ML19345F535
| ML19345F535 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/11/1981 |
| From: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| FVY-81-25, NUDOCS 8102180270 | |
| Download: ML19345F535 (3) | |
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- VERMONT YAN KEE NUCLEAR POWER CORPOR ATION SEVENTY sEVEN GROVE STREET U
RUTLAND, VERMONT 05701 FVY 81-25
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REPLY TO:
t-ENGINEERING OFFICE February 11, 1961 1671 WORCESTER ROAD FRAMINGH AM. MASSACHUSETTS o17ot TELEPHONE 617 872-etoo United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) USNRC letter dated November 24, 1980, Fire Protection Open Items (c) VYNPC letter WVY 80-43, dated March 14, 1980,
Subject:
Supplemental Safety Evaluation Report S ubj ect: Fire Protection Open Items D ear Sir: to Reference (b) above summarized the staff requirements to resolve several fire protection open items. We have reviaved that summary, and have the following comments on two items.
Item 3.2.3, Fire Water Loop Previous NRC requests were for the results of calculations, not for the calculations themselves. As the staff feels that more information is needed for review, additional information is attached here as Attachment 1.
We feel that your further review will result in the conclusion that one discharge main does not need to be relocated, and tha* this item should be considered closed. However, if the staff should decide that more discussion is necessary, we would be glad to discuss this matter with you, by telephone or in person, at your convenience.
I tem 3.2.4, Prima y Containment Analysis As you are aware, Vermont Yankee may soon have an inerted containment during normal operation. In addition, Vermont Yankee currently pro" ides standpipe and hose stations outside the drywell with adequate lengths of hose to reach any location of concentrated combustibles inside the drywell. Calculations have been perforned and are available wi'ich document this fact.
We, therefore, feel hat. Vermont Yankee me< *.s Appendix R for this item.
8102180c?-7 0
e United States Nuclear Regulatory Commission February 11, 1981 A t ten tion :
Mr. Thomas A. Ippolito. Chief Page 2 If after the review of the above information you have any further questions or comments, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATIO!1 R. L. Smith Licensing Engineer
o Attachment I c
Our analysis of the fire water discharge lines assumed a simple spanned beam configuration supporting a ten foot column of soil coupled wich the required design conditions for this piping.
The results of our analysis indicate that a thirty foot span of this piping would be acceptable, i.e.,
could be tolerated without failure of the piping.
The probability of washing out the soil underneath this pipe over a thirty foot length without the event being noticed is very unlikely. We believe that if one of these pipes fail, tn e condition would be revealed by sinking of the ground surface above the pipe, and that this condition would be noticed and appropriate action taken before a washout exceeding the allowable thirty foot span could occur. Therefore, we feel that the fire water discharge lines, as designed, present no problem from a safety standpoint.
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