ML11356A208: Difference between revisions

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==SUBJECT:==
==SUBJECT:==
DATE & TIME: LOCATION:
DATE & TIME: LOCATION:
PURPOSE: CATEGORY 1:* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 30, 2011 Shawn Williams, Acting Chief Plant Licensing Branch 111-1 J Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation q( }4r./ n}J /, Karl Feintuch, Project Manager. A. Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FORTHCOMING MEET I NG WITH NORTHERN STATES POWER COMPANY OF MINNESOTA (NSPM) TO DISCUSS THE LICENSEE'S FUTURE PROPOSED AMENDMENT REGARD I NG FUEL STORAGE CRITICALITY ANALYSIS (TAC NO. ME7372) Tuesday, January 17, 2012 1 :00 -3:30 p.m. u.s. Nuclear Regulatory Commission One White Flint North, Room 0-16 B4 11555 Rockville Pike Rockville, MD 20852 NRC and licensee participants will discuss the licensee's future proposed amendment concerning the fuel storage criticality analysis, specifically:  
PURPOSE: CATEGORY 1:* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 30, 2011 Shawn Williams, Acting Chief Plant Licensing Branch 111-1 J Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation q( }4r./ n}J /, Karl Feintuch, Project Manager. A. Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FORTHCOMING MEET I NG WITH NORTHERN STATES POWER COMPANY OF MINNESOTA (NSPM) TO DISCUSS THE LICENSEE'S FUTURE PROPOSED AMENDMENT REGARD I NG FUEL STORAGE CRITICALITY ANALYSIS (TAC NO. ME7372) Tuesday, January 17, 2012 1 :00 -3:30 p.m. u.s. Nuclear Regulatory Commission One White Flint North, Room 0-16 B4 11555 Rockville Pike Rockville, MD 20852 NRC and licensee participants will discuss the licensee's future proposed amendment concerning the fuel storage criticality analysis, specifically:
(1) Technical Specification maximum k-infinity values for fuel in the new fuel vault and spent fuel storage racks; (2) the new fuel vault criticality limits;(3) the spent fue l storage rack criticality limits; (4) the criticality safety analysis methodology; (2) the operating license language regarding the amount of fuel assemblies licensed for use and storage. This is a Category 1 meeting. The public is invited to observe this meeting and will have an opportunity to communicate with the NRC staff after the business portion, but before the meeting is adjourned.
(1) Technical Specification maximum k-infinity values for fuel in the new fuel vault and spent fuel storage racks; (2) the new fuel vault criticality limits;(3) the spent fue l storage rack criticality limits; (4) the criticality safety analysis methodology; (2) the operating license language regarding the amount of fuel assemblies licensed for use and storage. This is a Category 1 meeting. The public is invited to observe this meeting and will have an opportunity to communicate with the NRC staff after the business portion, but before the meeting is adjourned.
MEETING CONTACTS:
MEETING CONTACTS:
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-by-region.html.
-by-region.html.
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Revision as of 06:45, 30 April 2019

01/17/2012 Notice of Meeting with NSPM to Discuss a Future Proposed Amendment Regarding Revised Fuel Storage Criticality Analysis
ML11356A208
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/30/2011
From: Feintuch K D
Plant Licensing Branch III
To: Williams S A
Plant Licensing Branch III
Tam P S
References
TAC ME7372
Download: ML11356A208 (3)


Text

MEMORANDUM TO: FROM:

SUBJECT:

DATE & TIME: LOCATION:

PURPOSE: CATEGORY 1:* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 30, 2011 Shawn Williams, Acting Chief Plant Licensing Branch 111-1 J Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation q( }4r./ n}J /, Karl Feintuch, Project Manager. A. Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FORTHCOMING MEET I NG WITH NORTHERN STATES POWER COMPANY OF MINNESOTA (NSPM) TO DISCUSS THE LICENSEE'S FUTURE PROPOSED AMENDMENT REGARD I NG FUEL STORAGE CRITICALITY ANALYSIS (TAC NO. ME7372) Tuesday, January 17, 2012 1 :00 -3:30 p.m. u.s. Nuclear Regulatory Commission One White Flint North, Room 0-16 B4 11555 Rockville Pike Rockville, MD 20852 NRC and licensee participants will discuss the licensee's future proposed amendment concerning the fuel storage criticality analysis, specifically:

