BSEP-97-0033, Submits Response to RAI Re Control Room Personnel Exposures Resulting from Postulated Main Steam Line Break Accident

Submits Response to RAI Re Control Room Personnel Exposures Resulting from Postulated Main Steam Line Break Accident

ML20134A916
Person / Time
Site:	Brunswick
Issue date:	01/22/1997
From:	Campbell W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-97-0033, BSEP-97-33, TAC-M90644, TAC-M90645, NUDOCS 9701290172
Download: ML20134A916 (3)

Text

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. 7 CP&L Carolina Power & Light Company William R. Campbell PO Box 10429 Vice President Southport NC 28461-0429 Brunswick Nuclear Plant J;nuary 22,1997 SERIAL: BSEP 97-0033

U. S. Nuclear Regulatory Commission ATTN

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 AMENDMENT NOS.183 AND 214 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION - POWER UPRATE (NRC TAC NOS. M90644 / M90645)

Gentlemen:

On December 23,1996, Carolina Power & Light Company (CP&L) provided information on findings associated with reviews of the power uprate analyses for Brunswick Steam Electric Plant, Units 1 and 2. This letter provides additionalinformation related to Control Room personnel exposures resulting from a postulated Main Steam Line Break (MSLB) accident.  ;

Carolina Power & Light Company has completed a calculation of control room doses following a postulated MSLB accident. CP&L believes that this calculation is consistent with applicable regulatory guidance, and that the results of our calculation indicate General Design Criterion 19 l limits would not be exceeded following a MSLB accident. CP&L understands that the NRC staff has raised questions regarding certain assumptions and methodologies used in the CP&L calculation. Until we have reviewed and resolved these questions, CP&L will administratively limit the specific activity of the reactor coolant to less than or equal to 0.1 microcuries/ gram dose equivalent 1-131. Under this administrative lirr.?. M.h the unit in Operational Conditions 1, 2, or 3 and dose equivalent 1-131 greater than 0.1 microcuries/ gram, the requirements of Technical Specification 3.4.5. Action a.2 (i.e., shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) will be followed. Upon resolution, CP&L will either eliminate the administrative limit or propose a change to Technical Specification 3/4.4.5, Specific Activity, to incorporate appropriate specific activity limits.

Additionally, CP&L has completed testing of the Control Room Emergency Ventilation (CREV) system filtration train charcoal adsorber units. The laboratory testing of the charcoal adsorber, using samples obtained as described in Regulatory Guide 1.52, Revision 1, Position C.6.b, showed methyl iodide penetration of less than 2.5%. The testing was performed in accordance with ASTM D3803-1989, at a temperature of 5 30*C, with a relative humidity of > 95%. This t

testing demonstrates the capability of the Brunswick CREV filtration units to achieve in excess )

of 90% filtration efficiency under the environmental conditions noted above.

A COI I I

9701290172 970122 PDR ADOCK 05000324 l P PDR

""9 Tel 910 457 2496 Fox 910 457 28(1 1

- - - - - . - _ . _ ]

a

• Document Control Desk BSEP 97-0033 / Page 2 CP&L is evaluating humidity control and the NRC staff questions on the MSLB calculation in conjunction with our assessment of Control Building Heating, Ventilation, and Air Conditioning system. CP&L will provide a status of these evaluations to the NRC staff by March 21,1997.

Carolina Power & Light Company believes these actions resolve the outstanding issues associated with exceeding 95% rated thermal power on Unit 1. As such, CP&L requests approval to exceed 95% power and proceed with power uprate testing on Unit 1.

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

Sincerely,

$ 24t/LW -

m R. Campbell l KAH/kah I

4 Enclosure l

pc: U. S. Nuclear Regulatory Commission '

ATTN.: Mr. Luis A. Reyes, Regional Administrator 101 Marietta Street, N.W., Suite 2900 Atlanta, GA 30323-0199 Mr. C. A. Patterson NRC Senior Resident Inspector - Brunswick Units 1 and 2:

U.S. Nuclear Regulatory Commission ATTN,: Mr. David C. Trimble, Jr. (Mail Stop O'NFN 14H22) 11555 Rockville Pike Rockville, MD 20852-2738 The Honorable R. Hunt Chairman (Acting)- North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

i e 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 AMENDMENT NOS.183 AND 214 (NRC TAC NOS. M90644 / M90645) i LIST OF REGULATORY COMMITMENTS ,

i The following table identifies those actions committed to by Carolina Power & Light Company in i this document. Any other actions discussed in the submittal represent intended or planned l actions by Carolina Power & Light Company. They are described to the NRC for the NRC's

- information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs

, at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.

I Committed

Commitments date or outage Until CP&L has reviewed and resolved NRC staff questions regarding our N/A MSLB control room dose calculation, CP&L will administrative!y limit the specific activity of the reactor coolant to less than or equal to 0.1 microcuries/ gram dose equivalent 1-131. Upon resolution, CP&L will either 1 i eliminate the administrative limit or propose a change to Technical i Specification 3/4.4.5, Specific Activity, to incorporate appropriate specific activity limits for 1-131. Under this administrative limit, with the unit in i Operational Conditions 1,2, or 3 and dose equivalent 1-131 greater than l t 0.1 microcuries/ gram, the requirements of Technical Specification 3.4.5, Action a.2 will be followed.

CP&L is evaluating humidity control and the NRC staff questions on the 03/21/97 MSLB calculation in conjunctior with our assessment of Control Building Heating, Ventilation, and Air Conditioning system. CP&L will provide a status of these evaluations to the NRC staff by March 21,1997.

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