ML120750572

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4/4/2012 - Forthcoming Meeting with Exelon Generation Company, LLC Regarding the Proposed Extended Power Uprate License Amendment Request for LaSalle County Station, Units 1 and 2
ML120750572
Person / Time
Site: LaSalle  
Issue date: 03/20/2012
From: Nicholas Difrancesco
Plant Licensing Branch III
To: Jacob Zimmerman
Plant Licensing Branch III
DiFrancesco N, NRR/DORL/LPL3-2, 415-1115
References
TAC ME7495, TAC ME7496
Download: ML120750572 (22)
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Text

{{#Wiki_filter:MEMORANDUM TO: FROM:

SUBJECT:

DATE & TIME: LOCATION: PURPOSE: CATEGORY 1:* MEETING CONTACTS: UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 March 20, 2012 Jacob I. Zimmerman, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Nicholas J. DiFrancesco, Project Manage~..vf. / / Plant Licensing Branch 111-2

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Division of Operating Reactor Licensing -:r-"'""--... Office of Nuclear Reactor Regulation FORTHCOMING MEETING WITH EXELON GENERATION COMPANY, LLC REGARDING THE PROPOSED EXTENDED POWER UPRA TE LICENSE AMENDMENT REQUEST FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. ME7495 AND ME7496) Wednesday, April 4, 2012 Time 1 :00 p.m. - 4:00 p.m. - Eastern Daylight Time (EDT) U.S. Nuclear Regulatory Commission Two White Flint North ACRS Hearing Room (T-2B3) 11545 Rockville Pike Rockville, Maryland Presubmittal discussions of the LaSalle County Station, Units 1 and 2, Extended PowerUprate license amendment request. This is a Category 1 Meeting. The public is invited to observe this meeting and will have one or more opportunities to communicate with the NRC after the business portion, but before the meeting is adjourned. N. DiFrancesco, NRR J. Wiebe, NRR 301-415-1115 301-415-6606 Nicholas. DiFrancesco@nrc.gov Joel. Wiebe@nrc.gov

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

J. Zimmerman - 2 PARTICIPANTS: Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR). NRC/NRR Exelon Generation Company, LLC J. Zimmerman G. Casto K. Borton H.vinyard R. Denning A. Sallman T. Byam T. Simpkin N. DiFrancesco P. Hernandez V.Shah F. Pournia et al. S. Du Pont J. Rommel K. Ainger eta!. Interested members of the public can participate in this meeting via a toll-free audio teleconference. Please call one of the meeting contacts listed below before Monday. April 2. 2012. 2:00pm EDT to get the telephone number and the pass code. The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a 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 contact. 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-involvellistserver/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 Nos. 50-373 and 50-374

Enclosures:

1. Agenda
2. Pre-Submittal Guidance Checklist cc w/encls: Distribution via Listserv

AGENDA FORTHCOMING MEETING WITH EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 WEDNESDAY, APRIL 4, 2012 1 :00 p.m. - 4:00 p.m. Introductions of NRC and Exelon staff Meeting purpose and Background Technical Topics o Containment Peak Accident Pressure o Alternative Source Term o Technical Specification Setpoints Steam Dryer Replacement Plan and Schedule Questions Comments from the public

