ML15230A030

Sequoyah, Unit 1, Refueling Outage 20 - 90-Day Inservice Inspection Summary Report

ML15230A030
Person / Time
Site:	Sequoyah
Issue date:	08/13/2015
From:	Carlin J T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15230A030 (6)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000August 13, 201510 CFR 50.410 CFR 50.55aATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Unit IFacility Operating License No. DPR-77NRC Docket No. 50-327

Subject:

Unit I Refueling Outage 20 Day Inservice Inspection SummaryReportIn accordance with the American Society of Mechanical Engineers (ASME) Boiler andPressure Vessel Code, Section Xl, Article IWA-6230 and Code Case N-532-5, theTennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 1,Inservice Inspection (ISI) Summary Report within 90 days from completion of the Unit IRefueling Outage 20 (U1R20). The U1R20 refueling outage ended on May 16, 2015.Accordingly, this report is required to be submitted by August 14, 2015.The Enclosure to this letter contains the Owner's Activity Report, a list of items withflaws or relevant conditions that required evaluation for continued service (Table 1), anabstract of repair and replacement activities required for continued service due to a flawor relevant condition (Table 2), and the evaluation of acceptability of inaccessible areasof 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 haveany questions, please contact Erin Henderson at (423) 843-7170.Sequoyah Nuclear Plant --"/

U.S. Nuclear Regulatory CommissionPage 2August 13, 2015

Enclosure:

ASME Section Xl Inservice Inspection Summary Report,Unit 1 Refueling Outage 20cc (Enclosure):NRC Regional Administrator- Region IINRC Senior Resident Inspector -Sequoyah Nuclear PlantNRC Project Manager -Sequoyah Nuclear Plant ENCLOSURETENNESSEE VALLEY AUTHORITYSEQUOYAH NUCLEAR PLANT, UNIT 1ASME SECTION XIINSERVICE INSPECTION SUMMARY REPORTUNIT I REFUELING OUTAGE 20 FORM OAR-I OWNER'S ACTIVITY REPORTReport. NumberUIC20PlantSEQUOYAH NUCLEAR PLANT. P.O. Box 2000. Soddy-Daisy, TN 37384-2000Unit No. 1 Commercial service date July 1. 1981 Refueling outage no.(if epp:ic~e)Oe20Current inspection intervalCurrent inspection periodThird Inspection Interval(1", 2. 2'. 4*, nurwlThird Inspection Period(V. 2> 31Edition and Addenda of Section XI applicable to the inspection plans2001 Edition, 2003 AddendaDate and revision of inspectionplansMarch 27, 2015 SI-DXl-000-114.3, Revision 27Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _____Not ApplicableCode 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,for inspection and N-770-1evaluation:(f urol.ae eL"i1.t u"J.. , Sy Case N-532 aow wer. wsru(kisCERTIFICATE OF CONFORMANCEI certify that (al the statements made in this report are correct: Ib) the esarninations and tests meet the Inspection Plan as required bythe ASME Code Xl and (c) the repair/replacement activties and evaluations supporting the completion at UIC20conform to the requirements of Section XI. (yO!uoiw otorue w~/. lerDate 5"CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors andand employed by HSB Global Standards of Connecticut have inspected the itemsdescribed in this Owner's Activity Report, and elate that, to the best of my knowledge and belief, the Owner has performed allactivities represented by this report in accordance with the requirements of Section Xl.By signing this cartificate neither the Inspector nor his employer make any warranty, expressed or implied, concerning therepair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall beliable in mann pl} ersonal injury or property damage or a loss of any kind arising from or connected with this inspection.__________________Commission ,/, 2t',twoewors OSlaaroaLt N atio.nal soarS Nuawber and Sn'f~~eoownl)Date ~ tASME Code Section Xl Exception-

Reference:

T/A Condition Report 1024964.

Subject:

ASME Category 8-0-1 (RCP hydrastuds)Description: Using the EPRI guidance, the performance demonstration completed for these exams w.,as not performed as a "btindtest" as required by ASME Section XI, Appendix VIII. Supplement 8, paragraph 2.0. This CR documents the issue and referencesthe NRC issued EGM 14-003 as sufficient technical basis for accepting the examinations.E-1 ASME SECTION XlINSERVICE INSPECTION SUMMARY REPORTSEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20TABLE IITEMS WITH FLAWS OR RELEVANT CONDITIONS THATREQUIRED EVALUATION FOR CONTINUED SERVICEExaminationCategory and Item Description Evaluation DescriptionItem NumberEngineering evaluation, accept as is.The support remains functional. ThisF-AFI.10D Missing outer hex nut from support 1-RCH- condition was previously identified inF-,F ID 114, Report R0039, NOI 1-SQ-516. change document FCR #7927 andincorporated into calculation1 RCH01 14, Attachment I.cleaanc beteenpadsandthe Engineering evaluation, accept as is.Improper claac ewe asadte A zero gap is acceptable as long asF-A, FI.40 seismic plates on support 1-CRDH-1, Report the total gap along the array does notR0036, NOI 1-SQ-515 exceed the limits.Boric Acid Evaluation, No additionalC-H, C7 .10 Packing leak on 1-FCV-063-174, WO ato sncsay ovsa11670561evidence of corrosion.C-,C7 0 Packing leak on 1-FCV-063-0024, WO Boric Acid Evaluation, Cleaned andC-,C.0 116770560 observed, no active leak.E-2 ASME SECTION XIINSERVICE INSPECTION SUMMARY REPORTSEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20TABLE 2ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURESREQUIRED FOR CONTINUED SERVICECode Item Description Date Repair/ReplacementClass Description of Work Completed Plan NumberNo Applicable Repair/Replacement activities occurred duringq this period.REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)ASME Section Xl, Subsection IWESteel Containment Vessel Inspection Program10 CER 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessibleareas when conditions are identified in accessible areas during the performance of the ASMESection Xl, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that couldindicate the presence of or result in degradation to such inaccessible areas.The conditions identified during the SQN Unit 1 Cycle 20 refueling outage on the SCV in anaccessible area were determined to be acceptable and do not affect the degradationassessment for inaccessible areas.E-3