BSEP 02-0049, Response to Request for Additional Information Regarding Request for License Amendments - Extended Power Uprate

Response to Request for Additional Information Regarding Request for License Amendments - Extended Power Uprate

ML020650447
Person / Time
Site:	Brunswick
Issue date:	02/25/2002
From:	Keenan J Carolina Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 02-0049, TAC MB2700, TAC MB2701, TSC-2001-09
Download: ML020650447 (4)

Text

John S.Keenan CP&L Vice President A Progress Energy Company Brunswick Nuclear Plant FEB 2 5 2002 SERIAL: BSEP 02-0049 TSC-2001-09 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND M1B2701)

Ladies and Gentlemen:

On August 9, 2001 (Serial: BSEP 01-0086), Carolina Power & Light (CP&L) Company requested a revision to the Operating Licenses (OLs) and the Technical Specifications for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed license amendments increase the maximum power level authorized by Section 2.C.(1) of OLs DPR-71 and DPR-62 from 2558 megawatts thermal (MWt) to 2923 MWt. Subsequently, on February 14, 2002 (Serial: BSEP 02-0041), CP&L responded to a Request for Additional Information (RAI) concerning the offsite doses expected after extended power uprate. On February 15 and 19, 2002, the NRC requested additional information associated with the February 14, 2002, submittal. The response to this RAI is enclosed.

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Manager - Regulatory Affairs, at (910) 457-2073.

Sincerely, John S. Keenan MAT/mat P.O.Box 10429 Southport, NC 28461 T> 91045T72496 4 cODI F> 910.4572803

Document Control Desk BSEP 02-0049 / Page 2

Enclosure:

Response to Request for Additional Information (RAI) 21 C. J. Gannon, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, and agents of Carolina Power & Light Company.

Notary (Seal)

My commission expires:

cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mr. Allen G. Hansen (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Mr. Mohammed Shuaibi (Mail Stop OWFN 8H4A) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. Mel Fry Director - Division of Radiation Protection North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221

BSEP 02-0049 Enclosure Page 1 of 2 ENCLOSURE BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND MB2701)

Response to Request for Additional Information (RAI) 21

Background

On August 9, 2001 (Serial: BSEP 01-0086), Carolina Power & Light (CP&L) Company requested a revision to the Operating Licenses (OLs) and the Technical Specifications for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed license amendments increase the maximum power level authorized by Section 2.C.(1) of OLs DPR-71 and DPR-62 from 2558 megawatts thermal (MWt) to 2923 MWt. Subsequently, on February 14, 2002 (Serial: BSEP 02-0041), CP&L responded to a RAI concerning the offsite doses reported in: (1) the "Supplement to the Brunswick Steam Electric Plant Environmental Report," provided as of the August 9, 2001, submittal, and (2) CP&L's submittal dated December 17, 2001 (Serial: BSEP 01-0162). On February 15 and 19, 2002, the NRC requested additional information associated with the February 14, 2002, submittal. The response to this RAI follows.

NRC Ouestion 21-1 With respect to CP&L's response to NRC Question 16-2, provide the following information: (1) what type of dosimeter is used, (2) what is it's minimum sensitivity, (3) how are they configured in the field (concerned about potential shielding and underestimating the skyshine component),

(4) has the licensee used these types of measurements to demonstrate compliance for years prior to 1998, and if so, what type of dosimetry was used, (5) what type of radiation measurements were used during the 1998 HWC mini-test and what were the results.

Response to Question 21-1 The following table provides the requested information.

Request Response Dosimeter Type At BSEP, CP&L uses Panasonic UD-814 badge thermoluminescent dosimeters (TLDs) containing calcium sulfate phosphors.

Minimum Sensitivity I millirem

BSEP 02-0049 Enclosure Page 2 of 2 Request Response Field Configuration The TLDs are contained in weather resistant, light tight bags.

Type of Dosimetry Used Prior to 1998 The Panasonic UD-814 TLDs have been used since 1983.

Type of Radiation Measurement Used CP&L conducted radiation measurements by direct surveys with ion for the 1998 Hydrogen Water chambers during the 1998 HWC mini-test. The surveys were performed Chemistry (HWC) Mini-test from the protected area boundary, moving out, until radiation levels of 6 [tRem (i.e., background level) were encountered.

NRC Ouestion 21-2 Provide the extent and impact of permanent shielding (shielding reduction factors) installed for the moisture separator reheaters (relative to site boundary doses and beyond), and the new high density block for an administrative building.

Response to Question 21-2 The dose reduction factor from installed sheilding was approximately 18% for the site.

NRC Ouestion 21-3 Discuss the existing ODCM methodology for determining offsite skyshine.

Response to Question 21-2 The Offsite Dose Calculation Manual (ODCM) does not contain a specific methology for determining offsite skyshine. Section 4.0, "Radiological Environmental Monitoring Program,"

contains the sample point descriptions, sampling and collection frequency analysis, and analysis frequency for various exposure pathways in the vicinity of BSEP. Offsite doses are determined as described in the response to NRC Question 16-2 of the February 14, 2002, submittal (Serial:

BSEP 02-0041).