ML20067B714

Forwards Revised Prairie Island Large Break LOCA Calculation Using WCAP-10924,Vol 1 Addenda 4 Model Changes, to Support 900913 License Amend Request

ML20067B714
Person / Time
Site:	Prairie Island
Issue date:	02/05/1991
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20067B716	List: ML20067B714 ML20067B721
References
NUDOCS 9102110005
Download: ML20067B714 (1)

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Northem States Power Company 414 Nicollet Mall

%nneapolis, Wnnesota 55401 1927 Telephone (612) 330 5500 February 5, 1991 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENEP.ATINC PLANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 Supplemental information for License Amendment Request Dated September 13, 1990 Addition of Reference to Approy,td Methodolog i

Attached are two items requested by the MRC staff to support the license amendment request dated September 13, 1990. The first item is an example large break loss of coolant accident calculation using the revised methodology referenced in Section 6 of the proposed Technical Specification change. This calculation uses an To - 2.4. Calculations are currently being proformed to increase this value of Fg . The second item is a discussion of the acceptance criteria for the steady state calculatlon results, Please e tac t ja f you have any questions related to this request, aw,w I Thomas M Parker Manager Nuclear Support Services c: Regional Adrainistrator, Region III, NRC Senior Resident Inspector, NRC

.NRR Project Manager, NRC MPCA Attn: J W Ferman J E Silberg ,

Attachments:

Revised Prairie Island Large Break LOCA Calculation Using WCAP 10924 Volume 1 Addendum 4 flodel Changes Core Flow Difference Observed in MCCBRA/ TRAC Calculations 9102110005 910205 PDR ADOCK 05000282

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