Presubmittal Guidance Checklist* laSalle EPU Pr.Submlttal Meeting Scheduled April 4, 2012 Page 1 of 18 Proposed Ucenstng Action: Extended Power Uprate (EPU) LicenaealPlant: laSalle Units 1 and 2 EPU License Amendment Request - General DetaIled Deecrtptlon of the PropoMCI licensing Actton: Pursuant to 10 CFR 50.90, this proposed amendment would increase each unifs licensed core power level from 3546 megawatts thermal (MWt) to 3988 MWt and revise, as required, technical specifications to support operations at the Increased core thermal power level in accordance with the Constant Pressure Power Uprate Licensing Topical Report (CLTR) NEDC-33004P-A. Planned SubmIttal Dale: Third Quarter 2012 Requetted Approval Date Be eaala: Third Quarter 2014 to support Unit 2 Implementation during the First Quarter 2015 refueling outage and Unit 1 implementation during the First Quarter 2016 refueling outage. Other: This amendment fulfills the information requirements of RS-001, "Review Standard for Extended Power Uprates" Revision 0, dated December 2003. Exelon has evaluated all non-EPU licensing actions for impact on the EPU amendment request and have determined that there are no impacts. TeohnJaal: The technical analyses proVkfing the basis for the proposed amendment as prescribed by RS-(X)l are being pertormed. These analyses are being completed in accordance with the codes and methodologies described in the approved ClTA. The results of these technical analyses will be contained in of the proposed amendment. Safely: A comprehensive review of accident analyses. component and system analyses. and radiological dose consequences as prescribed by RS-001 is in progress. These analyses are being performed in accordance with the approved ClTR. The generic assessment provided in the ClTR will be confirmed in the laSalle amendment request. The results of these evaluations will be contained In Attachment 5 of the proposed amendment. Security: This proposed amendment does not change or impact the current laSalle Security Plan. No Significant Hazards Consideration: Exelon will perform a No Significant Hazards Consideration analysis in accordance with 10 CFR 50.91(a)(l) upon completion of all technical evaluations and safety analyses recommended in the guidance of RS-001. Based on initial reviews, It is expected that the proposed change will nol involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or Involve a significant reduction In a margin of safety. The results of the No Significant Hazards Consideration evaluation will be provided in Attachment 1 to the proposed amendment request. EnvIronmental: Exelon will complete an Environmental Assessment In support of the proposed amendment request in accordance with the approved CLTR. The generic input to this assessment provided in the ClTR will be verified to be applicable to LaSalle as part of the assessment pertormed. The laSalle specific assessment will reference all the applicable generic input. The supplemental environmental report will be contained in Attachment 8 of the proposed amendment.

PreBubmlttal Guidance Checklist - laSalle EPU Pre-Submlttal Meeting Scheduled April 4, 2012 Page 2 of 18 Proposed Llc<<aalng ActIon: Extended Power Uprste (EPU) LlcenseelPlanl: LaSalle Units 1 and 2 Extended Power Uprate amendment Increasing reactor core thermaJ power approXimately 15%. Nine Mile Point is the (ML113300040) Nine Mile Point Unit 2. 12122111 most recentJy approved BWR EPU. Nine Mile Point Unit 2 and laSalle Units 1 and 2 are BWR 5 with Mark II containment. Point Beach Units 1&2. 05l03I11 Extended Power Uprate amendment increasing reactor core thermal power approximately 17%. Point Beach is a (ML1111705 PWR comoared to laSalle units 1 &2 - BWR 5 with Mark II containment. Hope Creek. 05/14/08 (ML081230540) Extended Power Uprate amendment increasing reactor core thermal power approXimately 15%. Hope Creek is a BWR 4 with a Mark I containment comoared to laSalle units 1&2 - BWR 5 with Mark II containment. Susquehanna Units 1&2, dated 01130108 Extended Power Uprate amendment increasing reactor core thermal power approximately 13%. Susquehanna units (ML081050530) are Mark Ii containments of similar desian as laSalle Units 1&2.

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I Presubmlttal Guidance Checklist-laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 301 18 Topic Specific

1. Technical Specification Setpolnt Calculations Technlcall..ue: The purpo.. of thle topic 18 to identify changes to the Technlcal Specifications Allowable Valuea of Reactor Protection System and Primary Containment isolation Instrumentation with EPU and demonatrate that the chang_ are conalatent with the applicable regulatory criteria and follow regulatory guldell....