(1) Technical Specification maximum k-infinity values for fuel in the new fuel vault and spent fuel storage racks; (2) the new fuel vault criticality limits;(3) the spent fue l storage rack criticality limits; (4) the criticality safety analysis methodology; (2) the operating license language regarding the amount of fuel assemblies licensed for use and storage. This is a Category 1 meeting. The public is invited to observe this meeting and will have an opportunity to communicate with the NRC staff after the business portion, but before the meeting is adjourned.

MEETING CONTACTS:

Peter Tam, NRR 301-415-1451 peter.tam@nrc.gov Karl Feintuch, NRR 301-415-3079 karl.feintuch@nrc.gov

  • Commission's Policy Statement, "Enhancing Public Participation in NRC Meetings" (67 FR 36920), May 28, 2002.

S. Williams PARTICIPANTS: Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR). KentWood Matthew Yoder Peter Tam. et al. NSPM G.D.Adams G. F. Eckholt et al. Interested members of the public can participate in the meeting via a toll-f ree audio teleconference. Please call one of the meeting contacts listed before close of business on January 13, 2012, to get the telephone number and the pass code. The NRC provides reasonable accommodation to individuals with disabilities where appropriate.

If you need reasonable accommodation to participate in a meeting, or need a meeting notice or a transcript or other information from a meeting in another format (e.g., Braille, large print), please notify the NRC's meeting contacts.

Determinations on requests for reasonable accommodation will be made on a case-by-case basis. To receive a summary of this meeting and begin receiving other plant-specific e-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via http://www.nrc.gov/public-involve/listserver/plants-by-region

.html. Once subscribed, if you wish to discontinue receiving electronic distribution, you may unsubscribe at any time by visiting the same web address above. Docket No. 50-263 cc: Distribution via ListServ S. Williams PARTICIPANTS:

Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR). KentWood Peter Tam et al. NSPM G.D.Adams G. F. Eckholt et al. Int erested members of the public can participate in the meeting via a toll-free audio teleconference.

Please call one of the meeting contacts listed before close of business on January 13, 2012, to get the telephone number and the pass code. The NRC provides reasonable accommodation to individuals with disabilities where appropr i ate. If you need reasonable accommodation to participate in a meeting, or need a meeting notice or a transcript or other information from a meeting in another format (e.g., Braille, l arge print), please notify the NRC's meeting contacts.

Determinations on requests for reasonable accommodation will be made on a case-by-case basis. To receive a summary of this meeting and begin receiving other plant-specific e-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via http://www.nrc.gov/public

-in volve/listserver/plants

-by-region.html.

Once subscribed, if you wish to discontinue receiving electro ni c distribution, you may unsubscribe at any time by visiting the same web address above. Docket No. 50-263 cc: Distribution via ListServ DISTR I BUTION: PUBLIC RidsNrrDorl Resource RidsAcrsAcnw

_MailCTR Resource RidsNrrDorlLpl3-1 Resource RidsOgcMailCenter Resource RidsRgn3MailCenter Resource A, Snyder, EDO Region III OWFN Receptionist (hard copy) K. Wood, NRR ADAMS Accession No.: ML 11356A208 OFF I CE DORLlLPL3-1/PM DORLlLPL3-1/LA NAME KFeintuch BTuily DATE 121 ,kJ/11 12/22/11 LP3-1 R/F PMNS Resource RidsNrrPMMonticelio Resource RidsNrrLABTuily Resource RidsOpaMa il Resource C. Steger, NRR V. Mitlyng , OPA Region III TWFN Receptionist (hard copy) DORLlLPL3-j.L;BC(A) SWiliiams

(>(5-r l-r L 121 ,10/11 if OFFICIAL RECORD COPY v