ML993250129: Difference between revisions

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{{#Wiki_filter:NRC FORM 658                                                                            U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
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TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed)by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstanceswill this be done later than the working day after the meeting.
Do not include proprietarymaterials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s)                Project 691 Plant/Facility Name              General Electric TAC Number(s) (if available)    __
Reference Meeting Notice                      ,      *j  I2,/A Purpose of Meeting (copy from meeting notice)      To provide the staff a GE fuel experience and a nuclear methods qualification update, a discussion on GESTAR Am. 26 and Japanese joint venture.
Ma~n -PA~e4, A!4                          /Z/
NAME OF PERSON WHO ISSUED MEETING NOTICE                    TITLE Robert M. Pulsifer                                          Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licesning Project Management BRANCH Project Directorate III, Section 2 Distribution of this form and attachments:
Docket File/Central File PUBLIC PRINTED ON RECYCLED P-AP-ER                          nnwas es ig n9 d usin 9 InForms NRC FORM 658 (9-
 
GE Nuclear Energy GE/NRC Technology Update 10 November 1999
 
Agenda
"* GE/Hitachi/Toshiba Fuel Joint Venture
"* GE Fuel Experience Update
"* Nuclear Methods Qualification Update
"* GESTAR Amendment 26
 
JV Update GENE - Wilmington October, 1999
 
GE Fuel Experience Update Nuclear Methods Qualification Update GE Nuclear Energy Application of TGBLA06/PANAC11 to Core Design and Monitoring UPDATE
 
Items for Discussion e Plant Tracking Statistical Update
* Statistics Breakdown
    - TIPs
    - Thermal Limits
    - Eigenvalues
* Application of SLMCPR methodology for TGBLAO6IPANAC1 1 One European plant desigjned and operating with TGBL A06/PA NA Cl11 basis
 
Methods Introductionand Evaluation
* New physics exposure burn-in
    - Re-bum from cycle 1, or 3 cycles priorto cycle of interest
* Trending analysis
    - Hot eigenvalue: o(khot) last two complete cycles only
    - Cold eigen value: a(kcold) all cycles after bum-in
    - TIP comparisons: RMSrad, RMSnod all cycles after bum-in
 
Plant Tracking StatisticalUpdate Plant Tracking StatisticalUpdate, cont'd.
Plant Tracking Summary
"*BWR/2-BWR/6, ABWR, and others
"*GE6-GE14, ABB fuel, Siemens fuel, STEP-2
" HOT
    - 31 Plants, 154 cycles
"*COLD
    - 20 Plants, 81 cycles, 278 criticals
"*TIPs
    - 5 Plants, 8 cycles (Neutron TIPs)
    - 7 Plants, 30 cycles (Gamma TIPs)
An additional1Oplants and 80 + cycles since Spring 1998.
 
Sample TIP Agreement PANAC1i0        PANAC11 Radial RMS:      Radial RMS:
Nodal RMS:        Nodal RMS:
 
Small BWRI4 Case Study - TIP Comparison to Process Computer Summary of plant tracking database (P11 only)
  "*Neutron  TIP Plants
      - Radial (Bundle)*%
      - Total (Nodal)  :%
  "*Gamma    TIP Plants
      - Radial (Bundle):%
      - Total (Nodal)  *%
  "*Afl Plants
      - Radial (Bundle):%
      - Total (Nodal)                    %
  "*Case  Study
      - Radial (Bundle):%
      - Total (Nodal)                    %
GE actively pursuing TIP comparisonsacross the fleet.
 
Thermal Limits Predictive Capability*
* Compared with Process Computer evaluated thermal limit values. Population of data selected includes 10 plantsfor 14 cycles for a total of 690 points.
No surprisesin predictive capability.
 
Sample Cold Eigenvalue Statistics PANAC1i0                  Sample Definition 15 Plants, 55 Cycles 148 Cold Criticals PANAC11 Standard Deviations T4/P1 0:      % Ak T6/P11:      % Ak
 
Sample Hot Eigenvalue Statistics PANAC10 (CY.
N-  - - )
19 PANAC11 (Cy.
(CY. 1)
AVERAGE:                      AVERAGE:
AVG. SLOPE:                    AVG. SLOPE:
ST. DEV:            r)cm      ST. DEV:  pcm
 
OperationalTrends Driving New Capabilities Some challenges developing..
Plant C - Hot Eigenvalues for Cycles Design:        Enrichment:    Gadolinium:
 
Extension of Power Uncertaintyto PANAC11 Infinite Lattice Pin Power Uncertainty 16
 
Summary
"*Implementation of TGBLAO6IPANAC1 1 proceeding
* Qualificationand verification databaseis large and growing
"*Accuracy comparable to other advanced nucleardesign systems
"*Full range of applicationssupported
    - Licensing
    - Stability
    - Fuel cycle design
    - Cold shutdown
    - Core monitoring IMethods Accuracy Tracking is a PriorityI
 
Amendment 26 e General GESTAR revision (Amendment 26)
  - PANAC11
  - PRDF (BWR/6)
  - BWROG Stability Options
  - Updated references (LOCA)
  -Conversion to WORD/PDF format
 
Other Licensing Activities
* TRACG Application to Transients
  - LTR submittals in 4Q99
* Replace FABLE model with ODYSY
  - Stability analyses
  -Submit in 2Q00
* PANAC11 Rod Drop Accident version
  -Submit in 2Q00}}

Revision as of 09:15, 11 October 2021

Transmittal of Meeting Handout Materials for Immediate Placement in the Public Domain. November 10, 1999 Meeting Concerned GE Fuel Experience, Nuclear Methods Qualification Update and Discussion on Gestar Am. 26 and Japanese Joint Venture
ML993250129
Person / Time
Site: Boiling Water Reactor Owners Group
Issue date: 11/10/1999
From: Pulsifer R
NRC/NRR/DLPM/LPD3
To:
References
Download: ML993250129 (25)


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