ML20132E536
| ML20132E536 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 09/16/1985 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 0643K, 643K, NUDOCS 8510010111 | |
| Download: ML20132E536 (2) | |
Text
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O Address Reply to: Post Othee Box 767 chicago. Illinois 60690 September 16, 1985 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Initial Test Program NRC Docket Nos. 50-454,.50-455, 50-456 and 50-457 Reference (a): August 1, 1985 letter from L. O.
DelGeorge to J. G. Keppler
Dear Mr. Keppler:
This is to -inform you of a change to the Initial Test Program described in Chapter 14 of the FSAR in accordance with Byron Unit 1 Operating License NPF-37 Condition 2.C.(3). The change was made effective on August 20, 1985 and was initiated as corrective action-for violation la described in reference (a).
Attached is FSAR Table 14.2-78, " Control Rod Reactivity Worth Measurement," which has been revised to more clearly indicate the testing limitations associated with validating rod worths in the Westinghouse Nuclear Design Report.
We have determined that this change does not involve an unreviewed safety question because it is only an editorial change that does not affect the initial commitment in the FSAR with regard to physics testing. The bases for all Technical Specifications remain the same and the margin of safety is not affected.
One signed original and thirty-nine (39) copies of this letter and attachment are provided for your use. Please direct any questions regarding
'this matter to this office.
85 003 Very truly yours, i
A P
54 PDR 5
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K. A. Ainger d '*
Nuclear Licensing Administrator Attachment
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cc: Director of Inspection and Enforcement Byron Resident Inspector L-
I B/B-F57 I.!!E: DMT:IT 4 0 NOVEMBER 1982 TABLE 14.2-78 cot?PROL ROD REACTIVITY WORTH MEASUREMENT (Startup Test)
Plant Condition or Prerecuisite Reactor is critical with the neutron flux level in the zero power physics testing range.
RCS temperature and pressure are at hot no-load values.
Test Objective red (JorfAs by To determine g selected fferential individual,and bank integral rod worth and to verify rod worth for shutdown capability.
,g Test Summary Under zero power conditions at approximately operating tem-perature and pressure, the nuclear design predictions for Rod Cluster Control Assembly (RCCA) Banks' differential worth will be validated.
The validation will be made.from boron concentration sampling data, RCCA bank positions and recorder traces of' reactivity.
From this data the integral RCCA bank worths will be determined.
The minimum boron concentration for maintaining the reactor shutdown with the most reactive RCCA stuck in the full out position will be determined.
The determination will be made from analysis of boren concentration and RCCA worths.
Acceptance Criteria The control rod reactivity worths are.. : "..i... :'..
.1 in agreement with those given in the Westinghouse supplied Ep = E 5_1 z Nuclear Design Report wher e, sud warns, can be Me.h and frac 4ic-bly demons 4r*4 d by fes by Overall foe 4ke P awb will ke. veriOed i f iao(ivida a I l
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