ML18036A476
| ML18036A476 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/12/1991 |
| From: | Williams J Office of Nuclear Reactor Regulation |
| To: | Nauman D TENNESSEE VALLEY AUTHORITY |
| References | |
| TAC-M80618, TAC-M80619, TAC-M80620, NUDOCS 9112160218 | |
| Download: ML18036A476 (7) | |
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RE VEST FOR ADDITIONAL INFORMATION BROWNS FERRY NUCLEAR PLANT UNITS I 2
AND 3 DOCKET NOS. 50-259 50-260 AND 50-296 2 ~
On Page 8 of the Reference, it is stated that "TVA has demonstrated com-pliance of the design criteria with the FSAR requirements."
(a)
Identify and provide the specific FSAR requirements.
(b)
Discuss if the FSAR requirements cover steel platforms as well as miscellaneous steel.
If not, please provide the applicable requirements.
(c)
Descr ibe how the design criteria submitted in the Reference satisfy each FSAR requirement.
(d)
Provide examples for key items demonstrating compliance of your proposed criteria with the applicable FSAR requirements.
Does miscellaneous steel mean structural steel other than lower drywell steel platforms at elevations 566'nd 584'9k"? If so, are the criteria shown in FSAR Table 12.2-13 the criteria for miscellaneous steel?
3.
If not, provide a comprehensive discussion as to what the miscellaneous steels are and where in the FSAR applicable cr iteria are provided.
Do the discussions on Page 7 of the reference apply to both steel platforms and miscellaneous steel with regard to compliance with FSAR requirements?
If not, provide compliance-related discussions and examples for the miscellaneous steel (see guestion I).
4.
Provide a discussion for ductility ratio usage, including:
(a)
An exact definition with illustrative examples.
(b)
Bases for use of ductility ratio in terms of physical test data and analytical demonstration regarding ductility ratio associated with collapse mechanism (or other failure mechanism of various structures).
Describe how such ductility ratios are calculated and why the calculation methodology is reliable, including any experimental bases.
Also discuss the impact of your ductility ratio usage on structural design safety margins compared to the margins which would be provided if the applicable FSAR requirements and criteria were strictly followed.
(c)
Provide any specific references where the NRC staff approved such usage in the past.
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Mr. Dan A. Nauman CC:
Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. John B. Waters, Director Tennessee Valley Authority ET 12A 400 West Summit Hi11 Drive Knoxvi11e, Tennessee 37902 Mr. W. H. Kennoy, Director Tennessee Valley Authority ET 12A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. W. F. Willis Senior Executive Officer ET 12B 400 West Summit Hill Drive Knoxville, Tennessee 37902 General Counsel Tennessee Valley Authority ET llH 400 West Summit Hi 11 Drive Knoxvilie, Tennessee 37902 Mr. Dwight Nunn Vice President, Nuclear Projects Tennessee Valley Authority 3B Lookout P lace 1101 Market Street Chattanooga, Tennessee 37402-2801 Dr. Mark 0. Medford Vice President,. Nuclear Assurance Licensing and Fuels Tennessee Valley Authority 6B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. Edward G. Wallace
- Manager, Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority 5B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. 0. J. Zeringue, Site Vice President Browns Ferry Nuclear Plant Tennessee Va11ey Authority P. 0.
Box 2000
- Decatur, Alabama 35609 Mr. R.
R. Baron, Site Licensing Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35609 Mr. J.
A. Scalice, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35609
- Chairman, Limestone County Commission P. 0.
Box 188
- Athens, Alabama 35611 Claude Earl Fox, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Route 12, Box 637
- Athens, Alabama 35611 Tennessee Valley Authority Rockville Office 11921 Rockville Pike Suite 402 Rockv i 1 le, Maryland 20852
Distribution NRC PDR Local PDR S.
Varga G. Lainas F.
Hebdon B. llilson P. Kellogg C. Patterson M. Sanders J. Williams T. Ross D. Moran OGC D. Jeng ACRS (10)
BFN Rdg. File L. Reyes cc:
Plant Service list 14-E-4 14-H-3 RII RII RII 15-B-18 RII
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