ML14055A398
| ML14055A398 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/18/2014 |
| From: | John Carlin Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML14055A398 (7) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy. Tennessee 37384-2000 February 18, 2014 10 CFR 50.4 10 CFR50.55a 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 Refueling Outage 19 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-532-4, 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 1 Refueling Outage 19 (U1R19). The U1R19 refueling outage ended on November 21, 2013. Accordingly, this report is required to be submitted by February 19, 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).
U.S. Nuclear Regulatory Commission Page 2 February 18, 2014 There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty at (423) 843-7170.
Respectfully, John T. Carlin Site Vice President Sequoyah Nuclear Plant
Enclosure:
ASME Section Xl Inservice Inspection Summary Report, Unit 1 Refueling Outage 19 cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT I ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT UNIT I REFUELING OUTAGE 19
FORM OAR-I OWNER'S ACTIVITY REPORT Report Number UIC19 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.
19 (if applicable)
Current inspection interval Third Inspection Interval (1', 2--, 3'-, 4C, other)
Current inspection period Third Inspection Period (1-, 2'-. 3")
Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans September 18, 2013 SI-DXI-000-114.3, Revision 22 Edition and Addenda of Section Xl 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 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 XI and (c) the repair/replacement activities and evaluations supporting the completion of U1C19 conform to the requirements of Section Xl.
(refueling outage number)
Signed --A "
wne. o nes D ee, P m 5 A itr.
Date Owner or#Owner'ý Designee, Title 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 H.S.B. Global Standards 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 repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in manne fo ersonal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions
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,.r / TV' ef/ 2,v Inspector's Signature National Board, State, Province, and Endorsements Date 2 Ay/ 2ofe E-1
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT I REFUELING OUTAGE 19 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Engineering evaluation determined E-A, E1.11 Mechanical damage on steel containment the damage to be acceptable as is.
vessel discovered during IWE examination Pit depth measurements and design (NOIs 1-SQ-503, 506, 507 and 508) documents confirmed the acceptability of flaws.
Engineering evaluation determined A
Support clearance was below the minimum the clearance to be acceptable as is.
F-A, F.30A Suppolertaclearce was bew tThe clearance is only for thermal tolerance (NOI 1-SQ-499) expansion and the piping is abandoned in place.
F-A, F.20C Variable spring setting out of range Engineering evaluation determined (NOI 1-SQ-509) the setting to be acceptable as is.
Engineering evaluation determined F-A, F1.1OC Variable spring setting out of range the setting to be acceptable as is.
(NOI 1-SQ-504)
The setting was found to be within design tolerance.
F-A, F1.30B Support clearance was below minimum Engineering evaluation determined tolerance (NOI 1-SQ-502) the clearance to be acceptable as is.
Engineering evaluation determined C-H, C7.10 Boron on Centrifugal Charging Pump the boron to be acceptable as is.
Injection Tank (0-SI-SXI-062-300.2)
The corrosion is surface only with no significant degradation.
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ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 19 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 2
Main Feedwater Reset constant spring travel 11/7/2013 115214170 Pipe Support setting by adjusting the constant (1-FDH-282) spring load.
3 Auxiliary Feed Replaced hinge pin gaskets to 11/21/2013 111641655 Water Valve repair leaking seal weld.
(1 -VLV-003-0864) 3 Essential Raw Replaced piping section and weld 5/30/2012 113536197 Cooling Water to repair a thru-wall leak at the Piping connection at connection.
(1 -TW-067-046-B) 3 Air Handling Unit Replaced 18-B control rod drive 11/7/2013 115189293 (1-AHU-030-0092) mechanism cooling coil due to pin-hole leak between flange and header.
3 D-B Cooling Coil Installed blind flange on leaking 11/8/2013 115255129 (1-CLR-030-0078) coil.
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ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT I REFUELING OUTAGE 19 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 condition identified during the Unit 1 refueling outage 19 on the SCV in an accessible area was determined to be acceptable and does not affect the degradation assessment for inaccessible areas. The conditions were documented in NOls 1-SQ-503, 1-SQ-506, 1-SQ-507 and 1-SQ-508. Where applicable, pit depths were measured and confirmed to be acceptable by design documentation.
E-4