ML20049J947

From kanterella
Jump to navigation Jump to search
Forwards Proposed Tech Specs Re 811113 OL Amend Application Correcting Revision Markings on Pages 2-68,2-68a & 2-70, Adding Pages 2-65 & 2-70a & Revising Pages 2-62,2-62a, 2-64 & 2-64a to Incorporate Numerical Changes
ML20049J947
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/22/1982
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Clark R
Office of Nuclear Reactor Regulation
Shared Package
ML20049J948 List:
References
LIC-82-117, NUDOCS 8203290247
Download: ML20049J947 (2)


Text

, o Omaha Public Power District 1623 HARNEY a OMAHA. NEBRASAA 60102 e TELEPHONE 536-4000 AREA CODE 402 March 22, 1982 LIC-82-117 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation C M M Pk (9, vision of Licensing s

w. 'N

( pe mting Reactors Branch No. 3 Washington, D.C. 20555 9 Dp ,,

tem,QI9E., f D

- w Y * /N;

Reference:

Docket No. 50-285 h

Dear Mr. Clark:

D@

The Omaha Public Power District submitted an application for amendment to the Fort Calhoun Station operating license, dated November 17, 1981, regarding operability requirements for the safety grade auxiliary feedwater automatic actuation system (AFAS). The District has recently completed a final optimization of the AFAS setpoints based upon a final analysis of the AFAS equipment and drift uncertainties by the vendor.

This setpoint optimization resulted in the revision of the previously submitted nominal setpoint values for the low steam generator water level, low steam generator pressure, and steam generator delta pressure initiation limits. The revision to the low steam generator level set-point also includes a change resulting from using a setpoint of 15.0%

for the safety analysis. The safety analysis setpoint was lowered from 35.0% to 15.0% to eliminate a problem with inadvertent actuation of the AFAS. The new limit of 28.2% still provides for acceptable AFAS re-sponse to ensure auxiliary feedwater is provided to the steam generator (s).

The following table provides a summary of the numerical changes:

Previous Value New Value Low Steam Generator Water Level Technical Specification Limit 60.0% 28.2%

Uncertainty 25.0% 13.2%

Safety Analysis Setpoint 35.0% 15.0%

Low Steam Generator Pressure Technical Specification Limit 488 psia 466.7 psia Uncertainty +53 psi +31.7 psi .co /

High Steam Generator Gelta Pressure Technical Specification Limit 88 psid 119.7 psid Uncertainty -47 psi -15.3 psi //

Please find attached revised Pages 2-62, 2-62a, 2-64, 2-64a, and a revised Discussion which incorporate these changes.

h$bb!

P 0 0

. - .= . - -. - . - - _ _ . - . . .-

Mr. Robert A. Clark LIC-82-117 Page Two l- Several Technical Specification pages from the District's November.17, 1981 submittal were incorrectly marked with the vertical black lines which indicate the revision (s) to the page. Accordingly, attached are correctly marked Pages 2-68, 2-68a, and 2-70. Additionally, Pages 2-65 and 2-70a of the Fort Calhoun Station Technical Specifications were impacted by the November 17, 1981 submittal but were unintentionally omitted from that submittal. The revisions to Pages 2-65 and 2-70a are required to reflect movement of the information in Table 2-6 of the present Technical Specifications to Table 2-3, with the subsequent

deletion of Table 2-6. Properly edited Pages 2-65 and 2-70a are at-tached for inclusion into the District's safety grade AFAS Technical Specification submittal.

Sincerely, l; /0Yk W. Cd Jones i Division Manager Production Operations WCJ/KJM/TLP/RWS:jmm 1

Attachments cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C. 20036 i

i f

I I I

I I

e

! i l  !

. , , - pn-- , . . , - - , - - , . , , , , - , , , . . .-