ML17325B507

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Forwards Insp Repts 50-315/99-01 & 50-316/99-01 on 990114- 0302.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations.First Violation Pertains to Tagging Procedure for Plant Equipment
ML17325B507
Person / Time
Site: Cook  
Issue date: 03/26/1999
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Powers R
AMERICAN ELECTRIC POWER CO., INC.
Shared Package
ML17325B508 List:
References
50-315-99-01, 50-315-99-1, 50-316-99-01, 50-316-99-1, EA-99-044, EA-99-44, NUDOCS 9904010210
Download: ML17325B507 (6)


See also: IR 05000315/1999001

Text

CATEGORY 2

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CESSION NBR:9904010210

DOC.DATE: 99/03/26

NOTARIZED: NO

FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana

M

50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana

M

AUTH.NAME

AUTHOR AFFILIATION

GROBE,J.A.

Region

3 (Post

820201)

RECZP.NAME

RECIPIENT AFFILIATION

POWERS,R.P.

American Electric Power Co., Inc.

DOCKET I

05000315

05000316

SUBJECT: Forwards insp repts 50-315/99-01

&, 50-316/99-01

on 990114-

0302.Four violations of NRC requirements identified

&, being

treated

as non-cited violations. First violation pertained to

tagg'ing procedure for plant equipment.

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UNITEDSTATES

NUCLEAR REGULATORY COMMISSION

REGION III

801 WARRENVILLEROAD

LISLE, ILLINOIS605324351

Yarch 26,

1999

EA 99-044

Mr. R. P. Powers

Senior Vice President

Nuclear Generation Group

American Electric Power Company

500 Circle Drive

Buchanan, Ml 49107-1395

SUB JECT:

D. C. COOK INSPECTION REPORT 50-315/99001(DRP); 50-316/99001(DRP)

Dear Mr. Powers:

On March 2, 1999, the NRC completed an inspection at your D. C. Cook Units 1 and 2 reactor

facilities. The inspection was an examination of activities conducted under your license as they

relate to compliance with the Commission rules and regulations and with the conditions of your

'icense.

Areas reviewed included Operations, Maintenance, Engineering, and Plant Support.

Within these areas, the inspection consisted of selective examinations of procedures and

representative

records, interviews with personnel, and observations of activities in progress.

The enclosed report presents the results of that inspection.

During this inspection period, we noted that you developed an Operations Department

Leadership Plan and an Engineering Department Leadership Plan to establish a framework for

performance improvements.

We also noted that you established

a Shift Operability Review

Team which improved both the quality and the timeliness of operability determinations.

In

addition, we noted that following your identification of a missed Technical Specification

surveillance requirement, associated with the power operated relief valves, you implemented

comprehensive corrective actions which resulted in the identification of additional missed

surveillance testing requirements.

As a result, you appropriately broadened the scope of your

investigation to include surveillance testing requirements

in other modes of operation.

The

above initiatives and demonstrated

aggressive corrective actions reflect positively on your

commitment to identify and resolve safety issues.

In contrast to the above examples of improving performance,

a non-licensed operator started

the Unit'1 CD diesel generator starting air compressor and failed to monitor the system

.

response.

Consequently, the starting air receiver relief valve lifted on high pressure and an

alarm was received in the control room: In addition, we identified that the control room

operators observed, but did not question, abnormal indications on a residual heat removal flow

instrument.

Both of these occurrences indicated weaknesses

with operator control and

monitoring of plant systems and equipment.

Your continued attention to effect improved

performance in this area appears warranted.

g gV

99040i0210

990326

POR

ADQCK 050003i5

8

PDR

0

R. Powers

Based on

-2-

the results of this inspection, the NRC has determined that four violations of NRC

requirements occurred.

The first violation, which was identiTied by NRC inspectors pertained to

a tagging procedure for plant equipment that did not contain instructions to place tags at all

locations where out-of-service equipment may be operated.

The second violation, which was

identified by your staff, related to the failure to implement Technical Specification Action

Requirements for missed surveillance testing associated with the power operated relief valves.

The third violation, which was identified by your staff in 1994, involved the movement of fuel in

the spent fuel pool area with the spent fuel pool exhaust ventilation system inoperable.

The

fourth violation, which was identified by your staff in 1997, pertained to inadequate maintenance

instructions which permitted the installation of unqualified material in a safety-related system.

These Severity Level IVviolations are being treated as Non-Cited Violations (NCVs).

Appendix C of the Enforcement Policy requires that for Severity Level IVviolations to be

dispositioned as NCVs, they be appropriately placed in the licensee's corrective action program.

Implicit in that requirement is that the corrective action program be fullyacceptable.

The D. C.

Cook Plant corrective action program was not adequate and has been the focus of significant

attention by your staff to improve the program.

While your staff and the NRC have not yet

concluded that the corrective action program is fullyeffective, the corrective action program

improvement efforts are underway and captured in the D. C. Cook Restart Plan which is under

the formal oversight of the NRC through the NRC Manual Chapter 0350 Process, "Staff

Guidelines for Restart Approval." Consequently, these issues will be dispositioned as NCVs.

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

enclosure will be placed in the NRC Public Document Room.

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Sincerely,

Original signed

by A. Vegel

John A. Grobe, Director

Divisioriof Reactor Safety

Enclosure:

Inspection Report 50-315/99001(DRP);

50-316/99001(DRP)

cc w/encl:

A. C. Bakken III, Site Vice President

M. Rencheck, Vice President, Nuclear Engineering

D. Cooper, Plant Manager

R. Whale, Michigan Public Service Commission

Michigan Department of Environmental Quality

Emergency Management

Division

Ml Department of State Police

D. Lochbaum, Union of Concerned Scientists

OFFICE

RIII:DRP

RIII:DRP

RIII:EICS

Rill:DRS

DOCUMENT NAME: G:>COOKiDCC99001.DRP

To receive a co

of this document, Indicate in the box: "C" "- Co

w/o attach/encl "E" = Co

w/attach/encl "N"= No co

NAME

Cobe /k

DATE

03

LF/99

Ve el

03/'99

Cia

03/Z /9

Grobe'3/W/99

OFFICIALRECORD COPY

R. Powers

Distribution:

RRB1 (E-Mail)

RPC (E-Mail)

J. Lieberman, OE w/encl

J. Goldberg, OGC w/encl

B. Boger, NRR w/encl

Project Mgr., NRR w/encl

J. Caldwell, RIII w/encl

B. Clayton, Rill w/encl

SRI D .C. Cook w/encl

DRP w/encl

DRS (2) w/encl

Rill PRR w/encl

PUBLIC IE-01 w/encl

Docket File w/encl

GREENS

IEO (E-Mail)

DOCDESK (E-Mail)