ML20207G160

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Forwards Insp Rept 50-254/98-21 & 50-265/98-21 on 981112- 1218 & NOV Re Failure to Identify to NRC Those Weld Where Complete Exam Coverage Was Determined to Be Impractical Along with Bases for That Determination
ML20207G160
Person / Time
Site: Quad Cities  Constellation icon.png
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

NOTICE OF VIOLATION

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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License Nos.: DPR-29; DPR-30

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Enclosures:

1. Notice of Violation

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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

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