With EPU, the Analytical Limit (AL) for APRM Flow Blaeed Simulated Thermal Power Upacaje Scram and Main Steam Une High Flow Group lleolation will change. A r18W Allowable Value (Ay), Limiting Trip Satpolnt (LTSP), Nominal Trip Setpolnta (NTSP), Aa-Left Tolerance (AI.T) and Aa-Found Tolerance (AFT) are determined for each AL uelng the ExeIon Setpolnt Methodology. The revleed Htpolnt requirements for Main Steam Line High Flow are conslatent with TSTF - 493, Revision 4 Option A. Grand Gulf RAI Response (ML112101485) dated 712812011 Monticello RAJ Response (ML092320064) dated 8/19/2009 Nine Mile Point Request for Additional was requested to provide documentation of the methodology used (or NSP) and the limiting acceptable vaJues for the As-Found and As-Left setpoints as measured (ML100190072) dated 1212312009 Information (RAI) Response surveillance testing. LaSaJle will address the requested information in the application. laSalle Calculations will be verified to contain humidity effects. Please affirm that ail setpoints or allowabte value letter of February 23, 2009, will have the footnotes SODlied. During audit of the setpoint calculations, the NRC staff noted that calculation summary documents showed that the temperature effect and humidity effect errors for the NUMAC equipment were -included within the NUMAC accuracy performance specification." Upon review of a copy of a design calculation for the NUMAC performance, and its reference specifications. it was noted that a calculation had been performed to demonstrate the negligible magnitude of the temperature effect specification, but no calculation had been performed for the humidity effect specification.

Presubmittal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 4 of 18 Proposed Ucenelng ActIon: Extended Power Uprate (EPU) UceneeeIPlant: laSalle Units 1 and 2 181 Reactor Systema c...ran.ea and Interface) o kcldent Dose D I=lat!trlt!AI o Probabilistic Aisk Assessment 1:81 Inlllrument and Controls o Fire Proleclion o Mechanical and Civil o Piping and NDE o Balance of Plant o Steam Generator Tube Integrity D ContaInment and Ventilation o Component and Performance Testing o NMSS o Environmental o NSIA o OGC Branch Technical Positions None None o Securtty o Emergency Planning o Technical Specifications o Special Projects o Health Physics o COAL - Projects DOE o laSalle was not licensed as a SAP facility. SER (NUREG 0519) related to the operation of laSalle units 1 and 2 (March 1981) contaJned the scope of NRC staffs technical and radiological review. laSalle was not licensed as a SRP facility. SEA (NUREG 0519) related to the operation of laSalle units 1 and 2 (March 1981) contained the scope of NRC staff's technical and radiofoglcaJ review. NUREG 0519 used SAP NUAEG 751087 as guidance. During laSalle's conversion to Improved Technical Specification and MUA acceptance reviews, the NRC staff used SRP NUAEG-OSOO as guidance. laSalle did not commit to the SAP. NUAEG-oaoo referenced BTP 7-12, Guidance on establishing and Maintaining Instrument Setpoints and was used as review guidance only. Although laSalle is not committed to BTP 7-12, the application will be consistent with BTP 7-12 guidance.

Presubmlttal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 50f 18 Ucensing Action: Extended Power Uprate (EPU) UC8nll88lPlant: laSalle Units 1 and 2 tB:",".'71,Gu,...... _.......'I*.~. :;~':-"":.., [;.,_..... 11....'....",.,,".,..1\\* EPU RS-001 section 2.4 u'~§n~~i,.**~!". " .y .~.=.~.... EPU evaluations followed the RS-001 guidance ,l7':~,~**l;~l~;;q.. '. .' p*.",~",.

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'V'./:; 1"( ": {'< ~,~' {-/' The Power Uprate Safety Analysis Report (PUSAR) will be prepared In accordance with the RS-001 guidance Revlew Standards Regulatory Guides 1.12. Nuclear Power Plant Instrumentation for Earthquakes 1.30. Quality Assurance Requirements for the Installation, Inspection. and Testing of Instrumentation and Electric Equipment (Safety Guide 30) No change laSalle was not licensed as a SRP facility. SRP NUREG 0800 (BTP 7-12), used by the NRC staff for guidance during the ITS conversion and MUR during the acceptance reviews referenced Regulatory Guide 1.105, Revision 3. Setpoints for Safety-Related Instrumentation. The NRC staff found the ITS and MUR applications consistent with the BTP 7-12 guidance. Although laSalle is not committed to RG 1.105, the EPU application will be consistent with RG 1.105 guidance. NUREGs None None Interim Staff Guidance None None Other None None IIIIC~ -.' ~.:"I:;~.'."~* I 1/8;;;;; -==...........tll........... ~"...nl.~',... OI***a.-....: ,.*'~'"'.**IT <JO,. r,. NRC Bulletins None None NRC Generic Letters None None

