ML20149F525
| ML20149F525 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 08/03/1994 |
| From: | Axelson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kraft E COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20149F528 | List: |
| References | |
| NUDOCS 9408110010 | |
| Download: ML20149F525 (4) | |
See also: IR 05000254/1994013
Text
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Docket No. 50-254
Docket No. 50-.265
Commonwealth Edison Company
ATTN:
E. Kraft, Site Vice President
Quad Cities Station
22712 206th Avenue North
Cordova, IL 61242
Dear Mr. Kraft:
SUBJECT:
INSPECTION OF QUAD CITIES RADIATION PROTECTION PROGRAM (REPORTS N0.
50-254/94013(DRSS); 50-265/94013(DRSS)) AND MANAGEMENT MEETING
This refers to the inspection conducted by Messrs. R. A. Paul, N. Shah,
M. A. Kunowski, and S. K. Orth of this office on April 6 through June 15,
1994. The inspection included a review of authorized activities for your Quad
Cities Nuclear Power Station, Units 1 and 2.
This also refers to the
Management Meeting held on June 30, 1994, between Mr. T. O. Martin and others
of the NRC and you and members of your staff to discuss corrective actions for
recent problems in the radiation protection program.
Areas examined during the inspection are identified in the report. Within
these areas, the inspection consisted of a selective examination of procedures
and representative records, interviews with personnel, independent
measurements, and observation of activities in progress. The areas discussed
during the Management Meeting are also summarized in the report.
Based on the results of this inspection, certain of your activities appeared
to be in violation of NRC requirements, as specified in the enclosed
inspection report. The violation for inadequate survey is being cited to
emphasize the importance of the workers and the radiation protection
department fully communicating and understanding the job scope. A similar
problem was discussed in Inspection Report Nos. 50-254/94002; 50-265/94002
(Section 5) and corrective actions for that problem should have prevented
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these most recent problems. Although 10 CFR 2.201 requires you to submit to
this office, within 30 days of your receipt of this Notice, a written
statement of explanation, we note that this violation had been corrected and
those actions were reviewed during this inspection and discussed at the
Management Meeting. These actions included an outage work stoppage,
development of a radiation work performance improvement plan, and a phased
return to work. Therefore, no response with respect to this matter is
required.
The violation for not labeling a bucket that contained an irradiated component
with a contact dose rate of about 5170 rem / hour (51.7 Sieverts/ hour) is being
cited because ineffective corrective actions were taken for a related concern
raised by the resident inspectors about two months earlier. We reviewed this
latest incident for escalated enforcement under a criterion for substantial
9408110010 940803
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Commonwealth Edison Company
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Distribution
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J. C. Brons, Vice President,
Nuclear Support
S. Perry, Vice President, BWR Operations
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G. Campbell, Station Manager
N. Chrissotimos, Regulatory Assurance
Supervisor
D. Farrar, Nuclear Regulatory
Services Manager
OC/LFDCB
Resident Inspectors LaSalle
Dresden, Quad Cities
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
Licensing Project Manager, NRR
State Liaison Officer
Chairman, Illinois Commerce
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Commission
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S. Shelton, Vice President, Electric
Operation, IA-IL Gas & Electric
T. O. Martin, RIII
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S. Stein, SRS
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bec w/ enclosures:
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D. E. Funk, RIII
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Conconwealth Edison Company
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potential for an overexposure. Although our review determined that the
criterion was not met, we consider the incident a significant lapse in your
control over highly irradiated components stored in your reactor cavity and
spent fuel pool. A response is required for this violation.
Please include
in the response the results of your investigation into this problem.
We also reviewed planning and implementation problems with your torus
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recoating project. These problems resulted in a dose total for the project of
over 230 person-rem (2.3 person-Sieverts), compared to the pre-project
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estimate of 83 person-rem (0.83 person-Sievert).
In addition to the written
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response required for the violation, you are requested to describe the results
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of your assessment of the torus project and the corrective actions you have
taken or plan to take to preclude occurrence of a similar problem.
The violations, the problems with the torus recoating project, and the recent
significant number of self-identified problems with radiation worker
performance indicate that your radiological controls program needs substantial
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improvement. As discussed at the Management Meeting, the actions taken late
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in the outage to stop work, and develop and implement an improvement plan
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indicated that you understand the magnitude of that need and are committed to
address it. Continued, pertinent efforts are necessary to ensure that lasting
improvements are gained.
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In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
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this letter, the enclosures, and your response will be placed in the NRC
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Public Document Room.
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We will gladly discuss any questions you have concerning this inspection.
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Sincerely,
omcmAt sictRD SY
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W. L. Axelson, Director
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Division of Radiation Safety
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and Safeguards
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Enclosures:
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1.
2.
Inspection Reports
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No. 50-254/94013(DRSS);
No. 50-265/94013(DRSS)
SEE ATTACHED DISTRIBUTION
(See Attached Sheet)
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potential for an overexposure. Although our review determined that the
criterion was not met, we consider the incident a significant lapse in your
control over highly irradiated components stored in your reactor cavity and
spent fuel pool. A response is required for this violation.
Please include
in the response the results of your investigation into this problem.
We also reviewed planning and implementation problems with your
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recoating project. These problems esulted in a dose total for tne project of
over 230 person-rem (2.3 person-Sieverts), compared to the pre-project
estimate of 83 person-rem (0.83 person-Sievert).
In addition to the written
response required for the violation, you are requested to describe the results
of your assessment of the torus project and the corrective actions you have
taken or plan to take to preclude occurrence of a similar problem.
The violations, the problems with the torus recoating project, and the recent
significant number of self-identified problems with radiation worker
performance indicate that your radiological controls program needs substantial
improvement. As discussed at the Management Meeting, the actions taken late
in the outage to stop work, and develop and implement an improvement plan
indicated that you understood the magnitude of that need and were committed to
address it. Continued, pertinent efforts are necessary to ensure that lasting
i
improvements are gained.
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In accordance with 10 CFR 2.790 of the Commissior.'s regulations, a copy of
this letter, the enclosures, and your response will be placed in the NRC
Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
I
Sincerely,
'
W. L. Axelson, Director
Division of Radiation Safety
and Safeguards
Enclosures:
1.
2.
Inspection Reports
No. 50-254/94013(DRSS);
No. 50-265/94013(DRSS)
SEE ATTACHED DISTRIBUTION
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