ML20202F006
| ML20202F006 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/11/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20202F011 | List: |
| References | |
| 50-454-98-03, 50-454-98-3, 50-455-98-03, 50-455-98-3, NUDOCS 9802190107 | |
| Download: ML20202F006 (3) | |
See also: IR 05000454/1998003
Text
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February 11, 1998
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Mr. Oliver D. Kingsley
President, Nuclear Generation Group
Commonwealth Edison Company
ATTN: Regulatory Services
Executive Towers West 111
1400 Opus Place, Suite 500
Downers Grove,IL 60515
SUBJECT:
BYRON SECURITY INSPECTION REPORTS 50-454/98003(DRS);
50-455/98003(DRS) FOR SECURITY SUPPORT DURING THE UNIT 1
STEAM GENERATOR REPLACEMENT PROJECT
Dear Mr. Kingsley:
On January 27,1998, the NRC completed an Inspection at your Byron Nuclear Generating
Plant reactor facility. The onsite inspection was conducted between January 8-12,1998. The
enclosed report presents the results of that inspection.
Areas examined within your security program are identified in the report. Within those areas,
the inspection consisted of a selective examination of procedures and representative records,
observation of performance, and interviews with staff. The objectivo of the 'nspection effort was
to determine whether activities authorized by the license were conducted safely and in
accordance with NRC requlraments.
Based on the results of this inspection, no violations of NRC requirements were identified.
However, two unresolved items and an Inspection Followup ltem were noted. The unresolved
items pertain to the adequacy of the compensatory measures for a degraded portion of the
Vehicle Barrier Festem, and the adequacy of alarm system testing after retuming two perimeter
alarm system zor as to service. These issues will be reviewed by NRC Headquarters and
resolution of the issues, to include enforcement action if appropriate, will be addressed by
separate correspondence. The Inspection Followup Item pertained to a weaknes.s in access
controlin the Main Access Facility.
The overall management and utilization of the security force in support of the Steam Generator
Replacement project was very good. The overtime for the security force was demanding but
managed well. Loggable security incidents were not excessive, cor.sidering the number of
contractors onsite for the project, which is indicative of a workforce aware of their security
responsibilities.
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O. D. Kingsley
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February 11, 1998
In accordance with 10 CFR 2.790 of the NRC's ' Rules of Practice," a copy of this letter and its
enclosure will be placed in the NRC Public Document Room (PDA).
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
Original Signged by Harold O. Christensen (for)
'
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-454; 50-455
License Nos. NPF 37; NPF-66
Enclosure:
Inspection Reports 50-454/98003(DRS); 50-455/98003(DRS)
cc w/ encl:
M. Wallace, Chief of Staff
D. Helwig, Senior Vice President
G. Stanley, PWR Vice President
J. Perry, BWR Vice President
D. Farrar, Regulatory
Services Manager
I. Johnson, Licensing Director
DCD - Licensing
K. Graesser, Site Vice President
K. Kofron, Station Manager
D. Brindle, Regulatory Assurance
Supervisor
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
State Liaison Officer
State Liaison Officer. Wisconsin
Chairman, Illinois Commerce
Commission
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OFFICIAL RECORD COPY
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O. D. Kingsley
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February 11,1998
Distnbution
Docket File w/enci-
Rlli PRR w/ encl
Rlli Enf. Coordinator w/ encl
PUBLIC IE-01 w/enci -
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TSS w/ encl
J. L. Caldwell, Rlli w/ encl
R. A. Capra, NRR w/enci
DRP w/enci
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DOCDESK w/ encl
DRS w/ encl
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