ML17326B016

Forwards Safety Insp Repts 50-315/85-25 & 50-316/85-25 on 850814-0905 & Notice of Violation.Concerns Re Containment Temp Survey Requirements & Corrective Action Taken on Excessively Leaking Containment Isolation Valves Identified

ML17326B016
Person / Time
Site:	Cook
Issue date:	10/18/1985
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
Shared Package
ML17326B017	List: IR 05000315/1985025 IR 05000814/2009005 ML17326B016
References
NUDOCS 8510230160
Download: ML17326B016 (4)

See also: IR 05000315/1985025

Text

OCT 18 1985

Docket No. 50-315

Docket No. 50-316 /f5 L5

American Electric Power Service

Corporation

Indiana

and Michigan Electric Company

ATTN:

Mr. John

E. Dolan

Vice Chairman

Engineering

and Construction

1 Riverside Plaza

Columbus,

OH

43216

Gentlemen:

This refers to the routine safety inspection

conducted

by Mr. S.

M. Hare of this

office on August

14 through September

5, 1985, of activities at Donald C.

Cook

Nuclear Plant, Units

1 and 2, authorized

by NRC Operating Licenses

No.

DPR-58

and No. DPR-74 and to the discussion

of our findings with Mr. W. G. Smith at the

conclusion of the inspection.

The enclosed

copy of our inspection report identifies areas

examined during

the inspection.

Within these

areas,

the inspection consisted of a selective

examination of procedures

and representative

records,

observations,

and

interviews- with-personnel.

During this inspection, certain of your activities appeared

to be in violation

of NRC requirements,

as specified in the enclosed

Ap~endix.

A written response

is required.

Additionally, Paragraph

4.d and Paragraph

7.a of the enclosed

report identify

concerns

we have relative to containment

temperature

survey requirements

and

corrective action you have taken

on excessively

leaking containment isolation

valves.

In your response

to this inspection report you are requested

to;

respond to the unresolved

item (315/85025-03(DRS))

identified in Paragraph

4.d, pertaining to containment

temperature

survey requirements

and; include

a

Kist of containment isolation valves that have

been consistently failing (30%

or greater failure rate) their local leak rate tests,

a summary of the corrective

actions

taken

and your plans to preclude excessive

containment isolation valve

leakage in the future.

In accordance

with 10 CFR 2.790 of the Commission's

regulations,

a copy of

this letter, the enclosures,

and your response

to this letter will be placed

in the NRC's Public Document

Room.

8510230160

851018

PDR

ADOCK 05000315.

PDR ~

i/I

(

I

I

I'

~

I

lit

I

ll

1

41

It

f

I.

II

~

It ~

II I

I

I

I

II

American Electric Power Servic

Corporation

OCT l 8 1985

The responses

directed

by this letter and the accompanying

Notice are not subject

to the clearance

procedures

of the Office of Management

and Budget as required

by

the Paperwork

Reduction Act of 1980,

PL 96-511.

We will gladly discuss

any questions

you have concerning this inspection.

Sincerely,

Enclosures:

1.

Appendix, Notice

of Violation

2.

Inspection

Reports

No. 50-315/85025

DRS);

No. 50-316/85025

DRS)

cc w/enclosures:

W. G. Smith, Jr., Plant Manager

DCS/RSB

(RIDS)

Licensing

Fee Management

Branch

Resident

Inspector, RIII

Ronald Callen, Michigan

Public Service

Commission

EIS Coordinator,

USEPA

Region

5 Office

Nuclear Facilities

and

Environmental

Monitoring

Section

r

C. J.

Pa eriello, Director

Division of Reactor Safety

RIII

RIII

QI>>A'are/ls

Guldemond

10/15/85

>o[(e(gg

mermann

y s

RI

Pa

(el 1 o

Jo g,>

.n

I

V

I

Veil

~ I

I

I

~

~

I

I

I

l

I V

/

I

I I

I

i"

J

VF

V

V

, /1

I

J~I