GE Energy

NJoseph A. SavageManager, ABWR Licensing3901 Castle Hayne Road, M/CJ70Wilmington, NC 28402-2819USAT 910-602-1885F 910-602-1720oseph.savage@,ie.com

MFN 07-280May 17, 2007

Attention: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

Subject: Submittal of ABWR Licensing Topical Report (LTR)Synopsis and Table of Contents -- Update

Reference: GE Letter MFN 07-044, S. Stark to NRC Document Control Desk, datedJanuary 26, 2007GE Letter MFN 07-180, J Savage to NRC Document Control Desk, datedMarch 28, 2007

To aid the NRC in planning for the review of the upcoming Licensing Topical Reports(LTRs) associated with the Advanced Boiling Water Reactor (ABWR) licensing activities,the referenced letters provided a list of proposed General Electric (GE) LTRs to besubmitted in 2007 regarding the ABWR certified design. GE also provided theproposed submittal schedule, a synopsis of each LTR, and each LTR's proposed Tableof Contents. This letter provides a revision to the attached listing of LTRs.

The purpose of this letter is to update the NRC staff on changes to our proposedsubmittals and the current status. Note that GE has canceled two LTRs identified inprevious correspondence. The following two LTRs have been deleted from the listingof planned LTRs and will not be submitted:

1. The Preoperational Test Specifications LTR, an engineering document thatprovides detailed test requirements for each plant system down to the

QIDh51D

component level, was identified in the early phases of the STP project as acandidate LTR and proposed amendment to the ABWR certified design.This LTR was intended to respond to a COL Information Item required persubsections 14.2.13.1 and 14.2.13.2 of the DCD. GE has determined it willbe prudent to wait until the necessary site specific information is availableto prepare these specifications. The required information will not beavailable until significant equipment procurement and constructionengineering specific to STP 3&4 has been accomplished. The project teamwill submit the preoperational test specifications in a formal letter to theNRC after the necessary information to establish preoperational testingrequirements becomes available. The preoperational testingspecifications will be submitted after COLA approval.

2. The Editorial Changes to the US ABWR DCD LTR is cancelled due to recentNRC rulings. NRC Staff Requirements Memorandum, dated April 11, 2007,(with reference to SECY-06-220), limits the DCD amendment process tocorrection of "material" errors, which would not allow for GE to pursue aDCD amendment for correction of administrative errors, consistent withGE's initial plans. The DCD errors that are not material errors will now beincluded and evaluated in the combined license application (COLA). Theseadministrative errors will be treated as departures from certified designmaterial in Part 7 of the COLA, consistent with the COLA preparationrequirements.

If you have any questions about the information provided here, or during the courseof your reviews, please contact me at 910-602-1885.

Sincerely.

Joseph A. SavageProject Manager, ABWR Licensing

Enclosure: Updated Synopsis of LTRs and Table of Contents, May 18, 2007

cc: JA SavageGB StrambackGF WunderMA McBurnett

GE (Wilmington wI enclosure)GE (San Jose w/o enclosure)NRC (wI enclosure)STP (wI enclosure)eDRF 0000-0061-9949

Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included in RAIs Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

Alternate RCIC Submitted This LTR is generated to obtain Description of Certified Design 06/29/07 09/28/07 12/29/07Pumps to NRC on NRC approval of a generic change Description of Proposed Departure

December in the design certification for the Justification for Departure20, 2006 U.S. ABWR certified design, in Qualification Information

accordance with planned revisions Description of The TWL Type Alternateto 10 CFR 52.63. The design Designchange involves replacement of Operating Experiencecertain portions of the Reactor Core Nuclear Safety ReviewIsolation Cooling turbine and pump Consistency with ABWR Design Controlsystem design with an integrated Document (DCD)alternate turbine-pump system Descriptions of DCD Markupdesign. Operating experience isexamined. Qualification informationfor the proposed changes will bedocumented. The safety basis forthe proposed change is examined.The alternate design will result inimprovements in performance andreliability of the system. Theseproposed changes are to both Tier1 and Tier 2 of the ABWR DesignControl Document, Revision 4.These proposed changes weredeveloped during performance offirst-of-a-kind-engineering for theABWR.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included In RAls Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

