ML20207R014
| ML20207R014 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/03/1987 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20207R015 | List: |
| References | |
| NUDOCS 8703110054 | |
| Download: ML20207R014 (2) | |
Text
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Northern States Power Company 414 Nicollet Mau Minneapolis, Minnesota 55401 Telephone (612) 330-5500 March 3, 1987 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Changes to the 1981 LOCA Model for Operation of Unit 1 Cycle 12 Enclosed is a Loss of Coolant Accident (LOCA) analysis for Prairie Island Unit 1 Cycle 12.
This analysis was performed with the Westinghouse 1981 LOCA Model with minor modifications. Since these modifications have not been reviewed and approved by the NRC Staff for the 1981 Model, this is being submitted for your review. In accordance with 10 CFR Part 170, a check in the amount of $150.00 is enclosed.
The last LOCA analysis submitted for your review was submitted on January 13, 1986 and subsequently approved on April 3, 1986.
This analysis supported a peaking factor (F ) of 2.3 for a core of 2/3 Exxon TOPROD and q
1/3 Westinghouse Optimized fuel.
This analysis was only valid for Unit 1 Cycle 11 and Unit 2 Cycle 11 since it was anticipated that the new Upper Plenum Injection Best Estimate Methodology would be approved prior to the startup of Unit 1 Cycle 12.
Per discussions with Mr Domminic DiIanni and Mr Richard Lobel, of your staff, the new Upper Plenum Injection Best Estimate Methodology may not be approved for the startup of Unit 1 Cycle 12.
Unit 1 Cycle 12 is scheduled to startup May 12, 1987.
Since Unit 1 Cycle 12 will contain 2/3 Westinghouse Optimized and 1/3 Exxon TOPROD fuel, another analysis has been performed with the 1981 Model to support operation of Unit 1 Cycle 12.
The analysis also assumes peak pellet t
p burnups for the Westinghouse fuel up to 42,000 MWD /MTU and a lower hot assembly peaking factor. In order to support operation with the existirig Technical Specification peaking factors, a change to the metal heat inputs c
was made which is consistent with the metal heat modeling approved in WCAP-9561-P-A. The attached report describes this model change and provides the results of this change on the Prairie Island LOCA analysis.
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-March 3, 1987 Page 2 Approval of. th'is' model change is needed prior to the start'up of Unit l'
~ Cycle 12, scheduled to startup May 12, 1987.
In order to account for potential schedule changes, we request approval of this change prior. to r
l May:2, _
Please contact us if you have any. questions concerning 1987. '
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this submittal and/or the requested schedule.
c o s w.
c David Musolf Manager - Nuclear Support Services i.
DMM/TMP/tp i
c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC C Charnoff
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- \\ttachments: Report: Demonstrati*n of the Conformance of Prairie Island UnitstoAp['endixKand10CFR50.46forLarge~ Break I
- LOCAs, Feb vary 1987, Westinghouse Electric Corp.
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$150.00 check to th U S Nuclear Regulatory Commission j
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