ML20203D328
| ML20203D328 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/04/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Subalusky W COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20203D333 | List: |
| References | |
| 50-373-97-19, 50-374-97-19, NUDOCS 9712160165 | |
| Download: ML20203D328 (2) | |
See also: IR 05000373/1997019
Text
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December 4,1997
,
Mr. W. T. Subalusky, Jr.
Site Vice President
LaSalle County Station
Commonwealth Edison Company
2601 North 21st Road
Marseilles,IL 61341
Dear Mr. Subalusky:
SUBJECT:
NRC RADIATION PROTECTION INSPECTION REPORTS 50-373/97019(DRS);
50-374/97019(DRS)
On November 7,1997, the NRC completed an inspection at your LaSalle County Nuclear
Power Station. The purpose of the inspection was to review the as-low-as reasonably-
achievable (ALARA) planning and controls for Unit 1 forced outage activities and the
implementation of the respiratory potection and contamination monitoring programs. The
enclosed report summarizes the results of this inspection.
Overall, effective ALARA controls and planning continued to keep station dose reasonable
given the emergent work from your ongoing engineering reviews, in particular, we observed
good radiation protection coveraga of diving activities during emergency core cooling system
strainer replacements and good involvement by your ALARA staff during the engineering
design development of several significant system modifications. The maintenance of
contamination manitoring instrumentation and radworker performance were also considered
good.
However, there continued to be examples where problems with the station work planning and
scheduling process had a negative impact on overali dose. One particular example was the
inability to schedule and perform a chemical decontamination of the reactor water cleanup
system, which could have resulted in significant exposure savings. Another problem was a
recurrent failure to use the formal corrective actions process to document unexpected
radiolcgical conditions encountered during incore instrumentation work before proceeding with
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other similar work. The failure to fully implement the formal corrective actions process for
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incore instrumentation work was _ contributing cause for a previous violation documented in
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inspection report number 50-373/374-96014(DRS). The inspection also identified several
deficiencies associated with specific aspects of the radiological respiratory control program.
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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jW T Subalusky
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December 4, 1997
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We will gladly discuss any questions you have conceming this insoection.
Sincerely, -
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Original- Signed by John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-373; 50-374
License Nos. NPF 11; NPF-18
Enclosure:
Inspection Rr ports 50 373/97019(DRS); 50 374/97019(DRS)
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cc w/ encl:
O. Kingsley Nuclear Generation Group
President & Chief Nucisar Officer
M. Wallace, Senior Vice President,
Corporate Services
E. Kraft, Vice President, BWR Operations
Liaison Officer, NOC-BOD
D. A - Sager, Vice Presiden'.
Generation Support
D. Farrar, Nuclear Regulatory
Services Manager
I. Johnson, Licensing Operations Manager
Document Control Desk - Licensing
F. Dacimo, Plant General Manager
P. Bames. Regulatory Assurance Supervisor
Richard Hubbard
Nathan Schloss, Economist,
Office of the Attorney General
State Liaison Officer
Chairman, Illinois Commerce Commission
Distribution:
Docket File w/enci
SRI, LaSalle w/enct
R. A. Capra, NRR w/enci
PUBLIC IE-01 w/ encl
TSS w/enci
OCFO/LFARB w/ encl
LPM, NRR w/enci
A. B. Beach, Rill w/enci
CAA1 w/enci
DRP wienci
J. L. Caldwell, Rlli w/enci
DOCDESK w/ enc!
DRS w/enci
Rlli Enf. Coordinator w/enci
Rlli PRR w/enci
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