ML17187A966

From kanterella
Jump to navigation Jump to search
Summary of 970403 Meeting W/Commonwealth Edison Co & Siemens Power Corp to Discuss Advanced Nuclear Fuel for BWR Correlation for Atrium 9B Fuel Application & Mixed Core Analysis.List of Attendees Encl
ML17187A966
Person / Time
Site: Dresden, Quad Cities, LaSalle  
Issue date: 05/09/1997
From: Pulsifer R
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9705150362
Download: ML17187A966 (35)
v • d • e


Text

1

  • LICENSEE:

FACILITIES:

~U8JECT:

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205M-0001 May 9. 1997 Commonwealth Edison Company {ComEd)

Dresden Nuclear Power Station, Units 2 and 3 LaSalle County Station, Units 1 and 2 Quad Cities Nuclear Power Stati6n, Units 1 and 2

SUMMARY

OF MEETING CONCERNING THE USE OF SIEMENS ATRIUM 98 FUEL On April 3, 1997, the staff met with Commonwealth Edison Company {ComEd) and Siemens Power torporatiori {SPC) to discuss the Advanced Nuclear Fuel frir Boiling Water Reactors {ANF8) correlation for ATRIUM 98 fuel application and mixed core analysis. LaSalle, Units 1 and 2; Dresden, Units 2 and 3; and Quad Cities, Units 1 and 2, will be using ATRIUM 98 fuel; however, Quad Cities, Unit 2, will be the lead ComEd plant.

The discussion focused.on actions ComEd will take to address this concern for Quad Cities, Unit 2.

A list of attendees is provided as Enclosure 1.

ComEd and SPC discussed with the staff the ANF8 critical power correlation data base for 9x9 fuels with an internal water channel.

The ANF8 critical power correlation data base:does not cover a wide enough range of conditions to acc~rately establish the Additive tonstant uncertainty u~ed. in the Minimum Critical Power Ratio {MCPR) Safety Limit analysis.

The proposed resolution for Quad Cities, Unit 2, to load fuel and to proceed to power operation was discussed.

The licensee will provide the staff a technical specification {TS) request which will address the MCPR safety limit once additional information is provided by SPC.

A copy of the licensee's presentation is included as *.

Quad Cities will be able to load the ATRIUM 98 fuel assemblies after staff approval of the TS request dated June 10, 1996, concerning the transition from General Electric to SPC fuel and the approval of the.coresident Topical Report, EMF-96-0Sl{P).

Startup and power operation of Unit 2, with ATRIUM 98 fuel would not begin until approval from the staff of any MCPR safety limit changes developed from the further analysis to be provided to the staff and ComEd by SPC regarding the Additive Constant uncertainty used in the MCPR safety analysis, as mentioned above.

. Subsequent to the m~e~ing of April 3, 1997, the licensee on April 21, 1997, submitted an exigent TS change request to increase the MCPR safety limit *for Unit 2.

Also on April 29, 1997, the licensee submitted an emergency TS req~est to allow fuel load on Unit 2 not to exceed Operational Mode 3.

. Amendment No. 173 was issued by the staff a 11 owing the use of Siemens ATRIUM-98 fuel in Operational Modes 3, 4, and 5 which includes fuel loading.

9705150362 970509 'J

  • (~OR-' AOOCK 0500~~7 \\.--

j)fol

Commonwealth Edison Compa~y 2

Approval of Topical Report EMF-96:.*-'05l(P), issuanc*e of:. the June 6, 1996, TS request, along with the exigent.TS request*,, are:all requireq *fqr plant startup.

  • '."".'I.I

. -\\

  • ,Original signed by:'
Ro.ber'i,M.. Puisifer, *Project Manager Projecf.Direitor~te i11-2*

Pivi~ion of,R~~ctor ~r6jects - Ill/IV

Office bf Nucl~ar,Beactor Regulation

~*-

~

"i.*

Docket Nos. 50-237, 50-249,~~o~~t~;-~

. 50-374 50-254 50-265

Enclosures:

cc w/encls:

E-Mail Cw/encl 1):

SCol l ins, SJ°C1 JRoe, JWR CMoore, ACM THuang, TLH1 RFrahm, RKF1

~ */"

1.

