ML12240A105

American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners Activity Report for Cycle 15 Operation

ML12240A105
Person / Time
Site:	Browns Ferry
Issue date:	08/24/2012
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12240A105 (8)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 August 24, 2012 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner's Activity Report for Cycle 15 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for Unit 3 Cycle 15 operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section Xl, Division 1."

The report is an overview of the results from inservice examinations that were performed on components within the ASME Section Xl boundary, up to and including the Unit 3 Cycle 15 refueling outage, during the second inspection period of the third 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. The Unit 3 Cycle 15 refueling outage ended on May 26, 2012. Accordingly, this submittal is due by August 24, 2012.

,197 Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 August 24, 2012 There are no new regulatory commitments in this letter. If you have any questions regarding this report, please contact Thomas A. Hess at (423) 751-3487.

Respectful 0.r I \\N.*h Vice President, Nuclear Licensing

Enclosure:

American Society of Mechanical Engineers,Section XI, Third 10-Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Cycle 15 Operation cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs Owner's Activity Report for Cycle 15 Operation (See Attached)

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3C15 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

15 Current inspection interval 3rd Current inspection period 2nd FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number BFNU3C15 Plant Browns Ferry Nuclear Plant. P.O. Box 2000. Decatur AL 35602-2000 Unit No.

3 Commercial service date March 1. 1977 Refueling Outage no.

Cycle 15 (if applimable)

Current Inspection Interval Third Ten Year Inspection Interval (Ist, 2nd. 3rd. Outer)

Current Inspection Period Second Period Ist, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition throuoh 2003 Addenda Date and Revision of inspection plan 3-SI-4.6.G, Revision 040 03/2812012 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan 2004 Edition Code Cases used: N-460. N-508-3. N-528-1. N-532-4. N-552, N-577, N-586-1. N-613-1. N-648-1. N-686-1. N-695. N-702 CU Wlapw.el)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of U3C15 conform to the requirements of Section Xt.

(relueong outage nunmbet)

Signed LintL oi t.. Date Li zC 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 Hartford. 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 requirement of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concerning the examinations, tests, repairs, replacements, evaluations, and corrective measures described In this report. Furthermore, neither the Inspector nor his employer shall be liable ie manner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspection.

Commissions 7A)J W1011 tn pectons $grnotne National Board, State. Province and Endorsenrents Date

• 4 42/'-

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3C15 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

15 Current inspection interval 3rd Current inspection period 2nd TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description F-A, Item F.10B Material deformation on the lower EVALUATED ACCEPTABLE washer and top of RPV Head Flange (No Corrective Measures Required.

due to an entrapped foreign object The identified condition was the result during a VT-1 examination, of entrapment of a small washer (RPV-WASH-3-50) [NO[ U3RF15-002]

between the RPV washer and the RPV Flange that resulted in an impression of the entrapped washer in the upper side of the RPV head Flange that is not a pressure boundary sealing surface. RPV Closure Head Assembly drawing 131855E states that surface finishes may have isolated tool marks or similar depressions provided they are minor in nature and are not on sealing surfaces used to seal pressure boundaries. The RPV Flange thickness is 2'-7"+/- 1/8". The impression caused by the entrapped washer was approximately 1/64" in depth. As a measure of good practice, the RPV washer was replaced.

F-A, Item FI.10C As-Found constant spring support EVALUATED ACCEPTABLE setting out-of-range. Range 8.7 +/- 1/2 (No Corrective Measures Required.

increment. As-Found 9.7 West Spring Piping movement from the cold set to and 9.9 East Spring.

hot position is upward and thermal (3-47B400-1 14) [NO[ U3CRF15-004]

movement is less than the available travel. The springs did not bottom out during service. The as-found settings represent the final position after pipe movement through the available travel of the springs during the last operating cycle. This support was repaired U3R14. These springs have limited travel range tolerance and are difficult to reset. Since the as-found cold set positions were near bottoming out, the springs were reset to the. cold set position to provide acceptable margin for continued operation.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNL Plant Browns Ferry Unit No.

3 Current inspection interv4 J3C15 Commercial service date 03/01/1977 Refueling outage no.

15 al 3rd Current inspection period 2nd TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number CODE CLASS 3 Through wall leak in Cut old piping out and 08/07/2011 Work Order 2.5" EECW piping replace with new pipe 112536582

(-1/2 gallon per minute)

CODE CLASS 2 Physical damage on STUDS/NUTS 05/09/2012 Work Order studs. Not service REPLACED 111044049 induced.

(3-FCV-074-0071)

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3C15 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

15 Current inspection interval 3rd Current inspection period 2nd Summary of IWE Indications for U3C15 The summary table below is provided in accordance with the requirements of 10 CFR 50.55a(b)(2)(ix)(A) and 10 CFR 50.55a(b)(2)(ix)(D).

Examination Component Indication Acceptability/Corrective Inaccessible Additional Category and Identifier Description Action Area Samples Item Number (Location and Evaluation)

E-A E1.11 Suppression Mechanical Engineering accept-as-is.

None None Chamber damage, dings, Conditions noted do not dents, minor impact structural integrity PSC EXT 3-B-1 corrosion, pitting, or leak tightness of the PSC EXT 3-B-2 scrapes, arc SCV. The conditions PSC EXT 3-B-3 strikes, weld identified are expected PSC EXT 3-B-4 deposit, chip based on the age and PSC EXT 3-B-5 marks, grind marks, service conditions of the PSC EXT 3-B-6 and minor surface SCV. None of the PSC EXT 3-B-7 indications, conditions noted were PSC EXT 3-B-8

[NOI U3RF15-005]

suspect. No detrimental PSC EXT 3-B-9 flaws have been PSC EXT 3-B-10 observed.

PSC EXT 3-8-11 PSC EXT 3-8-12 PSC EXT 3-8-13 PSC EXT 3-6-14 PSC EXT 3-B-15 PSC EXT 3-B-16

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3C15 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

15 Current inspection interval 3rd Current inspection period 2nd ATTACHMENT A The following welds were calculated to have ASME Section XI Code examination coverage 90 percent or less. TVA will submit a request for relief for these weld examinations in separate correspondence.

WELD ID CONFIG Limitation GR-3-63 Valve to Pipe single side exam 50%

DRHR-3-12 Valve to Flued Head single side exam 30%

RWCU-3-007-003 Pipe to Tee single side exam 57.85%

RWCU-3-007-011 Valve to Pipe single side exam 88.6%

N1B-NV Nozzle to Vessel joint geometry 25.27%

N4A-NV Nozzle to Vessel joint geometry 32.31%

N4B-NV Nozzle to Vessel joint geometry 32.38%

N4C-NV Nozzle to Vessel joint geometry 32.38%

N4D-NV Nozzle to Vessel joint geometry 32.31%

N4E-NV Nozzle to Vessel joint geometry 32.38%

N4F-NV Nozzle to Vessel joint geometry 32.38%

N9-NV Nozzle to Vessel joint geometry 27.96%

N10-NV Nozzle to Vessel joint geometry 74.10%

N10-IR Inner Radius joint geometry 90%