ML20010E937

From kanterella
Jump to navigation Jump to search
Forwards Evaluation of Reactivity Response for Steam Line Break Event W/Unterminated Emergency Feedwater Flow. Rept Analysis Demonstrates That Return to Criticality Will Not Occur.No Tech Spec or FSAR Changes Needed
ML20010E937
Person / Time
Site: Crystal River 
Issue date: 09/03/1981
From: Baynard P
FLORIDA POWER CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20010E938 List:
References
3-091-01, 3-91-1, NUDOCS 8109090158
Download: ML20010E937 (2)


Text

ko

~ p s

r

~

z M

P.o. w..,e_r September 3, 1981 e

^

h D

10 k#b#

3 9

h Mr. John F. Stolz, Chief

'E k c[ Q' Operating Reactors Branch #4

?

p Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

'/

s IG

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Rupture Matrix Signals

Dear Mr. Stolz:

Enclosed are forty (40) copies of the report " Evaluation of Reactivity Response For a Steam Line Break Event With Unterminated Emergency Feedwater Flow." This report provides an analysis which d' monstrates that a return to criticality will not occur.

No changes to the Technical Specifications or the FSAR are required.

This report satisfies the final concerns with respect to our June 2,1980, submittal, " Evaluation of Steam Line Break Con-sequences Associated With Renoval of Eupture Matrix Signals From Emergency Feedwater Valves," and Conmitment Item 51 in Enclosure B of our May 2,1980 submittal.

This report also satilifies the final concern of not isolating emergency feedwater via the rupture matrix stated in Florida Power Corpora-tion s response to Question 1 of I.E.Bulletin 80-04.

Florida Power Corpo-ration requests concurrence by October 15, 1981, as stated in our response to 1.E.Bulletin 80-04, to remove valves FWV-161 and FWV-162 from the rup-ture matrix actuation logic. A substantial improvement in secondary cooling relicbility can be achieved by removing the automatic actuation of these valves.

In letters dated June 18, 1980, and July 30, 1980, the NRC informed Florida Power Corporation that the evaluation of our June 2, 1980, submittal was subject to the requirements of 10 CFR 170.22, and requested a Class III fee 1

0109090158 810903 b

)(

h PDR ADOCK 05000302 P

PDR h \\

J General Office 32o1 inirty fourin street soutn. e o som 14o42. St. Petersburg. Flor da 33733 813-866-5151

}

Mr. John F. Stolz, Chief Page Two September 3; 1981 i

. of $4,000.

Then in a telephone conversation on July 31, 1980, between Mr. P. Erickson of-the NRC, and Mr. R. Bright of Florida Power Corporation, the payment of $4,000 was agreed to be provided when Florida Power Corporation submitted the final analysis. Enclosed is a check for $4,000.

Sincerely, Dr. P. Y. Baynard Manager

. Nuclear Support Services Enclosure Klein(MCS)Cl-1 l

l l

l l

l l

.