List of Attendees

\\

2.

Licensee's see next page FMiraglia, FJM EAdensam, EGA1 DRoss, SAM LPhil lips, LEP1 EWang, EYW.

Present at i cfn PDII I-2 r/f WKropp, WJK J. Stang

~-

RZimmerman, RPZ RCapra,* RAC1 TAttard, ACA JLyons, JEL BMcCabe, BCM *

, ~

I

._1 DOCUMENT NAME:* G:\\CMNTJR\\QUAD\\QC43.SUM To receive a copy of this document. indicate i the b

"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE D:PDlll-2 NAME RCAPRA....._

DATE 05/9-/97

Commonwealth Edison Company _Approval of Topical Report EMF-96-0Sl{P}, issuance of the June 6, 1996, TS request, along with the exigent TS request, are all required for plant

  • startup.

Original signed by:

Robert M. Pulsifer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor.Regulation Docket Nos. 50-237, 50-249, *50-373, 50-374, 50-254, 50-265

~

Enc 1 osures:

1.
2.

List of Attendees Licensee's Presentation cc w/encls:

see next page DISTRIBUTION_(wle_r:icLLand_ 2).:

Q~~clcet File, l5C3 '.

P~fil_~-

ACRS RPuls1fer, RMP3

_OGC, 015818 DSlcay.

E-Mail Cw/encl 1):

SCol l ins, SJC1 JRoe, JIJR CMoore, ACM

. THuang, TLH1 RFrahm, RKF1 FMiragl ia, FJM EAdensam,

  • EGA 1 DRoss, SAM LPhi LL ips, LEP1 EIJang, EYIJ PDIII-2 r°tf IJICropp, IJJK J. Stang RZinmerman, RPZ RCapra, RAC1 TAttard, ACA Jlyons, JEL BMcCabe, BCM DOCUMENT NAME: G:\\CMNTJR\\QUAD\\QC43.SUM To receive a copy*of this document, indicate i the b "C",;, Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE G

NAME DATE

Commonwealth Edison Company Approval of Topical Report EMF-96-05l(P), issuance of the June 6, 1996, TS request, along with the exigent TS request, are all required for plant startup.

  • Docket Nos. 50-237, 50-249, 50-373, 50-374, 50-254, 50-265

Enclosures:

1.

List of Attendees

~~

Robert M. Pulsif r, Project Manager Project Directorate IIl-2 Division of Reactor Projects - III/IV Offite of Nuclear Reactor Regulation

2.

Licensee's Presentation cc w/encls: *see next page

cc:

Ms. I. Johnson

. Acting Manager, Nuclear Regulatory Services Commonwealth Edison*company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, Illinois. 60515 Michael I. Miller, Esquire Sidley.and Austin One First National Plaza Chicago, Illinois

  • 60603
  • Site Vite President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Station Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station
  • 6500 North Dresden Road Morris, Illinois 60450-9766 Richard J. Singer Manager - Nuclear MidAmerican Energy Company 907 Walnut Street P.O. Box 657 De~ Moines, Iowa 50303 Brent E. Gale, Esq..

Vice President - Law and Regulatory Affairs Mid American Energy Company One RiverCenter Place 106 East Second Street P.O. Box 4350 Da~enport; Iowa 52808 Dresden Nuclear Power Station Unit Nos. 2 and 3 Quad Cities Nuclear Power Station Unit Nos. 1 and 2 Chairman Rock Island County Board

  • of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.

