ML20198T282
| 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: |
| 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
Text
~
^
k l' .
hC
.
-
November 10, 1997
Mr. L. W. Pearce
- Site Vice President
Quad Cities Station
-
'
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.
.
' h
ll
~
,7
.
~
9711140249 971110
i
PDR- ADOCK 05000254
7 jf O j
G
te
,
,
--
-
.-
.
..
.
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
Enclosures:
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
&
'
OFFICIAL RECORD COPY
,
f
, --
,
n
--
. , , ,
,
- -
.
-
..
..
. , . ,
'L Pearce -
~3*
Novetter 10,-1997
_
h
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
i
!
i
l -..
'
!
i
')
l
il
<
.-
..
--
..
.
.