ML20199B143
| ML20199B143 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/06/1997 |
| From: | Mcdonald D NRC (Affiliation Not Assigned) |
| To: | Carns N NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M92879, NUDOCS 9711180227 | |
| Download: ML20199B143 (5) | |
Text
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-Mr.:Neil S. Carns November 6, 1997 l
Senior Vice President and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
. REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE CONTROL ROOM VENTILATION SYSTEM, MILLSTONE NUCLEAR POWER STATION, UNIT NO.~2 (TAC NO. M92879)
Dear Mr. Carns:
By letter' dated July 7,1997, Northeast Nuclee Energy Company (NNECO) i requested an amendment to the Technical Specifiutions (TS) for the Millstone Nuclear Power Station, Unit No. 2, which included increasing the allowable post accident in-leakage-rate for the control room.
The staff is currently reviewing the requested TS amendment and has determined that additional information is needed to complete its review.
The information needed is identified in the enclosure to this letter, if you have any questions relating to this iequest, please contact me at (301) 415-1408.
Sincerely, original sigrxxl by:
Daniel G. Mcdonald Jr., Sr. Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Request for Additional Information i
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%q Novmber 6,1997 Mr. Neil S. Carns Senior Vice President and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE CONTROL ROOM VENTILATION SYSTEM, MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO M92879)
Dear Mr. Carns:
By letter dated Jul' 7, 1997, Northeast Nuclear Energy Company (NNECO) requested an amendment to the Technical Specifications (TS) for the Millstone Nuclear Power Station, tinit No. 2, which included increasing the allowable post accident in-leakage rate for the control room.
The staff is currently reviewing the requested TS amendment and has determined that additional information is needed to complete its revieu.
The information needed is identified in the enclosure to this letter.
If you have any questions relating to this request, please contact me at (301) 415-1408.
Sincerely, v'=
Daniel G. Mcdonald Jr., Sr. Project 'anager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Request for Additional Information cc w/ encl: See next page
Northeast Nuclear Energy Company Millstone Nuclear Power Station l
Unit 2 cc:
Mr. F. C. Rothen Lillian M. Cuoco, Esquit; Vice President - Work Services Senior Nuclear Counsel Northeast Nuclear Energy Company Northeast Utilities Service Company P. O. Box 128 P. O. Box 270 Waterford, CT 06385 Hartford, CT 06141-0270 Ernest C. Hadley, Esc;uire Mr. John Buckingham 1040 B Main Street Department of Public Utility Nntrol P.O. Box 549 Electric Unit West Wareham, MA 02576 10 Liberty Square New Britain, CT 06051 Mr. D. M. Goebel Vice President - Nuclear Oversight Mr. Kevin T. A. McCarthy, Director Northeast Nuclear Energy Company Monitoring and Radiation Division P. O. Box 128 Department of Environmental Protection Wa9rford, CT 06385 79 Elm Street Hartford, CT 06106-5127 Mr. M. L. Bowling, Jr.
Recovery Officer - Millstone Unit 2 Regional Administrator, Region I Northeast Nuclear Energy Company U.S. Nuclear Regulatory Commission P. O. Box 128 475 Allendale Road Waterford, CT 06385 King of Prussia, PA 19406 Mr. David Amerine First Selectmen Recovery Officer - Nuclear Engineering Town of Waterford and Support Hall of Records Northeast Nuclear Energy Company 200 Boston Post Road P. O. Box 128 Waterford, CT 06385 Waterford, CT 06385 Mr. Wayne D. Lanning Mr. B. D. kenyon Deputy Director of Inspections President and Chief Specicl Projects Office Executive Officer 475 Allendale Road Northeast Nuclear Energy Company King of Prussia, PA 19406-1415 P. O. Box 128 Waterford, Connecticut 06385 Charles Brinkman, Manager Washington Nuclear Operations Mr. Allan Johanson, Assistant Director ABB Combustion Engineering Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 Policy Development and Planning Rockville, MD 20852 Division 450 Capitol Avenue - MS# 52ERN Senior Resident Inspectc..
P. O. Box 341441 Millstone Nuclear Power Station Hartford, CT 06134-1441 c/o U.S. Nuclear Power Station P.O. Box 513 Niantic, CT 06357 l
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 cc:
Citizens Regulatory Commission-ATTN: Ms. Susan Perry Luxton 180 Great Neck Road Waterford, Connecticut 06385 Deborah Katz, President Citizens Awareness Network P. O. Box 83 Shelburne Falls, MA 03170 The Henorable Terry Concannon Co-Chair Nuclear Energy Advisory Council Room 4035 Legislative Office Building Capitol Avenue Hartford, Connecticut 06106 Mr. Evan W. Woollacott s
Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, Connecticut 06070 Little Harbor Consultants, Inc.
Millstone - ITPOP Project Office P. O. Box 0630 Niantic, Connecticut 06357-0630 Mr. Daniel L. Curry Project Director-Parsons Power Group Inc.
2675 Morgantown Road Reading, Pennsylvania 19607 Mr. Don Schopfer Verification Team Manager Sargent & Lundy 55 E. Monroe Street Chicago, Illinois 60603
4 RE0 VEST FOR ADDITIONAL INFORMATION CONTROL ROOM EMERGENCY VENTILATION SYSTEM MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 53-2 1 1.
Calculation M2CRM2-Oll56-R2 evaluates the control room doses from a Design Basis Accident Loss-of-Coolant Accident. A containment bypass fraction of 4.025E-7 is determined on page 9 of the calculation.
This value was subsequent 1 8.388E-11hr{ for the period T-110 seconds to T 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.used to determine the containmen Millstone 2 Technical Specification 3.6.1.2 establishes a bypass limit of 0.017 x LA (LA 0.5%/ day). The staff believes that the appropriate release rate to be:
0.5%/ day x 1/100 x 0.017 x day /24 hr -3.54E-6 hr' The methodology used in the Millstone 2 calculation differs from the corresponding evaluation in Millstone 3 calculation M2CRM3-Oll46-R2, which developed a bypass leak rate of 0.0278%/ day or 1.16E-5hr'. A comparison of the staff exclusion boundary area and low-population zone analyses results with those documented in the Updated Fine' fety Analysis Report suggests that the suspect release rate was not used in the evaluation of offsite doses.
Justify the use of the 4.025E-7 value when the containment could be considered operable with a bypass fraction as high as 0.017.
af the bypass fraction assumption cannot be supported, the affected calculation should be revised and provided to the staff.
2.
The release activity in the Millstone 1 main steamline break analysis appears to be based, in part, on Appendix 1 source terms.
The staff does not believe that this is an appropriate source of isotopic fractions for the design basis calculation. Appendix I source terms are typically based on projections of releases over a year and often discount nuclides with short half-lifes by including a short period of decay. The isotopic fractions are being used in an analysis involving the release of fresh reactor coolant system (RCS) activity. The Millstone 1 Updated Final Safety Analysis Report does not contain a listing of the design basis RCS activity.
Provide a listing of the Millstone 1 design basis RCS activity for the halogens, xenons, and kryptons; and a brief description of the basis (e.g., percent failed fuel, x.x #Ci/gm, etc.).
l Enclosure
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