ML19347E218

From kanterella
Jump to navigation Jump to search
Forwards Response to IE Bulletin 79-26, Boron Loss from BWR Control Blades. Provides Results of Addl post-irradiation Exams & Comparisions of post-irradiation Exam Results to New Boron Depletion.Encl Withheld (Ref 10CFR2.790)
ML19347E218
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/13/1981
From: Furr B
CAROLINA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-26, IEB-79-26-R1, NO-81-632, NUDOCS 8104240272
Download: ML19347E218 (2)


Text

'/ l0 April 13, 1981 t -

FILE:

NG-3513 (B)

SERIAL:

NO-81-632 w\\

Mr. James P. O'Reilly, Director O

U.S. Nuclear Regulatory Commission b2

'I,O22Jggyg--)

Region II Q

101 Marietta Street, Suite 3100 S -\\ % %,yE,e**

J Atlanta, GA 30303 h

N

'Ni:.s BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2,,/ h 7

DOCKET NOS. @ AND 0-324 LICENSE NOS. DPR-71 AND D

-2 RESPONSE TO IE BULLETIN 79-26, REVISION 1, ITEM 4

References:

1.

" Control Blade Examination Results and Response to Item 4 of IE Bulletin 79-26," NEDE-24325-P, (General Electric Proprietary) and NED0-24325, March, 1981.

2.

" Evaluation of Control Blade Lifetime With Potential Loss of B C," NEDE 24226-P (General 4

Electric Proprietary) and NED0-24226, December, 1979; NEDE-24226-P (General Electric Proprietary)

Supplement 1, March, 1981.

3.

Letter, " Boron Loss From BWR Control Blades",

MFN-066-81, dated April 8, 1981, from R. L. Gridley (GE) to Dr. William V. Johnston (NRC).

Dear Mr. O'Reilly:

Carolina Power & Light Company submits one (1) copy each of the Reference 1 Reports wnich satisfies the requirements of Item 4 in IE Bulletin 79-26, Revision 1 for the Brunswick Steam Electric Plant (BSEP).

Reference 1 provides the results of additional post-irradiation examinations, and comparisons of the post-irradiation examination results to a new boron depletion analytical model developed by General Electric. The boron depletion model described in Reference 1 is shown to be in good agreement with the post-irradiation examination data.

8104 g4 0 M 2

Mr. Jtmeo P. O'R; illy April 13, 1981 The enclosed reports demonstrate that the control blade destructive examination data presented in References 1 and 2 are applicable to and representative of, the control blades in Brunswick 1 and 2.

The reports confirm that the loss of boron based on 50% local boron depletion is predictable, and is not affected by the plant's operating parameters.

The enclosed reports contain information which General Electric Company customarily maintains in confidence and withholds from public disclosure. The information has been handled and classified as proprietary to General Electric as indicated in the affidavit included with Reference 3, and we hereby request that NEDE-24325-P (Enclosure 2) be withheld from public disclosure in accordance with the provisions of 10CFR2.790.

Yours very truly, W

B.

Furr Vice President N: clear Operations Department DCS:kbb*

Enclosures (1) NEDO - 24325, March 1981 (2) NEDE - 24325-P, March 1981 (General Electric Proprietary) cc:

Mr. Norman C. Moseley

(