ML20154D180
| ML20154D180 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/30/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Jeffery Wood CENTERIOR ENERGY |
| Shared Package | |
| ML20154D182 | List: |
| References | |
| 50-346-98-16, NUDOCS 9810070147 | |
| Download: ML20154D180 (2) | |
See also: IR 05000346/1998016
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September 30, 1998
Mr. John K. Wood
Vice President - Nuclear
Davis-Besse Nuclear Power Station
Centerior Service Company
5501 North State Route 2
Oak Harbor, OH 43449
SUBJECT:'
NRC RADIATION PROTECTION INSPECTION REPORT 50-346/98016(DRS)
Dear Mr. Wood:
On September 4,1998, the NRC completed a routine inspection at your Davis-Besse Nuclear
Power Station. The enclosed report summarizes the results of this inspection.
The innection was an examination of activities conducted under your license as they relate to
radiatan safety and to compliance with the Commission's rules and regulations and with the
conditions of your license. The inspection consisted of a selective examination of procedures
and representative records, observations, and interviews with personnel. Specifically, the
inspection focused on the external exposure monitoring program, the calibration and test
program for radiation monitoring equipment and the program for the control of materials for
unconditional release from the radiologically restricted area (RRA). Also reviewed was the
station's response to a June 24,1998, condensate system resin intrusion incident; the
radiological controls for a containment entry during power operations that occurred during the
inspection period; and the as-low-as-is-reasonably-achievable (ALARA) program implemented
for the eleventh refueling outage.
Overall, programs were effectively implemented. In particular, administrative controls were
etiablished to maintain worker exposure ALARA, and your staff continued to maintain good
oversight of the dosimetry processor. Programs for the calibration and testing of radiation
monitoring equipment and for the control of material for release from the RRA were also well
implemented; however, some examples were identified where procedural improvement was
necessary to ensure consistency with station practices and to clarify program implementation.
We also concluded that your staff's response to the resin intrusion incident was appropriate,
and included increased management attention and coordination with vendor representatives to
ensure recovery plans were technically sound.
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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.
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9810070147 980930
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
Origina ISigned by Steven A. Reynolds (for)
John A. Grobe, Director
Division of Reactor Safety
Docket No.:
50-346
License No.: NPF-3
Enclosure:
Inspection Report 50-346/98016(DRS)
cc w/ encl:
J. Stetz, Senior Vice President - Nuclear
~ J. Lash, Plant Manager
J. Freels, Manager, Regulatory Affairs
M. O'Reilly, FirstEnergy
State Liaison Officer, State of Ohio
R. Owen, Ohio Department of Health
C. Glazer, State of Ohio Public ~
' Utilities Commission
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