ML20207G160
| ML20207G160 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 03/05/1999 |
| From: | Reynolds S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20207G165 | List: |
| References | |
| 50-254-98-21, 50-265-98-21, NUDOCS 9903120010 | |
| Download: ML20207G160 (4) | |
See also: IR 05000254/1998021
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March 5,-1999
Mr. Oliver D. Kingsley
President, Nuclear Generation Group
Commonwealth Edison Company
ATTN: Regulatory Services
Executive Towers West 111
1400 Opus Place, Suite 500
Downers Grove, IL 60515
SUBJECT:
NRC INSPECTION REPORT 50-254/98021(DRS); 50-265/98021(DRS) AND
Dear Mr. Kingsley
On December 18,1998, the Nuclear Regulatory Commission (NRC) completed an inspection at
the Quad Cities Nuclear Power Station. The purpose of the inspection was to determine
. whether activities authorized by the license were conducted safely and in accordance with NRC
requirements. The NRC and Illinois Department of Nuclear Safety conducted a routine
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inspection to review the implementation of the inservice inspection (ISI) program for the Quad
Cities Unit 1 refueling outage 15 (RFO15). This consisted of a selective examination of
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procedures and representative records, interviews with personnel, and observations of activities
- in progress. In addition, this inspection also reviewed activities associated with your overall ISI
program for each unit, as well as follow-up inspections for certain previously identified items.
The results of the inspection were discussed with Mr. J. Dimmette, Jr. and other members of
your staff on December 18,1998. The enclosed report presents the results of this inspection.
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In general, the inservice inspections performed during the Unit 1 RFO15 were adequately
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implemented and the observed activities were properly performed. We observed that material
condition problems continued to affect equipment. Of particular note were the number of
intergranular stress corrosion cracking (lGSCC) indications in the Unit 1 recirculation system
piping, core spray system, and reactor vessel jet pumps. While your inservice inspection'
program . identified the deficient conditions and the flaws were adequately addressed, the
identification of additional IGSCC cracking in the recirculation system provided further evidence
that previous stress improvement efforts were ineffective.
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The self-assessment for the inservice inspection ' restoration effort' was considered an
aggressive attempt to identify additional program problems, in response to issues previously
. identified by the NRC. Implementation of corrective actions however were slow, resulting in a
significant amount of work remaining.
After review of your last completed ISI Program interval, we concluded that a violation of NRC
regulatory requirements occurred. For the ASME Code weld examinations performed during the
Quad Cities Unit 1 and Unit 2 Second Ten Year ISI Intervals, you failed to identify to the NRC
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those welds where complete examination coverage was determined to be impractical along with
the bases for that determination. As this issue was brought to your attention by the NRC in
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1997, timeliness of corrective actions is considered poor. The violation is cited in the enclosed
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Notice of Violation (Notice) and the surrounding circumstances are described in detail in the
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subject inspection report. The violation serves as another example of the slow recovery of your
ISI program.
Ycu are required to respond to this letter and should follow the instructions specified in the
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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.
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosures, and your response will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have conceming this inspection.
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Sincerely,
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Original /s/ John A. Grobe for
Steven A. Reynolds, Deputy Director
Division of Reactor Safety
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Docket Nos.: 50-254; 50-265
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Enclosures:
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2. Inspection Reports 50-254/98021(DRS);
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50-265/98021(DRS)
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cc w/encis:
D. Helwig, Senior Vice President
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H. Stanley, PWR Vice President
C. Crane, BWR Vice President
R. Krich, Vice President, Regulatory Services
DCD - Licensing
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J. Dimmette, Jr., Site Vice President
W. Pearce, Quad Cities Station Manager
C. Peterson, Regulatory Affairs Manager
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M. Aguilar, Assistant Attomey General
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State Liaison Officer
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Chairman, Illinois Commerce Commission
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W. Leech, Manager of Nuclear
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MidAmerican Energy Company
See Attached Distribution
DCCUMENT NAME: G:DRS\\QUA98021.wpd
See Previous Concurrence
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