ML18039A688
| ML18039A688 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 02/23/1999 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML18039A689 | List: |
| References | |
| TAC-MA1971, NUDOCS 9903010198 | |
| Download: ML18039A688 (4) | |
Text
Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 February 23, 1999
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT2 - SECOND 10-YEAR INTERVAL INSPECTION - RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI REQUIREMENTS: RELIEF REQUEST 2-ISI-6 (TAC NO. MA1971)
Dear Mr. Scalice:
By letter dated April 3, 1998, the Tennessee Valley Authority submitted a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI (the Code) requirements.
This request for relief, No. 2-ISI-6, pertains to the Second 10-Year Interval Inservice Inspection for the Browns Ferry Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission (NRC) staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL) has reviewed and evaluated your submittal.
Based on its review, the NRC staff has determined, regarding Request for Relief No. 2-ISI-6, that the Code requirements are impractical and relief is granted pursuant to 10 CFR 50.55a(g)(6)(i).
Granting the relief is authorized by law, willnot endanger life, property, or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result ifthe requirements were imposed.
The Enclosure documents our evaluation and conclusions for the request for relief. The Enclosure also includes the INEELTechnical Letter Report.
Docket No. 50-260
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Sincerely, Original sigueti %-
Cecil O. Thomas, Jr., Project Director Project Directorate II-3 Division of Licensing Project Management Office of Nuclear Reactor Regulation DISTRIBUTION:
~.ocket-F-iles GHill (2)
ADeAgazio BClayton CNorsworthy (RCN)
PUBLIC OGC JZwolinski ACRS MTschiltz LRaghavan BFN R/F TMcLellan GGeorgiev LWert, Rll DOCUMENT NAME: G:FBFN>RELA1971 To receive a copy of this docunent, indicate in the box:
"C" = Copy without attachment/enclosure "E" = Copy uith attachment/enclosure aN" = No copy
- See revio OFFICE NAME DATE PDII-3:PM LRaghavan 02/
/99 E
PD II-3: LA BCIa ton 2/ 'L 5/99 E
~ OGC MYoung 2/4/99 OFFICIAL RECORD COPY P
0
/99 99030iOi PB 990223 PDR ADGCK 05000260 8
[LL U
I I
P C
J U
gyes R500 Wp0 Op
- 0O
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 Febnjary 23, 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 E
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT2 - SECOND 10-YEAR INTERVAL INSPECTION - RELIEF FROM ASME BOILER AND PRESSURE VESSEL
~
CODE, SECTION XI REQUIREMENTS: RELIEF REQUEST 2-ISI-6 (TAC NO. MA1971)
Dear Mr. Scalice:
By letter dated April 3, 1998, the Tennessee Valley Authority submitted a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI (the Code) requirements.
This request for relief, No. 2-ISI-6, pertains to the Second 10-Year Interval Inservice Inspection for the Browns Ferry Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission (NRG) staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL) has reviewed and evaluated your submittal.
Based on its review, the NRC staff has determined, regarding Request for Relief No. 2-ISI-6, that the Code requirements are impractical and relief is granted pursuant to 10 CFR 50.55a(g)(6)(i).
Granting the relief is authorized by law, willnot endanger life, property, or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden. upon the licensee that could result ifthe requirements were imposed.
The Enclosure documents our evaluation and conclusions for the request for relief. 'he Enclosure also includes the INEELTechnical Letter Report.
, Sincerely, C~w,.
Cecil O. Thomas, Jr., Project Director Project Directorate II-3 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-260
Enclosure:
Safety Evaluation cc w/enclosure:
See next page
J