B12556, Clarifies 861231 Application to Amend License DPR-61, Revising Tech Specs Re Significance of Value Represented as Three Loop Power Level,Per NRC Request

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Clarifies 861231 Application to Amend License DPR-61, Revising Tech Specs Re Significance of Value Represented as Three Loop Power Level,Per NRC Request
ML20215A902
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 06/09/1987
From: Mroczka E
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
B12556, NUDOCS 8706170133
Download: ML20215A902 (2)


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CONNECTICUT YANKEE ATO MIC POWER COMPANY B E R L I N, CONNECTICUT P.o. Box 270

  • HARTFORD, CONNECTICUT 061414270 2[".[ June 9,1987 Docket No. 50-213 Bj2556 I Re: 10CFR50 U. S. Nuclear Regulatory Commission l Attn: Document Control Desk Washington, D. C. 20555

Reference:

(1) E. J. Mroczka letter to C.1. Grimes, Proposed Revision to Technical Specifications on Reactor Coolant System, dated December 31,1986. I Gentlemen:

Haddam Neck Plant Clarification to Information, Proposed Revision to Technical Specifications As a result of the Staff's review of Reference (1) a request was made to clarify the significance of a value represented as the three loop power level which appeared in the third paragraph of page 2. Quoted, the paragraph reads as i follows: l "The revised vessel flow rate of 197,200 gpm was also evaluated for the impact on the three loop safety analysis. The three loop safety analysis was performed at a power level of 86% and an inlet temperature of 5480F. The DNBR sensitivities to core flow rate and power level, discussed above, were used to show that the conservative power level of 86% versus 67% more than compensates for the reduction in core flow rate. The reduction in DNBR due to the flow reduction was 4%, while the incease in DNBR due to the drop in power-level was 36%. Therefore, the three loop analyses remain conservative for the current operating conditions."

The 67% power level referred to in this paragraph represents the Haddam Neck Plant's nominal licensed three loop power level plus 2%. The 2% difference accounts for assumed instrument uncertainties associated with instruments required in determining core power level. For the purpose of analyses, the comparison made in the above quoted paragraph is conservative and proper.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY Ne- M E. 3DAfo6zka /

8706170133 870609 Senior Vice President

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'slon B12556/Page June 9,1987 cc:- _ W. T. Russell, Region 1 Administrator F. M. Akstulewicz, NRC Project Manager, Haddam Neck Plant -

P. D. Swetland,' Resident Inspector, Haddam Neck Plant Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, CT ,06116 l

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