ML17174A996

From kanterella
Jump to navigation Jump to search
Forwards Safety Inps Repts 50-237/91-32 & 50-249/91-35 on 911028-1112.One Violation Involving Inoperability of CP Valve 3-1601-24 Identified & Being Considered for Escalated Enforcement Action in Accordance w/10CFR2,app C
ML17174A996
Person / Time
Site: Dresden  
Issue date: 11/27/1991
From: Miller H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Reed C
COMMONWEALTH EDISON CO.
Shared Package
ML17174A997 List:
References
EA-91-164, NUDOCS 9112030117
Download: ML17174A996 (3)


See also: IR 05000237/1991032

Text

  • .

Docket No. 50-237

Docket No. 50-249

. EA-91-164

NOV 2 7 1991

Commonwealth Edison Company

ATTN:

Mr. Cordell Reed

Senior Vice President

Opus west IIl

1400 Opus Place

Downers Grove, Illinois 60515

Dear Mr. Reed:

SUBJECT:

NRC INSPECTION REPORT 50-237/91032; 50-249/91035

This ref e~s to the special safety inspection conducted by

Ms~ V. P. Lougheed and Mr. G. M. Nejfelt of this office on

October 28 through November 12, 1991.

During this inspection,

we evaluated activities at your Dresden Nuclear Power station,

Units 2 and 3, as authorized by NRC Operating Licenses

No. DPR-19 and No .. DPR-25.

We discussed our findings and

conclusions with Messrs. J. Kotowski and L. Gerner, as well as

others of your staff, at the conclusion of the inspection on

November 12, 1991..

Areas examined during the inspection are identified* in the

report.

This inspection specifically examined the events

surrounding the faiiure of the.local leak rate test for

containment drywell purge valve 3-1601-24.

Additionally, your

local leak rate testing program was reviewed.

Within these

areas,- the inspection consisted of selective examinations of

. procedures and representative records, interviews with personnel,

and observation of activities in progress.

Based on the results of this inspection, one apparent violation

was identified and is being considered for escalated enforcement

action in accordance with the "General Statement of Policy.and

Procedure for NRC Enforcement Actions" (Enforcement Policy) ,

.10 CFR Part 2, Appendix C (1991).

The apparent violation

involved the inoperability of containment isolation

valve 3-1601...;24 during the last operating cycle on Unit 3,. from

February 11, 1990, until September 8, 1991.

During this time

period, the valve was required to be operable by Technical

Specification 3.7.D.

The root cause of the valve being*

inoperable was due to a maintenance error which occurred during

valve operator work the previous operating cycie.

This

maintenance error was not discovered at

~AA2030117 911127

G

ADDCK 0_5000237

.

PDR

wr

.*

commonwealth Edison Company

2

NOV 2 'l 1991

the time because a local leak rate test was not performed

following the maintenance.

The failure to prescribe and perform

a local leak rate test as part*of the post-maintenance testing

was partially due to the use of *informal communication between

the maintenance groups and the local leak rate test group as to

when these tests were required.

Accordingly, no Notice of Violation is presently being issued for

this inspection finding.

Please be advised that the number and

characterization of apparent violations described in the enclosed

inspection report may change as a result of further NRC review.

You will be advised by separate correspondence of the results of

our deliberations on this matter.

No response regarding the

apparent violation is required at this time.

We do request, however, that you respond within 60 days of the

date of this letter to the unresolved item identified in the

attached inspection report.

Your response should include.the

date when you expect to submit the Technical Specification

amendment.

In accordance with 10 CFR 2.790 of the Commission's regulations,

a copy of this letter and the enclosures wi.11 be.placed in the*

NRC Public _Document Room.

The responses directed by this letter are not subject to the

clearance procedures of the Off ice 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,

OfdGINAL SIGNED BY .l. 0. flf:..,S. {:'.;

~&1. H1;1b7r~ J. Miller,* Director

D1v1s1on of Reactor Safety

Enclosure:

Inspection Reports

No. 50-237 /91032 (DRS) ;.

No. 50-249/91035(DRS)

See Attached Distribution

~

RIII 1 ,

y/t/

/ v:?\\

Lougheed

11/c;?J /91

RIII.

SEE-ATTACHED PAGE

  • Burgess

11/ . /91

RIII

RIII~

RJ;.J:I

Ne~lt

. hil ips

ight

. . .

.

~~./.~{fau

11;:?-D /91 '1111:1 /91 . 1/21/91

RIII

Rit'I

RII~

Pederson

11/ /91

Martin

11/ /91

Miller

11/ /91

Commonwealth Ed~son Company

Distribution

cc w/enclosure:*

D. Galle, Vice President -

BWR

Operations

T. Kovach, Nuclear

Licensing Manager

c. Schroeder, Station Manager

DCD/DCB (RIDS)

OC/LFDCB

Resident Inspectors LaSalle,

Dresden, Quad Cities

Richard Hubbard *

J. w. Mccaffrey, Chief, Public

Utilities Division

Robert Newmann, Office of Public

3

Counsel, State of Illinois Center

Licensing Project Manager, NRR

C. Paperiello, RA

B. Berson, RA

J. Lieberman, OE

J. Goldman, OGC

J. Partlow, NRR

NOV 2 7 1991