ML16021A066
| ML16021A066 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 01/21/2016 |
| From: | Walsh K Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16021A066 (6) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 January 21, 2016 10CFR 50.55a U.S. Nuclear Regulatory Commission ATTN; Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NFP-90 NRC Docket No. 50-390
Subject:
AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, SECOND 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 13 OPERATION The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME),Section XI, Owner's Activity Report for Unit 1 Cycle 13 operation as required by Article IWA-6000,Section XI, Division 1. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Cases N-532-4 and N-532-5, "Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission."
The report is an overview of the results from inservice examinations that were performed on components within the ASME Section XI boundary, up to and including the Unit 1 Cycle 13 refueling outage, during the third inspection period of the second 10-year inspection interval.
The applicable provisions of the ASME Code require that this report be submitted 90 days from the end of the applicable outage, i.e., by January 22, 2016.
U.S. Nuclear Regulatory Commission Page 2 January 21, 2016 There are no new regulatory commitments in this letter. Ifyou have questions regarding this letter, please call Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.
Respectfully, Kevin T. Walsh Site Vice President Watts Bar Nuclear Plant
Enclosure:
American Society of Mechanical Engineers,Section XI, Second 10-Year inservice Inspection Interval, Inservice Inspection Owner's Activity Report for Cycle 13 Operation cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1 NRR Project Manager - Watts Bar Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, SECOND 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 13 OPERATION
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U1C13 Plant WATTS BAR NUCLEAR PLANT, P.O. Box2000, Spring City. TN 37381-2000 Unit No.
1 Commercial servicedate May 27.1996 Refueling outageno.
U1C13 (Ifapplicable)
Current inspection interval 2nd (r, 2"". 3'. 4", other)
Current inspection period 3rd (1<< 2'3")
Edition and Addenda ofSection XI applicable totheinspection plans 2001 Edition. 2003 Addenda Date and revision of inspection plans October 23. 2015 / 1-TRI-0-10.2. Revision 14 Edition and AddendaofSection XI applicableto repair/replacement activities, ifdifferent than the inspection plans same Code Cases used:
N-460, N-526, N-532-4, N-532-5, N-566-2, N-586-1, N-578-1, N-624, N-685. N-686-1, N-700, N-706-1, N-722-1. N-729-1. N-731. N-753. andN-770-1 CERTIFICATE OF CONFORMANCE Icertify that(a)thestatements made In this report are connect; (b)the examinations and tests meetthe Inspection Planrequired by the ASME CodeXI and (c)the repair/replacement activities and evaluations supporting the completion of U1C13 conform to the requirements ofSectionXI.
, i
^
(refueling outage number) 4^ 7//V//4 owns;-. Design.,
/AhUcC
'J
" 'O CERTIFICATE OF INSERVICE INSPECTION I.the undersigned, holding a validcommissionissued bythe National Boardof Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. Connecticut have Inspectedthe itemsdescribed inthis Owner's Activity Report,and state that, to the best ofmyknowledge and belief, the Owner has performedallactivities represented by this report inaccordance withthe requirements ofSection XI.
Bysigningthiscertificate neitherthe Inspector norhisemployermake any warranty, expressed or implied, concerningthe repair/replacement activities and evaluationdescribed inthis report. Furthennore, neitherthe Inspectornor his employershall be liable in manner for personal Injury or property damage or a loss of any kind arising from or connected withthis inspection.
Commissions Hxl-z, National Board and Endorsements Date VWA'o ASME Code Section XI Exception - Reference TVA Condition Report 1124988,
Subject:
ASME Category B-G-1 (RPV studs and RCP hydrastuds).
Description:
Using EPRI guidance, tlie performance demonstration completed for these exams was not perfbnned as a "blindtesf as required by ASMESection XI, Appendix VIM, Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC-issued EGM-14-003 as sufficient technical basis for accepting the examinations.
Page E-1 of 3
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description None None None TAEiLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number E-A E1.30 Thermoshield, functioning as a Containment Moisture Barrier Repaired gouges and other minor physical damage incurred during outage work in Containment 10/16/15 Work Order (WO) 116640689 Page E-2 of 3
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 Cycle 13 refueling outage on the SCV Thermoshield in an accessible area was repaired by Work Order 116640689, "Repair of sheetmetal flashing in Reactor Building", and does not affect the degradation assessment for inaccessible areas. The conditions were documented in Notification of Indication N0I-U1R13-001, and are reported in Table 2 above.
