ML20207M968

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Forwards Safety Insp Repts 50-254/86-16 & 50-265/86-16 on 861009-1204 & Notice of Violation.Type a Test Must Be Performed During Each Refueling Outage Until Two Consecutive Tests Meet App J Acceptance Criteria
ML20207M968
Person / Time
Site: Quad Cities  
Issue date: 01/08/1987
From: Paperiello C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Reed C
COMMONWEALTH EDISON CO.
Shared Package
ML20207M969 List:
References
NUDOCS 8701130361
Download: ML20207M968 (2)


See also: IR 05000254/1986016

Text

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JAN 4 81987

,

Docket No. 50-254

Docket No. 50-265

Commonwealth Edison Company

ATTN:

Mr. 'Cordell Reed

Vice President

Post Office Box 767

Chicago, IL 60690

Gentlemen:

This refers to the routine safety inspection conducted by Mr. R. Mendez

of this office on October 9 through December 4, 1986, of activities at

Quad Cities Nuclear Power _ Station, Units 1 and 2, authorized by NRC Operating

Licenses No. DPR-29 and No. DPR-30 and to the discussion of our findings with

Mr. R. L. Bax at the conclusion of the inspection.

The enclosed copy of our inspection report identifies areas examined during

the inspection. Within these areas, the inspection consisted of a selective

examination of procedures and representative records, observations, and

interviews with personnel.

As stated in the report, the last two consecutive Type A tests at Quad-Cities

Unit 2 have been failures and, pursuant to 10 CFR 50, Appendix J,

Section III.A.6.(b), a Type A test shall be performed during each plant

shutdown for refueling until two consecutive Type A tests meet the acceptance

criteria of Appendix J.

Accordingly, unless you request, and are granted,

an exemption from this requirement by the Office of Nuclear Reactor Regulation,

we expect you to conduct a Type A test during each refueling outage until two-

consecutive Type A tests satisfy the Appendix J acceptance criteria.

During this inspection, certain of your activities appeared to be in violation

of NRC requirements, as described in the enclosed Notice.

With respect to

Item 1, the inspection showed that action had been taken to correct the

identified violation and to prevent recurrence.

Our understanding of your

corrective actions are described in Paragraph 7 of the enclosed inspection

report.

Consequently, no reply to the violation is required and we have no

further questions regarding this matter at this time.

Regarding Item 2, a written response is required.

In your response to Item 2,

please include an assessment of the compatibility of the J-Bar and Garlock

gasket materials sufficient to support an independent evaluation of material

properties.

.

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

of this letter and the enclosed inspection report will be placed in the

NRC Public Document Room.

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The responses directed by this letter and the accompanying Notice (Order)

are not subject to the clearance procedures of the Office 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,

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Carl J. Paperiello, Director

Division of Reactor Safety

Enclosure:

Inspection Reports

No. 50-254/86016(DRS);

No. 50-265/86016(DRS)

cc w/ enclosure:

D. L. Farrar, Director

of Nuclear Licensing

R. L. Bax, Plant Manager

DCS/RSB (RIDS)

Licensing Fee Management Branch

Resident Inspector, RIII

Phyllis Dunton, Attorney

General's Office, Environmental

Control Division

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