Rock Island, Illinois 61201 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Illinois Department 9f Nuclear Safety*

Office bf Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administ~ation Buildtng 1320 Union Street Morris, Illinois 60450 Mr. L. William Pearce Station Manager Quad Cities Nuclear Power Station' 22710 206th Avenue North Cordova, Illinois '61242 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office 22712 206th Avenue North Cordova, 11 li noi s

  • 61242 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois* 60515

V-

~'

cc: -

Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Assisttnt Attorney General -

100 West Randolph Street Suite 12 Chicago, Illinois 60601 U. s~ Nuclear Regulatory Comrni ssi on _

Resident Inspectors Office LaSalle Station 2605 N. 21st Road Marseilles, Illinois 61341-9756 Chairman LaSalle County Board of Supervisors LaSalle County Courthouse -

Ottawa, Illinois 61350

- Attorney General 500 South Second Street Springfield, Illinois 62701 Chairman Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator U. S. N,RC, Re.g ion I II 801 Warrenville Road Lisle, Illinois 60532-4351 LaSalle Station Manager LaSalle County Station Rural Route I P.O. Box 220 Marseilles, Illinois 61341 LaSalle County Station Unit Nos. I and 2 Robert Cushing Chief, Public Utilities Division Illinois Attorney General's Office 100 West Randolph Street Chicago, Illinois 60601 Michael I. Miller, Esquire Sidley and Austin One First National Plaza

Chicago, Illinoi~ 60603 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place~ Suite 400 Downers Grove, Illinois 60515

I..

  • ~

LIST OF ATTENDEES MEETING WITH COMMONWEALTH EDISON COMPANY (COMED)

AND SIEMENS POWER CORPORATION (SPC)

April 3, 1997 NAME COMPANY TELEPHONE NO.

1.

Tony Attard NRC (301) 415-287.6

2.

Tai Huang NRC (301) 415-2867

3.

Robert Pulsifer NRC (301) 415-3016

4.

Larry Phillips NRC/SRXB (301) 415-3232

5.

Al Chernick Com Ed (309) 654-2241.X3100

6.

Ed McVey Com Ed (630) 663-3079

7.

M. McDonough

  • ComEd (309) 654~2241 X3370
8.

Mark Wagner Com Ed (630) 663-6645

9.

Rich~rd Collingham SPC (509) 375-8392

10.

Michael Garrett SPC (509) 375-8294

11. *Jim Lyons
  • NRC/SRXB

'(301) 415-2895.

12.

Bob Copeland SPC (509) 375-8290

13.

Don Curet SPC

{509) 375-8563.

14.

Ron Frahm NRC

{301) 415-2866

15.

Egan Wang NRC

{301) 415-1076 ENCLOSURE 1

ComEd/NRC Meeting For Quad Cities April 3, 1997 ENCLOSURE 2

\\,

Purpose of Meeting

  • Identify. actions and schedule needed to support plant startup

.

  • Present plan for resolution of ANFB
  • uncertainty concern for A TRIUM'-9B

Agenda**

  • *Purpose--M Wagner (ComEd)
  • ComEd Plant Status--E McVey (ComEd)
    • Current TS Requirements--£ McVey (ComEd) *
  • ANFB Uncertainty Non conformance~-

e

  • R Collingham (SPC).

Agenda (continued)

  • . Interim Approach--R Collingham (SPC)
  • Co-Resident Fuel Application Report--

M Garrett* (SPC) *

  • Actions Required 'for Startup/Schedule--

E Mc Vey (ComEd)

ComEd BWR. PLANT STATUS

  • LASALLE STATION UNIT 1
  • IN AN EXTENDED MAINTENANCE OUTAGE
  • *HAS AN ALL GE FUEL CORE
  • WILL BE TRANSITIONING TO SIEMENS POWER CORPORATION (SPC).FUEL BEGINNING WITH THE NEXT REFUEL OUT AGE, SCHEDULED TO BEGIN FALL OF 1998
  • NRC HAS APPROVED A LICENSE AMEND:tv.IBNT CHANGE IN SUPPORT OF UNIT 1 SPC TRANSITION, TO BE IMPLE:tv.IBNTED PRIOR TO STARTUP FOLLOWING ITS NEXT REFUEL OUTAGE

