ML18213A041
| ML18213A041 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/31/2018 |
| From: | Anthony Williams Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18213A041 (6) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 July 31, 2018 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 10CFR50.4 10 CFR 50.55a Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
Unit 1 Refueling Outage 22 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 1, Inservice Inspection (ISI)
Summary Report within 90 days from completion of the Unit 1 Refueling Outage 22 (U1R22).
The U1R21 refueling outage ended on May 7, 2018. Accordingly, this report is required to be submitted by August 6, 2018.
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)843-7170.
mthony L. Williams Site Vice President Sequoyah Nuclear Plant printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 July 31, 2018
Enclosure:
ASME Section XI Inservice Inspection Summary Report, Unit 1 Cycle 22 Refueling Outage cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector-Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT UNIT 1 CYCLE 22 REFUELING OUTAGE
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U1R22 Plant SEQUOYAH NUCLEAR PLANT, P.O. Box2000, Soddy-Daisy, TN 37384-2000 UnitNo.
1 Commercial service date July 1,1981 Refueling outage no.
22_
(if applicable)
Currentinspectioninterval FourthInspection Intervals (1**. 2"*. 3'. 4". other)
Current inspection period First Inspection Period of the Fourth Interval (1u.2M.3'a)
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda 2007 Edition, 2008 Addenda Date and revision of inspection April4, 2017 SI-DXI-000-114.4, Revision 1 plans April 4, 2018 PI-DXI-000-114.4 Revision0 Edition and Addenda of Section XI applicable to repair/replacement activities, ifdifferent than the inspection plans NotApplicable CodeCases used:
N-508-4, N-513-3, N-532-5, N-566-2, N-586-1, N-716-1, N-722-1, N-729-4, N-770-2 (if applicable, including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE Icertify 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) therep/IWreplacement activities and evaluations supporting the completion of U1R22 conform to the requirements of Section XI.
(refueling outagenumber)
Signed /,Au>i/^l-^-v~ (/
R/R Program Owner Date 7/20/2018 fieY 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 ActivityReport, 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.
Bysigning this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described inthis report. Furthermore, neither the Inspector nor his employer shall be liable in manner for personal injuryor property damage or a loss of any kind arising from or connected with this inspection.
w7Z 7H<.
Commissions NB 10822 A.N.I inspectors Signature (NationalBoard and Endorsement)
Date \\J~U,t*f ZO, ZOf 3
Examination Category and Item Number C-H.C7.10 C-H, C7.10 C-H.C7.10 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 22 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Item Description Valve 1-VLV-062-0715 flange connection boric acid accumulation due to leak.
Condition Report (CR) 1345720 Valve 1-VLV-063-0870 valve stem boric acid accumulation due to leak. CR 1411825 Valve 1-VLV-063-0868 valve stem boric acid accumulation due to leak. CR 1411832 E-2 Evaluation Description Boric Acid Leakage Evaluation found valve and connection materials undamaged and no corrosion rate due to being stainless steel materials Boric Acid Leakage Evaluation found valve and connection materials undamaged and no corrosion rate due to being stainless steel materials Boric Acid Leakage Evaluation found valve and connection materials undamaged and no corrosion rate due to being stainless steel materials
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 22 TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 1
SQN-1-VLV-068-0563 Replaced PZR Safety 1-VLV-068-0563 10/09/2017 118617283 3
SQN-0-MTRA-067-0444-B Repair support bracket 01/22/2018 119183698 3
SQN-0-MVOP-067-0208-B Replace Pipe Section due to FAC Erosion 04/18/2018 119526319 REPORTING REQUIRED BY 10CFR 50.55a(b)(2)(lx)(A)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10CFR 50.55a(b)(2)(ix)(A) requires reporting ofthedegradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance oftheASME Section XI, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that could indicate the presence ofor result in degradation to such inaccessibleareas.
The conditions identified during the Unit 1Cycle 22 refueling outage on theSCV Moisture Barrier prompted evaluation ofthe inaccessible area ofthe SCV and weredetermined to be acceptable and do not affectthe degradation assessment for inaccessible areas. The conditions weredocumented in NOI1-SQ-526. Only general surfacecorrosion that metthe acceptancecriteria was found. No corrective actions are required.
E-3