ML092080450

Cycle 16 (U1C16) 90-Day Inservice Inspection (ISI) Summary Report

ML092080450
Person / Time
Site:	Sequoyah
Issue date:	07/24/2009
From:	Cleary T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML092080450 (8)

Text

Tennessee Valley Authority Post Office Box 2000 Soddy Daisy, Tennessee 37384-2000 Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant July 24, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant (SQN)

Facility Operating Licensee No. DPR-77 NRC Docket No. 50-327 UNIT 1 CYCLE 16 (U1C16) 90-DAY INSERVICE INSPECTION (ISI)

SUMMARY

REPORT In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Article IWA-6230, TVA is providing the SQN ISI Summary Report within 90 days from completion of the inspections performed during the U1C16 refueling outage.

The summary report contains an overview of the inservice examination results that were performed on ASME Class 1 and 2 components up to and including the U1C16 refueling outage during the first inspection period of the third 10-year inspection interval.

Enclosure 1 contains the Owner's Activity Report, an abstract of examinations and tests (Table 1), evaluation of conditions for continued service (Table 2),

and the ASME Section XI, subsection IWE steel containment inspections.

This report is being provided in accordance with ASME Section XI and Code Case N-532-4.

contains a commitment to submit a relief request to extend the first period of the third interval.

Please direct any questions concerning this issue to Beth A. Wetzel (423) 843-7170.

Sincerely, Timothy P. Cleary Enclosures cc:

See page 2 printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 July 24, 2009 cc (Enclosure):

Mr. Siva P. Lingam, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 3 July 24, 2009 BAW:JWP:SKD cc (Enclosures):

Mr. Siva P. Lingam, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 G.Arent, EQB1B-WBN P. M. Billingsley, OPS-4C-SQN (For Web posting)

C. R. Church, POB 2B-SQN L. D.

Clift, OPS 4G-SQN T. Coutu, LP 3R-C K. R. Jones, OPS 4A-SQN D. E. Jernigan, LP 3R-C R. M. Krich, LP 3R-C L. E. Nicholson, BR 4X-C NSRB Support, BR 4X-C M. A. Purcell, BR 4X-C P. D. Swafford, LP 3R-C L. E. Thibault, LP 3R-C E. J.Vigluicci, ET10A-K B. A. Wetzel, OPS 4C-SQN R. J. Whalen, LP 3R-C WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K l:License/ASME ISI/U1C16 90-Day ISI Summary Report

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U1C16RFO Plant Sequoyah Nuclear Plant. P.O. Box 2000. Soddy-Daisy. TN 37384-2000 Unit No.

1 (if applicable)

Commercial service date July 1.1981 Refueling Outage no.

Cycle 16 Current Inspection Interval Third Ten Year Inspection Interval (1st, 2nd, 3rd, other)

Current Inspection Period First Period (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Date and Revision of inspection plan U1C16 Inspection Scan Plan Revision

1. July 9. 2009 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan Same as above Code Cases used:

N-460: N-526: N-586: N-624; N-648-1: N-658: N-695; N-532-4: N-706: N-722: N-729-1 (if applicable)

Reference PER 176254 for Examination Category B-B welds and actions taken to request relief (No. 1-ISI-34) for inspection period extension and recurrence control.

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of U1C16 conform to the requirements of Section XI.

Signed

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'Owner or Owner's Designee. Title (refueling outage number)

Date CERTIFICATE OF INSERVICE INSPECTION I, 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 CT of Hartford. Connecticut 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 requirement of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations, and corrective measures described in this report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from the connected with this Inspection.

.Commissions Inspector's Signature National Board. State, Province and Endorsements Date 7/7-H /n

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY (TVA)

SEQUOYAH NUCLEAR PLANT (SQN)

UNIT1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT FROM UNIT 1 CYCLE 16 The following limitations were noted during the performance of examinations during the Unit 1 Cycle 16 refueling outage and a relief request will be initiated in accordance with applicable ASME Code requirements.

Component CVCF-020 CSF-058 SIF-029 RHRF-106 Exam Category R-A R-A R-A R-A Item Number R1.11 R1.11 R1.11 R1.11 Limitation percentage, configuration 41.9 percent, tee to valve 34 percent, elbow to pipe 50 percent, tee to valve 50 percent, pipe to valve Additionally, it is noted that SQN failed to properly substitute a weld for an inaccessible weld during the Unit 1 Cycle 16 refueling outage.

This issue was documented in the Corrective Action Program.

Problem evaluation report (PER) 176254 was initiated to document the noncompliance with Examination Category B-B minimum percentage requirements.

A relief request is being prepared to request an extension to the first period of the third interval.

TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Examination Category and Item Number F-A,F1.20A F-A, F1.30B F-A.F1.40E E-A, E1.11 Item Description 1-SIH-461, support misalignment CCH-0486, broken tack weld SGH-2-1, gap and misalignment (cold condition)

SCV-1, SCV-2, SCV-3, SCV-4, and Dome; areas of rust, unpainted, scrapes and dings.

Evaluation Description Engineering accept-as-is.

Admin change to document alignment condition on support drawing.

Tack weld not essential for support function.

Engineering accept-as-is.

The gap specified is for hot conditions; expect gap and alignment to be correct in hot condition.

Engineering accept-as-is.

Conditions noted do not impact structural integrity of the SCV, no detrimental flaws have been observed.

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class 1

MC 3

3 3

3 Item Description 1.5" SI piping TB-1, thermal barrier 6" ERCW piping 4" ERCW piping^

5/8" tubing 6" ERCW piping Description of Work Replace piping and elbow associated with weld Sl-1610 Repair indications of missing caulk and dents Replace piping and elbow Replace flange and pipe Penetration room cooler 1A-Atube plug Replace piping and elbow Date Completed 5/29/09 4/21/09 10/6/08 10/16/08 2/26/09 5/6/09 Repair/Replacement Plan Number WO 09-773437-000 WO 08-773344-000 WO 08-778015-000 WO 08-780088-000 WO 08-772583-001 WO 08-778171-000

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

ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10 CFR 50.55a(b)(2)(ix) requires the reporting of inaccessible areas and additional examinations identified during the performance of the ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.

For the examinations performed during the Unit 1 Cycle 16 refueling outage, there were no degraded conditions identified in accessible portions of the SCV which would require additional examinations or evaluation of inaccessible areas.

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY (TVA)

SEQUOYAH NUCLEAR PLANT (SQN)

UNIT1 COMMITMENT SQN failed to properly substitute a weld for an inaccessible weld during the Unit 1 Cycle 16 refueling outage.

A relief request is being prepared to request an extension to the first period of the third interval.