ML17326A016
| ML17326A016 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/18/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17326A017 | List: |
| References | |
| 50-315-99-14, 50-316-99-14, NUDOCS 9906240245 | |
| Download: ML17326A016 (5) | |
See also: IR 05000315/1999014
Text
CATEGORY 2
REGULATORY INFORMATION DXSTRXBUTION SYSTEM (RIDS)
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ACCESSION NBR:9906240245
DOC.DATE: 99/06/18
NOTARIZED: NO
ACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana
M
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana
M
AUTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
'egion
-3 (Post
820201)
RECIP . NAME
RECIPIENT AFFILIATION
POWERS,R.P.
American Electric Power Co., Inc.
DOCKET'¹
05000315
05000316
SUBJECT:
Forwards insp repts 50-315/99-14
&, 50-316/99-14
on
990517-0603.No violations were identified.Insp evaluated
control of radiological effluents
& Offsite Dose Calculation
Manual implementation
& internal exposure control program.
DISTRIBUTION CODE: IE06F
COPIES
RECEIVED:LTR
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SIZE:
TITLE:,Environ & Radiological
(50 DKT)-Insp Rept/Notice of Violation Respons
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NOTES:
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INTERNAL: AEOD/TTC
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NUDOCS-ABSTRACT.
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NUDOCS FULLTEXT
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13
ENCL
13
June
18,
1999
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC ROUTINE RADIATIONPROTECTION INSPECTION REPORT
50-315/99014(DRS); 50-316/99014(DRS)
Dear Mr. Powers:
On June 3, 1999, the NRC completed a routine inspection of your D.C. Cook Units 1 and 2
reactor facilities. A meeting was conducted at the facilityat the conclusion of the site inspection
on May 21, 1999, and the preliminary inspection findings were discussed with station
management
and staff. Your staff provided additional information and documentation to the
inspector on May 27 and 28, 1999, which was reviewed in the NRC Region III office. On June
3, 1999, a telephone conversation was conducted with the radiation protection program
manager,
and the results of the NRC in office review were discussed.
The enclosed report
presents the results of this inspection.
No cited violations of NRC requirements were identified.
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.
Specifically, the inspection evaluated the control of radiological
effluents and Offsite Dose Calculation Manual (ODCM) implementation, aspects of the internal
exposure control program including the use and maintenance of respiratory protection
equipment, the radiological control for access into high radiation areas and for tools and other
equipment used in the radiologically restricted area, and the audit and self-assessment
program.
Within these areas, the inspection consisted of a selective examination of procedures
and representative
records, observations, independent measurements,
and interviews with
personnel.
Overall, programs reviewed were generally well implemented.
In particular, respiratory
protection equipment was in good physical condition and was properly maintained and stored,
and the radiological control for access into high radiation areas and for tools and other
equipment used in the radiologically restricted area was effective. Recent audits of the
radiological effluent control program were thorough.
Several good initiatives were recently
completed or ongoing to critically assess
the radiation protection and chemistry programs as
part of your restart readiness
review. Additionally, effluent releases generally remained low and
990b240245 990bi8
ADQCK 050003i5
8
R. Powers
-2-
associated
doses were calculated in accordance with the ODCM. However, your staff identiTied
that the 1998 Annual Radioactive Effluent Release Report was not submitted timely to the NRC,
resulting in a violation of minor safety significance that is not subject to formal enforcement
action. Also, the inspector identified some deficiencies with the radiological control of portable,
filtered vacuum units, with the consistency of labeling containers housing radioactive materials
and with the timely reevaluation of derived air concentration values used to assess
internal
dose, which were planned to be addressed
by your staff.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure willbe placed in the NRC Public Document Room.
We willgladly discuss any, questions you have concerning this inspection.
Sincerely,
Original Signed
by John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-315; 50-316
Enclosure:
Inspection Report 50-315/99014(DRS); 50-316/99014(DRS)
cc w/encl:
A. C. Bakken III, Site Vice President
T. Noonan, Acting Plant Manager
M. Rencheck, Vice President, Nuclear Engineering
R. Whale, Michigan Public Service Commission
Michigan Department of Environmental Quality
Emergency Management
Division
MI Department of State Police
D. Lochbaum, Union of Concerned Scientists
See Attached Distribution
DOCUMENT NAME: G:DRS>DCC99014.WPD
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DATE
06// /99
06/II /99
06/tc/99
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R. Powers
Distribution:
RRB1 (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encl
J. Caldwell, Rill w/encl
B. Clayton, Rill w/encl
SRI D. C. Cook w/encl
DRP w/encl
DRS w/encl
Rill PRR w/egcl
PUBLIC I@41 w/encl
Docket File w/encl
GREENS
IEO (E-Mail)
DOCDESK (E-Mail)