- *UNIT2

  • IN AN EXTENDED REFUEL OUTAGE *
  • WILL BE LOADING 292 ATRIUM-9B FUEL ASSEMBLIES DURING THIS REFUEL OUT AGE FOR CYCLE 8 OPERATION; THE CORESIDENT FUEL IS GE9.
  • FUEL
  • NO DATE IS CURRENTLY ESTABLISHED FOR CORE LOAD AND STARTUP
  • NRC HAS APPROVED A LICENSE AMEND:tv.IBNT CHANGE IN SUPPORT OF UNIT 2 SPC TRANSITION, TO BE IMPLE:tv.IBNTED PRIOR TO STARTUP FOLLOWING THE CURRENT REFUEL OUTAGE
  • NRC HAS APPROVED A SIE:tv.IBNS TOPICAL REPORT SUBWTTED ON THE LASALLE UNIT 2 DOCKET FOR THE APPLICATION OF THE ANFB CRITICAL POWER CORRELATION TO CORESIDENT GE FUEL FOR UNIT 2 CYCLES

~.*

Co*mEd BWR PLANT STATUS

  • DRESDEN STATION UNIT2
  • CURRENTLY OPERATING IN CYCLE 15 WITH SPC 9X9-2 FUEL AND 8 ATRIUM-9B LEAD USE ASSEMBLIES
  • . WILL BE TRANSITIONING TO ATRIUM-9B FUEL BEGINNING WITH THE NEXT REFUEL OUTAGE, SCHEDULED TO BEGIN 3-7-98
  • CO:MED HAS SUBMITTED A LICENSE AMEND:MENT REQUEST TO THE NRC IN SUPPORT OF THE USE OF ATRIUM-9B FUEL, TO BE IMPLE:MENTED PRIOR TO STARTUP FOLLOWING THE 1998 REFUEL OUTAGE UNIT3 BEGAN REFUEL OUTAGE ON 3-29-97 *

.

  • WILL BE LOADING 232 ATRIUM-9B.FUEL ASSEMBLIES DURING THIS REFUEL OUTAGE FOR CYCLE 15 OPERATION; THE CORESIDENT FUEL IS SPC 9X9-2 FUEL
  • CORE LOAD IS SCHEDULED TO BEGIN 12-97 WITH STARTUP SCHEDULED TO BEGIN 6-5-97
  • CO:MED HAS SUBMITTED A LICENSE AMEND:MENT REQUEST TO THE NRG IN SJ]PPORT OF THE USE OF ATRIUM-9B FUEL, TO BE IMPLE:MENTED PRIOR TO STARTUP FOLLOWING THE CURRENT REFUEL OUTAGE
  • NRC APPROVAL OF TIDS LICENSE AMEND:MENT IS REQUIRED IN SUFFICIENT TIME TO SUPPORT DRESDEN UNIT 3 STARTUP

~-

c:omEd BWR PLANT-STATUS

  • QUAD CITIES STATION UNIT I
  • CURRENTLY OPERATING IN CYCLE 15 WITH AN ALL GE CORE (GE8, GE9, AND GE 10 FUEL)
  • WILL BE TRANSITIONING TO SIEMENS POWER CORPORATION (SPC) FUEL B.EGINNING WITH THE.

NEXT REFUEL OUTAGE, SCHEDULED TO BEGIN.

SPRING OF 1998

  • CO:MED HAS SUBMITTED.A LICENSE MIBNiJMENT.

