ML14259A334

Cycle 19 Refueling Outage - 90-Day Inservice Inspection Summary Report

ML14259A334
Person / Time
Site:	Sequoyah
Issue date:	09/11/2014
From:	John Carlin Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14259A334 (7)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 September 11, 2014 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 2 Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Unit 2 Cycle 19 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-6230 and Code Case N-532-4, 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 19 (U2R19). The U2R19 refueling outage ended on June 18, 2014. Accordingly, this report is required to be submitted by September 16, 2014.

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).

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U.S. Nuclear Regulatory Commission Page 2 September 11, 2014 There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Erin Henderson at (423) 843-7170.

Respectfully, v John T. Carlin Site Vice President Sequoyah Nuclear Plant

Enclosure:

ASME Section XI Inservice Inspection Summary Report, Unit 2 Cycle 19 Refueling Outage cc (Enclosure):

NRC Regional Administrator- Region I1 NRC Senior Resident Inspector - Sequoyah Nuclear Plant

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

SUMMARY

REPORT UNIT 2 CYCLE 19 REFUELING OUTAGE

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number U2C19 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. 19 Current inspection interval Third Inspection Interval (11. 2 V3*.4. orrrer Current inspection period Third Inspection Period Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans May 9. 2014 - O-SI-DXI-000-1 14.3. Revision 23 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-566-2. N-586-1. N-686-1, N-706-1. N-722-1, N-729-1. N-770-1, N-579 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 X1and (c) tho repairlrepracement activities and evaluations supporting thle completion of U2C19 conform to the requirements of Section Xl. VONrnfo. .. Aag rrura*,)

Signed ., .Date O-ar w Owr' ODe ege., rdTv CERTIFICATE OF INSERVICE INSPECTION 1.the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Tennessee and employed by HSB Global Standards of Connocticut 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 neilher 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 mannago 1 personal injury or property damage or a loss of any kind arising from or connected with this inspection.

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ASME SECTION Xl INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 19 REFUELING OUTAGE 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, acceptable Corrosion on steel containment vessel as is. Corrosion is less than 10% of E-A, El.11 (SCV) discovered during IWE examination. SCV thickness. Acceptable in (NOI 2-SQ-437) accordance with ASME XI, IWE-3122.3(a).

Engineering evaluation, acceptable ALow Thickness Reading on SCV Dome. as is. Thickness reading was greater N/A Low Thickness Rethan 90% of design thickness (95%).

(NOI 2-SQ-431) Acceptable in accordance with ASME XI, IWE-3122.3(a).

F-A, F1.20 Spring Can Settings outside Design Criteria Engineering Evaluation, acceptable Tolerance, 0 (NOI 2-SQ-424) as is, but setting was corrected to ToeaneNO_-Q-2)with tolerance.

Loose nuts on pipe supports. (NOls, 2-SQ- Engineering evaluation, all cases F-A, F1.20 42were acceptable as is, but were 426, 429, 435, 436) corrected by tightening.

C-A, C1.20 Re-inspection of previously found indication Engineering evaluation, acceptable in Boric Acid Injection Tank. (NOI 2-SQ-427) as is. Indication showed no growth.

Re-inspection of previously found indication B-K, B10.20 on integral attachment 2-SIH-020-IA. (NOI Engineering evaluation, acceptable 2-SQ-428) as is. Indication showed no growth.

Boric Acid found on 2-HEX-072-0007 bottom Engineering evaluation, cleaned and C-H, C7.10 flange. (PER 858554/858525) accepted as is per ASME Code Case N-566-2.

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ASME SECTION Xl INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 19 REFUELING OUTAGE 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 during this period.

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ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 19 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 19 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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