L-MT-03-077, 2003 Report of Changes and Errors in ECCS Evaluation Models

From kanterella
(Redirected from L-MT-03-077)
Jump to navigation Jump to search
2003 Report of Changes and Errors in ECCS Evaluation Models
ML033010523
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 10/16/2003
From: Thomas J. Palmisano
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-03-077
Download: ML033010523 (2)


Text

NR Monticello Nuclear Generatinq Plant Committed to Nuclear Operated by Nuclear Management Company, LLC October 16, 2003 L-MT-03-077 10 CFR Part 50 Section 50.46(a)(3)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 LICENSE No. DPR-22 2003 REPORT OF CHANGES AND ERRORS IN ECCS EVALUTION MODELS Pursuant to 10 CFR 50.46(a)(3), Nuclear Management Company, LLC (NMC), is providing an annual report of changes or errors identified in the Emergency Core Cooling System (ECCS) analytical models or their application for the period of July 2002 through July 2003 for the Monticello Nuclear Generating Plant (MNGP).

The MNGP Loss of Coolant Accident (LOCA) analyses of record are contained in the General Electric (GE) reports submitted as part of the license amendment request for MNGP rerate (Reference 1) and the LOCA analysis for the GE14 fuel type (Reference 2). Five notifications of changes or errors in these analyses were received from GE during this reporting period (References 3 through 7). These notifications in total resulted in a 150 F reduction in Peak Cladding Temperature (PCT) for both GE11 and GE14 fuel. The current adjusted licensing basis PCTs for the fuel types in use at MNGP are listed below. The PCT includes all adjustments from this reporting period, and all previous reporting periods dating back to the analysis of record.

Fuel Tvpe Licensing PCT (OF)

GE11 2137 GE14 1945 This letter makes no new commitments. If you have any questions regarding this submittal, please contact Rick Loeffler, Senior Regulatory Affairs Engineer, at (763) 295-1247.

Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75

  • Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
  • Fax: 763.295.1454 Aoa

USNRC Nuclear Management Company, LLC Page 2 CC: Regional Administrator, Region lii, USNRC Senior Project Manager, Monticello, USNRC Senior Resident Inspector, Monticello, USNRC Minnesota Department of Commerce References

1. GE Report: NEDC-32514P, Revision 1, "Monticello SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," October 1997. This report is Exhibit G of "Revision 1 to License Amendment Request Dated July 26, 1996, Supporting Monticello Nuclear Generating Plant Power Rerate Request Program."
2. GE Report: GE-NE-J1 103878-09-02P, "Monticello ECCS-LOCA Evaluation for GE14," GE Proprietary Information, dated August 2001.
3. 10 CFR 50.46 Notification Letter 2002-03, "Impact of GESTR Input File Interpolation Error on the Peak Clad Temperature (PCT)," GE Proprietary Information, correspondence dated August 26, 2002.
4. 10 CFR 50.46 Notification Letter 2002-04, "Impact of SAFER04 Computer Platform Change on the Peak Clad Temperature (PCT)," GE Proprietary Information, correspondence dated August 26, 2002.
5. 10 CFR 50.46 Notification Letter 2002-05, "Impact of WEVOL S1 Volume Error on the Peak Clad Temperature (PCT)," GE Proprietary Information, correspondence dated August 26, 2002.
6. 10 CFR 50.46 Notification Letter 2003-01, "Impact of SAFER Level/Volume Table Error on the Peak Cladding Temperature (PCT)," GE Proprietary Information, correspondence dated May 6, 2003.
7. 10 CFR 50.46 Notification Letter 2003-03, "Impact of SAFER Initial Separator Pressure Drop Error on the Peak Cladding Temperature (PCT)," GE Proprietary Information, correspondence dated May 6, 2003.