REQUEST TO THE NRC IN SUPPORT OF THE USE OF ATRIUM-9.B FUEL, TO BE IMPLEMENTED PRIOR TO STARTUP FOLLOWING THE 1998 REFUEL OUTAGE UNIT2

  • . BEGAN REFUEL Out AGE ON 3-1-97
  • WILL BE LOADING 216 ATR1UM-9B FUEL*
  • ASSEMBLIES DURING THIS REFUEL OUTAGE FOR CYCLE 15 OP~RATION; THE CORESIDENTFUEL Is*

GE9 AND GElO FUEL

  • .CORE LOAD IS SCHEDULED TO BEGIN 4-23~97 **

WITH STARTUP SCHEDULED TO BEGIN 5-13.:97

  • COI\\tffiD HAS SUBWTTED A LICENSE Al\\t1ENDI\\t1ENT REQUEST TO THE NRC IN SUPPORT OF THE USE OF ATRIUM-9B FUEL, TO BE IMPLEMENTED PRIOR TO STARTVJ> FOLLOWING THE. CURRENT REFUEL OUTAGE*
  • COI\\tffiD HAS SUB:rv.t:ITTED A SIEMENS TOPICAL

. REPORT ON THE QUAD C~TIES UNIT 2 DOCKET FOR THE APPLICATION OF THE ANFB CRITICAL POWER.

CORRELATION TO CORESIDENf GE FUEL FOR Q2Cl5

  • NRC APPROVAL OF THE LICENSE Al\\tffiNDI\\tffiNT AND THE TOPICAL REPORT IS REQUIRED IN SUFFICIENT Tll\\t1E TO SUPPORT UNIT 2 STARTUP

SIEMENS

. ANFB/ATRIUM-98 Additive* Constant Uncertainty Nonconf ormance

. Siemens Power.Corp.

Siemens Power Corporation 3120/97 Fllonomo.PPT l8:97:001

SIEMENS..

Outline -* Nonconformance/Resolution

  • Nonconf ormance
  • Plants Affected
  • Resolution
  • Generic

.

  • Interim
  • Summary -.

Siemens Power Corporation

  • J/20/97 Fllonomo.PPT LB:97:001

SIEMENS Purpose of* Resolution Present actions being takeri to* address the nonconformance identified du.r:ing the recent N RC_. vendor inspection relative

  • to the* uncertainty of ANFB Additive Constants used for 9x9 fuels with an internal water channel in the MCPR Safety Limit Analyses*

These a.ctions will protect the a_cceptance criteria of assuring 99.9% of the rods will not. experience dryout during *normal operation *and AOO's These actions are scheduled to all.ow all affected plants to be started as scheduled;. first scheduled* startup is in less than 6 weeks 3/20197 Siemens Power Corporation*

Fllonome.Pl'T LB:97:001

SIEMENS

  • ATRIUM-.98.

ATRIUM-98 is the latest SPC 9x9 fuel with an internal water channel Siemens Power Corporation 3/20197 FU..-.PPT LB:97:001

SIEMENS

-Nonconformance The ANFB critical power correlation data base for 9x9 fuels with an internal water channel does not cover a wide enough range -of conditions to accurately *establish t_h*e Additive Constant

-uncertainty used in the MCPR _Safety Limit

  • analysis
  • There is ho Nonconformance relative to the ANFB correlation or the v*alue of the Ad.ditive Constants
  • Resolution is to increase the Additive Constant -

uncertainty and *address impact on MCPR Limits -

Siemens Power Corporation J/20197 Fllanomo.PPT l8:97:001

SIEMENS

  • Affected. Plants A SPC Nonconformance Report has been issued which requires a* Part 21 Evaluation; Plants affected are:
  • WNP-2.
  • Shutdown for refueling *.
  • Affected reload fuel will be in third cycle or greater cycle
  • Supply System has been notified by phone
  • ABB current fuel supplier
  • Further actions will.be considered as part of Part 21

, Evaluation.

  • Scheduled startup is in July 1997 Siemens Power Corporation 3120197 FU......,..Pl'T l8:97:001

SIEMENS Affected Plants (cont.)

