ML13067A401

American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection and Repair and Replacement Programs - Owners Activity Report for Cycle 9 Operation

ML13067A401
Person / Time
Site:	Browns Ferry
Issue date:	03/01/2013
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13067A401 (8)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 March 1, 2013 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259

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 9 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN),

American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for BFN, Unit 1, Cycle 9 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, Repair/Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission, Section Xl, Division 1.

The report is an overview of the inservice examination results that were performed on components within the ASME Section Xl boundary, up to and including the Unit 1 Cycle 9 refueling outage, during the second 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. The BFN, Unit 1, Cycle 9 refueling outage ended on December 4, 2012. Accordingly, this submittal is due by March 4, 2013.

AocVY

. "W.--

U.S. Nuclear Regulatory Commission Page 2 March 1, 2013 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. E. Emens, Jr., Nuclear Site Licensing Manager, at (256) 729-2636.

Resp ly, W. Shea Vice President, Nuclear Licensing

Enclosure:

American Society of Mechanical Engineers, Section Xl, Second 10-Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Cycle 9 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 I American Society of Mechanical Engineers,Section XI, Second 10-Year Inspection Interval Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs Owner's Activity Report for Cycle 9 Operation

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C9 Plant Browns Ferry Unit No.

1 Commercial service date 08/01/1974 Refueling outage no. 9 Current inspection interval 2nd Current inspection period 2nd FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number BFNU1C9 Plant Browns Ferry Nuclear Plant, PO. Box 2000, Decatur, AL 35609 Unit No.

1 Commercial service date August 1, 1974 Refueling Outage no.

Cycle 9 (Of applcatde)

Current Inspection Interval Second Ten Year Inspection Interval (ISf. 2nd. 3M. other)

Current Inspection Period Second Period (I 1t, 2nO. 3i01 Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Date and Revision of inspection plan 1-SI-4.6.G Revision 029 12/10/2012 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-586-1. N-613-1. N-648-1, N-686-1. N-695 Of ae0IaUt)

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 UIC conform to the uirements of Section Xl.

"(lreftno outlage

.nmber)

Signed Date

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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 in ananner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspection.

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FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C9 Plant Browns Ferry Unit No.

1 Commercial service date 08/01/1974 Refueling outage no.

9 Current inspection interval 2nd Current inspection period 2nd TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description F-A, Item F1.10C As-Found variable spring support EVALUATED ACCEPTABLE setting out-of-range. Range 9,815 to (No Corrective Measures Required.)

10,316 lbs. As-Found 10,622 lbs.

The as-found setting was (1-47B452-3038) [NOI U1RF9-002]

approximately 1/16 inch or 3% outside the specified spring setting range. The as-found setting was approximately at the mid-point of the spring economic range and well within the spring working range with considerable margin from topping or bottoming out.

The setting out-of range had no detrimental affect on the Residual Heat Removal (RHR) system piping or adjacent supports. The spring was reset to the range specified on the support drawing to restore the as-designed configuration.

F-A, Item F1.10C Loose bolting was found at two EVALUATED ACCEPTABLE locations on variable support.

(No Corrective Measures Required.)

(1-47B455-621) [NOI U1 RF9-003]

The loose nuts did not impair the ability of the support to carry the designed load. The loose nuts were tightened to prevent further loosening.

F-A, Item F1.10C Bolt in pipe clamp was loose. Nut was EVALUATED ACCEPTABLE tight on bolt.

(No Corrective Measures Required.)

(1 -47B465-455) [NOI U 1 RF9-004]

The loose bolt was one of four bolts on a pipe clamp. The other three bolts on the pipe clamp were tight. The nut on the loose bolt was tight and prevented the bolt from becoming dislodged. The support remained capable of performing its design function. The loose bolted connection was tightened.

F-A, Item F1.40C As-Found dual variable spring support EVALUATED ACCEPTABLE setting out-of-range. Range 9,949 to (No Corrective Measures Required.)

10,450 lbs. As-Found N-W spring The as-found setting was 10,497 lbs. and As-Found S-E spring approximately in the middle of the 10,747 lbs.

working range 7,616 lbs. to 12,376 lbs.

(1-47B415-44) [NOI UIRF9-005]

and did not top or bottom out. The setting out-of range had no detrimental affect on the Feedwater system piping or adjacent supports. The springs were reset to the range specified on the support drawing to restore the as-designed configuration.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C9 Plant Browns Ferry Unit No.

1 Commercial service date 08/01/1974 Refueling outage no.

9 Current inspection interval 2nd Current inspection period 2nd F-A, Item F1.20C As-Found dual variable spring support setting out-of-range. Range 5,916 to 6,166 lbs. As-Found both springs 5,750 lbs.

(1-47B452-3063) [NOI U1RF9-006]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The as-found setting was approximately in the middle of the working range 3,500 lbs. to 7,000 lbs.

and did not top or bottom out. The as-found setting was less than 2 increments outside the specified setting range, which is less than 3% of an acceptable load applied to the piping. The As-Found setting out-of range had no detrimental affect on the RHR system piping or adjacent supports. The springs were reset to the range specified on the support drawing to restore the as-designed conflauration.

F-A, Item F1.40B A loose bolt at welded attachment. Nut EVALUATED ACCEPTABLE is tight on bolt. Bolt can be rotated in (No Corrective Measures Required.)

place and is not tight against steel One bolt in a four bolt connection was member.

found loose on the lower support (RHRG-1-14-C) [NOI U1RF9-007]

bracket of the lC RHR Heat Exchanger. The lower support bracket provides only lateral support for the heat exchanger. Sufficient margin exists in the support design for the remaining bolts to carry all applied seismic forces. The loose bolt was tightened to restore the as-designed I configuration.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C9 Plant Browns Ferry Unit No.

1 Commercial service date 08/01/1974 Refueling outage no. 9 Current inspection interval 2nd Current inspection period 2nd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number 1-CLR-064-0071 Repair tube to header 3

1D RHR Room connection 04/18/2012 113413064 Cooler 1-HEX-074-0900ARe ar R plc 2

1A RHR Heat RepairtiReplace 11/12/2012 114083400 Exchanger partition plate

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number Plant Browi BFNUIC9 ns Ferry Unit No.

1 Commercial service date 08/01/1974 Refueling outage no.

9 Current inspection interval 2nd Current inspection period 2nd Summary of IWE Indications for UIC9 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, Item Moisture Seal Gouge in seal 1 The gouge did not The entire seal None E1.30 Barrier inch long and 1/2 penetrate the depth of the was examined.

MSB-1-1 inch deep.

seal. Function of the seal The damaged

[NOI U1 RF9-001]

to prevent moisture portion of the penetration was seal was maintained. The removed and damaged portion of the exposed drywell seal was excavated and liner visually repaired under Work examined Order 112592893.

(VT-3). No evidence of damage to the liner in this area I was observed.

I