Presubmlttal Guidance Checklist - laSalle EPU Pre-Submlttal Meeting Scheduled AprIl 4, 2012 Page 6 of 18 Propoeed LI AcUon: Extended Power Uprate (EPU) LlcenaeelPlant: laSalle Units 1 and 2 NRC...... ~:~*.;:;t;*.... ,,,.;. f> PJ.,,,*., .~..

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",.'_'_.;\\l~; ~t;{-=..r.'.'.~f 'i~:~t'~~~~t".t~.'I""i.~......tI...,..... Regulatory Information None None LaSalle was not licensed as a SRP facility. SRP NUREG-Summaries 0800. used by the NRC staff for guidance during the ITS conversion. referenced BTP 7-12. Subsequently to ITS conversion, BTP 7-12 was revised to reference RIS 2006 017. The NRC staff used BTP 7-12 and RIS 2006 017guidance during the MUR acceptance review. The NRC found the MUR application to be consistent to the BTP 7-12 guidance. Although laSalle is not committed to RIS 2006-017, the EPU application will be consistent with RaS 2006-017guidance. NRC Information Notices None None Other TSTF-493 No change I ~.~ zzt .::='~~". ""+~" ............TJ***

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c.***** _.{' . I** .........",......IT..... Updated Final Safety Analysis Report Chapter 7 Change to reflect EPU conditions and TSTF-493 recommendations UFSAR revision to reflect analytical limits changes. No changes in methodologies as described in the UFSAR Technical Specifications Bases TS Table 3.3.1.1.1-1 TS Table 3.3.6.1-1 Change to reflect EPU conditions and addition of TSTF-493 notes Incorporation of TSTF-493 Technical Requirements Manual TAM Appendix D. Instrumentation Trip Setpoints Appendix 0 wiD be revised to reference the New MSL High Flow Calculation and the revision to existing APRM calculations New MSL High Flow Calculation and revision to exiting APRM calculations addresses change in instrument range and setpolnt requirements for EPU. Calculations Incorporate TSTF-493 recommendations.

Presubmittal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 7 of 18 I............. Aclon: Extended Power.....n..... 1............'11: LaSalle Units 1 and 2 Fire Hazards Analysis Report NRC Safety Evaluation Reports NUAEG-0519 NRC Correspondence None Regulatory Commitments None Computer Codes As referenced in TRM Other None None None No change In computer codes or setpoint methodologies. None ...........,~ ~ ,...........1..... T......Tapfc. ""III** ~........... """'***IT.,. Codes and Standards None None Topical Reports None ClTA and documented in PUSAA section 2.4 Industry Initiatives and Guidelines ANSIlISA-S67.04.- 1994 ANSI/ASME PTC 19.1-1985 Nochaoge Other NEI Letter dated 7I05I07, comments on implementing TSTF*493 Implement TSTF-493 _ ***., Ii eo... ...........a**,IT.......IIITopIo:...... TSTF-493 notes for MSl to be added to TS Markups -~~