Kuosheng

  • Reloads operating with ATRIUM-98
  • Notification as* part of *spc Nonconformance process Leads
  • In *several plants
  • Safety limit not impacted by leads
  • Evaluated as part of SPC.Nonconformance process Siemens Power Corporation Jno191 Fllename.PPT LB:97:001

SIEMENS*

  • Affected Plants
  • All plants will i*ntrodu_ce ATRIUM-98 fuel as part of the next refueling.
  • Scheduled startups *
  • Qu~d-Cities 2 Cycle 15 - May 13, 1997
  • Dresden 3 Cycle 15. -
  • LaSalle 2 Cycle 8 -

Siemens. Power Corporation June 1997 July 1997 3/20/97 Fllonamo.PPT LB:97:001

SIEMENS**

  • Resolution ~ Generic Develop a statistically based methodology for using e

existing critical power data to address the range of conditions not explicitly covered. in the tests of 9x9 fuels with internal water channels;.result wiH be an increase in Additive Constant uncertainty

  • Methodology to be completed by April 10
  • Methodology to* be documented and submitted to NRC for review by A.pril 19 Because of the minimal review time, an Interim Approach is tq be implen*1ented 3/20/97 Siemens Power Corporation Fllenomo.PPT LB:97:001

SIEMENS

  • Action Plan - Interim Approa*ch Impose. a conservative adder to the MCPR Operating Limit until the new statistical uncertainty methodology is approved and implemented
  • Establish increase 'in Additive Constant uncertainty by new statistical methodology
  • Double this increase for extra conservatism
  • Determine increase in Safety Limit using this conservative value *
  • Apply the Safety.Limi_t increase to the MCPR Operating Limit th_rough COLR *procedures
  • Apply this Interim Approach to Quad Cities 2 and other ComEd BWR's as necessary Siemens Power Corpo(ation FU...-.PPT LB:97:001

SIEMENS

  • Resolution - Generic When the.new: statistical methodology is approved:
  • Use ap*proved methodology to determine MCPR Safety Limit
  • Revise Technical Specifications to incorporate revised MCPR Safety Limit (if Safety Limit is calc. to change)
  • *Remove Administrative adder on MCPR Operating Limit by COLR procedures
  • Do* for all ComEd plants consistently Siemens Power Corporation 3120/97 Fl-.PPT LB:97:001

('

SIEMENS

  • Summary *of Resolution Nonconformance immediately *addressed by e

. conservative, statistically. based MCPR Operating Limit adder to protect the 99.9% a:cceptance criteria Safety Limit will directly incorporate the new statistical uncertaint*y methodology when approved Other Plant Specif.ic submittals should proceed independently of this.unc.ertainty concern Siemens Power Corporation.

3120/97 FUon.M.WT LB:97:001

SIEMENS Impact of ANFB Nonconformance on ANFB Coresident Fuel Report

  • Nonconformance impacts the additive constant uncertainty for 9x9 fuel designs with intern.al water cha_nnels. (such as the *.

e ATRIUM-98).

  • The statistical methodology will result in *an increase in the additive constant uncerta_inty for ATRIUM-9 fuel.
  • The statistical methodol*ogy *will not result in.a change to the ANFB correlatio*n.
  • Approval of the topical repo_rts for ANFB application for GE fuel is not dependent on corrective actions underway to resolve the nonconformance.

Siemens Power Corporation

  • APf 97 MEG:97:000

SIEMENS ANFB Coresident *Fu~I Report -

Application of ANFB to GE Fuel

  • SPC has submitted tqpical reports describing a.pplication of ANFB to the coresident GE fuel -in transition. cycles at Quad Cities and e

LaSalle.*

  • The topical reports describe a method for applying ANFB to GE fuel coresident with any spc* fuel type.
  • The reports describe how additive.constants and uncertainty are determined for GE fuel. *
    • No change to the ANFB cbrre.lation is required.
  • Additive constants for GE fuel are established usin_g the e

methodology approved for SPC fuel with the exception that calculated critical power data provided by the utility is used rather than measured data.

