BSEP-97-0147, Forwards Updated MSLB CR Dose Calculation,Per 970228 Commitment
| ML20137Y641 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| 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) | |
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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)
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 o30031
Enclosures:
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 Atlanta, GA 30323-0199 s.
U. S. Nuclear Regulatory Commission ATTN: Mr. C. A. Patterson, NRC Senior Resident inspector 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
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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
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