ML20154A463
| ML20154A463 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/25/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20154A466 | List: |
| References | |
| 50-456-98-11, NUDOCS 9810020317 | |
| Download: ML20154A463 (3) | |
See also: IR 05000456/1998011
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Septaber 25, 1998
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Mr. Oliver D. Kingsisy .
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President, Nuclear Generation Group
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Commonwealth Edison Company
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ATTN:' Regulatory Services
Executive Towers West lli
1400 Opus Place, Suite 500
Downers Grove, IL 60515
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SUBJECT:
NRC INSPECTION REPORT NO. 50-456/98011(DRS)
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Dear Mr. Kingsley:
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On August 28,1998, th'e NRC completed an inspection at your Braidwood Generating Station, Unit 1.
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The enclosed report presents the results of that inspection.
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The inspection was an examination of activities conducted under your license as they relate to the
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engineering and maintenance activities for the replacement of the steam generators for compliance
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with the Commission's rules and regulations. Within these areas, the inspection consisted of selective
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examinations of procedures and representative records, interviews with personnel, and observation of
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activities in progress. Specifically, the inspection focused on your construction activities in preparation
for the steam generator replacement.
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Based on the results of the inspection, no violations were identified. Overall, your staff properly
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implemented the special process procedures and work instructions. Procedure and preparation
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. improvements were implemented from lessons learned at Byron. This was particularly evident in the
tendon work preparation, the welding of the feedwater piping elbows to the steam generator nozzles,
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and the shop fabrication welding. These improvements demonstrated a dedication to assure the
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highest quality product which enhances the safety culture and plant reliability.
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In accordance with 10 CFR 2.790 of the NRC'S " Rules of Practice," a copy of this letter, the
enclosures, and your response to this letter will be placed in the NRC Public Document Room (PDR).
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We will gladly discuss any questions you have concerning this inspection.
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Sincerely,
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Original /s/ S. A. Reynolds for
John A. Grobe, Director
Division of Reactor Safety
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Docket No. 50-456
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License No. NPF-72
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- Enclosure: Inspection Report 50-456/98011(DRS)
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9810020317 900925
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Ege Attached Distribution
ADOCK 05000456
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DOCUMENT NAME: G:DRS\\ BRA 98011.DRS
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OFFICIAL RECORD COPY
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0. Kingsley
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cc w/ encl:
M. Wallace, Senior Vice President
D. Helwig, Senior Vice President
G. Stanley, PWR Vice President
J. Peny, BWR Vice President
D. Farrar, Regulatory Services Manager
I. Johnson, Licensing Director
DCD - Licensing _
T. Tulon, Site Vice President
K. Schwartz, Station Manager
T. Simpkin, Regulatory Assurance Supervisor
R. Hubbard, MHB Technical Associates
N. Schloss, Economist
Office of the Attomey General
State Liaison Officer
Chairman, Illinois Commerce Commission
Distribution:
SAR (E-Mail)
Project Mgr., NRR w/enci
J. Caldwell, Rlli w/enci
C. Pederson, Rill w/enci
B. Clayton, Rlli w/enci
SRI Braidwood w/enci
DRP w/enci
TSS w/enci
DRS (2) w/ enc!
Rlli PRR w/enci
PUBLIC IE-01 w/ encl
Docket File w/enci
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
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Mr. Oliv:r D. Kingstsy
President, Nuclear Generation Group
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Commonwealth Edison Company
ATTN: Regulatory Services
Executive Towers West til
1400 Opus Place, Suite 500
Downers Grove, IL 60515
SUBJECT:
NRC INSPECTION REPORT NO. 50-456/98011(DRS)
4
Dear Mr. Kingsley:
On August 28,1998, the NRC completed an inspection at your Braidwood Generating Station, Unit 1.
The enclosed report presents the results of that inspection.
The inspection was an examination of activities conducted under your license as they relate to the
'
engineering and maintenance activities for the replacement of the steam generators for compliance
I
with the Cornmission's rules and regulations. Within these areas, the inspection consistad of selective
examinations of procedures and representative records, interviews with personnel, and observation of
activitics in progress. Specifically, the inspection focused on your construction activities in preparation
for the steam generator replace.nent.
Based on the results of the Irispection, no violations were identified. Overall, your staff properly
,
implemented the special process procedures and work instructions. Procedure and preparation
'
improvements were implemented from lessons learned at Byron. This was particularly evident in the
preparation for the tendon work and in the welding of the feedwater piping elbows to the steam
generator nozzles and shop fabrication welding. These improvements demonstrated a dedication to
assure the highest quality product which enhances the safety culture and plant reliability.
In accordance with 10 CFR 2.790 of the NRC'S " Rules of Practice," a copy of this letter, the
enclosures, and your response to this letter will be placed in the NRC Public Document Room (PDR).
j
We will gladly discuss any questions you have conceming this inspection.
Sincerely,
,
John A. Grobe, Director
Division of Reactor Safety
Docket No. 50-456
License No. NPF-72
Enclosure: Inspection Report 50-456/98011(DRS)
See Attached Distribution
DOCUMENT NAME: G:DRS\\ BRA 98011.DRS
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