Siemens Power Corporation Apr 97 MEG:97:000

SIEMENS ANFB Coresident. Fuel Report {c9ntinued)'

  • Additive. constant uncertainty for GE. fuel is based -on two components:

Standard deviation between ANFB and the GE GEXL correlation Standard deviation between GEXL and measured critical power data.

  • The ANFB-GEXL correlation,uncertainty is obtained from comparisons of ANFB predicted CPR to GEXL predicted CPR for the same assembly conditions.
  • The GEXL. correlation uncertainty relative to. test data is pr~vided by the utility.
  • The additive constant uncertainty for GE fuel is determined by statistically combining th~ ANFB~GEXL and GEXL-Data uncertainties.

Siemens Power Corporation.

Apr 97 MEG:97:000 ii.*

I.

~

-~

SIEMENS ANFB Coresid.ent Fuel Report (continued}

  • The additive constants and the additive constant uncertainty for.

GE fuel are independent of the SPC fuel present in transition :

e cores.

    • The additive constants nor the additive constant uncertainty for the coresident SPC fuel are used in the topical reports describing application of ANFB to GE fu~I.

Apr 97 Siemens Power Corporation

~

MEG:97:000

l.O I

SIEMENS Mixed Core MCPR-Safety Limit Analyses

  • The topical reports for ANFB 'application to GE fuel do not address mixed core safety limit.issues.

e

  • SPC addresses mixed core configurations* in cycle specific MCPR safety limit analyses
  • actual core loading used
  • additive constant uncertainties appropriate for each fuel type used
  • Additive constant uncertainty for GE fuel is obtained using the methods described in ANFB coresident fuel topical reports.
  • Additive constant uncertainty for ATRIUM-98 fuel is obtained
    • . using the statistical methods currently being developed and
  • documented for NRC review.

Siemens Power Corporation.

Apr 97 MEG:97:000

SIEMENS Impact. of Increased Additive Constant

. Uf)certainty on SLMCPR

  • Current MCPR safety limit analyses are based on an ATRIUM-98 I
  • i*

}

additive constant uncertainty of 0.01.

e

  • Increasing the ATRIUM~98 uncertainty to the maximum value for any SPC fuel design (0.02) has the following impact:
  • Quad Cities 2 Cycle 15

+ 0.01

  • Dresd~n 3 Cycle 1 5 No change
  • LaSalle 2 Cycle 8

. No change

  • Percentage* increase in uncertainty at which current Tech Spec MCPR safety limit is* ex_ceeded:
  • e
  • Quad Cities 2 Cycl*e 15
  • Dresden -3 Cycle 15
  • LaSalle 2 Cycl~ 8 Siemens Power Corporation
  • 60°/o 280%

300%

Apr 97 MEG:97:000

Actions Needed for Quad Cities

. Startup

  • Quad Cities critical path licensing schedule
  • -*Fuel" load--April 23 *

- Startup--May 13.

  • TS amendment and Co-Resident Fuel topical report approval necessary

(~

J

',l'.;*

.0:

  • schedule*
  • April 19*
  • - SPC. submits generic.uncertainty topical report *

- SPC tran*smits interim procedure for uncertainty and MCPR operating limit determination (to be used fir~t at Quad Cities)

. *.Apri122~-NRC approval of TS package and Co~Resident Fuel Application Report

  • April 23--Quad Citie*s fuel load starts.

4

.i.1, _,

. -~

~

  • .J
  • Schedule (continued) *
  • May 13--ComEd submits COLR with revised operating limit

. *. May 13--Quad Cities Plant Startup

  • May 12--DresdenFuel Load
  • June 5--Dresden Startup_

4

'f t* *'

..:~

1.
Retrieved from "https://kanterella.com/w/index.php?title=ML17187A966&oldid=5131698"