ML15230A030

Refueling Outage 20 - 90-Day Inservice Inspection Summary Report

ML15230A030
Person / Time
Site:	Sequoyah
Issue date:	08/13/2015
From:	John Carlin 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 37384-2000 August 13, 2015 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit I Facility Operating License No. DPR-77 NRC Docket No. 50-327

Subject:

Unit I Refueling Outage 20 Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Article IWA-6230 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 I Refueling 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 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 Erin Henderson at (423) 843-7170.

Sequoyah Nuclear Plant A* (..* --"/

U.S. Nuclear Regulatory Commission Page 2 August 13, 2015

Enclosure:

ASME Section Xl Inservice Inspection Summary Report, Unit 1 Refueling Outage 20 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 I REFUELING OUTAGE 20

FORM OAR-I OWNER'S ACTIVITY REPORT Report. Number UIC20 Plant SEQUOYAH NUCLEAR PLANT. P.O. Box 2000. Soddy-Daisy, TN 37384-2000 Unit No. 1 Commercial service date July 1. 1981 Refueling outage no. 20 (if epp:ic~e)Oe Current inspection interval Third Inspection Interval (1", 2. 2'. 4*, nurwl Current inspection period Third Inspection Period (V. 2> 31 Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection March 27, 2015 SI-DXl-000-114.3, Revision 27 plans Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _____

Not Applicable 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, for inspection and N-770-1 evaluation:

(f urol.ae eL"i1.t u"J.. , wosesro*ed Sy Case N-532aowwer. wsru(kis CERTIFICATE OF CONFORMANCE I certify that (al the statements made in this report are correct: Ib) the esarninations and tests meet the Inspection Plan as required by the ASME Code Xl and (c) the repair/replacement activties and evaluations supporting the completion at UIC20 conform tothe requirements of Section XI. (yO!uoiw otorue nrm'*.ert SindJ* w~/. ler Date .*l//h/I 5" CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and and employed by HSB Global Standards of Connecticut have inspected the items described in this Owner's Activity Report, and elate 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 Xl.

By signing this cartificate neither the Inspector nor his employer make 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 mann pl} ersonal injury or property damage or a loss of any kind arising from or connected with this inspection.

__________________Commission (3'*1?.. ,/, 2t',

twoewors OSlaaroaLt N atio.nalsoarSNuawberand Sn'f~~eoownl)

Date ~ t ASME 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.,asnot performed as a "btind test" as required by ASME Section XI, Appendix VIII. Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC issued EGM 14-003 as sufficient technical basis for accepting the examinations.

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ASME SECTION Xl INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Engineering evaluation, accept as is.

The support remains functional. This F-AFI.10D Missing outer hex nut from support 1-RCH- condition was previously identified in F-,F ID 114, Report R0039, NOI 1-SQ-516. change document FCR #7927 and incorporated into calculation 1 RCH01 14, Attachment I.

cleaanc beteenpadsandthe Engineering evaluation, accept as is.

Improper claac ewe asadte A zero gap is acceptable as long as F-A, FI.40 seismic plates on support 1-CRDH-1, Report the total gap along the array does not R0036, NOI 1-SQ-515 exceed the limits.

Boric Acid Evaluation, No additional C-H, C7 .10 Packing leak on 1-FCV-063-174, WO ato sncsay ovsa 11670561evidence of corrosion.

C-,C7 0 Packing leak on 1-FCV-063-0024, WO Boric Acid Evaluation, Cleaned and C-,C.0 116770560 observed, no active leak.

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ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number No Applicable Repair/Replacement activities occurred duringq this period.

REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)

ASME Section Xl, Subsection IWE Steel Containment Vessel Inspection Program 10 CER 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 Xl, 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 SQN Unit 1 Cycle 20 refueling outage on the SCV in an accessible area were determined to be acceptable and do not affect the degradation assessment for inaccessible areas.

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