Plant Submitted This LTR prescribes and guides the Reference Documents 07/31/07 10/30/07 01/29/08Procedures to NRC on conduct of procedure development Supporting DocumentsDevelopment January 19, for the US ABWR. Regulatory Codes and StandardsPlan 2007 requirements are identified. This Regulation and Regulatory Requirements

implementation plan meets the Implementation Planrequirements of ABWR Design Administrative Procedures DevelopmentControl Document/Tier 2 sections Maintenance and Other Procedures13.5.3.1 through 13.5.3.4. Development

Plant Operating Procedures DevelopmentThe scope of the procedures Emergency Operating Procedurescovered in this Implementation Plan Developmentincludes the following categories: Additional RequirementsAdministrative Procedures, Procedures Included in Scope of PlanMaintenance and Other Administrative ProceduresProcedures, Plant Operating Maintenance and Other ProceduresProcedures, Emergency Operating Procedures for Radiation ControlProcedures (EOP). Types of Integrated Operating Proceduresprocedures in each category are System Operating Proceduresspecified. The generic processes Alarm (Anunciator) Response Proceduresfor development of procedures are Abnormal Operating Proceduresdescribed. Links to TMI Action Surveillance Test ProceduresItems are specified. Verification Emergency Operating Proceduresand validation requirements areidentified.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included in RAls Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety Approval

Date Evaluation NeededBy:

StartupAdministrativeManual

Submittedto NRC onFebruary28, 2007

This LTR is provided to respond toa COL Information Item requiredper subsection 14.2.13.2 of theDCD. A startup administrativemanual defining variousadministrative controls to be inplace during the initial plant testprogram is required per 14.2.13.2items (5) - (9).

The purpose of this document is toprovide a written outline of methodsand practices for administering theInitial Test Program for the ABWR.This manual establishes methodsfor controlling the start of testing, forperforming tests, for preparing andmodifying approved procedures, foridentifying and correcting testexceptions, and for reviewing andapproving test results.

Purpose and ScopeApplicable DocumentsSupporting and Supplemental DocumentsCodes and StandardsRegulations and Regulatory RequirementsStartup Organization and ResponsibilitiesInitial Test Program Planning -SchedulingTest PlateausTest SequenceStartup Test Program PlanningStartup Test Program SchedulingConduct of TestingDistributions and Control of ProceduresAdherence to ProceduresUse of ProceduresPerformance of Pre-op and Startup TestsTest Procedure and Test ControlContent of Test ProceduresPreparation, Initial Review, and ApprovalProcedure ModificationsTest Results Review and Acceptance

08/29/07 11/28/07 02/27/08

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR items to be included in RAts Draft LTRSubmittal Table of Contents (Planned) (If needed) Safety ApprovalDate Evaluation Needed

By:APRM Submitted This LTR is provided to respond to Description Of the Design 10/01/07 01/02/08 04/02/08Oscillation to NRC on a COL Information Item requiredMonitoring April 2, per subsection 7.6.2.1 of the DCD. Justification for DepartureLogic 2007(OPRM) The BWROG Stability Solution Qualification Information

Option III is applied to the OPRMdesign. These changes will deviate Operating Experiencefrom the certified design. Themajor changes are: (1) the time Nuclear Safety Reviewconstant of the Butterworth signalfilter is changed; (2) the Backup Consistency with ABWR DCDStability Protection regions areestablished for operation when Descriptions of DCD MarkupsOPRM is inoperative; (3) thePeriod-Based Detection Algorithm Figuressettings (cut-off frequency, periodtolerance, maximum period, and LPRM Assignment to OPRM Channelsminimum period) are modified toresolve the unexpected OPRM LogicConfirmation Count reset concern;(4) an Option III Trip enabled region Appendixwill be added and the *Region 111" inthe original DCD is eliminated, (5) ABWR DCD Significant Tier 2 Changesan OPRM Inoperative trip isseparated from the APRMInoperative trip; and (6) the OPRM2/4 trip logic is performedseparately from other APRM trips.

