ML20058E689
| ML20058E689 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/26/1990 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20058E690 | List: |
| References | |
| NUDOCS 9011070274 | |
| Download: ML20058E689 (2) | |
See also: IR 05000254/1990019
Text
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Docket No'. 50-254
OCT 2619%
Docket No. 50-265
Commonwealth Edison Company
ATTN: Mr. Cordell Reed
Senior Vice President
Opus West 111
1400 Opus Place
Downers Grove,'IL 60515
This refers to the management meeting conducted by Mr. H. J. Miller, and
other members of the Region 111 staff, with Mr. D. Galle, and other members
of your staff, on September 25, 1990 at the Region 111 office in Glen Ellyn,
Illinois, and subsequent _ telephone call between Mr. N. Kalivianaks of your
staff and Mr. H. J. Miller on 0ctober 3,1990.
The meeting and call were held
.
.to discuss NRC concerns related to containment performance testing at the
-Quad Cities Nuclear Station authorized by HRC Operating Licenses No. DPR-29
and No. DPR-30.
- The' enclosed copy of our report identified those matters discussed during the
meeting, which focused on your response to violation 50-254/89024-02;
50-265/89024-02, dealing with the results of Quad Cities local leak rate
testing -
We considered the' actions planned and being taken with respect to the selected
valves discussed in the September-25, 1990, meeting to be reasonable.
~However,= and notwithstanding the information provided in your letter of
October 9,'1990, the NRC staff continues to be concerned about Commonwealth
Edison!s plan, to take no action on the remaining valves until a comprehensive
assessment:of valve maintenance and performance history is completed in its-
entirety; ;The staff believes that you should review the data on valve
performance' already 'in hand to determine what, if any, _ maintenance might be
_
prudent during this-upcoming outage - that is, not wait until all precise-
idspects of the assessment are complete before anything is done.- These'
concerns are rooted in.the greater than ten year history of penetration
failures at the end of. operating cycles which indicate that- containment
_ performance at some point in each of these cycles has significantly fallen
- below requirements. At the present time, the NRC staff will not. pursue the
. issue of' accelerated valve penetration testing pursuant to your commitment to
-Regulatory Guide 1.33 ( ANS 18.7 - 1972). .However, this matter and any
-enforcement actions will be reconsidered in connection with'NRC staff review
of. testing done during .the upcoming Unit 1 outage in the fall'of 1990 and the
unit 2 outage in 1991.
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OCT _2 61YD
.
Additionally, we are documenting our review of your responses, as submitted by
letter dated August 17, 1990, to the other violation and unresolved items
contained in the above reports, and to our review of the results of your Unit 2
April 1990 integrated leak rate test as submitted on July 26, 1990,
in accordance with 10 CFR Part 2.790 of the Commission's regulations, a copy
of this letter and the enclosures will be placed in the Public Document Room.
We will gladly answer any questions you have regarding either the meeting, or
the report.
Sincerely,
u m J a S:C:!t0 Di W.h a ! L I' T.![3
Hubert J. Miller, Director
Division of Reactor Safety
Enclosure:
Inspection Reports
-No.
50-254/90019(DRS)
No.
50-265/90019(DRS)
cc w/ enclosure:
~,
D. Galle, Vice President - BWR
Operations
T. Kovach, Nuclear
LLicensing Manager-
,
R. L. Bax,_ Station-Manager
!
DCD/DCB(RIDS)'
OC/LFDCB-
- Resident Inspectorr. LaSalle
Dresden, Quad Cities
Richard Hubbard
'
J. W. McCaffrey, Chief, Public
Utilities' Division
L. 01shan, NRR LPM
Robert Newmann, Office of Public
Counsel, State of Illinois Center
J. Kudrick, SPLB, NRR-
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