ML17201J323
| ML17201J323 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/23/1988 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17201J324 | List: |
| References | |
| NUDOCS 8807110365 | |
| Download: ML17201J323 (6) | |
See also: IR 05000249/1988200
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
June 23, 1988
Docket No. 50-249
Mr. Cordell Reed, Senior Vice President
ColTITionwealth Edison Company
P.O. Box 767
Chicago, IL
60690
Dear Mr. Reed:
SUBJECT:
DRESDEN UNIT 3 - SAFETY SYSTEMS OUTAGE MODIFICATIONS
CORRECTIVE ACTIONS INSPECTION 50-249/88-200
This letter conveys the report for the followup inspection to the Safety
Systems Outage Modifications Inspections (SSOMis) performed by an- NRC
Headquarters team during February 22-26 and March 7-11, 1988 at the Dresden
Unit 3 station. The inspection team was composed of personnel from the NRC's
Office of Nuclear Reactor Regulation and consultants. At the conclusion of
the inspec,tion the findings were discussed with members of your staff identi-
fied in the enclosed report.
.
This SSO~I followup assessed the corrective actions taken by the Corrmonwealth
Edison Company in response to the initial Dresden Unit 3 SSOMI findings
documented in inspection reports 50-249/86-009 and 50-249/86-012, and closed
some items that remained open after the original inspections. The specific
areas reviewed included deficiencies, unresolved items, and observations from
those two reports~ and the corrective actions taken to resolve them.
The inspectors found improvements in procedures, programs and the physical
condition of the plant, and did not identify any additional violations or
deviations .. However, the team was unable to close a number of items that had
been opened by the previous SSOMis, because the root causes had not been
adequately determined or corrective actions that addressed the root causes
were inadequate. Actions had not yet been taken to prevent recurrence of
a number of concerns. Weaknesses identified by the. team are discussed in
the enclosed inspection report and su11111arized in the enclosed executive
summary.
A response to this letter is not required.
The rec011111ended actions for
closing the open items discussed in this report have been reviewed with Region
I I I personne 1. The regi ona 1 office wi 11 notify you of any further responses
that its personnel consider necessary with regard to the open items. The
regional office will also notify you of any enforcement actions which result
from this inspectio~.
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In accordance with 10 CFR 2.709(a) a copy of this letter and the enclosure
will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we would be pleased
to discuss them with you.
Enclosures:
1 .. Executive Summary
2.
Inspection report 50-249/86-200
cc w/enclosures:
See next page
Sincerely,
~
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Dennis M. Crutchfield, Director
Division of Reactor Projects - III, IV, V
and Special Projects
Office of Nuclear Reactor Regulation
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'cc w/enclosures:
Michael 1. Miller, Esq .
Sidley and Austin
One First National Plaza
Chicago, Illinois 60602
Mr. J. Eenigenburg
Plant Superintendent
Dresden Nuclear Power Station
Rural Route #1
Morris, Illinois 60450
U.S. Nuclear Regulatory Conunission
Resident Inspectors Office
Dresden Nuclear Power Station
Rura 1 Route #1
Morris, Illinois 60450
Chainnan
Board of Supervisors of
Grundy County
Grundy County Courthouse
Morris, Illinois 60450
Regional Administrator
U.S. Nuclear Regulatory C001T1ission, Region III
799 Roosevelt Road
Glen Ellyn, Illinois 60137
Mr. Michael E. Parker, Chief
Division ~f Engineering
Illinois Department of Nuclear Safety
. 1035 Outer Park Drive, 5th Floor
Springfield, Illinois 62704
Institute for Nuclear Power Operations
1100 Circle 75 Parkway
Atlanta, Georgia
30339
June 23, 1988
... *
EXECUTIVE SUMMARY
The reviews and improvement programs undertaken by the licensee for the Dresden
Unit 3 Nuclear Generating Station as a result of the SSOMis and subsequent
Region III and headquarters inspections were extensive.
The follow up inspec-
tion noted improvements in a number of CEC.o engineering and Dresden site
procedures and programs, and with the physical condition of the plant. Discus-
sions with the licensee on the individual items revealed in some cases that,
although not discussed in the official response to the Notice of Violation,
actions had been taken which resolved the items.
The written response to the
NRC's Notice of Violation from the SSOMis was, in many cases, not complete or
did not address the concern described in the inspection reports.
The team noted
weaknesses in the following areas:
1.
Root Cause Corrective Actions
Although a CECo task force, established as a result of the SSOMis, tdentified
employees' failure to adequately follow procedures as a major root cause for
the SSOMI findings, the corrective actions taken were not comensurate with the
significance of the problem.
The team did not find evidence that a management
philosophy of strict procedural adherence extended beyond the operations
department.
2.
Safety Evaluation Corrective Actions
The SSOMis identified in a number of cases that evaluations done in accordance
with 10 CFR 50.59 were not adequately justified or were not performed at all.
The followup inspection team found that the safety evaluations performed to
address the SSOMI findings were also deficient. The safety evaluation for the
reactor. building penetration modification was reperfonned because di mens ions*
in the original analysis did not match the actual installation. The team
found that the analysis used for the new safety evaluation still referenced
incorrect location dimensions.
The SSOMI team found that the safety evalu-
ations for analog trip system modifications did not address the effects that
significant chang~s made by the modifi~ations would have on the system.
The
reevaluations performed as* a result of the SSOMI finding did address the
specific effects identified in the SSOMI report.
However, the evaluations
were reviewed and approved even though they identified a potential degradation
of safety-related equipment.
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