ML17334A551
| ML17334A551 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/24/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER SERVICE CORP. |
| Shared Package | |
| ML17334A552 | List: |
| References | |
| 50-315-97-20, 50-316-97-20, NUDOCS 9711280160 | |
| Download: ML17334A551 (4) | |
See also: IR 05000315/1997020
Text
November 24,
1997
Mr. E. E. Fitzpatrick
Executive Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC ROUTINE RADIATIONPROTECTION INSPECTION REPORTS
50-315/97020(DRS); 50-316/97020(DRS)
Dear Mr. Fitzpatrick:
On October 31, 1997, the NRC completed an inspection at your D. C. Cook, Units 1 and 2
reactor facilities. The enclosed report presents the results of that inspection.
The inspection was an examination of activities conducted under your license as they relate to
radiation safety and to compliance with the Commission's rules and regulations and with the
conditions of your license.
Within these areas, the inspection consisted of selective
examinations of procedures and representative
records, interviews with personnel, and
observation of activities in progress.
The focus of this inspection was to review the
radiological'ontrols
implemented during the Unit 2 refueling outage, as-low-as-reasonably-achievable
goals
and results, and several radiologically significant work packages.
Overall, the implementation of radiological controls for the outage have been effective in
maintaining a reasonable
collective dose for the work accomplished.
However, we observed
some weaknesses
in your staffs actions for work which exceeded original estimates.
For one
radiation work permit the dose estimate was exceeded
by 33 percent before work was
suspended,
and the job was reevaluated.
We observed several pre-job briefings and job
evolutions.
Overall communications between your staff members was good; however, there
was some difficultyin communications noted on the reactor head set job.,
We also reviewed your evaluation and investigation of a contractor who arrived at your station
with radioactive contamination in his shoe.
Your radiation protection staff identified the
contamination and were evaluating the individual's dose.
However, preliminary results
indicated that the individual had received a dose of about 82.7 rads to the skin, which is an
exposure in excess of the limits specified in 10 CFR 20.1201.
As your staff was able to
demonstrate that the contamination did not originate at your station, we did not identify any
violations of NRC requirements at D. C. Cook.
llllllllllllllllllllllllllllllllllllllll
97ii280i60 97ii24
ADQCK 05000325
8
I
$
4
E. E. Fitzpatrick
November 24,
1997
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be placed in the NRC Public Document Room.
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
Docket Nos. 50-315; 50-316
Original Signed By J. A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Enclosure:
Inspection Report 50-315/97020(DRS); 50-316/97020(DRS)
cc w/encl:
A. A. Blind, Site Vice President
John Sampson, Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of Environmental Quality
~Di tribution:
Docket File w/encl
PUBLIC IE-01 w/encl
'OCFO/LFARB w/encl
DRP w/encl
DRS w/encl
Rill PRR w/encl
SRI, D. C. Cook w/encl
LPM, NRR w/encl
A. B. Beach, Rill w/encl
J. L. Caldwell, Rill w/encl
Rill Enf. Coordinator w/encl
TSS w/encl
DOCDESK w/encl
CAA1 w/encl
DOCUMENT NAME: G:DRSiDCC97020.DRS
TO reoehre a COP
Of this dOCument. IndICate In the bOX: 'C
~ COO
Withcut attaohrnentrendneure
'E'
CO
tNrth attaohinent/endeaure
'N'
NO COO
OFFICE
NAME
Rill
DHart:jp Ql~ +
Rill
C
GShear
BBurgess
JGrobe
Rill
8
Rill
DATE
11//~/97
11/
/97
11//'F97
OFFICIAL RECORD COPY
11/SQ7