ML13101A120: Difference between revisions
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| issue date = 04/08/2013 | | issue date = 04/08/2013 | ||
| title = Refueling Outage 18 - 90-Day Inservice Inspection Summary Report | | title = Refueling Outage 18 - 90-Day Inservice Inspection Summary Report | ||
| author name = Shea J | | author name = Shea J | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
| addressee name = | | addressee name = | ||
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=Text= | =Text= | ||
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 8, 2013 10 CFR 50.4 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 | {{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 8, 2013 10 CFR 50.4 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:== | ==Subject:== | ||
Unit 2 Refueling Outage 18 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, 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 18 (U2R18). The U2R18 refueling outage ended on January 6, 2013. Accordingly, this report is required to be submitted by April 8, 2013. The report 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 repairs, replacements, or corrective measures required for continued service (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). | Unit 2 Refueling Outage 18 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, 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 18 (U2R18). The U2R18 refueling outage ended on January 6, 2013. Accordingly, this report is required to be submitted by April 8, 2013. The report 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 repairs, replacements, or corrective measures required for continued service (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). | ||
There are no regulatory commitments associated with this submittal. | There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty (423) 843-7170. | ||
Should you have any questions, please contact Mike McBrearty (423) 843-7170.R~espectf J. . | R~espectf J. .WShea V~ President, Nuclear Licensing | ||
==Enclosure:== | ==Enclosure:== | ||
ASME Section Xl Inservice Inspection Summary Report, Unit 2 Refueling Outage 18 cc (Enclosure): | |||
NRC Regional Administrator- Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant Apt/ | |||
Printed on recycled paper | |||
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 2 ASME SECTION XI INSERVICE INSPECTION | |||
==SUMMARY== | ==SUMMARY== | ||
REPORT UNIT 2 REFUELING OUTAGE 18 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number U~2C1 8 Plant | REPORT UNIT 2 REFUELING OUTAGE 18 | ||
Commercial service date June 1, 1982 Refueling outage no.18 Current inspection interval | |||
114.3, Revision 18 Edition and Addenda of Section XI applicable to repair/replacement activities, | FORM OAR-I OWNER'S ACTIVITY REPORT Report Number U~2C1 8 Plant SEQUOYAH NUCLEAR PLANT, P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Unit No0. 2 Commercial service date June 1, 1982 Refueling outage no. 18 (if applicable) | ||
_____ _____ ____ Commissions 116 (13912 A4 /y, | Current inspection interval Third Inspection Interval (1-, 2'-, 3'-. 4", other) | ||
Current inspection period Third Ins ection Period Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans August 15, 2011 SI-DXI-000. 114.3, Revision 18 Edition and Addenda of Section XI applicable to repair/replacement activities, ifdifferent 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 U2C18 conform to the requirements of Section Xl. (refueling outage number) | |||
Signed 1 -i~ -- /fZ.., S~ , r- 0 Date Owner or Owner'd 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 HSB CT 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 hisemployer 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 ma r personal injury or property damage or a loss of any kind arising from or connected with.this inspection. | |||
_____ _____ ____ Commissions 116 (13912 A4/y, T,' qI2y 2/ | |||
( Inspectors Signature National Board, State. Province, and Endorsements Date (//c/ | |||
E-1 | |||
ASME SECTION XI INSERVICE INSPECTION | |||
==SUMMARY== | ==SUMMARY== | ||
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 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 | REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 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 Mechanical Damage on SCV discovered Engineering as-is. evaluation, Pit depth acceptable measurements and E-A, El. 11 during IWE examination. (NOls 2-SQ-420 dsign documenscrmed and 421) design documents acceptability confirmed of flaws. | ||
E-2 | |||
ASME SECTION XI INSERVICE INSPECTION | |||
==SUMMARY== | ==SUMMARY== | ||
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE E-3 ASME SECTION XI INSERVICE INSPECTION | REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE E-3 | ||
ASME SECTION XI INSERVICE INSPECTION | |||
==SUMMARY== | ==SUMMARY== | ||
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A) | REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A) | ||
ASME Section Xl, 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 2 Cycle 18 refueling outage on the SCV in an accessible area was determined to be acceptable and does not affect the degradation assessment for inaccessible areas.E-4}} | ASME Section Xl, 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 2 Cycle 18 refueling outage on the SCV in an accessible area was determined to be acceptable and does not affect the degradation assessment for inaccessible areas. | |||
E-4}} | |||
Latest revision as of 20:40, 4 November 2019
| ML13101A120 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/08/2013 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13101A120 (6) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 8, 2013 10 CFR 50.4 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 Refueling Outage 18 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, 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 18 (U2R18). The U2R18 refueling outage ended on January 6, 2013. Accordingly, this report is required to be submitted by April 8, 2013. The report 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 repairs, replacements, or corrective measures required for continued service (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).
There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty (423) 843-7170.
R~espectf J. .WShea V~ President, Nuclear Licensing
Enclosure:
ASME Section Xl Inservice Inspection Summary Report, Unit 2 Refueling Outage 18 cc (Enclosure):
NRC Regional Administrator- Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant Apt/
Printed on recycled paper
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 2 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT UNIT 2 REFUELING OUTAGE 18
FORM OAR-I OWNER'S ACTIVITY REPORT Report Number U~2C1 8 Plant SEQUOYAH NUCLEAR PLANT, P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Unit No0. 2 Commercial service date June 1, 1982 Refueling outage no. 18 (if applicable)
Current inspection interval Third Inspection Interval (1-, 2'-, 3'-. 4", other)
Current inspection period Third Ins ection Period Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans August 15, 2011 SI-DXI-000. 114.3, Revision 18 Edition and Addenda of Section XI applicable to repair/replacement activities, ifdifferent 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 U2C18 conform to the requirements of Section Xl. (refueling outage number)
Signed 1 -i~ -- /fZ.., S~ , r- 0 Date Owner or Owner'd 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 HSB CT 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 hisemployer 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 ma r personal injury or property damage or a loss of any kind arising from or connected with.this inspection.
_____ _____ ____ Commissions 116 (13912 A4/y, T,' qI2y 2/
( Inspectors Signature National Board, State. Province, and Endorsements Date (//c/
E-1
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 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 Mechanical Damage on SCV discovered Engineering as-is. evaluation, Pit depth acceptable measurements and E-A, El. 11 during IWE examination. (NOls 2-SQ-420 dsign documenscrmed and 421) design documents acceptability confirmed of flaws.
E-2
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE E-3
ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 18 REFUELING OUTAGE REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
ASME Section Xl, 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 2 Cycle 18 refueling outage on the SCV in an accessible area was determined to be acceptable and does not affect the degradation assessment for inaccessible areas.
E-4