ML20092E051
| ML20092E051 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/08/1995 |
| From: | Graesser K COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYRON-95-0308, BYRON-95-308, NUDOCS 9509150017 | |
| Download: ML20092E051 (1) | |
Text
Commonwealth Ediv>n Company 4,#
11)run Generating Station 4 650 North German Churt h Road fly ron, II. 61010 9N i Tel H1423 s 5 ill A
September 8, 1995 LTR:
BYRON 95-0308 FILE:
1.10.0101 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTN:
Document Control Desk
SUBJECT:
Commonwealth Edison - Byron Station BIR07 Steam Generator Inspection to Verify Load Path Necessary to Support 3 Volt Interim Plugging Criteria
REFERENCE:
D. Saccomando letter to Document Control Desk transmitting Commonwealth Edison Steam Generator Structural Inspection Plan for Verification of Load Path Necessary to Support 3 Volt Interim Plugging Criteria, dated September 2, 1995, submitted in response to a Request For Additional Information.
In the reference letter, Commonwealth Edison (Comed) transmitted the response to Request for Additional Information question 64.
The Inspection Plan submitted in this reference covered load path inspections to be conducted during the Braidwood A1R05 refuel outage in Fall 1995 and during the Byron
.91P02 steam generator (SG) inspection outage also in Fall 1995.
At a meeting between Comed and the Staff held on September 6, 1995, to discuss the Inspection Plan, the Staff indicated a desire to have Byron conduct additional structural inspections during their next refuel outage, B1R07, to be conducted in Spring 1995.
Comed will visually inspect the vertical support block welds at the bottom of the Flow Distribution Baffle in all SGs as part of the post sludge lance video inspection during B1R07.
The details of this inspection are described in the reference, Section 3.1 " Vertical Support Bars."
In addition, Byron will also conduct an eddy current examination of the tube support plates in all SGs consistent with the EPRI Guidelines / eddy current techniques developed for this purpose.
Section 4.0 of the reference provides additional discussion of the eddy current inspection.
If you have any questions, please contact Denise Saccomando, Nuclear Licensing Administrator.
Sincerely,
,{
na K.
L.
G a sser y Site Vice resident Byron Nuclear Power Station KLG/LZ/RP cc:
D. Lynch, Senior Project Manager-NRR G. Dick, Byron Project Manager-NRR H.
Peterson, Senior Resident Inspector-Byron H. Miller, Regional Administrator-RIII Office of Nuclear Safety-IDNS (p:\\95hyrlts\\950308\\090895) 9509150017 950908 A Unicom Company DR ADOCK 0500 4
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