ML20198A166

Informs of Review of Unresolved Item Identified in Insp Rept 50-461/85-60 Re Acceptability of Preoperational Type a Test Conducted at Plant.Justification for Not Performing Another Type a Test Requested

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

1. ..

..

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

O 10

IN

,_

.. m

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

.

RIII RIII RIII RIII RIII RIII RIII

.

KaFe mab Ring lips K op

Y

Heh

Y

Chri Qtimos Papa)iello

u

5/15/86 6

6

g ,