ML19338G461

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Repts 50-324/80-29 & 50-325/80-32
ML19338G461
Person / Time
Site: Brunswick  
Issue date: 10/16/1980
From: Murphy C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Jackie Jones
CAROLINA POWER & LIGHT CO.
Shared Package
ML19338G462 List:
References
NUDOCS 8010290392
Download: ML19338G461 (1)


See also: IR 05000324/1980029

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UNITED STATES

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NUCLEAR REGULATORY COf.it.ilSSION

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101 MARIE TT A ST., N.W., SulTE 3100

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ATL ANTA, GEoHGIA 30303

OCT 16 w80

In Reply Refer To:

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0-324/80-29

,50-325/80-32

Carolina Power & Light Company

ATTN:

J. A. Jones, Senior Executive

Vice President & Chief Operating

Officer

411 Fayetteville Street

Raleigh, NC 27602

Centlemen:

Thank you for your letter of October 1,1980, informing us of steps you h

taken to correct thi item of noncompliance concerning activities u d ave

Operating License Nos. DPR-71 and DPR-62 brought to your attention in

n er NRC

of September 10, 1980.

subsequent inspections. We will examine your corrective actions and plans during

our letter

We appreciate your cooperation with us.

Sincerely,

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Charles E. Murphy, Chief

Reactor Construction & Engineering

Support Branch

A. C. Tollison, Jr.

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Plant Manager

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Carolina Power & Light Company

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Brunswick Steam Electric Plant

P. O. Box 10429

Southport, N. C.

28461

October 1, 1980

FILE: B09-13514

SERIAL: BSEP/80-1631

Mr. James P. O'Reilly, Director

U. S. Nuclear Regulatory Commission

Region II, Suite 3100

101 Marietta Street N.W.

Atlanta, GA 30303

BRUNSWICK STEA'4 ELECTRIC PLANT, UNIT NOS. 1 & 2

LICENSC NOS. DPR-71 AND DPR-62

DOCKET NOS. 50-325 AND 50-324

RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS

Dear Mr. O'Reilly:

The Brunswick Steam Electric PJant (BSEP) has received IE Inspection

Report 50-324/80-29 and 50-32K/80-32 and finds that it does not contain

any information of a proprietary nature.

The report identified an item that appears to be in noncompliance with

NRC requirements. This item and Carolina Power & Light Company's re-

sponse is addressed in the following text:

Infraction:

As required by Section 6.8 of the Technical Specification " Written

proedures shall be established, implemented, and maintained...as

recommended in Appendix A of Reg. Guide 1.33, Nov. 1972."

Contrarf to the above, CP&L's Special Test procedure SP-79-22

" Inspection and Testing Procedure for Concrete Expansicn Anchors"

and response to IE Bulletin 79-14, Serial: GD-79-1844 dated

June 23, 1979, failed to list the Control Rod Drive (CRD) and

Recirculation lines as safety related. The inspections required by

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Bulletins 79-02 and 79-14 were not performed.

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G7FICIAL COPY

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Mr. J. P. O'Reilly

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October 1, 1980

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Carolina Power & Light Compaav's Response:

1.

Corrective steps which have been taken and the results achieved:

The inspections required by IE Bulletins 79-02 and 79-14 were

ic=ediately performed on both systems when the omission was dis-

covered and the initial results for the CRD system were reported in

LER's 1-80-61 and 2-80-55.

Final reports on the CRD inspections

will be issued by December 31, 1980. No problems were noted with

the Reactor Recirculation System.

A comprehensive review of all safety related systems to assure that

no other systems or portions of systems were omitted from the

original program conducted by our A/E is in progress.

The base

documents used in this review include the Brunswick FSAR, the Plant

Q-list, the IE Bulletin 79-07 list and the Brunswick final stress

report for Unit-2 (1978).

The results of this review to date indicate that no systems were

overlooked, with the exception of the CRD and reactor recirculation

piping which were previously reported and discussed with Mr. Modenos

on August 5 - 7.

We have, however, determined that fuel oil supply

lines to the diesel generators and service water supply and return

lines for the diesel generators were not reanalyzed as required by

IE Bulletin 79-07, nor were the anchor bolts tested in accordance

with 79-02.

These lines were inadvertently omitted from the listing

supplied to the NRC even though they were on the UE&C internal

listing of lines to be analyzed. This omission was discovered on

September 23, 1980. Necessary reanalysis has been performed on an

expedited basis with no resulting short term fixes required.

Thirty-seven (37) long term support fixes will be needed.

Anchor

bolt testing required under IE Bulletin 79-02 has been completed on

the 26 base plates contained within this piping. Of these 26

plates, one anchor bolt failed and has been repaired. This was

reported by Mr. W. M. Tucker, BSEP, to Mr. L. Modenos, of your

office, at 1445 on October 1, 1980.

2.

Corrective steps which will be taken to avoid further non-compliance:

Increased CP&L involvement in directing and monitoring A/E support

in IE Bulletin and other safety related activities will provide

better contact and help assure proper compliance. This increased

involvement is being provided by a site engineering unit which will

manage this Brunswick related A/E activity.

In addition, the A/E

is better structuring his organization and upgrading procedures to

provide " task planning documents" which delineate the activities to

be conducted to accomplish a given task.

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Mr. J. P. O'Reilly

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October 1, 1980

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The date when full compliance will be achieved:

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The engineering review to assure no other systems or portions of

systems were omitted from the original program will be completed by

November 15, 1980. A supplement to this response will be provided

by November 30, 1980, documenting the results of the program review,

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providing an updated status on the work in progress, and providing

a schedule for completion of the identified long term fixes.

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Very truly yours,

A. C. Tolliso , Jr., General Manager

Brunswick Steam Electric Plant

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Mr. R. A. Hartfield

Mr. V. Stello, Jr.

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