ML20202E742
| ML20202E742 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/25/1997 |
| From: | Mcdonald D NRC (Affiliation Not Assigned) |
| To: | Carns N, Loftus P NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M92879, NUDOCS 9712080132 | |
| Download: ML20202E742 (6) | |
Text
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Nd r5,M7 eir i re dent and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus a
Director - Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE CONTROL ROOM VENTILATION SYSTEH, MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO. M92879)
Dear Mr. Carns:
By letter dated July 7, 1995, Northeast Nuclear Energy Company (NNECO) requested an amendment to the Technical Specifications (TS) for the Millstone Nuc. lear Power Station, Unit No. 2, which would increase the allowable post accident in-leakage rate for the control room.
By letter dated November 6, 1997, the staff identified additional information needed to complete its review. Upon further review, the staff has identified the need for more information than in its initial recuest.
The enclosure to this letter delineates the needed information.
In atdition, the initial request incorrectly identified the date of your amendment request as July 7, 1997, instead of July 7, 1995. We hope this error has not caused any inconvenience.
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' JIf you have any questions relating to this supplemental request, please econtact me at (301) 415-1408.
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NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 300eH001 li,. h 25, 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:
SUPPLEMENTAL 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 7,1995, Northeast Nuclear Energy Company (NNECO) requested an amendment to the Technical Specifications (TS) for the Hillstone Nuclear Power Station, Unit No. 2, which would increase the allowable post accident in-leakage rate for the control room.
By letter dated November 6,1997, the staff identified additional information needed to complete its review. Upon further review, the staff has identified tne need for more information than in its initial request.
The enclosure to this letter delineates the needed information.
In addition, the initial request incorrectly identified the date of your amendment request as JLly 7, 1997, instead of July 7,1995. We hope this error has not caused any inconvenience.
If you have any questions relating to this supplemental request, please contact me at (301) 415-1408.
Sincerely, Wol
.. iiel
. Mcdonald Jr., Sr. Project Manager pecial Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Request for Additional Information cc w/ encl:
See next page i
RE0 VEST FOR ADDITIONAL INFORMATION CONTROL ROOM EMERGENCY VENTILATION SYSTEM MlltSTONE NUCLEAR POWER STATION. UNIT NO. 2 NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-3 M 1.
The proposed Technical Specification Bases contains the position that the nominal recirculation system flo,. rate of 2500 cubic feet per minute (cfm) can be used in lieu of the minimum acceptable flow of 2250 cfm since the range of flow fluctuation is overwhelmed by other conservatisms found in the control room dose calculations. The staff finds this position to be unacceptable.
If the flow value of 2250 cfm is in some way limiting, the proper approach is to explicitly identify the site-specific analysis assumption value deemed to be conservative that can 'oe modified tu compensate for the reduced recirculation flow while still maintaining an adequate margin of safety.
The staff requests that the licensee delete this language from the proposed amendment.
2.
In the licensee's analysis of the Unit 3 loss of-coolant accident, it wts assumed that the activity released to the containment and available f.c release to the environment was 25% rather than the 50% assumed in prior versions of the calculation.
However, the licensee's calculation tabulated spray parameters that are incompatible with the assumption of 25% core inventory.
The difference between the assumed activities availsble for release is the method for crediting plate out of the activity released from the Reactor Coolant System (RCS).
The spray parameters tabulated in the licensee's calculation appear to be based on Revision 2 to the Standard Review Plan (SRP) 6.5.2.
However, it is the staff's position that Revision 2 to the SRP is appropriate only for use with an assumption of 50% core inventory available for release.
In assuming 25% core inventory and the spray parameters used in the calculation, the licensee is crediting plate out twice - the first being the 50% de of 3.1 hr',terministic credit and the second being the plate out lambda Revision 0 of SRP 6.5.2 core inventory available for relea,se. provided for an assumption of 2 However, this revision also limited the spray lambda to 10 hr' with an overall iodine decontamination factor limited to 100.
The staff requests that the licensee correct this deficiency in the analysis.
3.
In the analysis of the Unit I main steamline break (MSLB), the licensee did not assess the dose consequences of an MSLB with the RCS activity at the maximum technical specification value of 4.0 Ci/g.
This is provided for by Safety Guide 5, and by SRP 15.6.4.
ThE licensee's analysis took the position that assuming a preincident spike was unnecessary because of the low probability of an MSLB accident in the Enclosure
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s 48-hour period when coolant activities are at 4.0 pCi/g.
This position is not acceptable. Since the preincident iodine spike value represents an increase by a factor of 20 in concentration level, it is unlikely that doses will be acceptable.
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The staff requests that the licensee provide an analysis of the control i
room dose associated with an MSLB with RCS concentrations at 4.0 pCi/g dose equivalent I-131.
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Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 CC:
Waterford, CT 06385 Lillian M. Cuoco. Esquire Senior Nuclear Counsel Ernest C. Hadley, Esquire Northeast Utilities Service Company 1040 B Main Street P. O. Box 270 P.O. Box 549 Hartford, CT 06141-0270 West Wareham, MA 02576 Mr. John Buckinghtm Mr. D. M. Goebel Departmer.' of Public Utility Control Vice President - Nuclear Oversight Electric Unit Northeast Nuclear Energy Company 10 Liberty Square P. O. Box 128 New Britain, CT 06051 Waterford, CT 06385 Mr. Kevin T. A. McCarthy, Director Mr. M. L. Bowling, Jr.
Monitoring and Radiation Division Recovery Officer - Millstone Unit 2 Department of Environmental Protection Northeast Nuclear Energy Company 79 Elm Street P. O. Bcx 128 Hartford, CT 06106-5127 Waterford, CT 06385 Regional Administrator, Region I Mr. David Amerine U.S. Nuclear Regulatory Commission Recovery Officer
,;uclear Engineering 4'5 Allendale Road and Support King of Prussia, PA 194J6 Northeast Nuclear Energy Company P. O. Box 128 First Selectmen Wai.rferd, CT 06385 Town of Waterford Hall of Records Mr. B. D. Kenyon 200 Boston Post Roar'.
President and C'ief Waterford, CT 06385 Executive Officer Northeast Nuclear Energy Company j
Mr. Wayne D. Lanning P. O. Box 128 Deputy Director of Inspections Waterford, Connecticut 06385 Special Projects Office 475 Aliendale Road Mr. Allan Johanson, Assistant Director King of Prussia, PA 19406-1415 Office of Policy and Management Policy Development and Planning Charles Brinkman, Manager.
Division Washington Nuclear Operations 450 Capitol Avenue - MS# 52ERN ABF Combustion Engineering P. O. Box 341441 1230: Twinbrock PL<y, Suite 330 Hartford, CT 06134-1441 Rockville, 33 20852 Senior Resident T spector Millstone Nucl*. Power Station c/o U.S. Nuclear Power Station P.O. Box 513 Niantic, C7 06357 Mr. F. C, Rothen Vice President - Work Services Northeast Nuclear Energy Company P. O. Box 128 3
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Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 cc:
Citizens Regulatory Commission ATTN: Ms. Susan' Perry Luxton 180 Great Neck Road
-Watertord, Connecticut 06385 Deborah Katz, President Citizens Awareness Network P. 0. Box 83 Shelburne Falls, MA 03170 The Honorable Terry Concannon Co-Chair Nuclear Energy-Advisory Council Room 4035 Legislative Office Building Capitol Avenue
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Hartford, Connecticut 06106 Mr. Evan W. Woollacott 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
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