ML20138R055

Forwards Request for Addl Info to Complete Review of 850614 & 0925 Design Repts for IGSCC Insps During Nov 1984 & Mar-Oct 1985 Outages,Respectively.Response Requested within 60 Days of Ltr Receipt

ML20138R055
Person / Time
Site:	Brunswick
Issue date:	11/07/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Utley E CAROLINA POWER & LIGHT CO.
References
NUDOCS 8511180403
Download: ML20138R055 (3)

Text

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November 7,1985 t

Docket No. 50-325 DISTRIBUTION tDocket. File i

Reading File NRC PDR r

Local POR Mr. E. E. Utley HThompson Senior Executive Vice President SNorris 4 Power Supply and Engineering & Construction MGrotenhuis

! Carolina Power & Light Company WKoo j Post Office Box 1551 ELJordan i Raleigh, North Carolina 27602 BGrimes JPartlow j

Dear Mr. Utley:

OELD/ACRS (10)

Gray File

SUBJECT:

INTEGRANULAR STRESS CORROSION CRACKING (IGSCC) INSPECTION i I FOR UNIT 1 CYCLE 4, MARCH 1985 TO OCTOBER 1985 1 Re: Brunswick Steam Electric Plant Unit 1 1

i By letter dated June 14, 1985 you submitted the design report for the IGSCC inspection during tho November 1984 outage. By letter dated September 25, 1985 you submitted the design report for the IGSCC inspection during the March-October 1985 outage. We have received additional information t

regarding the March-October 1985 outage by letters dated October 10, 1985.

In order to complete our review of the two design reports we find that we need the additional information identified in the enclosure to this

. letter. Please respond within 60 days from the receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required 1 under P.L. 96-11.

1 Sincerely.

Original signed by/

Domenic B. Vassallo, Chief Operating Reactors Branch #2 1 Division of Licensing i

Enclosure:

As stated l

cc w/ enclosure:

See next page l

l l ORB # :0L ORB #2:DL OR #2:0L SNo s:rc MGrotenhuis 0Vassallo 11/ 7/85 11/j/85 11/1[/85 0511180403 851107 PDR ADOCK 05000325 O PDR

O .

Mr. E. E. Utley Carolina Power & Light Company Brunswick Steam Electric Plant; Units 1 and 2 cc:

Richard E. Jones. Esquire J. Nelson Grace Carolina Power & Light Company Regional Administrator 336 Fayetteville Street Region II Office Raleigh, North Carolina 27602 U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 George F. Trowbridge, Esquire Atlanta, Georgia 30303 Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W. Dayne H. Brown, Chief

. Washington, D. C. 20036 Radiation Protection Branch Division of Facility Services Mr. Charles R. Dietz Department of Human Resources Plant Manager Post Office Box 12200 Post Office Box 45B Raleigh, North Carolina 27605 Southport, North Carolina 28461 Mr. Franky Thomas, Chairman 1

Board of Commissioners ,

Post Office Box 249

! Bolivia, North Carolina 28422 '

Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector

, ' U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 4

. o Request for Additional Information Brunswick Unit 1 IGSCC Inspection .

A. With respect to the design report transmitted on September 25, 1985 please provide the following information:

1. A detailed sample calculation for each kind of an overlay design used for the repair of cracked welds

2. The overlay inspection of welds repaired prior to October 1984.

B. With respect to the design report transmitted on June 14, 1985, please provide the following information:

1. The "as built" overlay thickness, including the first layer, for the 4-12" and 1-4" repaired welds (see Table 2.1 page 9)

2. The ultrasonic testing (UT) measured pipe wall thickness for the one unrepaired weld and the five repaired welds identified in

', B.1 above

3. The method of calculating the shrinkage stress for weld 12-AR-B4A (page 26)

4. The design menthod for the overlay for weld 1-RR-4A 10-A. Due to the accessibility constraint, the flaws in the sub,iect weld were not sized.

5. A sample calculation for the overlay design for weld 12-13R-F4A

6. The data of the ferrite measurements made on the first layer of the overlay for the repaired welds identified in B.1 above

7. The stress information for welds 28 (table 4.1, page 21).

. . . .