ML20217Q142
| ML20217Q142 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/22/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kraft E COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20217Q145 | List: |
| References | |
| 50-254-97-10, 50-265-97-10, NUDOCS 9708290215 | |
| Download: ML20217Q142 (3) | |
See also: IR 05000254/1997010
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August 22, 1997
l Mr. E. Kraft
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Site Vice President
i Quad Cities Statiori
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Commonwealth Edison Company.
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22710 206th Avenue North-
Cordova, IL- 61242
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lSUBJECTf. LNRC ENGINEERING INSPECTION REPORT 50 254/97010(DRS);
UO 265/97010(DRS) AND NOTICE OF VIOLATION
i Dear Mr. Kraft:
1
,
On July 25,1997, the NRC completed an inspection at your Quad Cities, Units 1 and 2,
reactor facilities. During this period, inspection activities centered on problems with the
suitability of replacement emergency diesel generator air start motors which were installed
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during the Unit 2 refueling cutage. The inspection was later expanded to include an overall
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review of the application of the design change and alternate parts replacement programs.
The inspection results were discussed in an exit meeting held on July 11,1997; however,
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additional reviews were conducted in the NRC office and these results were discussed in
telephone conversations with members of your staff on July 22,23 and 25,1997. The
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enclosed report provides the results of this inspection.
Based on the inspector's findings, the applicetion of the engineering design change and
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corrective action processes appeared to be weak and good engineering practices and plant
procedures were not always followed. Improper application of the alternate parts
replacement program allowed the installation of safety significant parts whose form, fit or
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function differed from the original, As a result,'the safety functions of equipment were
- affected.~ Actions taken on problems noted in this area were not adequate to prevent
repetition. Near the end of.the inspection, however, your staff had taken steps to correct
some of the poor practices and ensure proper use of the design change process.- At the
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conclusion of the inspection, the findings were discussed with members of your staff
identified in the enclosed report.
-Three violations of NRC requirements were identified during the inspection. In the first
~ violation, two instances were noted whare the alternate parts replacement process was
- inappropriately used and attemate parts with different fit or function were evaluated by
.. procurement engineering, released for use and installed without using the design change
process. In the two noted instances, the replacement parts failed during testing and would
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not have performed .the required safety-related functions.
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August 22, 1997
In the second violation, adequate testing was not performed following changes made to
plant equipment to verify that the equipment would satisfactorily perform the required
safety-related functions.
The third violation documented two instances where actions were inadequate or untimely
to correct significant problems in using the design change and alternate parts evaluation
processes. Adequate corrective actions, after the discovery of the relief valve problem in
April of this year, could have substantially reduced the impact of problems with the
emergency diesel generator air start motors in May.
The violations are cited in the enclosed Notice of Violation (Notice) and the circumstances
surrounding them are described in detailin the enclosed report. Please note that you are
required to respond to this letter end 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,
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of tnis letter
and its enclosures will be placed in the NRC Public Document Room,
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
/s/
J. M. Jacobson (for)
John A. Grobe, Acting Director
Division of Reactor Safety
Docket Nos, 50-254, 50-265
License Nos, DPG-29, DPR 30
Enclosures:
2, inspoction Report 50 254/265/97010(DRS)
See Attached Distribution
DOCUMENT NAME: G:\\DRS\\QUA97010.D
To receive a cc py of this document, Indicato in the box *C's Copy wto attach /end "E" = Copy w/ attach /end "N' =2No copy
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OFFICIAL RECORD COF'Y
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August 22, 1997
cc w/encis:
T. J. Malman, Seinar Vice President,
Nuclear Operations Division
D. A. Sager, Vice President,
Generation Support
- H. W. Keiser, Chief Nuclear
Operating Officer
L. W. Pearce, Station Manager
C. C. Peterson, Regulatory Affairs Manager
1. Johnson, Acting Nuclear Regulatory
Services Manager
Document Control Desk Licensing
- Richard Hubbard
Nathan Schloss, Economist,
Office of the Attorney General
State Liaison Officer
Chairman, Illinois Commerce Commission
- J. R. Bull, Vice President, General &
Transmission, MidAmerican Energy Company
Distribution:
Docket Fife w
SRis, Quad Cities,
R. A. Capra, NRR w/ encl
fg M flE E,/ encl _
Whkeli
Dresden, LaSalle w/ encl
TSS w/enci
DC/LFDCB w/enct
LPM, NRR w/ encl
CAA1 w/enci
DRP w/ encl
A. B. Beach, Rlli w/ encl
DOCDESK w/enci
DRS w/enci-
J. L. Caldwell, Rllt w/onci
Rlli PRR w/enci
Rlli Enf. Coordinator w/enci
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