ML20247H785

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Forwards Safety Insp Repts 50-219/89-06 & 50-219/89-09 on 890217-24 & 0320-23,respectively.Enforcement Conference Will Be Planned to Further Review Preliminary Safety Concern Process & Unresolved Significant Safety Concerns
ML20247H785
Person / Time
Site: Oyster Creek
Issue date: 05/24/1989
From: Kane W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Fitzpatrick E
GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20247H792 List:
References
NUDOCS 8905310325
Download: ML20247H785 (2)


See also: IR 05000219/1989006

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Docket / License: 50-219/DRP-16

'GPU Nuclear Corporation

ATTN: Mr. ' Eugene E. Fitzpatrick

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Nice. President and Director

Oyster Creek Nuclear Generating . Station

.P. 0. Box 388

Forked River, New Jersey 08731

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Gentlemen:

Subject:

Inspection Report Nos. 50-219/89-06 and 50-219/89-09

During the period Feb'ruary 17-24, 1989, a special safety' inspection was con-

ducted by Messrs. J. Wechselberger, E.. Collins, and D. Lew at the Oyster Creek

. Nuclear Generating Station.

This inspection reviewed the Preliminary Safety.

Concern process and.in particular. documentation involving the Standby Gas

Treatment System, Automatic Depressurization-. System, and the Containment Spray

System. Each preliminary safety concern identified valid' safety issues that we

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[feelwerenotadequatelyresolved. The results of this inspection are docu-

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"mented in the enclosed report 50-219/89-06. The technical findings were dis-

cussed with you and other members of.your staff by regional management at the

ranclusion of the inspection.

During the period March 20-23, 1989,' a followup safety inspection was conducted

by Messrs. J. Trapp and T. Easlick. This inspection further reviewed the items

discussed in NRC Inspection Reports. 50-219/88-38 Enj 50-219/89-06. The in-

'spection included a. review of the. corrective actions to the Preliminary Safety

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Concerns dealing with the Automatic Depressurization: System, Containment Spray.

System, and the Standby Gas Treatment System.

The results of-. this inspection

are documented in the enclo::ed report 50-219/89-09. The technical findings

were -discussed by J. Trapp with Mr. J. Barton and other members of:your staf f

at the: conclusion of the inspection.

Based'on the results of these inspections, we are concerned with the identifi-

cation and timely resolution of Preliminary Safety Concerns at your facility.

These concerns are a single failure vulnerability in your Standby Gas Treatment

System and conflicting statements with respect to this system in your Updated

. Facility Safety Analysis Report; a single failure vulnerability in your Auto-

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matic Depressurization System initiation logic when the Core Spray System is

out of' service; and a design deficiency in your Containment Spray System.

In' order.to further review the preliminary safety concern process, the unre-

solved significant safety concerns, the evaluation and management attention

.given to the concerns and your corrective action, an enforcement conference

. 8905310325 090524

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will be scheduled at the NRC Region I office.

Our enforcement actions in re-

sponse to these findings and related issues will t,e forwarded at a later date.

Therefore, no written response is required at this time.

Your cooperation with us in these matters is appreciated.

Sincerely,

ORIGINAL stGNED BT

William F. Kane, Director

Division of Reactor Projects

Enclosure:

NRC Region I Report Nos. 50-219/89-06 and 50-219/89-09

cc w/ encl:

M. Laggart, BWR Licensing Manager

Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

State of New Jersey

bcc w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

Section Chief, DRP

,

A. Dromerick, Project Manager, NRR

Robert J. Bores, DRSS

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