ML12017A085
| ML12017A085 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/10/2012 |
| From: | Tam P Plant Licensing Branch III |
| To: | |
| Tam P | |
| Shared Package | |
| ML12017A093 | List: |
| References | |
| TAC ME7372 | |
| Download: ML12017A085 (3) | |
Text
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'1-1] ****i<"'o February 10, 2012 LICENSEE:
Northern States Power Company of Minnesota (NSPM)
FACILITY:
Monticello Nuclear Generating Plant
SUBJECT:
SUMMARY
OF THE JANUARY 17, 2012, MEETING TO DISCUSS ISSUES RELATED TO A FUTURE APPLICATION FOR AMENDMENT CONCERNING STORED FUEL CRITICALITY SAFETY ANALYSIS (TAC NO. ME7372)
On January 17, 2012, the Nuclear Regulatory Commission (NRC) staff held a public meeting with representatives of NSPM at NRC hearquarters. The purpose of the meeting was for the licensee to discuss issues related to a future application for amendment concerning stored fuel criticality safety analysis (CSA). The Enclosure to this summary contains the list of participants.
The licensee's presentation followed the licensee's handout material (docketed at Agencywide Documents Access and Management System, Accession No. ML12017A048). As shown in the handout material, the licensee plans to submit the application for the CSA amendment by the fourth quarter of 2012, and a few months later submit a separate application for amendment to transition the nuclear fuel to that supplied by AREVA.
The NRC staff members present in the meeting indicated that they are most concerned about the proposed elimination (see page 27 of handout) of Technical Specifications 4.3.1.1.a, which specifies that spent fuel storage racks are designed and shall be maintained with "[f]uel assemblies having a maximum k-infinity of 1.33 in the normal reactor core configuration at cold conditions." The staff members stated that the licensee may propose to revise this requirement, but not to eliminate it.
A member of the public was in attendance. No portion of this meeting was closed to the public because no proprietary information was used by the participants. Before the meeting adjourned, all participants were given the opportunity to comment on any aspects of the meeting. No comment or feedback was provided.
Please direct any inquiries to the undersigned (Tel. 301-415-~il peter.tam@nrc.gov).
Pe er S. Tam, s;'l~ct Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
List of participants cc w/encl: Distribution via ListServ
LIST OF PARTICIPANTS MEETING BETWEEN NUCLEAR REGULATORY COMMISSION (NRC)
AND NORTHERN STATES POWER COMPANY OF MINNESOTA (NSPM)
MONTICELLO NUCLEAR GENERATING PLANT (MNGP)
FUTURE AMENDMENT CONCERNING STORED FUEL CRITICALITY ANALYSIS January 17. 2012 NAME ORGANIZATION Shaun Anderson NRC/NRRfSTSB**
Cliff Bonneau NSPM Glenn Adams NSPM Gene Eckholt NSPM Edward Fowles AREVA (contractor of NSPM)
Alan Meginnis AREVA (contractor of NSPM)
Peter Tam NRC Project Manager for MNGP KentWood NRC/NRR/SRXB*
The following participated by telephone:
Maureen Conley Platts/McGraw-Hili Nuclear Publications GeraldWaig NR C/NRR/STSB**
- Office of Nuclear Reactor Regulation/Reactor Systems Branch
- Office of Nuclear Reactor RegulationlTechnical Specifications Branch Enclosure
February 10, 2012 LICENSEE:
Northern States Power Company of Minnesota (NSPM)
FACILITY:
Monticello Nuclear Generating Plant
SUBJECT:
SUMMARY
OF THE JANUARY 17, 2012, MEETING TO DISCUSS ISSUES RELATED TO A FUTURE APPLICATION FOR AMENDMENT CONCERNING STORED FUEL CRITICALITY SAFETY ANALYSIS (TAC NO. ME7372)
On January 17, 2012, the Nuclear Regulatory Commission (NRC) staff held a public meeting with representatives of NSPM at NRC hearquarters. The purpose of the meeting was for the licensee to discuss issues related to a future application for amendment concerning stored fuel criticality safety analysis (CSA). The Enclosure to this summary contains the list of participants.
The licensee's presentation followed the licensee's handout material (docketed at Agencywide Documents Access and Management System, Accession No. ML12017A048). As shown in the handout material, the licensee plans to submit the application for the CSA amendment by the fourth quarter of 2012, and a few months later submit a separate application for amendment to transition the nuclear fuel to that supplied by AREVA.
The NRC staff members present in the meeting indicated that they are most concerned about the proposed elimination (see page 27 of handout) of Technical Specifications 4.3.1.1.a, which specifies that spent fuel storage racks are designed and shall be maintained with "[f]uel assemblies having a maximum k-infinity of 1.33 in the normal reactor core configuration at cold conditions." The staff members stated that the licensee may propose to revise this requirement, but not to eliminate it.
A member of the public was in attendance. No portion of this meeting was closed to the public because no proprietary information was used by the participants. Before the meeting adjourned, all participants were given the opportunity to comment on any aspects of the meeting. No comment or feedback was provided.
Please direct any inquiries to the undersigned (Tel. 301-415-1451, e-mail peter.tam@nrc.gov).
IRAJ Peter S. Tam, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
List of participants cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource LPL3-1 R/F RidsNrrPMDCCook Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource B. Reilly, R-III RidsRgn3MailCenter Resource G. Waig, NRR K. Wood, NRR S. Anderson, NRR C. Steger, NRR Package: ML12017A093 Meeting Summary Accession No.: ML12017A085 Meetin Notice Accession No.: ML11356A208 Licensee's Handout Accession No.: ML12017A048 FFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRRISRXB/BC NRR/LPL3-1/BC A NRR/LPL3-1/PM PTam BTuli AUlses SWilliams PTam 1/31/12 1/30/12 1/12 2/8112 2/10112 OFFICIAL RECORD COpy