ML20129H238
| ML20129H238 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 10/23/1996 |
| From: | Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Stanley H COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20129H243 | List: |
| References | |
| NUDOCS 9610310174 | |
| Download: ML20129H238 (4) | |
See also: IR 05000456/1996012
Text
'.
,
Oh
October 23, 1996
Mr. ti. G. Stanley
Site Vice President
-
Braidwood Station
'
Commonwealth Edison Company
RR #1, Box 84
Braceville, IL 60407
SUBJECT:
NRC INSPECTION REPORT 50-456/96012; 50-457/96012
.
Dear Mr. Stanley:
On September 6, 1996, the NRC completed an inspection at your Braidwood 1 & 2
reactor facilities. The enclosed report presents the results of that
xinspection.
,
During tM 6-week inspection period, a significant weakness regarding out-of-
'date co:
i room drawings was identified by the inspectors.
In addition,
E
there were several examples of failing to follow procedures during plant
activities. Through these failures, non-licensed operator performance
indicated a lack of understanding regarding valve position verification,
independent verification, and procedure adherence requirements.
Procedure
adherence problems have been previously discussed in Inspection Reports 95017,
96006, and 96011.
Preconditioning a cooling water supply valve for the 1A diesel generator prior
to surveillance testing the diesel generator, the failure to perform an
independent verification of valves during a Unit 2 diesel generator
surveillance, and the failure to indicate out-of-date drawings in the control
'
room that had pending revisions are cited in the enclosed Notice of Violation.
The circumstances surrounding the violations are described in detail in the
enclosed report.
Please note that you are required to respond to this letter and should follow
the instructions specified in the enclosed Notice when preparing your
response. The NRC will use your response, in part, to determine whether
further enforcement action is necessary to ensure compliance with regulatory
requirements.
l
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9610310174 961023
ADOCK 05000456
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. _ - _ . _ _
-
,
.
.
H. Stanley
-2-
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and the enclosures will be placed in the NRC Public Document Room
(PDR).
Sincerely,
/s/ John A. Grobe for
James L. Caldwell, Acting Director
Division of Reactor Projects
Docket Nos.:
50-456, 50-457
Enclosures:
1.
2.
Inspection Report
No. 50-456/457/96012
cc w/ encl:
D. A. Sager, Vice President,
Generation Support
H. W. Keiser, Chief Nuclear
Operating Officer
T. Tulon, Station Manager
T. Simpkin, Regulatory
Assurance Supervisor
I. Johnson, Acting Nuclear
Regulatory Services Manager
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
State Liaison Officer
Chairman, Illinois Commerce
Commission
Document Control Desk-Licensing
Docket File w/ encl
DRP w/enci
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OC/LFDCB w/ enc 1
RIII PRR w/enci
PUBLIC IE-01 w/ encl
CAAl w/ encl (E-mail)
Skl Byron, Braidwood, Zion w/ enc 1
B. L. Burgess, w/ enc 1
Project Mgr., NRR w/ enc 1
A. B. Beach, w/ encl
RACI (E-Mail)
W. L. Axelson, w/ encl
DOCUMENT NAME: R:INSPRPTS\\ POWERS \\BRAI\\ BRA 96012.DRP
To receive a copy of ede document, Indicate in the bon 'C" = Copy w/o attach /enci T = Copy w/ attach /enci "N" = No copy
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October 23, 1996
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Mr. H. G. Stanley
Site Vice President
Braidwood Station
Commonwealth Edison Company
RR #1, Box 84
Braceville, IL 60407
'
~
SUBJECT:
NRC INSPECTION REPORT 50-456/96012; 50-457/96012
Dear Mr. Stanley:
On September 6,1996, the NRC completed an inspection at your Braidwood 1 & 2
reactor facilities. The enclosed report presents the results of that
i
,
inspection.
,
1
During this 6-week inspection period, a significant weakness regarding out-of-
date control room drawings was identified by the inspectors.
In addition,
'
there were several examples of failing to follow procedures during plant
activities. Through these failures, non-licensed operator performance
indicated a lack of understanding regarding valve position verification,
1
independen*, verification, and procedure adherence requirements.
Procedure
adherence problems have been previously discussed in Inspection Reports 95017,
96006, ard 96011.
Preconditioning a cooling water supply valve for the 1A diesel generator prior
to surveillance testing the diesel generator, the failure to perform an
independent verification of valves during a Unit 2 diesel generator
surveillance, and the failure to indicate out-of-date drawings in the control
room that had pending revisions are cited in the enclosed Notice of Violation.
The circumstances surrounding the violations are described in detail in the
enclosed report.
Please note that you are required to respond to this letter and should follow
the instructions specified in the enclosed Notice when preparing your
response. The NRC will use your response, in part, to determine whether
further enforcement action is necessary to ensure ccmpliance with regulatory
requirements.
i
l
4
--
. . = .
- - ,-
.
_
.
. - . -
.-
.
,
.
.
,
H. Stanley
-2-
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and the enclosures will be placed in the NRC Public Document Room
~
(PDR).
,
Sincerely,
h.
i
.
,
ames L. Caldwell, Acting Director
Division of Reactor Projects
l
Docket Nos.:
50-456, 50-457
,
Enclosures:
1.
2.
Inspection Report
No. 50-456/457/96012
l
cc w/ encl:
D. A. Sager, Vice President,
Generation Support
H. W. Keiser, Chief Nuclear
Operating Officer
T. Tulon, Station Manager
)
T. Simpkin, Regulatory
Assurance Supervisor
I. Johnson, Acting Nuclear
Regulatory Services Manager
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
State Liaison Officer
Chairman, Illinois Commerce
Commission
Document Control Desk-Licensing