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{{#Wiki_filter:NRC FORM 658                                                                           U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
{{#Wiki_filter:NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
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.
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 no materials, will be sent to the Document Control Desk on the same day of the meeting; under circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
 
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:
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
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
 
NRC FORM 658 (9-PRINTED ON RECYCLED P-AP-ER nn was es g 9 9i n d usin InForms GE Nuclear Energy
 
GE/NRC Technology Update


Agenda
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/Hitachi/Toshiba Fuel Joint Venture


GE Fuel Experience Update Nuclear Methods Qualification Update GE Nuclear Energy Application of TGBLA06/PANAC11 to Core Design and Monitoring UPDATE
"* GE Fuel Experience Update


Items for Discussion e Plant Tracking Statistical 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
* Statistics Breakdown
    - TIPs
- TIPs
    - Thermal Limits
- Thermal Limits
    - Eigenvalues
- Eigenvalues
* Application of SLMCPR methodology for TGBLAO6IPANAC1 1 One European plant desigjned and operating with TGBL A06/PA NA Cl11 basis
* Application of SLMCPR methodology for TGBLAO6IPANAC1 1


Methods Introductionand Evaluation
One European plant desigjned and operating with TGBL A 06/PA NA Cl11 basis Methods Introduction and Evaluation
* New physics exposure burn-in
* New physics exposure burn-in
    - Re-bum from cycle 1, or 3 cycles priorto cycle of interest
- Re-bum from cycle 1, or
- 2-3 cycles prior to cycle of interest
* Trending analysis
* Trending analysis
    - Hot eigenvalue: o(khot) last two complete cycles only
- Hot eigenvalue: o(khot) last two complete cycles only
    - Cold eigen value: a(kcold) all cycles after bum-in
- Cold eigen value: a(kcold) all cycles after bum-in
    - TIP comparisons: RMSrad, RMSnod all cycles after bum-in
- TIP comparisons: RMSrad, RMSnod all cycles after bum-in Plant Tracking Statistical Update Plant Tracking Statistical Update, cont'd.
Plant Tracking Summary
 
"* BWR/2-BWR/6, ABWR, and others
 
"* GE6-GE14, ABB fuel, Siemens fuel, STEP-2


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
  " HOT
    - 31 Plants, 154 cycles
- 31 Plants, 154 cycles
  "*COLD
 
    - 20 Plants, 81 cycles, 278 criticals
  "* COLD
"*TIPs
- 20 Plants, 81 cycles, 278 criticals
    - 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:
"* TIPs
Nodal RMS:        Nodal RMS:
- 5 Plants, 8 cycles (Neutron TIPs)
- 7 Plants, 30 cycles (Gamma TIPs)


An additional 1Oplants 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)
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.


"* 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 comparisons across the fleet.
Thermal Limits Predictive Capability*
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.
* Compared with Process Computer evaluated thermal limit values. Population of data selected includes 10 plants for 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
No surprises in predictive capability.
Sample Cold Eigenvalue Statistics


Sample Hot Eigenvalue Statistics PANAC10 (CY.
PANAC1i0 Sample Definition
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..
15 Plants, 55 Cycles
Plant C - Hot Eigenvalues for Cycles Design:        Enrichment:    Gadolinium:


Extension of Power Uncertaintyto PANAC11 Infinite Lattice Pin Power Uncertainty 16
148 Cold Criticals


Summary
PANAC11
"*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)
Standard Deviations
  - PANAC11
  - PRDF (BWR/6)
  - BWROG Stability Options
  - Updated references (LOCA)
  -Conversion to WORD/PDF format


Other Licensing Activities
T4/P1 0: % Ak
 
T6/P11: % Ak Sample Hot Eigenvalue Statistics
 
PANAC10 (CY. ) PANAC11 (Cy.
- - -- -- - - - - N - - - 191)
AVERAGE: AVERAGE: (CY.
 
AVG. SLOPE: AVG. SLOPE:
ST. DEV: r)cm ST. DEV:pcm Operational Trends Driving New Capabilities Some challenges developing..
 
Plant C - Hot Eigenvalues for Cycles
 
Design: Enrichment: Gadolinium:
Extension of Power Uncertainty to PANAC11 Infinite Lattice Pin Power Uncertainty
 
16 Summary
 
"* Implementation of TGBLAO6IPANAC1 1 proceeding
* Qualification and verification database is large and growing
 
"* Accuracy comparable to other advanced nuclear design systems
 
"* Full range of applications supported
- Licensing
- Stability
- Fuel cycle design
- Cold shutdown
- Core monitoring
 
I Methods Accuracy Tracking is a Priority I 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
* TRACG Application to Transients
  - LTR submittals in 4Q99
- LTR submittals in 4Q99
* Replace FABLE model with ODYSY
* Replace FABLE model with ODYSY
  - Stability analyses
 
  -Submit in 2Q00
- Stability analyses
-Submit in 2Q00
* PANAC11 Rod Drop Accident version
* PANAC11 Rod Drop Accident version
  -Submit in 2Q00}}
-Submit in 2Q00}}

Latest revision as of 05:01, 14 September 2024

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)


Text

NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)

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 no materials, will be sent to the Document Control Desk on the same day of the meeting; under circumstances will this be done later than the working day after the meeting.

Do not include proprietary materials.

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

NRC FORM 658 (9-PRINTED ON RECYCLED P-AP-ER nn was es g 9 9i n d usin InForms 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 A 06/PA NA Cl11 basis Methods Introduction and Evaluation

  • New physics exposure burn-in

- Re-bum from cycle 1, or

- 2-3 cycles prior to 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 Statistical Update Plant Tracking Statistical Update, 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 additional 1Oplants 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 comparisons across the fleet.

Thermal Limits Predictive Capability*

  • Compared with Process Computer evaluated thermal limit values. Population of data selected includes 10 plants for 14 cycles for a total of 690 points.

No surprises in 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. ) PANAC11 (Cy.

- - -- -- - - - - N - - - 191)

AVERAGE: AVERAGE: (CY.

AVG. SLOPE: AVG. SLOPE:

ST. DEV: r)cm ST. DEV:pcm Operational Trends Driving New Capabilities Some challenges developing..

Plant C - Hot Eigenvalues for Cycles

Design: Enrichment: Gadolinium:

Extension of Power Uncertainty to PANAC11 Infinite Lattice Pin Power Uncertainty

16 Summary

"* Implementation of TGBLAO6IPANAC1 1 proceeding

  • Qualification and verification database is large and growing

"* Accuracy comparable to other advanced nuclear design systems

"* Full range of applications supported

- Licensing

- Stability

- Fuel cycle design

- Cold shutdown

- Core monitoring

I Methods Accuracy Tracking is a Priority I 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

- LTR submittals in 4Q99

  • Replace FABLE model with ODYSY

- Stability analyses

-Submit in 2Q00

  • PANAC11 Rod Drop Accident version

-Submit in 2Q00