Preaubmittal Guidance Checklist* laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 8 of 18 Proposed Llcen8lng ActIon: Extended Power Uprate (EPU) UcenaeafPlant: laSalle Units 1 and 2 Technical: Purpose is to reach agreement with the NRC that plans for a current p. change is not linked to the proposed EPU related p. change. Points of Oiscussion: LaSaUe recently Identified an issue with the existing calculation for post accident peak drywall pressure (PI) which results in the need to increase PI' laSalle has entered this issue into the corrective action program and addressed this condition through an Operability Evaluation for the current operating cycle. Based on this identification, laSalle Station plans on submitting a license application change request for the current licensed power level. EPU power levels will also require an additional increase in the PI Technical Specification value. Neither the current change nor the proposed change due to EPU is contingent upon each other. Therefore per LlC-109. the changes may be submitted and accepted concurrently. Susquehanna Units 1 & 2 EPU Technical ISusquehanna's Peak DBA Primary Containment Pressure (P.) increased to 48.6 psig due to EPU. laSalle projects Specifications dated 113012008 an increase in p. value. (MlO803OO472) Hope Creek EPU Technical Specifications dated 511412008 (Ml081230623) Hope Creek's Peak OBA Primary Containment Pressure (P.) increased to SO.6psig due to EPU. laSalle projects an increase in P,. value.

Presubmlttal Guidance Checklist* laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 90t 18 PropoMd Ucenslng Action: Extended Power Uprate (EPU) UceneealPlant: laSalle Units 1 and 2 I8l R**1:IIOr 8yetema (aw_ and Interface) o Electrical o Instrument and Controls o Mechanical and Civil o Balance of Plant 181 Containment and Ventilation ONMSS o NSIR Standard Review Plan None Branch Technical Positions None Review Standards RS-001 Regulatory Guides RG 1.163 NUREGs Interim Staff Guidance Other: o ProbabiUstIc Risk Assessment o Fire Protection o Piping and NDE o Steam Generator Tube Integrity o Component and Performance Tesllng o Environmental o OGC None EPU evaluations followed the R8-001 guidance No change None None o Emergency Planning o Technical Specifications o Special Projects o Health Physics o OORL* Projects DOE o LaSalle was not licensed as a SAP facility. SEA (NUREG 0519) related to the operation of LCS units 1 and 2 (March 1981) contained the scope of NRC staff's technical and radiological review. The intent and requirements of SAP 6 2.1.1.C is met and documented in original licensing SEA NUREG-0519 The Power Uprate Safety Analysis Aeport (PUSAR) will be prepared in accordance with the RS-001 guidance

.. lit.. b I Presubmittal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 100f 18 ActIon: Extended Power uunIlB UcenaeelPlant: laSalle Units 1 and 2 tllCG..... c..-aIl,QIrJ*.'-. NRC Bulletins NRC Generic Letters Regulatory Information Summaries NRC Information Notices Other ,..,.......Li****"" N,. ",-{,,~,;.. j.' .~=,.. l'.('. ,.....,'~ -=r.=.~' -::""':1 CMn.1ltIt I .............I......,........TapID: I Updated Final Safety Analysis Report Section 3.11. 6.2.1, 6.2.6. Figure 6.2-2A, Table 6.2 16.2-3A, 6.2-8,6.2-8A, 6.2-23, and 3.2-1 New projected EPU p. value Technical Specifications LCO & Operating Ucense Administrative TS 5.5.13 New projected EPU Pa value Technical Specifications Bases 83.6.1.5 Will discuss increase in projected EPU p. value Technical Requirements Manual None None No TRM changes expected for areas affected by changes to Pa* Fire Hazards Analysis Report Current revision No change None NRC Safety Evaluation Reports NUREG*0519 No change NRC Correspondence None None Regulatory Commitments None None

Presubmlttal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 11 of 18 Propoeed Licensing Action: Extended Power U Ucenaeal'Plant: laSalle Units 1 and 2 ...,.... D..L..... Computer Codes Other ~:~,./::.* t'~ M3CPT Version 05V LAMB Version 07V None JJ!~I!,~.*". l~...............__

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Qz.~ ~.....d Codes and Standards Topical Reports Industry Initiatives and Guidelines Other I None I None I None ......................,......T

Preaubmlttal Guidance Checklist* laSalle EPU P.....Submlttal Meeting Scheduled April 4, 2012 Page 12 of 18 Propoeed Ucenalng ActIon: Extended Power Uprate (EPU) Llcen8eelPlant: LaSalle Units 1 and 2

