ML18039A771
| ML18039A771 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/03/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML18039A772 | List: |
| References | |
| TAC-M97805, NUDOCS 9905100090 | |
| Download: ML18039A771 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 May 3, 1999 Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT3-RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI REQUIREMENTS: RELIEF REQUEST 3-ISI-2 (TAC NO. M97805)
Dear Mr. Scalice:
By letter dated January 22, 1997, as supplemented by letter dated October 29, 1998, the Tehnessee Valley Authority (TVA)submitted a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, requirements for inservice inspection (ISI) of snubbers for the Browns Ferry Nuclear Plant (BFN), Unit 3, Second 10 year Interval ISI Program.
Currently, TVA is required to incorporate the 1989 Edition of the ASME Code,Section XI, as the governing document for the second 10-year ISI interval for BFN Unit 3. ASME Code,Section XI, Article IWF-5000, provides the ISI requirements for Code Class snubbers, including the requirement to examine and test the snubbers in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4 (OMa-1988, Part 4). The OMa-1988, Part 4 scope requires that all ASME Code Class 1, 2, and 3 snubbers be inspected and tested to Part 4 requirements.
However, requirements for the examination and functional testing of all safety-related snubbers to ensure their operability are also contained in the BFN Unit 3 Technical Requirements Manual (TRM) Section 3.7.4. The snubbers are already within the current TRM scope, but OMa-1988, Part 4 would require the creation of a separate program.
TVA has requested relief, that would allow the examination and testing of snubbers in accordance with TRM Section 3.7.4.
The staff has reviewed the information provided in support of TvA's relief request.
The staff's prdr/
evaluation and conclusions are contained in the Enclosure.
The staff finds that the use of the K='-tt'. QK CPifIF~>'f UefI"If 99'05i00090 990503 PDR ADOCK 050002'Pb P
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Mr. J. A. 5calice TRM program provides an acceptable.level'of safety and quality. Accordingly, the staff authorizes the use of such alternative pursuant to 10 CFR 50.55a(a)(3)(i).
Sincerely, Sheri R. Peterson, Chief, Section 2 Project. Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosure:
As stated cc w/encl: See next page
Mr. J. A. Scalice May 3, 1999 TRM program provides an acceptable level of safety and quality. Accordingly, the staff authorizes the use of such alternative pursuant to 10 CFR 50.55a(a)(3)(i).
Sincerely, Origixml signed by:
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. $0-296
Enclosure:
As stated ccw/encl: See next page DISTRIBUTION:
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