ML100541580
| ML100541580 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/19/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100541580 (7) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 February 19, 2010 10 CFR 50.55a(b)(2)(ix) 10 CFR 50.55a(g)(4)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 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 16 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, TVA is providing the Sequoyah Nuclear Plant, Unit 2 Inservice Inspection Summary Report within 90 days from completion of the inspections performed during the Unit 2 Cycle 16 (U2C16) 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 U2C16 refueling outage during the second period of the third 10-year inspection interval.
The Enclosure contains the Owner's Activity Report, an inservice inspection summary report, 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 Xl, Subsection IWE Steel Containment Inspection Summary.
Please direct any questions concerning this issue to J. W. Proffitt at (423) 843-6651.
Respectfully, R. M. Krich Vice President Nuclear Licensing
Enclosure:
ASME Section Xl Inservice Inspection Summary Report from Unit 2 Cycle 16 cc: See Page 2 Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 February 19, 2010 Enclosure cc: (Enclosure)
NRC Regional Administrator-Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT FROM UNIT 2 CYCLE 16 El-1
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2CI 6RFO Plant SEQUOYAH NUCLEAR PLANT, P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Unit No.
2 Qt applicable)
Commercial service date June 1, 1982 Refueling outage no.
Cycle 16 Current inspection interval Current inspection period Third Inspection interval (1W, Z-, 3', 4", other)
Second Inspection Period Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans August 31, 2009 Sl-DXI-000.1 14.3, Revision 13 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-526, N-532-4, N-58B, N-624, N-648-1, N-658, N-686, N-695, N-706, N-722, N-729-1 CERTIFICATE OF CONFRONMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan required by theASME Code XI and (c) the repair/replacement activities and evaluations supporting the completion of U2C16 conform to the req ireents of Sectin Xl.
(refuefing outage number)
- Signed Qenor's Oe/igne.
itDate 2kI\\2.O.\\
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 Hartford Insurance Co.
of 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 requirements of Section XI.
By signing this certificate neither the Inspector nor his employer make any warranty, expressed or implied, concerning the repalr/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in manner for personal injury or property damage or a loss of any kind arising from or connected with this inspection.
eCommissions 4io,
at 1
I acotor'5sSignature National Board. State, Province, and Endorsements
'ate a/&h
- One U2C16ASME Section Xl repair/replacement work plan package (Class 3) has not yet been reviewed, post work, due to the work package being lost. PER 216976 has been initiated to locate or recreate the package.
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ASME SECTION Xl INSERVICE INSPECTION
SUMMARY
REPORT FROM UNIT 2 CYCLE 16 The following limitations were noted during the performance of examinations during the Unit 2 Cycle 16 refueling outage and a relief request will be initiated in accordance with the applicable 10CFR50.55a requirements.
Component Exam Exam Number Cat.
Item Description of Limitation No.
RCW-21 B-D R1.11 Examination volume achieved: 59.5%. Pressurizer surge nozzle exam was limited by pressurizer heater penetrations.
AFWF-007 R-A R1.11 Examination volume achieved: 81.1%. Examination volume was limited by weld crown.
MSF-046B R-A B1.11 Examination volume achieved: 60.5%. This pre-service examination for installation of a new valve was limited by the flange to which the valve was welded.
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TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category Item Description Evaluation Description and Item Number F-A, FI.10C Pipe Support 2-RCH-922, Spring can settings were Engineering evaluation slightly less than the designed range acceptable-as-is.
E-A, El. 11 Surface pitting on penetration X-79A flange face.
Engineering evaluation acceptable-as-is.
E-A, E1.11 Surface pitting on penetration X-79B flange face.
Engineering evaluation acceptable-as-is.
F-A, F1.20C Pipe Support 2-MSH-425, Spring can settings were Engineering evaluation slightly less than the designed range acceptable-as-is.
F-A, FI.40E Pipe Support 2-AFDH-061, Spring can settings were Engineering evaluation slightly less than the designed range and one bolt was acceptable-as-is for the missing from the pipe clamp, support setting and replacement of missing bolt.
C-B, C2.21 Re-inspection of previously. identified flaw in Steam Essentially no change in flaw Generator No. 1 nozzle MSW-l.
size or configuration. The previous Engineering acceptable-as-is evaluation remains valid.
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 Pipe Support The missing bolt from the pipe clamp Work Order No.
2 2-AFDH-061 on the spring can support was 11/18/2009 09-780221-000.
replaced.
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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.
The Class MC examinations performed during the Unit 2 Cycle 16 Refueling Outage did not identify degradation in accessible portions of the Steel Containment Vessel that would require additional examinations or evaluation of inaccessible areas.
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