3. Alternate Source Term (AS1):

USNRC Letter and Safety EvaJuation for The reference Safety Evaluation (SE) Is the basis for laSalle's AST approvaJ. This proposed license amendment and Acceptance of laSalle Units 1 and 2 analysis consisted of re-analyses of the Loss of Coolant Accident (LOCA). Fuel Handling Accident (FHA, post-LOCA Technical Specification Changes to suppression pool pH in support of the LOCA analysis, and Vital Access Area considerations. Although included as Support the Application of Altemative part of LaSalle's design basis for radiological consequences, the Main Steam Line Break (MSLB) and Control Rod Source Term Methodology, September 6, Drop Accident (CRDA) analyses were not required to be performed with AST characteristics nor part of the laSalle 2010, ADAMS Accession No. License Amendment Request for AST. Consistent with verbiage in the SE, aD analyses performed to demonstrate ML101750625. compUance with regulatory requirements as part of EPU have been updated with aU characteristics of AST and TEDE criteria as described In the LSCS design basis. Nine Mile Point Unit 2, Extended Power Extended Power Uprate amendment increasing reactor core thermal power approximately 15%. Nine Mile Point is the Uprate amendment request. Approved most recently approved BWR EPU. laSalle's application for EPU AST is consistent to the Nine Mile Unit 2 12122111 (ML11

Presubmlttal Guidance Checkllst-laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 13 of 18 Proposed Licensing ActIon: Extended Power UcensealPlant: LaSali. Units 1 and 2 D Security 181 Reactor SyaterM (ew.......... and Interface) 181 AccIdent Dote D Emergency Planning o Electrtcel o ProbabiHstic Risk Assessment D T echnicel Specifications D Instrument and Controls o Rre Protection D Mechanical and CIvil D Special Projects o Piping and NDE D Balance of Plant o Steam Generator Tube Integrity D Health Physics D Component and Performance Testing D DOAL* Projects D Environmental DOE DOGe o laSalle was not licensed as a SAP facility. SEA (NUREG 0519) related to the operation of LCS units 1 and 2 (March 1981) contained the scope of NRC staff's technical and radiological review. Branch Technical Positions Aeview Standards RS-001, Section 2.9.1 EPU evaJuations followed the IThe Power Uprate Safety Analysis Aeport (PUSAA) will be AS-001 guidance prepared In accordance with the R8-001 guidance

Presubmlttal Guidance Checkllst-laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 140' 18 Proposed Licensing ActIon: Extended Power Uprate (EPU) Ucenaeell'lant: laSalle Units 1 and 2 IIICII.IOlr.I,.,GuIIIII._ '. **'**".IJ~'."'i;,);,,',;. ikl':;;""Y,.; ...........~".., l1li.'.

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,t" ~~,~"'..,I," .. **;.;.~_!J!i~.;.{~.a.. t:"t!,'F*":;~:,~~* __......~"~._,..........T.... Regulatory Guides RG 1.183, Alternative No change In current In compliance with the referenced Regulatory Guides Radiological Source Terms calculation method for Evaluating Design Basis Accidents at Nuclear Power Reactors RG 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,I Rev.1,Novenmer1982 RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," Rev. 0, June 2003 NUREGs NUREG-073711.B.2 No change In NUREG*0737 No change in defined vital areas for EPU anaJysis. Vital area II.B.2 commitments doses are recaJcuJated for EPU and continue to meet NUREG 0737 Item II.B.2 requirements. NUREG-1465 "Accident NUREG-1465 applied to EPU Source Term~ for light-Water conditions No change in assumptions for current Acctdent Source Nuclear Power Plants* Terms. Interim Staff Guidance None None

