ML20033A745
| ML20033A745 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/19/1981 |
| From: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| FVY81-166, NUDOCS 8111270211 | |
| Download: ML20033A745 (2) | |
Text
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VERMONT Y AN KEE NUCLEAR POWER CORPORATION
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SEVENTY SEVEN GROVE STREET RuTLAso, VERMONT 057O1 R E Pt.Y TO :
ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGHAM M ASSACHUSETTS 01701 TEl.EPHONE 817-872-8100 2.C.2.1 FVY81-166 November 19, 1981 United States Nuclear Regulatory Commission
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Washington, D.C.
20555 3-b P
Attention:
Office of Nuclear Reactor Regulation D
Mr. T. A. Ippolito, Chief
.cd NOV2 51981> _9 Operating *:eactors Branch #2 j.
Division of Licensing coussp4 g
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References:
(a) License No. DPR-28 (Docket No. 50-271).
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t (b) Vermont Yankee Proposed Change No. 98 (FVY 81-128), dated September 2, 1981.
(c) Vermont Yankee Proposed Change No. 98, Supplement 1 (FVY 81-160), dated November 13, 1981.
(d) Telecon, J. C. Voglewede (NRC) to S. P. Schultz, (VY),
November 9,1981.
7 l
(e) Letter, R. E. Engle (GE) to T. A. Ippolito (NRC),
f
" Extension of Emergency Core Cooling Sys^em
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Performance Limits," May 6, 1981.
(f) Letter, R. E. Engle (GE) to T. A. Ippoloito (NRC),
" Extension of Emergency Core Cooling System Performance Limits," May 28, 1981.
(g) Amendment No. 57, August 22, 1980.
Subject:
Additional Information on the Extension of Emergency Core Cooling System Performance Limits for Vermont Yankee
Dear Sir:
Reference (c) proposed an extension of emergency core cooling system limits (MAPLHGR limits) to higher applicable burnup ranges for specific Vermont Yankee fuel types. As stated in Reference (c), the limits were calculated by General Electric using methodology approved by the staff. This letter responds to Reference (d) in which the staff requested additional information regarding the applicability of these limits for Vermont Yankee in 00/
consideration of the NRC's models for enhanced fission gas release at high S
burnups. The specific information requested was a verification that the j
evaluation and assumptions made by General Electric in a generic response to
//o these concerns (References (e) and (f)) are appropriate and representative for Ve rmont Yankee.
t 8111270211 811119 PDR ADOCK 05000271 P
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U. S. Nuclear Regulatory Commission November 19, 1981 Page 2 We have reviewed the e-taluatien and analysis assumptions of the generic response and have determined that they are appropriate and representative for the Vermont Yankee analysis. This evaluation applies to the limits proposed for each Vermont Yankee fuel type as presented in Reference (c).
This evaluation also applies to the limits as approved for each Vermont Yankee fuel type as presented in Reference (g).
We trust this information is satisfactory; however, should you have any further questions, please contact us.
Very truly yourt,
VERMONT YANKEE N0 CLEAR POWER CORPORATION s
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R. L. Smith Licensing Engineer RLS/am
.