ML20198A166
| ML20198A166 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/16/1986 |
| From: | Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 8605200350 | |
| Download: ML20198A166 (2) | |
See also: IR 05000461/1985060
Text
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MAY 1 0 1985
Docket No. 50-461
Illinois Power Company
ATTN:
Mr. W. C. Gerstner
Executive Vice President
500 South 27th Street
Decatur, IL 62525
Gentlemen:
Our inspection report sent to you on April 7, 1986 (Inspection Report No.
50-461/85060(ORS)), identified an unresolved item relating to the acceptability
of the preoperational Type A test conducted at the Clinton Nuclear Power
Station. We have completed our review and have determined that the work effort
and activities in and on the containment liner since the January 1986 Type A
test results were obtained have left Region III doubtful that these results
will be representative of the containment's leakage when containment integrity
is required.
The intent of 10 CFR Part 50, Appendix J, as it relates to the Preoperational
Type A test, is to accurately measure the Primary Reactor Containment overall
leakage rate after the containment is complete and ready for operation.
Specifically, Appendix J requires that the Type A test be conducted after the
construction of the primary containment is complete and prior to any reactor
operating period.
Appendix J also requires that modifications to the
containment liner after the Preoperational Type A test be followed by an
applicable leak test.
The test performed in January 1986 does not appear to meet the intent of
. .
Appendix J for a Preoperational Type A test in that the Type A test was
performed prior to the completion of the containment structure as evidenced by
,
a hole in the liner during the test, the numerous modifications that occurred
following the test as described in the inspection report (50-461/85060(DRS)),
and the lack of stringent control of work activities in containment after the
test.
These findings bring into question the validity of the test results.
Please provide to the Region III office your justification as to why you should
not perform another Preoperational Type A test prior to the time that technical
specifications would require containment integrity.
In particular, please
demonstrate the following:
1.
The adequacy of the controls in place subsequent to the January 1986 test
'
to protect the containment liner from damage and to ensure containment
,
integrity; and
%[MO
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10
IN
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Illinois Power Company
2
MAY 161986
2.
The integrity of the portions of the containment involved in the
modifications described in inspection report 50-461/85060(DRS).
.We will gladly discuss any questions you may have concerning this matter.
Sincerely,
b
Carl J! Pap
ello, Director
Division of Reactor Safety
cc:
DCS/RSB (RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII
Richard Hubbard
Gary N. Wright, Manager
Nuclear Facility Safety
Jean Foy, Prairie Alliance
Mark Jason, Assistant
Attorney General,
Environmental Control Division
H. S. Taylor, Quality Assurance
Division
.
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