Presubmlttal Guidance Checklist - laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 150f 18 ActIon: Extended Power UcenaaalPlant: LaSalle UnHs 1 and 2 -=::rll* ~..;',;> .,., ctp'(U"" L ',*,n ~"c,", ,"V IV.'.... Other: Doses were recalculated for EPU conditions. Doses for LOCA and FHA analyses (previously perfonned with AST) increased approximately proportion81 to power level increase. Doses newly calculated with AST (MSLB and CRDA) and the LOCA and FHA dose analyses 811 met doses specified in regulation criteria 10 CFA 50.67 with EPU. NRC Bulletins None None NRC Generic Letters None None Regulatory Infonnation RI8--2006-004, Experience No change. No change. The EPU submittal will address the issues Summaries discussed in RIS 2()(J6..04 regarding level of detail and With Implementation of Alternative Source Terms technical requirements. NRC 'nfonnation Notices Other

Preaubmlttal Guidance Checklist* laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 160f 18 Propoaecl Licensing ActIon: Extended Power U LlcensealPlant: laSalle Units 1 and 2 The UFSAR will be updated IThe UFSAR wHI be updated to reflect analysis at EPU Report Updated Final Safety Analysis 115.6.5.5 and Table 15.6-23, for EPU conditions. conditions and 15.7.4.5 Amendment 145 implemented AST. Technical Specifications Bases I Various No change Technical Requirements I None Manual Fire Hazards Analysis Report I None NRC Safety Evaluation Reports LIcense Amendment No. 145. dated September 6, 2010 (ML10175(625). NRC Correspondence None Regulatory Commitments None Computer Codes RADTRAD 3.03 None Other Radiological consequences as reported In the current Safety Evaluation will increase for EPU and require NRC approval. No additional changes will be made for EPU AST analyses.. Radiological consequences for the existing AST analyses (LOCA and FHA) contained In the reference SE will have Increased dose consequences, approximately proportional to power Jevellncrease, with EPU.

Presubmlttal Guidance Checklist* laSalle EPU Pre-Submittal Meeting Scheduled April 4, 2012 Page 17 of 18 Llc:enaeelPlant: LaSalle Un". 1 None and 2 InliH Ill'_1111_.

"11111" I qll Codes and Standards Tapical Reports NEDC -33004P-A (CLTA)

None and NEDC-32424P-A (ELTR1). Documented in PUSAA section 2.9 None None Industry Initiatives and Guidelines Other None None 1**~*Ajl',": t;'i'1i~~ "C'JU**

Presubmlttal Guidance Checkllst-laSalle EPU Pre-Submlttal Meeting Scheduled April 4, 2012 Page 180f 18 Proposed Licensing Action: Extended Power Uprate (EPU) LlceneeelPlent: LaSalle Units 1 and 2

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J. Zimmerman - 2 PARTICIPANTS: Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR). NRC/NRR Exelon Generation Company, LLC J. Zimmerman G. Casto K. Borton H.vinyard R. Denning A. Sallman T. Byam T. Simpkin N. DiFrancesco P. Hernandez V.Shah F. Pournia et al. S. Du Pont J. Rommel K. Ainger et al. Interested members of the public can participate in this meeting via a toll-free audio teleconference. Please call one of the meeting contacts listed below before Monday, April 2, 2012, 2:00pm EDT to get the telephone number and the pass code. The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a 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 contact. 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 Nos. 50-373 and 50-374

Enclosures:

1. Agenda
2. Pre-Submittal Guidance Checklist cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsOgcRp Resource SBagley, EDO Region 3 LPL3-2 RlF RidsOpaMail Resource OWFN Receptionist (paper) RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource TWFN Receptionist (paper) RidsNrrDorl Resource LLund PMNS Resource RidsNrrDorlLpl3-2 Resource JZimmennan R Denning RidsNrrPMLaSalie Resource JWiebe JStrasma RidsNrrLASRohrer Resource CSteger, NRR OPA Region 3 ADAMS Accession No ML120750572 NRC-001 OFFICE DORULPL3-2/PM DORULPL3-2/LA DORULPL3-2/BC DORULPL3-2/PM NAME Nicholas DiFrancesco KGoldstein JZimmennan /JWiebe for Nicholas DiFrancesco DATE 3/20/12 3/19/12 3/20/12 3/20/12 OFFICIAL RECORD COpy}}

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