ML20202G238
| 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: |
| References | |
| 50-254-97-22, 50-265-97-22, NUDOCS 9802200093 | |
| Download: ML20202G238 (4) | |
See also: IR 05000254/1997022
Text
{(,,M
o
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
200007
\\
\\
L .h lh.l .] c
1y l
/A
~
I
9902200093 980213
PER
ADOCK 05000254
"!
y Ui
.
G
. ,
_
_
__-
$
%
0. D. Kingsley
2
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.
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.
1
i
Sincerely,
/s/ H. O. Christensen for
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-254;50-265
Enclosures:
2. Inspection Report 50-254/97022(DRS);
50-266/97022(DRS)
See Attached Distribution
DOCUMENT NAME: G:\\DRS\\QUA97022.DRS
(SEE PREVIOUS CONCURRENCE)
To receive a co py of this document, Indicate in the box "C" = Copy 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
Enclosures:
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
t
.
_,
_
_ _ - . .
. . . _ _ _ _ , ,
.
_
- , _ _ . _ _ _ _ .
. _ , _ .
.
. .
-
-_
_ - - _ - - - - -
'
!
,
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
a