ML17243A004
| ML17243A004 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/30/2017 |
| From: | Anthony Williams Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17243A004 (6) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 August 30, 2017 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 2 Refueling Outage 21 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, "Summary Report Submittal," and Code Case N-532-5, "Repair/Replacement Activity Documentation," 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 2 Refueling Outage 21 (U2R21). The U2R21 refueling outage ended on June 2, 2017. Accordingly, this report is required to be submitted by August 31, 2017.
The Enclosure to this 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 of acceptability of inaccessible areas of the 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. Michael McBrearty, Site Licensing Manager at (423) 8*
)ny L. Williams 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 21 REFUELING OUTAGE E1 of 5
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R21 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.
21_
(if applicable)
Current inspection interval Third and Fourth Inspection Intervals Current inspection period Third Inspection period of the Third Interval, First Inspection Period of the Fourth Interval (1a, 2"°,3")
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda 2007 Edition, 2008 Addenda Date and revision of inspection November 23, 2015 SI-DXI-000-114.3, Revision 28 plans April 4, 2017 S1-DXI-000-114.4, Revision 1 Edition and Addenda of Section XI applicable to repair/replacement activities, ifdifferentthan the inspection plans NotApplicable Code Cases used:
N-460, N-513-3, N-532-4, N-532-5, N-566-2, N-586-1, N-686-1, N-706-1, N-716-1, N-722-1, N-729-1, N-770-1 (if applicable, including 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 required by the ASME Code XI and (c) the repair/replacement activities and evaluations supporting the completion of U2R21 conform to the requirements of Section XI.
(refueling outagenumber)
Signed
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Program Owner Date
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J Humar r\\r fVamnr1!? nacifmno Title*
Owner or Owner's Designee, Title 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, 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.
\\
J Inspectors Signature Commissions (National Board and Endorsement)
Date
/4ug. Z% f2Ql~l E2of5
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 21 REFUELING OUTAGE TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description F-A, F1.10C Component ID 2-RCH-832, Variable Spring Support, setting found out of tolerance (NOI 2-SQ-449)
Evaluation found the support would have performed its intended design function. The setting was corrected by WO# 118718105.
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ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 21 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 3
Flex hose for 2-CLR-030-0097 (2B-B Upper Containment Cooler)
Replaced flex hose that was found to be leaking.
4/8/2016 114675125 3
Flex hose for 2-CLR-030-0100 (2D-B Upper Containment Cooler)
Replaced flex hose that was found to be leaking.
4/8/2016 114675126 3
Cooler SQN-2-CLR-030-0184, (BAXFER&
AUX FW PUMP COOLER A-A)
Replaced cooler due thru-wall ERCW leak.
9/21/2016 117493967 2
Braided hose down stream of 2-VLV-001-276A Replaced flex hose that was found to be leaking.
5/29/2017 117575883 3
Flex hose for 2-CLR-030-0100 (2D-B Upper Containment Cooler)
Replaced flex hose that was found to be leaking.
10/26/2016 117743019 E4of5
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 21 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.
The conditions identified during the Unit 2 Cycle 21 refueling outage on the SCV in an accessible area were determined to be acceptable and do not affect the degradation assessment for inaccessible areas. The conditions were documented in NOI 2-SQ-447 and 2-SQ-448. Only general surface corrosion and minor pitting were found and these conditions were found to meet the site acceptance criteria. No corrective actions are required.
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