ML17191A937
| ML17191A937 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/21/1998 |
| From: | Jeffrey Jacobson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17191A939 | List: |
| References | |
| 50-237-98-23, 50-249-98-23, NUDOCS 9810270191 | |
| Download: ML17191A937 (3) | |
See also: IR 05000237/1998023
Text
,'! ...
Mr. Oliver D. Kingsley
President, Nuclear Generation Group
Commonwealth Edison Company
ATTN: Regulatory Services
Executive Towers West Ill
1400 Opus Place, Suite 500
Downers Grove, IL 60515
O:;tober 21, 1998
SUBJECT:
NRC INSPECTION REPORT NOS. 50-237/98023(DRS) & 50-249/98023(DRS),
NOTICE OF VIOLATION, AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Kingsley:
On September 23, 1998, the NRC completed an inspection at your Dresden facility. The focus
of this inspection was to review the engineering and technical support provided to the station. In
addition, an assessment of the effectiveness of controls for identifying, resolving, and preventing
problems was performed. The endosed report presents the results of that inspection.
Overall, the NRC concluded that the engineering and technical support provided by the
engineering organization remained acceptable and had improved. Only minor deficiencies were
identified regarding the modifications, calculations, and 10 CFR 50.59 safety evaluations
reviewed. In addition, engineering department self-assessments were effective. The threshold
for the identification of problems was low; identified problems were elevated to ~e proper levels
of management for resolution; operability issues were addressed; and corrective actions were
adequate, timely, and properly prioritized.
However, the NRC identified three examples in which the temporary alteration program was not
adequately implemented. In one case, two temporary alterations were installed without utilizing
the temporary alteration process. In a second case, a number of temporary alterations were not
reviewed for extended installation. In a third case, required quarterly walkdowns of installed
temporary alterations were not performed.
The NRC also reviewed various aspects of the inservice testing program during this inspection.
Following that review, the NRC identified two examples of a violation of technical specifications
regarding the implementation of this program. In the first example, a procedure failed to specify
appropriate containment cooling service water pump flow for inservice testing: In a second
example, test acceptance criteria in a procedure used to demonstrate that check valves were
sufficiently leak tight was not adequate.
Regarding your controls in identifying, resolving, and preventing problems, the NRC concluded
that problem identification was at an appropriate low threshold, root cause evaluations were
thorough, and effective corrective actions were implemented for identified problems. In addition,
9810270191 991021
POR
ADOCK 05000237
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0. Kingsley
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the conduct of safety review committee meetings and the review of operating experience
information was effective, and the nuclear oversight organization was effectively identifying and
eorrecting problems.
As discussed above, the NRC has determined that violations of NRC requirements occurred.
These violations are cited in the enclosed Notice of Violation (Notice) and the circumstances
surrounding them are described in detail in the subject inspection report. The violation
regarding the temporary alteration program is of concern because adequate implementation of
this program is important to ensure that changes to the plant are properly evaluated prior to
installation and periodically reviewed following installation. The violation concerning the
inservice testing program is also of concern since proper implementation of this program is
required to ensure that equipment which is important to safety is operating properly.
The NRC has concluded that information regarding the reason for the violations associated with
implementation of the temporary alteration program and the inservice testing program, and the
corrective actions taken and planned to correct the violations and prevent recurrence, is already
adequately addressed in this inspection report. Therefore, you are not required to respond to
this letter unless the description therein does not accurately reflect your corrective actions or
your position. In that case, or if you choose to provide additional information, you should follow
the instructions specified in the enclosed Notice.
In addition, during this inspection, the team reviewed a number of violations which were self-
identified. These violations will not be subject to enforcement action because your efforts meet
the criteria specified in Section Vll.B.1 of the *General Statement of Policy and Procedures for
NRC Enforcement Actions,* (Enforcement Policy), NUREG-1600.
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 (PDR).
Docket Nos. 50-237; 50-249
Enclosures:
Sincerely,
Original I sf J. M. Jacobson
John M. Jacobson, Chief
Lead Engineers Branch
Division of Reactor Safety
2. Inspection Report 50-237/98023(DRS);
50-249/98023(DRS)
See Attached Distribution
DOCUMENT NAME: G:DRS\\DRE98023.DRS
To rec-a
DATE
0. Kingsley
3
cc w/encls:
D. Helwig, Senior Vice President
G. Stanley, PWR Vice President
C. Crane, BWR Vice President
Distribution:
R. Krich, Regulatory Services Manager
D. Greene, Licensing Director
DCD - Licensing
M. Heffley, Site Vice President
P. Swafford, Station Manager
F. Spangenberg, Regulatory Assurance
Manager
Richard Hubbard
M. Aguilar, Assistant Attorney General
State Liaison Officer
Chainnan, Illinois Commerce
Commission
SAR(E-Mail)
RPC (E-Mail)
.
Project Mgr., NRR w/encl
J. Caldwell, Riii w/encl
C. Pederson, Riii w/encl
B. Clayton, Riii w/encl
SRI Dresden w/encl
DRP w/encl
TSS w/encl
DRS (2) w/encl
Riii PRR w/encl
PUBLIC IE-01 w/encl
Docket File w/encl
GREENS
IEO (E-Mail)
DOCDESK (E-Mail)
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