI applicable to repair/ replacement activities, if different than the inspection plans Not A licable Code Cases used : N-508-4 , N-513-3, N-532-5, N-586-1 , N-716-1 , N-722-1 , N-729-4 , N-770-2 (if applicable, including ca ses mod ified by Case N-532 and later revisions)

CERTI FICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan required by the ASME Code XI and (c) the repair/replacement activities and evaluations supporting the completion of U2R22 (refueling outage number)

R/R Program Owner Date 2/12/2019 CERTIFIC ATE OF INSERVICE INSPECTION I, the undersigned , holding a valid comm ission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford , CT 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 manner for personal injury or property damage or a loss of any kind arising from or connected with this inspection .

Commissions NB 10822 A,N,I (National Board and Endorsement)

Date F~ . tz Z,ol'i'

ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 22 REFUELING OUTAGE TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Rigid support 2-AFDH-220 was found with Evaluation found support will F-A, F1 .308 no clearance from as shown by drawing . CR continue to perform its design 1462256. function . Accepted as-is.

Rigid support 2-SIH-451was found to out of Evaluation found support will F-A, F1 .20A alignment vertically from as shown on continue to perform its design drawinQ . CR 1462529. function . Accepted as-is.

No evidence of pressure boundary Reactor Vessel Lower Head was found to leakage was detected. Chem istry have accumulated residue and discoloration 8-P, 84.10 results and further exam found not present compared to previous exam .

source to be cavity seal and/or CR 1463750 sandbox cover leakage.

ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 22 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number Replace Cooler Coil 2A-A 3 SQN-2-CLR-030-0186 10/1 /2017 114560783 Pen Room Cooler Replace pipe with thru-wall SQN-2-GENB-082-3 leak between 2-FCV-67-65 9/15/2018 119655843 0002B-B and 67-513B Replace brazed joint on 2B-B 3 SQN-2-CLR-030-0092 CROM Cooler with 12/1/2018 120025322 compression fittinQ .

ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 22 REFUELING OUTAGE 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.

There were no conditions identified during the Unit 2 Cycle 22 refueling outage on the items exam ined that prompted an evaluation of the inaccessible area of the SCV, as required .