ML20210A315

Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations

ML20210A315
Person / Time
Site:	Byron
Issue date:	07/16/1999
From:	Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Kingsley O COMMONWEALTH EDISON CO.
Shared Package
ML20210A319	List: IR 05000454/1999008 ML20210A315
References
50-454-99-08, 50-454-99-8, 50-455-99-08, 50-455-99-8, NUDOCS 9907220064
Download: ML20210A315 (3)

See also: IR 05000454/1999008

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UNITED STATES

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NUCt. EAR REGULATORY COMMISSION

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j 801 WARRENVILLE ROAD

LISLE, ILLINOIS 60532-4351

%o...+j* July 16,1999

Mr. Oliver D. Kingsley

President, Nuclear Generation Group

Commonwealth Edison Company

ATTN: Regulatory Services -

Executivs Towers West lit

1400 Opus Place, Suite 500 ,

Downers Grove,IL 60515

l SUBJECT: BYRON INSPECTION REPORT 50-454/99008(DRP); 50-455/99008(DRP)

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Dear Mr. Kingsley:

l On June 21,1999, the NRC completed an inspection at the Byron 1 and 2 reactor facilities.

l The enclosed report presents the results of that inspection.

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! During this inspection period, control room operations were conducted in a safe, professional,

i and controlled manner. We observed that your operators' response to the Unit 1 automatic reactor trip from full power was excellent. The operators effectively controlled and stabilized

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plant parameters'and all plant safety-related systems operated as designed. The shift manager

I and unit supervisor demonstrated strong command and control throughout the event.

Throughout this inspection period, we observed that operators generally adhered to the

station's standards for control room conduct, procedural adherence, annunciator response, and

use of three-way communications.

We note eat human performance errors at Byron Station continue, and while we recognize that

you have hnplemented corrective actions to address these human performance issues over the

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past year, those actions have not yet been fully effective. On May 13,1999, Unit 1 experienced

an automatic reactor trip from full power when an instrument maintenance technician, while

l performing a calibration test, incorrectly removed instrument power fuses from a power range

! nuclear instrument. We noted that following this event, you conducted a " stand down" of

maintenance work activities to discuss the event and to reinforce the importance of performing

error reduction techniques.

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We have also observed that your process for engineering design modifications has not been

consistently implemented. In recent inspection reports, we identified examples where operators

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were not properly trained and procedures were not appropriately revised following the

installation of plant systems modifications. During this inspection period, we identified three

examples wherein testing requirements were not incorporated into modification work request

instructions, and the post-modification testing requirements were either not completed or test

completion was not appropriately documented.

9907220064 990716'

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PDR ADOCK 05000454

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O. Kingsley -2-

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Based on the results of this inspection, the NRC has determined that three violation's of NRC .

requirements occurred. These violations are being treated as Non-Cited Violations (NCVs),  !

consistent with Appendix C of the Enforcement Policy. These NCVs are described in the l

subject inspection report. If you contest the violation or severity level of these NCVs, you

should provide a response within 30 days of the date of this inspection report, with the basis for

your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk,

Washington DC 20555-0001, with copies to the Regional Administrator, Region lil, and the

Director, Offico of Enforcement, United States Nuclear Regulatory Commission, Washington, j

DC 20555-0001. l

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its

enclosure, and your response, if you choose to provide one, will be placed in the NRC Public

Document Room.

l

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

Sincerely,

/s/ M. J. Jordan

Michael J. Jordan, Chief

Reactor Projects Branch 3

Docket Nos. 50-454; 50-455

License Nos. NPF-37; NPF-66

Enclosure: Inspection Report 50-454/99008(DRP);

50-455/99008(DRP)

cc w/ encl: D. Helwig, Senior Vice President

H. Stanley, PWR Vice President

C. Crane, BWR Vice President -

R. Krich, Vice President, Regulatory Services

DCD - Licensing

W. Levis, Site Vice President

R. Lopriore, Station Manager

B. Adams, Regulatory Assurance Manager

M. Aguilar, Assistant Attorney General

State Liaison Officer

State Liaison Officer, State of Wisconsin ,

Chairman, Illinois Commerce Commission

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DOCUMENT NAME: G:\BYRO\BYR99008.DRP i

To receive a co py of this document , Indicate in the boxj *C" = Cop 9 w/o attach /end *E's Copy w/ attach /enci "N" = No copy i

OFFICE Rlll:DRP E Rill:DRnN \\ l Rlll:DRP hB l

NAME Tongue /kjco(7f Jacobson WEk ) Jordan @ Q/

DATE 07//Y/99 07/Y\/99 NI\ 07//6 /99 //

OFFICIAL RECORD COPY

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! O. Kingsley -3- l

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Distribution:

i COT (E-Mail)

l RPC (E-Mail) .

i Project Mgr., NRR w/ encl

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J. Caldwell, Rlil w/ encl

B. Clayton, Rllt w/enci j '

SRI Byron w/enci

DRP w/enci  !

DRS w/enci (

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Rlli PRR w/enci

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PUBLIC IE-01 w/enci

Docket File w/enci

GREENS

LEO (E-Mail)

DOCDESK (E-Mail) -

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