ML20033A970
| ML20033A970 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/19/1981 |
| From: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.145, RTR-REGGD-1.145, TASK-02-02.C, TASK-2-2.C, TASK-RR NUDOCS 8111300235 | |
| Download: ML20033A970 (2) | |
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Director of Nuclear Reactor Regulation Attn:
Mr. Dennis M. Crutchfield, Chief N
Operating Reactors Branch #5 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
(1)
D. M. Crutchfield letter to W, G. Counsil, dated September 29, 1981.
(2)
W. G. Counsil letter to D. M. Crutchfield, dated May 19, 1981.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 SEP Topic II-2.C, Atmospheric Transport and Diffusion Characteristics for Accident Analysis Via Reference (1), the Staff forwarded the evaluation for SEP Topic II-2.C, Atmospheric Transport and Diffusion Characteristics for Accident Analysis, for Millston? Unit No. 1.
Reference (1) was based upon the Staff's review of the Safety Assessment Report (SAR) submitted by Northeast Nuclear Energy Company (NNECO) in Reference (2).
NNECO has reviewed Reference (1) and offers the following comments.
In Section V, second paragraph, third sentence, it is stated that "the wind speed and wind direction were measured at the 10m (33 f t) and 114m (374 ft) levels." This is incorrect, as wind speed and wind direction were measured at the 10m (33 f t) and 136m (446 ft) levels.
The letter forwarding the Reference (1) evaluation indicates that the Staf f's values do not agree with the values submitted in Reference (2) and that possible reasons for the lack. of agreement are included in the Staff's evaluation. However, no explanation or reasoning was given in Reference (1).
8111300235 8i1119 DR ADOCK 05000245 PDR L
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Reference (1) also states that "The Staff values are more conservative and are thought to be more in agreement with the guidance presented in Regulatory Guide 1.145.
NNECO ?.grees that the Staff values are more conservative, however, they are not necessarily more in agreement with the guidance of Regulatory Guide 1.145.
The Staff has not pro-vided a basis for this statement in Reference (1) or in telephone conversations with NNECO.
NNECO maintains that the values submitted in Reference (2) are in accordance with the guidance of Regulatory Guide 1.145.
NNECO has concluded that the Staff's values presented in Reference (1) are acceptable for use in accident calculations. The balance of the Staff's evaluation is factually correct.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Yht1/k W. G. Counsil Senior Vice President t.