The OPRM LTR will revise the STPDCD Section 7.6.1.1.2.2, includingany text, tables, figures,appendices, and data that arenecessary for NRC review perNEDO-32465-A.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included In RAIs Draft LTR

Submittal Table of Contents (Planned) (If needed) Safety ApprovalDate Evaluation Needed

By:

Vibration Submitted The ABWR DCD Subsection Summary And Conclusions 10/18/07 01/17/08 04/17/08Assessment to NRC on 3.9.2.4 and COL Information Item Test DescriptionProgram May 1, 3.27 are the bases for this LTR. Component Selections

2007 Sensor LocationsThis LTR will provide the results of Test Conditionsthe vibration assessment program Data Reduction Methodsfor the ABWR prototype internals, a Time History Analysisrequirement for the first ABWR COL Frequency Analysisapplicant. These results will include Data Evaluation Methodsthe information specified in Finite Element ModelsRegulatory Guide 1.20. NRC Stress Evaluationreview and approval of the above Results And Discussioninformation on the first COL In-Core Monitor Guide Tubesapplicant's docket will complete the In-Core Monitor Housingsvibration assessment program Control Rod Guide Tubes And Cr Driverequirements for prototype reactor Housingsinternals. Core Flooder Sparger

Core Flooder Coupling And Thermal RingFurthermore, the first COL applicant Shroudwill provide the information on the Steam Dryerschedules in accordance with the Pressure Sensorsapplicable portions of position C.3 Summary Of Component Maximum Stressesof Regulatory Guide 1.20 for non-prototype internals. Subsequent AppendixCOL applicants need only provide Unbalanced, Steady State Pumpingthe information on the schedules in Configurationsaccordance with the applicableportions of position C.3 ofRegulatory Guide 1.20 for non-prototype internals.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included In RAts Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

Materials and Submitted This LTR will respond to FSAR COL Codes and Standards 10/18/07 01/17/08 04/17/08

Surveillance to NRC on Information Item - 5.5 (FSARCapsule April 27, 5.3.4.2) - RPV Material Description of Plan

2007 Surveillance Program. Two reportsare necessary. The initial report will Surveillance Capsule Withdrawal Scheduleidentify: 1) the specific materials ineach surveillance capsule, 2) the RPV Material Surveillance Programcapsule lead factors 3) thewithdrawal schedule for each Surveillance Test Specimenssurveillance capsule, 4) the neutronfluence to be received by each Location of Installed Specimencapsule at the time of itswithdrawal, and 5) the vessel end- Fluence and Lead Factorsof-life peak neutron fluence. SeeSubsection 5.3.1.6.4. The ABWR Operation of ReactorDCD is the basis for thisrequirement. The initial report will Normal Heating & Temperature Change Rateprovide estimated values of leadfactors, capsule and RPV peak Minimum RPV TemperatureEOL fluence data. Existing ABWRoperating experience data will beidentified.

The final report will be preparedfollowing completion of the fuel andcore design and fluence analysis.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included In RAIs Draft LTR

Submittal Table of Contents (Planned) (if needed) Safety Approval

Date Evaluation NeededBy:

Common Submitted The LTR will describe the STP two Certified Design Layout 10/18/07 01/17/08 04/17/08

Equipment and to NRC on units ABWR site layout and designStructures May 1, of structures and systems in Description of Buildings

2007 relationship to the certified design,and building footprints. Shared Proposed Changesstructures and systems includingRadwaste building and equipment, Common Radwaste Building and Equipmentfirewater pump house andequipment, and the circulating Common Firewater Pump House Equipmentwater intake and dischargestructures and equipment will be Common Circulating Water Intake anddescribed. The amendment will Discharge Structure and Equipmentindicate that the common systemsare only applicable to a 2-unit plant, DCD Markupsand that the existing DCD (Revision4) continues to apply to a 1-unit Nuclear Safety Reviewplant.

