ML20078H998: Difference between revisions

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W Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 February 2, 1995 U S Nuclear Regulatory Commission Attn Document control Desk Washington, DC 20555 1
                                      ,                        Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 February 2, 1995 U S Nuclear Regulatory Commission Attn Document control Desk Washington, DC 20555                                                                                 1 l
1 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 i
1 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22                                       i Request for Approval of Revision 3 of NSPNAD 8608, " Reload Safety Evaluation Methods for                               ;
Request for Approval of Revision 3 of NSPNAD 8608, " Reload Safety Evaluation Methods for Aeolication to the Monticello Nuclear Generatino Plant" r
Aeolication to the Monticello Nuclear Generatino Plant"                               r l
The currently approved reactor safety topical for Monticello is Revision 2 of NSPNAD-86J8, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant". The purpose of this letter is to submit Revision 3 of NSPNAD-8608 for NRC approval.
The currently approved reactor safety topical for Monticello is Revision 2 of NSPNAD-86J8, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant". The purpose of this letter is to submit Revision 3 of NSPNAD-8608 for NRC approval.
A revision of the physics topical (NSPNAD-8609), to incorporate the use of CASMO-3/ SIMULATE-3, was submitted to the NRC by a {{letter dated|date=August 23, 1994|text=letter dated August 23, 1994}} and is currently under review. This revision of the safety topical incorporates changes required to use the output of CASMO-3/ SIMULATE-3 physics methods for reload safety evaluation applications. The major changes made in this revision of the safety topical are contained in Appendix A and a list of all the changes is included at the end of the report.
A revision of the physics topical (NSPNAD-8609), to incorporate the use of CASMO-3/ SIMULATE-3, was submitted to the NRC by a {{letter dated|date=August 23, 1994|text=letter dated August 23, 1994}} and is currently under review. This revision of the safety topical incorporates changes required to use the output of CASMO-3/ SIMULATE-3 physics methods for reload safety evaluation applications. The major changes made in this revision of the safety topical are contained in Appendix A and a list of all the changes is included at the end of the report.
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Sincerely,
Sincerely,
[
[
W Roger O Anderson                                                                                       l Director Licensing and Management Issues c: Regional Administrator III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg 9502070170 950202                                                                       i PDR    ADDCK0500g3                                                                       g}}
W Roger O Anderson l
Director Licensing and Management Issues c: Regional Administrator III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg 9502070170 950202 i
ADDCK0500g3 g
PDR}}

Latest revision as of 00:33, 15 December 2024

Forwards Rev 3 of NSPNAD-8608, Reload Safety Evaluation Methods for Application to Monticello Nuclear Generating Plant for NRC Approval
ML20078H998
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 02/02/1995
From: Richard Anderson
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078J002 List:
References
NUDOCS 9502070170
Download: ML20078H998 (1)


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W Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 February 2, 1995 U S Nuclear Regulatory Commission Attn Document control Desk Washington, DC 20555 1

1 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 i

Request for Approval of Revision 3 of NSPNAD 8608, " Reload Safety Evaluation Methods for Aeolication to the Monticello Nuclear Generatino Plant" r

The currently approved reactor safety topical for Monticello is Revision 2 of NSPNAD-86J8, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant". The purpose of this letter is to submit Revision 3 of NSPNAD-8608 for NRC approval.

A revision of the physics topical (NSPNAD-8609), to incorporate the use of CASMO-3/ SIMULATE-3, was submitted to the NRC by a letter dated August 23, 1994 and is currently under review. This revision of the safety topical incorporates changes required to use the output of CASMO-3/ SIMULATE-3 physics methods for reload safety evaluation applications. The major changes made in this revision of the safety topical are contained in Appendix A and a list of all the changes is included at the end of the report.

It is desired to use the safety evaluation methods described in Revision 3 for Monticello Cycle 18, in which we intend to transition to Gell fuel. In order to make a smooth transition to the CASMO-3/ SIMULATE-3 physics methods for cycle 18, NRC approval is needed by 8/1/95.

If you have any questions or comments please contact Mel opstad at 612-295-1653.

Sincerely,

[

W Roger O Anderson l

Director Licensing and Management Issues c: Regional Administrator III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg 9502070170 950202 i

ADDCK0500g3 g

PDR