ML20212F075

Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii)

ML20212F075
Person / Time
Site:	Sequoyah
Issue date:	09/23/1999
From:	Peterson S NRC (Affiliation Not Assigned)
To:	Scalice J TENNESSEE VALLEY AUTHORITY
Shared Package
ML20212F082	List: ML20212F075 ML20212F083
References
TAC-MA5177, TAC-MA5179, NUDOCS 9909280020
Download: ML20212F075 (2)

Text

u n l

• - Mr. J.- Af Sc lice .

e Chief Nuclear Officer -

and Executive Vice President

< Tennessee Valley Authority

6A Lookout Place 1101 Market Street 1 Chattanooga, Tennessee 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR RELIEF FROM CERTAIN CODE INSPECTIONS (TAC NOS. MA5177 AND MA5179)

Dear Mr. Scalice:

' By letter dated October 21,1998, the Tennessee Valley Authority (TVA) submitted a request for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI (the Code) requirements for certain inservice inspections (ISls) at the

Sequoyah Nuclear Plant, Units 1 and 2. Specifically, TVA requested relief from the VT-3 visual examination of integrally welded attachments required by the applicable ASME Section XI Code for 1-inch and smaller auxiliary feedwater (AFW) piping ouring the second ISI interval for Sequoyah, Units 1 and 2. TVA has proposed adopting the 1991 Addenda to the 1989 Edition of the ASME Code,'Section XI, which exempts the visual examination of the subject attachments to 1-inch and smaller piping in the AFW system.

Based on our evaluation of the 1991 Addenda to the Code, we conclude that compliance with the 1989 ASME Code for the subject AFW system components would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore,

. on the basis of the enclosed Safety Evaluation, the U.S. Nuclear Regulatory Commission hereby grants relief pursuant to 10 CFR 50.55a(a)(3)(ii) for Sequoyah, Units 1 and 2, for the second ISI interval.

Sincerely,'

Ori@=1 signed by:

Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos: 50-327 and 50-328 DISTRIBUTION- @

Enclosure:

Safety Evaluation tDocket File 3 BCla OGC td@6 h GHill(4)

PUBLIC SPeterson ACRS RHernan SQN R/F MSatorius PFredrickson, Ril cc w/ enclosure: See next page HBerkow TSullivan ' PPatniak RScholl(e-mail RFS)

DOCUMENT NAME: G:\PDil-2\SQN\ RELA 6177.wpd

• See previous concurrences I l

To receive a copy of this document, indicate in the box: "C" = Copy without attachmentlenclosure "E" = Copy with attachment / enclosure "N" = No copy

- l OFFICE PDil-2/PM, PDll-2/LA l OGC l PDil-2/SG-[G o\

RHernanMBelayton* ETD for lNAME lDATE 9/3 3/99' 9/21/99 SUttal*

9/23/99 SPetersoh" '

9 / D/99 Official Record Copy 1 P y P pg -

f f %, l l e t UNITED STATES

, g  ; NUCLEAR REGULATORY COMMISSION i 2 WASHINGTON, D.C. 20M1

• • • • • p' September 23, 1999 j

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:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR RELIEF l FROM CERTAIN CODE INSPECTIONS (TAC NOS. MA5177 AND MA5179)

Dear Mr. Scalice:

By letter dated October 21,1998, the Tennessee Valley Authority (WA) submitted a request for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI (the Code) requirements for certain inservice inspections (ISIS) at the Sequoyah Nuclear Plant, Units 1 and 2. Specifically, TVA requested relief from the VT-3 visual l

examination of integrally welded attachments required by the applicable ASME Section XI Code '

for 1-inch and smaller auxiliary feedwater (AFW) piping during the second ISI interval for Sequoyah, Units 1 and 2. WA has proposed adopting the 1991 Addenda to the 1989 Edition of the ASME Code,Section XI, which exempts the visual examination of the subject attacl:ments to 1-inch and smaller piping in the AFW system.

Based on our evaluation of the 1991 Addenda to the Code, we conclude that compliance with '

the 1989 ASME Code for the subject AFW system components would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, on the basis of the enclosed Safety Evaluation, the U.S. Nuclear Regulatory Commission hereby grants relief pursuant to 10 CFR 50.55a(a)(3)(ii) for Sequoyah, Units 1 and 2, for the second ISI interval.

Sincerely, k Ah,\

Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosure:

Safety Evaluation cc w/ enclosure: See next page I