Page 7 of 14

Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR items to be Included in RAIs Draft LTRSubmittal Table of Contents (Planned) (If needed) Safety Approval

Date Evaluation NeededBy:

Startup Test Submitted This LTR responds to a COL Specification Scope 10/29/07 02/01/08 04/28/08

Specifications to NRC on Information Item per 14.2.13.1 andApril 14.2.13.2 of the DCD. A "scoping Power-Flow Operating Map26,2007 document" covering the initial

startup test program is required, Startup Test Conditions14.2.13.2 item (1), will include.other testing' as needed per Startup Test Sequence14.2.13.1.

This LTR examines the Startup Test Criteria Definitions

Test Phase in three parts: 1) initial Applicable Documentsfuel loading and open vesseltesting; 2) testing during nuclear Supporting and Supplemental Documentsheatup to rated temperature andpressure (approximately 5% of Codes and Standardsrated power); and 3) powerascension tests from 5 tolO % of Regulations and Regulatory Requirementsrated power.

The Startup Test Program General Design Basisevaluates safety concerns andperformance warranties. The tests Individual Test Requirementslisted represent the minimumstartup tests required to be Startup Test Signal Listperformed.Required tests and operating (LTR = -150 pages)conditions are defined. The testpurpose, a brief discussion of thetest methods and philosophy, andthe test criteria for each test areincluded. A list of signals (processparameters) that are to be availableduring each specified test isincluded. LTR will be based onSRP 14.2.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included in RAIs Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

Plant Medium 05/18/07 This LTR will define departures Description Of Certified Design 11/16/07 02/15/08 05/16/08Voltage from Tier 2 DCD material in ChapterElectrical 8 related to the medium voltage Description Of Proposed DepartureSystem electrical distribution system.

Specifically, it covers the change Justification for Departurefrom a single 6.9kV to a dual13.8kV/4.16kV system. The LTR Nuclear Safety Reviewwill provide an alternative approachto the single 6.9kV medium voltage Descriptions of DCD Markupdesign as described in the DCD.No Tier 1 or Tier 2* material isaffected by this change.

Hydrogen 05/18/07 This LTR is generated to obtain US Description Of Certified Design 11/16/07 02/15/08 05/16/08Recombiner Nuclear Regulatory CommissionRequirements approval of a generic change in the Description Of Proposed DepartureElimination design certification for the U.S.

ABWR design, in accordance with Justification for Departureplanned revisions to 10 CFR 52.63.The design change involves Nuclear Safety Reviewdeletion of the hydrogenrecombiner equipment from the Descriptions of DCD MarkupABWR design. The nuclear safetybasis for the proposed change willbe established. The proposedchanges will be an amendmentrequest or generic LTR applicableto both Tier 1 and Tier 2 of theABWR DCD Revision 4, US NRCDocket #52-001.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included In RAts Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

BY:Life CycleManagementProgram

05/18/07 This LTR is provided to respond toa COL Information Item requiredper subsection 1.2.3.1 of the DCD.

The design life for STP is 60 years.The license for the STP plant isinitially for 40 years. STP mayapply for license renewal for anadditional 20 years in accordancewith the License Renewal Rule 10CFR 54.

GE intends to develop a design lifeplan (also known as "life cyclemanagement (LCM)" plan) thatincludes a design life classificationsystem, condition monitoring andplant environmental monitoringsystem. The design life plan willidentify the information that STP willneed to submit a license renewalapplication to extend the license by20 years.

