ML072560554

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Transmits Browns Ferry Unit 1, American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inspection (Iwe), & Repair & Replacement Programs - Summary Reports (NIS-1 & NIS-2) for Cycles 6 & 6
ML072560554
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 08/31/2007
From: Langley D
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NIS-1, NIS-2
Download: ML072560554 (5)


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Aabama 35609-2000 August 31, 2007 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop:

OWFN.PI-35 Washington, D.C. 20555-0001 Gentlemen:

in the Matter of

)

Docket No.

50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 1 -

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

SECTION XI, INSERVICE INSPECTION, SYSTEM PRESSURE TEST, CONTAINMENT INSPECTION (IWE),

AND REPAIR AND REPLACEMENT PROGRAMS SUMMtARY REPORTS (NIS-1 AND NIS-2)

FOR CYCLES 6 AND 6R OPERATION In accordance with paragraphs IWA-6220, IWA-6230, and IWA-6240 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, TVA is submitting BFN Unit 1 outage summary reports for NRC review.

The summary reports are for Inservice Inspection, System Pressure Test, (NIS-1 Report),

and Repair and Replacement activities (NIS-2 Report) for Unit 1 Cycle 6 operation.

Also included, in accordance with 10 CFR 50.55a, are areas of containment where indications were noted and subsequently evaluated for degradation.

The Cycle 6 refueling outage is the last outage in the third period of the first Inservice Inspection Interval.

The first Inservice Inspection Interval was suspended from 1984 until startup on June 2, 2007, due to an extended shutdown and subsequent recovery effort.

These outage summary reports (NIS-1 and NIS-2) contain the results of Cycle 6, the refueling outage in effect at the time of the Unit 1 extended shutdown, and Cycle 6R, the Unit 1 recovery

U.S. Nuclear Regulatory Commission Page 2 August 31, 2007 effort.

The first Inservice Inspection interval has been extended to June 2,

2008, in accordance with ASME Section XI, Subarticle IWA-2430(d).

The ASME Section XI Code of record for the BFN Unit 1 Cycle 6 refueling outage is the 1974 Edition with Addenda through Summer of 1975.

The ASME Section XI Code of record for Cycle 6R is the 1995 Edition with 1996 Addenda, as amended by 10 CFR 50.55a "Mandatory Limitations and Modifications."

ASME Section XI Code, Inservice examination, component selection remained in accordance with the 1974 Edition with Addenda through Summer of 1975.

TVA has determined that certain BFN Unit 1 components had nondestructive examination (NDE) coverage limitations (less than 90 percent coverage completed) which exceed that specified in NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements."

Specifically, three Reactor Pressure Vessel (RPV) longitudinal shell welds received ultrasonic examination (UT) coverage of less than essentially 100 percent (i.e.,

less than 90 percent).

Also, 39 piping welds received UT coverage less than essentially 100 percent.

In addition, 19 RPV nozzle-to-vessel welds and one RPV weld repair received UT examination coverage less than essentially 100 percent.

These examination limitations will be addressed by TVA in requests for relief and submitted to NRC for staff review and approval at a later date. of this letter contains the BFN Unit 1 Inservice Inspection, System Pressure Test, and Containment Inspection Summary Report (NIS-I) for Code Class 1 and 2 pressure retaining components and their supports.

contains the Repair and Replacement Summary Report (NIS-2) for Code Class 1 and 2 components and supports.

U.S. Nuclear Regulatory Commission Page 3 August 31, 2007 There are no new regulatory commitments in this letter.

If you have any questions regarding these reports, please contact me at (256) 729-2636.

Sincerel T. Langleyy Manager of Licensing and Industry Affairs Enclosures cc (see page 4)

U.S. Nuclear Regulatory Commission Page 4 August 31, 2007 Enclosures cc (Enclosures):

Mr. Tilda Y. Liu, Interim Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Ms.

Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

0 U.S. Nuclear Regulatory Commission Page 5 August 31, 2007 JEE:JWD:BAB Enclosures cc (w/o Enclosures):

R.

H. Bryan, Jr.,

LP 4J-C W. R.

Campbell, Jr., LP 6A-C J.

R.

Douet, LP 6A-C Samuel Flood, CMB IB-BFN (w/Enclosures)

J.

C.

Fornicola, LP 6A-C R.

G. Jones, POB 2C-BFN G.

V.

Little, POB 2C-BFN R.

F. Marks, PAB 1C-BFN D. C. Matherly, BFT 2A-BFN B.

J.

O'Grady, PAB IE-BFN S.

A. Vance, WT 6A-K E.

J. Vigluicci, ET IIA-K (w/Enclosures)

B.

A. Wetzel, BR 4X-C NSRB Support LP 5M-C EDMS WT CA-K (w/Enclosures)

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