ML20141E682
| ML20141E682 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/26/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Stanley H COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20141E686 | List: |
| References | |
| 50-456-97-10, NUDOCS 9707010140 | |
| Download: ML20141E682 (3) | |
See also: IR 05000456/1997010
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June 26, 1997
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Mr. H. G. Stanley
Site Vice President
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Braidwood Nuclear Power Station
Commonwealth Edison Company
R.R. #1, Box 84
Braceville, IL 60407
SUBJECT: NRC INSPECTION REPORT 50-456/97010(DRS)
Dear Mr. Stanley:
On June 2,1997, the NRC completed an inspection at your Braidwood, Unit 1, reactor
facility. The enclosed report presents the results of that inspection.
The inspection included a review of inservice inspection activities and the examination of
steam generator tubes. Your efforts to evaluate tube integrity by assessing growth rates
for outside diameter stress corrosion cracking using historical eddy current data
reviews / comparisons and in situ pressure testing were indicative of an aggressive program.
The decision to provide additional oversight of the contractors' activities and procedures
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for eddy current examination of the steam generator tubing was considered a program
improvement.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
and the enclosed inspection report will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
/s/ John ti. Jacobson (for)
John A. Grobe, Acting Director
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Division of Reactor Safety
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Docket No. 50-456
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Enclosure: Inspection Report 50-456/97010(DRS)
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(See Previous Concurrence)
To rocsive a copy of this document, indicate in the box 'C" = Copy w/o attach /enci T = Copy w/ attach /enci
"N" = Nopopy
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Mr. H. G. Stanley
Site Vice President
Braidwood Nuclear Power Station
Commonwealth Edison Company
R.R. #1, Box 84
Braceville, IL 60407
SUBJECT: NRC INSPECTION REPORT 50-456/97010(DRS)
Dear Mr. Stanley:
On June 2,1997, the NRC completed an inspection at your Braidwood, Unit 1, reactor
facility. The enclosed report presents the results of that inspection.
The inspection included a review of inservice inspection activities and the examination of
steam generator tubes. Your efforts to evaluate tube integrity by assessing growth rates
for outside diameter stress corrosion cracking using historical eddy current data
reviews / comparisons P.nd in situ pressure testing were indicative of an aggressive program.
'
The decision to previde additional oversight of the contractors' activities and procedures
for eddy current examination of the steam generator tubing was considered a program
improvement.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
and the enclosed inspection report will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
John A. Grobe, Acting Director
Division of Reactor Safety
Docket No. 50-456
Enclosure: Inspection Report 50-456/97010(DRS)
See Attached Distribution
DOCUMENT NAME: G:\\DRS\\ BRA 97010.DRS
To receive a copy of this document, indicate in the box 'C" = Copy, w/o attach!enct
'E" = Copy w/ attach /enct
"N" = No copy
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OFFICE
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OFFICIAL RECORD COPY
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H. G. Stanley -
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June 26, 1997
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cc w/ encl:
T. J. Maiman, Senior Vice President,
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Nuclear Operations Division
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D. A. Sager, Vice President,
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Generation Support
H. W. Keiser, Chief Nuclear
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Operating Officer
T. Tulon, Station Manager
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T. Simpken, Regulatory Assurance
Supervisor
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1. Johnson, Acting Nuclear
Regulatory Services Manager
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Document Control Desk - Licensing
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Richard Hubbard
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Nathan Schloss, Economist,
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Office of the Attorney General
State Liaison Officer
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Chairman, Illinois Commerce Commission
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Distribution:
Docket File w/enct
Rlli PRR w/ encl
J. L. Caldwell, Rlll w/enci
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PUBLIC IE-01 w/enct
SRIs, Braidwood, Byron,
Rlli Enf. Coordinator w/enci
OC/LFDCB w/enci
Zion w/ encl
R. A. Capra, NRR w/enci
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DRP w/enct
LPM, NRR w/ encl
TSS w/enci
DRS w/enci
A. B. Beach, Rlll w/ encl
CAA1 w/enci
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