ML20115H280

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Forwards COLR for Cycle 18,Rev 2 to Provide Corrected Power Dependent Minimum CPR Limits,Figure 3 of COLR
ML20115H280
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 07/16/1996
From: Hill W
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20115H283 List:
References
NUDOCS 9607230025
Download: ML20115H280 (2)


Text

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Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 July 16,1996 Technical Specification 6.7.A.7 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Submittal of the Core Operatino Limits Report for Cvele 18. Revision 2 The Core Operating Umits Report (COLR) for Cycle 18 has been revised. Revision 2 was issued to provide corrected Power Dependent Minimum Critical Power Ratio (CPR) Umits, Figure 3 of the COLR.

NSP personnelldentified a non-conservative assumption used for the generation of the power dependent CPR limits and Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) Umits. This non-conservative assumption affected the portion of the Power Dependent CPR curve below 45% power. The power dependent CPR limits (Figure 3) were adjusted to adequately bound the results of the transient analysis below 45% of rated power and at a steam dome pressure low in the normal operating range. The previously published power depencent Maximum Average Planar unear Heat Generation Rate (MAPLHGR) Umits (Figure 1) bound the results of the transient analysis initiated at a steam dome pressure low in the normal operating range and do not require adjustment.

NSP has confirmed that this non-conservative assumption had no adverse effect on core operating limits as Monticello has either operated in a region unaffected by the non-conservative assumption or fuel limits have been conservative with respect to the revised core operating limit. As a results of NSP's assessment of this issue and NSP's intemal corrective action process, NSP has initiated corrective actions to prevent re-occurrence of this self identified issue as well as similarissues.

The enclosed report provides the values of the limits for Cycle 18 as required by Technical Specification Section 6.7.A.7. These values have been established using NRC approved methodology such that all applicable limits of the plant safety analysis are met.

Please contact Marv Engen at 612-295-1291 if you have any questions related to this submittal.

9607230025 960716 PDR ADOCK 05000263 P PDR 7/15/96 NSP JAD04560\MONTILMliNRCCORR\COLR_C18.R2 g 1

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USNRC NORTHERN STATES POWER COMPANY July 16,1996 Page 2 d 45w 6 William J Hill Plant Manager Monticello Nuclear Generating Plant -  !

c: Regional Administrator-Ill, NRC NRR Project Mgr, NRC NRC Resident inspector State of Minnesota Attn: Kris Sanda J Silberg

Enclosure:

Core Operating Limits Report for Cycle 18 (Rev 2) e f

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