ML17334B722

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Forwards Insp Repts 50-315/98-05 & 50-316/98-05 on 980121- 0227 & 0319.Violations Noted.Insp Reviewed Activities Related to Surveillance Testing,Corrective Action & Maint of Design Basis for Ice Condenser
ML17334B722
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/10/1998
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Fitzpatrick E
AMERICAN ELECTRIC POWER CO., INC.
Shared Package
ML17334B723 List:
References
50-315-98-05, 50-315-98-5, 50-316-98-05, 50-316-98-5, EA-98-150, EA-98-151, EA-98-152, NUDOCS 9804170060
Download: ML17334B722 (8)


See also: IR 05000315/1998005

Text

CATEGORY 2

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9804170060

DOC.DATE: 98/04/10

NOTARIZED: NO

DOCKET ¹

FACIL:50-315 Donald C.

Cook Nuclear

Power Plant, Unit 1, Indiana

M

05000315

50-316 Donald C.

Cook Nuclear

Power Plant, Unit 2, Indiana

M

05000316

AUTH.NAME

AUTHOR AFFILIATION

GROBE,J.A.

Region

3

(Post

820201)

RECIP.NAME

RECIPIENT AFFILIATION

FITZPATRICK,E.

Indiana Michigan Power Co.

(formerly Indiana

& Michigan Ele

SUBJECT:

Forwards insp repts

50-315/98-05

& 50-316/98-05

on 980121-

0227

& 0319.Violations noted.Insp

reviewed activities

related to surveillance testing, corrective action

& maint of

design basis for ice condenser.

DISTRIBUTION CODE'EOIF

COPIES

RECEIVED'LTRI ENCL

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SIZE'

7

TITLE: General

(50 Dkt) -Insp Rept/Notice of Violation Response

NOTES:

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INTERNAL:

RECIPIENT

ID CODE/NAME

PD3-3

PD

AEOD/SPD/RAB

DEDRO

NRR/DRCH/HHFB

NRR/DRPM/PERB

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RGN3

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01

COPIES

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NUDOCS-ABSTRACT

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EXTERNAL: LITCO BRYCE,J H

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NUDOCS FULLTEXT

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NRC FLOPPY

NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS

OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL

DESK

(DCD)

ON EXTENSION 415-2083

TOTAL NUMBER OF COPIES

REQUIRED:

LTTR

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April 10,

1998

EA 98-150;98-151; 98-152

Mr. E. E. Fitzpatrick

Executive Vice President

Nuclear Generation Group

American Electric Power Company

500 Circle Drive

Buchanan, Ml 49107-1395

SUBJECT:

NRC INSPECTION REPORT NO. 50-315/98005(DRS); 50-316/98005(DRS)

Dear Mr. Fitzpatrick:

On February 27, 1998, the NRC completed an on-site inspection at your D. C. Cook 1 and 2

reactor facilities. A final exit to update your staff on the regulatory characterization of issues

identified in this inspection was conducted by telephone on March 19, 1998. The purpose of

this inspection was to review your activities related to surveillance testing, corrective action and

maintenance of the design basis for the ice condenser.

The enclosed report presents the

results of this inspection.

Based on the results of this inspection, 29 apparent violations were identified and are being

considered for escalated enforcement action in accordance with the "General Statement of

Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600.

These apparent violations are grouped into three areas; surveillance testing, corrective action

and maintenance of the design basis as discussed

below.

Eight apparent violations of 10 CFR 50 Appendix B (three Criterion V, four Criterion XI, and one

Criterion Vll)and two apparent violations of technical specifications were identiTied pertaining to

inadequate surveillance testing of the ice condenser.

Specifically, these violations related to,

inadequate instructions, inadequate acceptance

limits, inadequate control of contractors, failure

to implement technical specification requirements and entry into an unanalyzed condition.

Additionally, an apparent violation 10 CFR 50 Appendix B, Criterion V was identiTied for failure

to followthe procedure change process for completed surveillance tests.

Collectively, these

apparent violations represent a programmatic breakdown in surveillance testing of the ice

condenser.

