ML20238A933
| ML20238A933 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/24/1987 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 3493K, NUDOCS 8709010005 | |
| Download: ML20238A933 (2) | |
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C:mmsnwrith Edison 2j- [ j On3 First National Plea, Chiago, Illinois 4
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Address RIply to: PoM CMice Box 767 I
Chicago, Illinois E0690 - 0767 August 24, 1987 l
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Byron Station Unit 2 I
Startup Test Program NRC Docket No. 50-455 Reference (a): July 22, 1987 letter from S.C. Hunsader to T.E. Murley Gentlemen:
This is to inform you of a change to the Initial Startup Test Program for Byron Unit 2 described in FSAR Chapter 14.
The change was made in accordance with the provisions of 10 CFR 50.59.
FSAR Table 14.2-67 1
l describes the startup test to verify indexing and fr'ec.. passage of the detectors in the incore flux monitor system.
It states the test will be performed with the plant in hot shutdown (Mode 4) following completion of core loading and prior to initial criticality. Mode 4 limits reactor coolant system temperature to 350*F.
The Byron Unit 2 test to verify indexing and free passage of incore detectors was performed in hot standby (Mode 3).
The reactor coolant system was near full temperature (557'F) conditions when this test was performed in Mode 3.
Testing at these conditions more closely represents incore system and reactor internals thermal expansion that would be present during actual flux mapping. Our safety evaluation of this change concluded that no unreviewed safety question exists.
Reference (a) reported this same change to.the startup test program fer Braidwood Unit 1 on July 22, 1987 and that letter included a summary of the safety evaluation for the change. This change to the Byron Unit 2 startup test program was identified on July 1, 1987 and, in accordance with Facility Operating License NPF-66 condition C.3, should have been reported to the NRC by July 31, 1987.
Please direct any questions regarding this matter to this' office.
Very tr uly yours, 8709010005 870824
}-
PDR ADOCK 05000455 e
ba K. A. Ainger Nuclear Licensing Administrator cc:
Byron Resident Inspector NRC Region III Office 3493K 0
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