ML110470405

Cycle 17 - 90-Day Inservice Inspection Summary Report

ML110470405
Person / Time
Site:	Sequoyah
Issue date:	02/14/2011
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML110470405 (6)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing February 14, 2011 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327

Subject:

Unit I Cycle 17 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 1 Inservice Inspection Summary Report within 90 days from completion of the inspections performed during the SQN, Unit 1 Cycle 17 (U1CI7) refueling outage. The Unit 1 Cycle 17 refueling outage ended on November 16, 2010. Accordingly, this report is required to be submitted by February 14, 2011. 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 U1C17 refueling outage during the second period of the third 10-year inspection interval. The enclosure contains the Owner's Activity Report and an inservice inspection summary report comprised of an evaluation of conditions for continued service (Table 1), an abstract of repair and replacement activities required for continued service (Table 2), and the ASME Section X1, Subsection IWE Steel Containment Inspection Summary.

Please direct any questions concerning this issue to J. W. Proffitt at (423) 843-6651.

Respectf R. M. Krich

Enclosure:

ASME Section Xl Inservice Inspection Summary Report, Unit 1 Cycle 17 Refueling Outage cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant printed on recycled paper

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

SUMMARY

REPORT UNIT I CYCLE 17 REFUELING OUTAGE

FORM OAR-I OWNER'S. ACTIVITY REPORT Report. Number Q 017 Plant SEWOYAH NUCLEAR PLANT I P . 0 . Bo'ký200m 1ýotld yJ" a I- 7ý TN '17384-20m Unit N0. 1.!

apcae CommErcial service date . July 1, 1981 Refueling butage no. 17 Current inspection interval. Third Inspecton Interval Current=.inspection period Second Inspection Period (P", z";,3"*;

Editioh and Add*nda of. Section XIlipplicabletdtlieinspection plans . 2001 Editi6n, 2003 Addenda Date and revisionof inspection plans,, August 31. 2009 - O-SInDXI'000.114,3, Revision 15 Edition andAddenda of Sertion XI applicable to repairhreplacement activities, if different than the inspectioh iilabs

.Not Applicable Code Cases used: WN460,N-5.13-2, N-526. N,532Aý, N-56&-2. N-586-1, N-658, NW695, N-706-1; N7722, N-729-11.

CERTIFICATE OF CONFORMANCE I certifythat (a) the statements made in this report are cOrrect; (b) the:examiratlons.srrd tests meet the Inspection Plan required.by the ASME Code XI and (I) the repair'replacement activities and evaluations supporting the ompletien of aUIC11 conriforrmto the requirementsof.-Section XI, (re.eteng eosae number):

.Signed . z Dat.a, Oý.nuor 0n's Deigete-,eTae.

CERTIFICATE OF INSERVICE INSPECTION, I 'the uhdersigned holding a Valid commission issued by the National Board 6f Boiler and Pressure Vessel Inspectors and the.statelor Province of Tennessee and:employed by H.S.B. Global Standards' of Connecticut have Inspected the.Items described in this OwnersActivity Report, and slate that to the best:of my knowledge and bellef; the Owner has perormed all .activities reprersented by this repot in accordance With tBd requ iremnts of Section IX1.

By signing this certificate.neither the Inspector nor his employer make any warranty, expressed or implied. concerning the repaii/replacement activities and evaluatieri.described in this report. Furthermore, neither the Inspector nor his employer shall, be liable in marha, for personal injury or property damage or a loss of any i-nrd'arising.fr*m or connected With tr.isiinspectioh.

... .Co.missions i Sigss5,es, NationaBeard.Stare SPmeese.

and Enodasemeee:

Date /,

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ASME SECTION Xl INSERVICE INSPECTION

SUMMARY

REPORT UNIT I CYCLE 17 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 Component Cooling Heat Engineering evaluation, acceptable as-is.

F-A, F1.40 Exchanger lower support bracket; Adjustment performed to maintain design one bolt and one nut were loose, configuration.

Pipe Support 1-CVCH-565; Spring Engineering evaluation, acceptable F-A, F1.20 can settings were slightly less than as-is. Adjustment performed to the designed range. maintain design configuration.

F- .l0 Pipe Support 1-RCH-922; pipe Engineering evaluation, acceptable F-A, clamp was slightly misaligned, as-is.

Non Regenerative Letdown Heat Engineering evaluation, acceptable F-A, F1.40 Exchanger support bracket; one bolt as-is. Adjustment performed to was loose, maintain design configuration.

Pipe Support 1-AFDH-061; Spring Engineering evaluation, acceptable F-A, F1.40 can settings were slightly less than as-is. Adjustment performed to the designed range. maintain design configuration.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ASME SECTION Xl INSERVICE INSPECTION

SUMMARY

REPORT UNIT 1 CYCLE 17 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Note, the Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service submitted following the Sequoyah Nuclear Plant, Unit 1 Cycle 15 refueling outage, dated February 12, 2008, erroneously documented one pressurizer nozzle repair as the result of a Scheduled Section Xl examination. Instead, the finding was the result of an owner elected examination performed prior to installation of the pressurizer nozzle weld-overlays.

This is a documentation error in reporting only, with no consequence. The error was identified during performance of an assessment of the Inservice Inspection Program.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT UNIT I CYCLE 17 REFUELING OUTAGE 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.

During the Sequoyah Nuclear Plant, Unit 1 Cycle 17 refueling outage, there was no degradation identified in accessible portions of the steel containment vessel that would require additional examinations or evaluation of inaccessible areas.

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