Seven apparent violations of 10 CFR 50 Appendix B, Criterion XVIwere identified pertaining to

your staffs failure to promptly identify conditions adverse to quality or take appropriate

cor'rective actions.

Inspectors'ntervention

was necessary to prompt your staff to identify:

blocked flow passages,

missing ice segments,

dented/buckled basket webbing, unweighable

ice baskets, and nonencapsulated

insulation within the ice condenser.

Further,

inspectors'ntervention

was necessary

to prompt your staff: to implement corrective actions for missing ice

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E. Fitzpatrick

basket sheet metal screws, to take corrective actions for preventing the recurrence of loose

U-bolt nuts and separated

ice baskets, and to take appropriate corrective actions for the ice

baskets with defective hold down bar welds.

Collectively, these apparent violations represent a

breakdown in your corrective action program for the ice condenser.

Seven apparent violations of 10 CFR 50.71(e) were identified pertaining to your staff's failure to

update and maintain the Final Safety Analysis Report Appendices J and M, which contain the

detailed description and design basis for the ice condenser.

Additionally, four apparent

violations of 10 CFR 50 Appendix B, Criterion IIIwere identified pertaining to a failure to follow

the established design control process for ice basket modifications. Collectively, these

apparent violations represent a programmatic breakdown in the maintenance of the design

basis for the ice condenser.

NRC intervention was needed to call attention to these programmatic problems.

Further, the

weaknesses

in each of these program areas has directly or indirectly contributed to a poor state

of materiel condition for each ice condenser,

such that the ability of the ice condenser to

perform its design function during past plant operation is in question.

Allowingthe ice

condensers

to degrade to this condition demonstrates

that your staff did not pay appropriate

attention to maintaining the reliability and availability of a key safety system.

No Notice of Violation is presently being issued for these apparent violations.

In addition, be

advised that the number and characterization of the apparent violations described in the

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

An open predecisional enforcement conference to discuss these apparent violations will be

scheduled

in the near future. The decision to hold a predecisional enforcement conference

does not mean that the NRC has determined that violations occurred or that enforcement action

willbe taken.

This conference will be held to obtain information to enable the NRC to make an

enforcement decision, such as a common understanding of the facts, root causes,

missed

opportunities to identify the apparent violations sooner, corrective actions, significance of the

issues, and the need for lasting and effective corrective action.

In addition, this is an

opportunity for you to provide any information concerning your perspectives

on:

1) the severity

of the violations, 2) the application of the factors that the NRC considers when it determines the

amount of a civil penalty that may be assessed

in accordance with Section VI.B.2 of the

Enforcement Policy, and 3) any other application of the Enforcement Policy to this case,

including the exercise of discretion in accordance with Section Vll.

You will be advised by separate correspondence

of the results of our deliberations on this

matter.

No response

regarding these apparent violations is required at this time.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its

enclosures will be placed in the NRC Public Document Room.

h

',1

E. Fitzpatrick

We willgladly discuss any questions you have concerning this inspection.

Sincerely,

original /s/ J. A. Grobe

John A. Grobe, Director

Division of Reactor Safety

Docket Nos.: 50-315, 50-316

License Nos.: DPR-58, DPR-74

Enclosure:

Inspection Report No. 50-315/98005(DRS);

50-316/98005(DRS)

cc w/encl:

John Sampson,

Site Vice

President

A. A. Blind, Vice President

Nuclear Engineering

Douglas Cooper, Plant Manager

Richard Whale, Michigan Public

Service Commission

Michigan Department of

Environmental Quality

Emergency Management

Division, Ml Department

of State Police

~DI jiijtiqn:

Docket File w/encl

PUBLIC IE-01 w/encl

Project Manager, NRR w/encl

Rill Enf. Coordinator w/encl

IEO w/encl (E-mail)

TSS w/encl

DRP w/encl

SRI DC Cook w/encl

A. B. Beach w/encl

J. L. Caldwell w/encl

Rill PRR w/encl

DRS (2) w/encl

DOCDESK (E-mail)

GREENS

J. Lieberman, OE

J. Goldberg, OGC

B. Boger, NRR

DOCUMENT NAME: G:ttDRSiDCC98005.DRS

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