BSEP-97-0147, Forwards Updated MSLB CR Dose Calculation,Per 970228 Commitment

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Forwards Updated MSLB CR Dose Calculation,Per 970228 Commitment
ML20137Y641
Person / Time
Site: Brunswick  Duke energy icon.png
Issue date: 04/15/1997
From: Jury K
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137Y645 List:
References
BSEP-97-0147, BSEP-97-147, NUDOCS 9704230163
Download: ML20137Y641 (3)


Text

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37 1

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CP&ii.

Caro::na Power & Ught Company

'P.O. Box 10429 Southport, NC 28461-0429 i

April 15,1997 SERIAL: BSEP 97-0147 U. S. Nuclear Regulatory Cor1 mission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 MAIN STEAM LINE BREAK CONTROL ROOM DOSE CALCULATION Gentlemen:

In a letter dated February 28,1997 (Serial: BSEP 97-0099), Carolina Power & Light (CP&L) i Company committed to submit an updated Main Steam Line Break (MSLB) control room dose calculation by April 15,1997. Enclosure 1 contains this calculation.

' The results of the updated MSLB calculation indicate that the thyroid dose to the operators -

could be as high as 34.2 rem following an accident if the reactor coolant activity is assumed to  ;

be 4.0 micro-curies per gram dose equivalent I-131. As stated in the letter dated February 28, 1997, CP&L has implemented administrative controls to limit reactor coolant activity to less than 0.1 micro-curies per gram dose equivalent 1-131. CP&L will maintain this administrative control until a license amendment request limiting reactor coolant peak activity can be approved. A

license amendment request limiting reactor coolant peak activity to less than 3.0 micro-curies per gram dose equivalent 1-131 will be submitted by May 23,1997. A peak reactor coolant activity of 3.0 micro-curies per gram dose equivalent 1-131 results in a calculated thyroid dose of 25.5 rem thyroid, well below the General Design Criterion 19 limit.

Please refer any questions regarding this submittal to Mr. Mark Turkal, Supervisor - Licensing at (910) 457-3066.

f,incerely, 9

'OL L 2 Ma ager Regulatory Affairs j P PDR ig Brunswick Steam Electric Plant MAT / mat

Enclosures:

o30031

1. Main Steam Line Break Control Room Dose Calculation
2. List of Regulatory Commitments 2 111 51511111115 4 J

Document Control Desk BSEP 97-0147 / Page 2 pc (with enclosures):

U. S. Nuclear Regulatory Commission ATTN.: Mr. Luis A. Reyes, Regional Administrator ,

101 Marietta Street, N.W., Suite 2900 l Atlanta, GA 30323-0199 s.

U. S. Nuclear Regulatory Commission ATTN: Mr. C. A. Patterson, NRC Senior Resident inspector l 8470 River Road Southport, NC 28461 U. S. Nuclear Regulatory Commission .

ATTN.: Mr. David C. Trimble, Jr. (Mail Stop OWFN 14H22)  !

11555 Rockville Pike Rockville, MD 20852-2738 The Honorable J. A. Sanford Chairman - North Carolina Utilities Commission P.O. Box 29510 '

Raleigh, NC 27626-0510 l

'4 r 7

i ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324  ;

OPERATING LICENSE NOS. DPR-71 AND DPR-62 SUBJECT MAIN STEAM LINE BREAK CONTROL ROOM DOSE CALCULATION l F

Main Steam Line Break Control Room Dose Calculation ,

i l