ML20202G238

Forwards Insp Repts 50-254/97-22 & 50-265/97-22 on 971027- 1121 & Nov.Violations Highlight Weaknesses in Procedure Adherence & in Quality of Procedures

ML20202G238
Person / Time
Site:	Quad Cities
Issue date:	02/13/1998
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Kingsley O COMMONWEALTH EDISON CO.
Shared Package
ML20202G241	List: IR 07100027/2011021 ML20202G238 ML20202G307
References
50-254-97-22, 50-265-97-22, NUDOCS 9802200093
Download: ML20202G238 (4)

See also: IR 05000254/1997022

Text

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February 13, 1998

Mr. Oliver D. Kingsley

President, Nuclear Generation Group

Commonwealth Edison Company

ATTN: Regulatory Services

Executive Towers West til

1400 Opus Place, Suite 500

Downers Grove,IL 60515

SUBJECT: NRC SYSTEM OPERATIONAL PERFORMANCE INSPECTION REPORTS

50-254/97022(DRS); 50-265/97022(DRS) AND NOTICE OF VIOLATION

Dear Mr. Kingsley:

On November 21,1997, the NRC completed a system operational performance inspection

(SOPI) at your Quad Cities Nuclear Power Station. The inspection team assessed the high

pressure coolant injection (HPCI) system's operational performance by a detailed review of

HPCI design, maintenance, operation, surveillance and testing. Additionally, the inspection

team assessed the effectiveness of licensee controls in identifying and resolving problems. The

enclosed report presents the results of this inspection.

The inspection team noted several positive attributes. These included good operator

knowledge of HPCI and supporting systems, overall good operator training lesson plans, and

an effective maintenance training facility, in preparation for and during the inspection, your staff

formed a SOPl counterpart team that demonstrated a high sensitivity toward identification and

documentation of HPCI problems resulting in a review of HPCI design basis information and in

detailed system walkdowns. The Quad Cities SOPl counterpart team Identified numerous

design basis document (DBD) and updated final safety analysis report (UFSAR) discrepancies,

drawing errors, and missing calculations. Similar findings were also noted by the NRC

in~,pectors.

Over the course of the inspection, the t'RC Inspectors noted that availaoility and retrievability of

design basis information continues to be an ongoing concem at Quad Cities. It is important that

design documents reflect the station's as-built configuration and that the design basis is well

understood by engineering particularly when modifying the station and performing operability

evaluations. We understand that Quad Cities Station has plans to validate the DBDs and to

complete a line by line validation of UFSAR design information. The NRC encourages you to

complete these efforts.

In addition, the inspection team noted deficiencies M the 10 CFR 50.59 safety evaluation

process includina weakr' esses with the 50.59 coeening proceas, and inconsistencies in safety

evaluations and SE reviews. While we understand that the station has created an engineering

assurance group (EAG) to independently review safety evaluations, actions taken to date have

not been fully effective in comprehensively addressing the program deficiencies. It will be

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February 13, 1998

necessary for Quad Cities Station to remain ;0cused on the identified deficiencies to ensure that

all aspects of the 10 CFR 50.59 process are being met.

Based on the results of th;s inspection, the NRC has determined that violations of NRC I

requkements occurred. These violations are cited in the enclosed Notice of Violation (Notice)

and the circum::tances surroundir.g them are described in detail in the subject inspection

report. The violations are of concern because they highlight weaknesses in procedure

adherence and in quality of procedures. Additionally, the procedure adherence issues also

implicate the overall quality of your 10 CFR 50.59 program. The design controlissue cited

illustrates how inadequate reviews of design basis information can affect the quality of

modifications,

You are required to respond to this letter and should foilow 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.

