ML17199F790

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Forwards Safety Sys Outage Mod Insp Rept 50-249/86-09 on 851202-06,16-20 & 860106-11 & 23.Deficiencies,unresolved Items & Observations Noted
ML17199F790
Person / Time
Site: Dresden 
Issue date: 05/29/1986
From: Taylor J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Reed C
COMMONWEALTH EDISON CO.
Shared Package
ML17199F791 List:
References
NUDOCS 8606110055
Download: ML17199F790 (4)


See also: IR 05000249/1986009

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

Docket No. 50-249

Conunonwealth Edison Company

ATTN:

Mr. Cordell Reed

Vice President

Post Office Box 767

Chicago, IL

60690

Gentlemen:

IAY 2 9 1986

SUBJECT:

SAFETY SYSTEM OUTAGE MODIFICATION INSPECTION

(DESIGN) 50-249/86009

'

This letter conveys the results and conclusions of the design portion of the

Safety System Outage Modification Inspection of the Dresden Station, Unit 3

conducted by the NRC's Office of Inspection and Enforcement.

The inspection

team was composed of personnel from the Office of Inspection and Enforcement,

Region*III and consultants. The inspection took place at the Dresden Station,

your offices and the offices of contractors responsible for engineering related

to modifications; it was conducted December 2-6, 16-20, 1985, and January

6-11, 23, 1986. *This inspection was part of a trial NRC program being imple-

mented to examine the adequacy of licensee management and control of modifications

performed during scheduled major plant outages.

The purpose of this portion of the Safety Systems Outage Modification Inspection

was to examine, on a sampling basis, the detailed design and engineering which was

required to support modifications implemented during the outage.

Coordination

was required with teams conducting other portions of the inspection, including

vendor inspections, installation inspection, and the testing inspection.

At the

conclusion of these inspections the NRC will provide a report sununarizing these

efforts.

The items identified by the team during the inspection have been classified as

deficiencies, unresolved items, and observations.

Deficiencies identify errors,

procedural violations and inconsistencies. Unresolved items are identified where

more information is needed to reach conclusions. Observations are identified

where it was considered appropriate to call your attention to matters which are

not deficiencies or unresolved items, but which are recommended for your

consideration.

Section 1 of the report provides a summary of the results of the inspection and

the conclusions reached by the inspection team.

For analog transmitter modifi-

cation packages, one significant deficiency identified that redundant reactor

protection system transmitter trip channels were not separated in the analog

trip system panels.

As a consequence, a single event within a trip system panel

could disable the reactor vessel water leve~ trips of the reactor ~roteqtion and

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primary containment isolation systems.

This and several other design errors

related to analog transmitter modifications indicated design process weaknesses;

six separate organizations were involved in the design process for these modi-

fications, and, in the team's opinion, could have identified the design errors.

found by the team.

For other modifications, the team identified programmatic

weaknesses in the design process with respect to (1) not using the original

  • design basis for the plant feature being mod~fied, (2) not assuring that co~rect

and appropriate data is transferred between interfacing organizations, and

(3) unavailability of technical procedures prescribing methodology for develop-

ing important engineering data.

You should respond. in writing to the deficiencies and unresolved items within *

60 days after receipt of this .letter;

In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure

will be placed in the NRC Public Documen~ Room.

Should you have any questions concerning this inspection, please contact me or

Mr. Ted Ankrum (301-492-4774) of this office.

Sincerely;

.fl'

es M. Taylo , Director

fice of Ins ection and Enforcement

Enclosure:

Inspection Report 50-249/86009

cc w/enclosure:

See .next page

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Commonwealth Edison Company

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Mr. Cordell Reed

Commonwealth Edison Company

cc:

Mr. Michael I. Miller

Isham, Lincoln & Beale

Three First National Plaza

Suite 5200

Chicago~ Illinois 60602

Mr. Doug Scott

Plant Superintendent

Dresden Nuclear Power Station

Rural Route #1

Morris, Illinois 60450

U. S. Nuclear Regulatory Commission

Resident Inspectors Office

Dresden Station

Rural Route #1

Morris, Illinois 60450

Chairman

Board of Supervisors of

Grundy County

Grundy County Courthouse

Morris, Illinois 60450

Regional Administrator

Nuclear Regulatory Commission, Region III

799 Roosevelt Road

Glen Ellyn, Illinois 60137

Gary N. Wright, Manager

Nuclear Facility Safety

Illinois Department of Nuclear Safety

1035 Outer Park Drive, 5th Floor

Springfield, Illinois 62704

Dresden Nuclear Power Station*

Units 1, 2 and 3-