Page E-3 of 3
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 January 21, 2016 10CFR 50.55a U.S. Nuclear Regulatory Commission ATTN; Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NFP-90 NRC Docket No. 50-390
Subject:
AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, SECOND 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 13 OPERATION The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME),Section XI, Owner's Activity Report for Unit 1 Cycle 13 operation as required by Article IWA-6000,Section XI, Division 1. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Cases N-532-4 and N-532-5, "Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission."
The report is an overview of the results from inservice examinations that were performed on components within the ASME Section XI boundary, up to and including the Unit 1 Cycle 13 refueling outage, during the third inspection period of the second 10-year inspection interval.
The applicable provisions of the ASME Code require that this report be submitted 90 days from the end of the applicable outage, i.e., by January 22, 2016.
U.S. Nuclear Regulatory Commission Page 2 January 21, 2016 There are no new regulatory commitments in this letter. Ifyou have questions regarding this letter, please call Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.
Respectfully, Kevin T. Walsh Site Vice President Watts Bar Nuclear Plant
Enclosure:
American Society of Mechanical Engineers,Section XI, Second 10-Year inservice Inspection Interval, Inservice Inspection Owner's Activity Report for Cycle 13 Operation cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1 NRR Project Manager - Watts Bar Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, SECOND 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 13 OPERATION
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U1C13 Plant WATTS BAR NUCLEAR PLANT, P.O. Box2000, Spring City. TN 37381-2000 Unit No.
1 Commercial servicedate May 27.1996 Refueling outageno.
U1C13 (Ifapplicable)
Current inspection interval 2nd (r, 2"". 3'. 4", other)
Current inspection period 3rd (1<< 2'3")
Edition and Addenda ofSection XI applicable totheinspection plans 2001 Edition. 2003 Addenda Date and revision of inspection plans October 23. 2015 / 1-TRI-0-10.2. Revision 14 Edition and AddendaofSection XI applicableto repair/replacement activities, ifdifferent than the inspection plans same Code Cases used:
N-460, N-526, N-532-4, N-532-5, N-566-2, N-586-1, N-578-1, N-624, N-685. N-686-1, N-700, N-706-1, N-722-1. N-729-1. N-731. N-753. andN-770-1 CERTIFICATE OF CONFORMANCE Icertify that(a)thestatements made In this report are connect; (b)the examinations and tests meetthe Inspection Planrequired by the ASME CodeXI and (c)the repair/replacement activities and evaluations supporting the completion of U1C13 conform to the requirements ofSectionXI.
, i
^
(refueling outage number) 4^ 7//V//4 owns;-. Design.,
/AhUcC
'J
" 'O CERTIFICATE OF INSERVICE INSPECTION I.the undersigned, holding a validcommissionissued bythe National Boardof Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. Connecticut have Inspectedthe itemsdescribed inthis Owner's Activity Report,and state that, to the best ofmyknowledge and belief, the Owner has performedallactivities represented by this report inaccordance withthe requirements ofSection XI.
Bysigningthiscertificate neitherthe Inspector norhisemployermake any warranty, expressed or implied, concerningthe repair/replacement activities and evaluationdescribed inthis report. Furthennore, neitherthe Inspectornor his employershall be liable in manner for personal Injury or property damage or a loss of any kind arising from or connected withthis inspection.
Commissions Hxl-z, National Board and Endorsements Date VWA'o ASME Code Section XI Exception - Reference TVA Condition Report 1124988,
Subject:
ASME Category B-G-1 (RPV studs and RCP hydrastuds).
Description:
Using EPRI guidance, tlie performance demonstration completed for these exams was not perfbnned as a "blindtesf as required by ASMESection XI, Appendix VIM, Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC-issued EGM-14-003 as sufficient technical basis for accepting the examinations.
Page E-1 of 3
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description None None None TAEiLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number E-A E1.30 Thermoshield, functioning as a Containment Moisture Barrier Repaired gouges and other minor physical damage incurred during outage work in Containment 10/16/15 Work Order (WO) 116640689 Page E-2 of 3
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 Cycle 13 refueling outage on the SCV Thermoshield in an accessible area was repaired by Work Order 116640689, "Repair of sheetmetal flashing in Reactor Building", and does not affect the degradation assessment for inaccessible areas. The conditions were documented in Notification of Indication N0I-U1R13-001, and are reported in Table 2 above.
Page E-3 of 3