ML20198T282

Forwards Insp Repts 50-254/97-18 & 50-265/97-18 on 970922-25 & Notice of Violation.Violation Identified for Lack of Corrective Action After Identifying Substantial Recirculation Piping Cracks in 1996

ML20198T282
Person / Time
Site:	Quad Cities
Issue date:	11/10/1997
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Pearce L COMMONWEALTH EDISON CO.
Shared Package
ML20198T288	List: IR 05000254/1997018 ML20198T282 ML20198T311
References
50-254-97-18, 50-265-97-18, GL-88-01, GL-88-1, NUDOCS 9711140249
Download: ML20198T282 (3)

See also: IR 05000254/1997018

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November 10, 1997

Mr. L. W. Pearce

Site Vice President

Quad Cities Station -

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Commonwealth Edison Company

22710 206th Avenue North

Cordova,IL 61242

SUBJECT: NRC INSERVICE INSPECTION REPORT 50-254/97018(DRS);

50-265/97018(DRS) AND NOTICE OF VIOLATION

Dear Mr. Pearce;

On Sep' amber 25,1997, the NRC completed an inspection at the Quad Cities Nuclear Power

Station. The purpose of the inspection was to review the implementation of the inservice

. inspection (ISI) program for the past refusiing outages and the resolution of previously identified

issues. The enclosed report presents the results of this inspection.

We concluded that, overall, the implementation of your ISI program met ASME,Section XI

requirements and that the planned revision to the ISI program was a positive initiative.

However, we identified one examination record, in which a limited volumetric inspection was

performed, that apparently did not meet the ASME Code required percentage of coverage.

This limitation had not been noted in the ISI examination summary report, and no relief request

had been submitted. When viewed in context with the number and variety of the site's recent

problem identification forms for ISI related issues, this appears to warrant additional oversight to

assare that program weaknesses are corrected.

We identified a violation for your lack of corrective action after identifying substantial

recirculation piping cracks in 1996, which called into questicn the effectiveness of the induction

heat stress improvement process for crack mitigation. This was of concern since the

associated welds were not re-classsied in accordance with Generic Letter 88-01, Category D,

and intervals for the recircu!stion piping weld inspections were not adjusted. We recognize that

schedule adjustments can be made such that the recirculation system welds could be inspected

in accordance with GL 88-01 Category D; however, your staff's recent actions to resolve this ]f

issue were prompted by this inspection. I

We also identified a concern regarding the fatigue usage factor for the reactor vessel head

. studs. According to your previous evaluations, these studs will reach the ASME Code allowable

fatigue usage of 1.0 in 1998,"which will then require a more rigorous visual examination or

replacement." Since Unit 1 and 2 are scheduled to continue operation !nto 1998, and these

evaluation actions have not been completed, we request that you submit y Jur planned

corrective actions and schedule to resolve this issue with your violation response.

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9711140249 971110 i

PDR- ADOCK 05000254

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L. W. Pearce 2 Novmber 10, 1997

The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances

surrounding it is described in detail in the enclosed report. Please note that your 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. 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.

We will gladly discuss any questions you have conceming this inspection.

Sincerely,

Original Signed Bf J. A. Grobe

John A. Grobe, Director

Division of Reactor Safety

Dockets No. 50-254; 50-265

Licenses No. DPR-29; DPR-30

Enclosures: 1. Notice of Violation

2. Inspection Report 50-254/97018(DRS;;

50-265/97018(DRS)

cc w/encls: R. J. Manning, Executive Vice President, Generation

M. Wallace, Senior Vice President, Corporate Services

E. Kraft, Vice President, BWR Operations

Liaison Officer, NOC-BOD

D. A. Sager, Vice President, Generation Support

D. Farrar, Nuclear Regulatory Services Manager

1. Johnson, Licensing Operations Manager

Document Control Desk - Licensing

Quad Cities Station Manager

C. C. Peterson, Regulatory Affairs Manager

Richard Hubbard

Nathan Schloss, Economist,

i Office of the Attorney General

State Liaison Officer

Chairman, Illinois Commerce Commission

W. D. Leech, Manager of Nuclear,

MidAmerican Energy Company

DOCUMENT NAME: G:Qua97018.DRS

To receive a copy of this document. Indicate in the box *C" = Copy w/o attach /end *E* = Copy w/ attach /end *N" = No copy

OFFICE Rill:DRS lE Rill:DRS , . ,l A/ Rill:DRP ld Rlll:DPR l

NAME Holmberg/lc A Gavula YL/ ~ Miller /Z intut Grot $df/T

DATE 10hM97 10/11/97 \) " 10/4 97 j$/t &91

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OFFICIAL RECORD COPY

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Distribution:

' J Docket File w/enci SRI, Quad Cities w/ enc! TSS w/ enc!

PUBLIC IE-01 w/enci . LPM, NRR w/enct CAA1 w/enci

OCFO/LFARB w/enct A. B. Beach, Ritt w/enct DOCDESK w/enci'

- DRP w/enci - J. L. Caldwell, Rlli w/enci

- DRS w/ encl . Rill Enf. Coordinator w/enci-

Rill PRR w/enci R.' A. Capra, NRR w/enci- j

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