ML20004B612: Difference between revisions

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I TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENN ESSEE 37401 400 Chestnut Street Tower II                       g s     r- %
TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENN ESSEE 37401 400 Chestnut Street Tower II g
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MAY 2 Q,1981 * -^
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Mr. Harold R. Denton, Dimotor
~J MAY 2 Q,1981 * ^
* 31 Offio of Nuclear Reactor Regulation                                           "'" EnTs/ " 49'f U.S. Nuolear Regulatory Commission                                                           ,@
Mr. Harold R. Denton, Dimotor 31 Offio of Nuclear Reactor Regulation
Washington, DC 20555                                                                         V/
"'" EnTs/ " 49'f U.S. Nuolear Regulatory Commission Washington, DC 20555 V/
4   &
4 Dear Mr. Dentons In the Matter of the Application of
Dear Mr. Dentons In the Matter of the Application of             )         Dooket, Nos. 50-327 Tennessee Valley Authority                     )                       50-328 As agreed with Edson Case during our telephone conversation of May 22, 1981, TVA will provide a report by October 1,1981 that identifies and                     .
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justifies, based on a plant specific evaluation, differences between existing or proposed fire protection features of Sequoyah 1 and 2 and those features specified in sections III.G, III.J, and III.0 of Appendix R to 10 MR Part 50. A schedule for implementing any modifications to the fire prvtection features of Sequoyah 1 and 2, as a result of the evaluation, including proposed modification 9 requiring prior NRC approval as specified in 50.48(o) of 10 CFR Part 50 will also be provided. Differences in implementation schedule and the schedule for implementing fire protection modifications en other operating plants specified in 50.48(o) will be justified.
Dooket, Nos. 50-327 Tennessee Valley Authority
Very ' July yours, TEIGIESSEE VALLEY AttfBORITY fQV L. M. Mills,
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                                                                      'I or Nuclear Regulation and Safety Sworn to and subsor' bed before as this.8dddayo           Avf r1981
50-328 As agreed with Edson Case during our telephone conversation of May 22, 1981, TVA will provide a report by October 1,1981 that identifies and justifies, based on a plant specific evaluation, differences between existing or proposed fire protection features of Sequoyah 1 and 2 and those features specified in sections III.G, III.J, and III.0 of Appendix R to 10 MR Part 50. A schedule for implementing any modifications to the fire prvtection features of Sequoyah 1 and 2, as a result of the evaluation, including proposed modification 9 requiring prior NRC approval as specified in 50.48(o) of 10 CFR Part 50 will also be provided. Differences in implementation schedule and the schedule for implementing fire protection modifications en other operating plants specified in 50.48(o) will be justified.
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Very ' July yours, TEIGIESSEE VALLEY AttfBORITY fQV
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'I L. M. Mills, or Nuclear Regulation and Safety Sworn to and subsor bed before as this.8dddayo Avf r1981
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Latest revision as of 12:40, 23 December 2024

Confirms That Util Will Provide Rept by 811001 Identifying & Justifying Differences Between Existing or Proposed Fire Protection Features of Facilities & Sections Iii.G,J & O of App R to 10CFR50
ML20004B612
Person / Time
Site: Sequoyah  
Issue date: 05/26/1981
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8105290168
Download: ML20004B612 (1)


Text

.

TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENN ESSEE 37401 400 Chestnut Street Tower II g

i s

r-C II

$h

^

~J MAY 2 Q,1981 * ^

Mr. Harold R. Denton, Dimotor 31 Offio of Nuclear Reactor Regulation

"'" EnTs/ " 49'f U.S. Nuolear Regulatory Commission Washington, DC 20555 V/

4 Dear Mr. Dentons In the Matter of the Application of

)

Dooket, Nos. 50-327 Tennessee Valley Authority

)

50-328 As agreed with Edson Case during our telephone conversation of May 22, 1981, TVA will provide a report by October 1,1981 that identifies and justifies, based on a plant specific evaluation, differences between existing or proposed fire protection features of Sequoyah 1 and 2 and those features specified in sections III.G, III.J, and III.0 of Appendix R to 10 MR Part 50. A schedule for implementing any modifications to the fire prvtection features of Sequoyah 1 and 2, as a result of the evaluation, including proposed modification 9 requiring prior NRC approval as specified in 50.48(o) of 10 CFR Part 50 will also be provided. Differences in implementation schedule and the schedule for implementing fire protection modifications en other operating plants specified in 50.48(o) will be justified.

Very ' July yours, TEIGIESSEE VALLEY AttfBORITY fQV

'I L. M. Mills, or Nuclear Regulation and Safety Sworn to and subsor bed before as this.8dddayo Avf r1981

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