1

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

enclosur6(s), and your response will be placed in the NRC Public Document Rocm.

i

Sincerely,

/s/ H. O. Christensen for

John A. Grobe, Director

Division of Reactor Safety

Docket Nos.: 50-254;50-265

License Nos.: DPR-29; DPR-30

Enclosures: 1, Notice of Violation

2. Inspection Report 50-254/97022(DRS);

50-266/97022(DRS)

See Attached Distribution

DOCUMENT NAME: G:\DRS\QUA97022.DRS

To receive a co py of this document, Indicate in the box "C" = Copy (SEE PREVIOUS CONCURRENCE)

w/o attach /enci "E' = Copy w/ attach /end 'N' = No copy

OFFICE Rill:DRS l Rlll:DRS l Rill:DRP l Rill:DRS l

NAME Guzman/sd Jacobson Ring Grobe

DATE 2/ /98 2/ /98 2/ /98 2/ /98

OFFICIAL RECORD COPY

_ _ _ _ _ .

.. . . - - - . _ _ - _ - - - - . - . - . . . - . . - . . .

, i

1

O. D. Kingsley 2 February 13, 1998

Based on the results of this intpection, the NRC has determined that violations of NRC

requirements occurred. These violations are cited in the enclosed Notice of Violation (Notice)  :

and the circumstances surrounding them era described in detail in the subject inspection

report. The vlocations are of concern because they highlight weaknesses in procedure

adherence and in quality of procedures. Additionally, the procedure adherence lasues also

implicate the overall quality of your 10 CFR 50.59 program. The design controiiswo cited ,

illustrates how inadequate reviews of design basis information can affect the quality of

modificctions.

. i

Yc.. Je required to respond to this letter and should follow the instructions specified in tha ,

ent.lvsed 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 c, the NRC's * Rules of Practice," a copy of this letter, its

enclosure (s), and your response will be placed in the NRC Public Document Room.-

Sincerely,

John A. Grobe, Director

Division of Reactor Safety

Docket Nos.: ' 50 254; 50 265

License Nos,: DPR 29; DPR 30

Enclosures: 1, Notice of Violation

2. Inspection Report 50-254/97022(DRS);

50-265/97022(DRS)

Sag,Atte,ched Distribution

,

DOCUMENT NAME: G:QUA97022.DRS

- To receive a copy of this document. Indicate in the bot *C's Copy w/p httacNend *E's Copy w/ attach /end *H* a No copy

OFFICE- Rill:DRS 6 Rill:DRSA m t// Rill:DRP 6 Rlll:DRS _ lh

NAME Guzman/sd G5 Jacobso}LitA.X RirWO Grobe %E res

DATti 2/11/9 8 #

2/0/98 / \} ( ) 2A2/98 2/(S98

OFFICil4Rt: CORD COPY

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. _, _ _ _ - . . . . . _ _ _ _ , , - , _ _ . _ _ _ _ . . _ , _ . -

-_ _ - - _ - - - - -

'

! ,

O. D. Kingsley 3 February 13, 1998

cc w/encls: M. Wallace, Chief of Staff

D. Helwig, Senior Vice President

G. Stanley, PWR Vice President

J. Perry, BWR Vice President

i D. Farrar, Regulatory

l Servlees ManaCor

l l Jot..ison, Lloensing Director

l

DCD - Lloonsing

. E. Kraft, Jr., Site Vios President

i

D. Cook, Quad Cities Station Ma, Jer l

C. C. Peterson, Regulatory Affairs .

Menacer

Richard Hubbard

Nathan Schloss, Economist

Office of the Attorney General

State Llaison Officer

Chairman, !!linois Coramerce

Commission

W. D. Leech, Manager of Nuclear

MidAmerican Energy Company

Distribution

Docket File w/encls Rlli PRR w/encls Rlli Enf. Coordinator w/encls

PUBLIC IE-01 w/encls SRI, Quad Cities w/encls TSS w/encls

LPM, NRR w/encls J. L. Caldwell, Rlll w/encls R. A. Capra, NRR w/encls

DRP w/encls A. B. Beach, Rlli w/encls DOCDESK w/encls

DRS w/encls LEO w/encls

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