The LCM plan is to define anintegrated program to optimizeplant performance, managingaging, and controlling the lifetime ofthe STP plant and its systems,structures and components. STPwill develop life cycle managementprogram during plant operation.

Plant Design Life Plan 11/16/07 02/15/08 05/16/08

Design Life Classification System

Condition Monitoring

Environmental Monitoring System

Aging Management Plan

Life Cycle Management ProgramDevelopment Plan

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included in RAIs Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

ABWR Stability 06/15/07 This LTR will be addressing the Solution Design Philosophy 12/17/07 03/14/08 06/16/08Evaluation analysis to support the ABWR

APRM Oscillation Monitoring Logic Solution DescriptionLTR (NEDO-33328). The analysiswill be performed using a GE 14 Licensing Methodologycore, and not GE 7 that was thebasis of the original DCD safety Defense in Depth Algorithmsanalysis. The technicalspecifications associated with the Backup Stability ProtectionOption III for STP stabilityimplementation will be included. References

The LTR will provide any text, Tables:tables, figures, appendices, and Tables of Analysis Resultsdata that are necessary for theNRC to review and conclude Figures:acceptability of the resulting safety Multiple Figures with Analysis Resultsanalyses. The LTR will be Power Flow Mapstructured to support the areas ofreview and acceptance criteriaprovided in SRP Section 4.4.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included In RAts Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:

Radiation 07/13/07 This LTR will address top Safety Design Bases 01/15/08 04/16/08 07/14/08Protection conceptual design requirements for

radiation protection (ABWR DCD Codes and StandardsTier 1 Section 3.2) features in theABWR for both plant personnel and General Requirements Descriptionthe general public. This LTR willprovide design details for Implementation Detailsradiological shielding, ventilationand airborne monitoring equipment Safety Evaluationof the Reactor, Turbine, Control,Service and Radwaste Buildings. Inspection and Testing Requirements

This LTR will also provide Instrumentation Requirementsimplementation details for STPUnits 3 & 4. The design will be in Tables:conformance with Standard ReviewPlan (SRP) Sections 12.3-12.4. None at this time

The LTR will provide any text, Figures:tables, figures, appendices, anddata that are necessary for the General Arrangement Radiation ZonesNRC to review and concludeacceptability of the design. TheLTR will be structured to supportthe areas of review and acceptancecriteria provided in SRP Sections12.3- 12.4.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be included In RAts Draft LTRSubmittal Table of Contents (Planned) (If needed) Safety ApprovalDate Evaluation Needed

By:Containment 09/1/07 This LTR will be the amendment for Safety Design Bases 03/03/08 06/02/08 09/03/08Analysis for the containment analysis DCDABWR Section 6.2. The previous analysis Codes and Standards

was based GE 7 fuel, that is nolonger available, so the new General Requirements Descriptionanalysis will be performed usingdecay heat from a GE 14 core. Descriptions of differences in the model and

inputs between the DCD and the Amendment

The LTR will provide any text,tables, figures, appendices, and Safety Evaluationdata that are necessary for theNRC to review and conclude Safety Analysis Descriptionacceptability of the resulting safetyanalyses. The LTR will be Tables:structured to support the areas ofreview and acceptance criteria Comparison of GE 7 vs. GE 14 fuel (designprovided in SRP Sections 6.2.1, details)6.2.1.1.C, 6.2.1.3, 6.2.1.4, and Comparison of Decay Heats6.2.2. The content of the LTR will Analysis Resultssupport an evaluation of the designagainst the guidance of the SRP Figures:revision mandated by the Multiple figures with analysis resultsregulations in effect at the time ofthe COLA submittal.

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Attachment to MFN 07-280May 17, 2007

Title of LTR Proposed Synopsis of LTR Items to be Included in RAIs Draft LTRSubmittal Table of Contents (Planned) (if needed) Safety ApprovalDate Evaluation Needed

By:Design 09/06/07 The Design Reliability Assurance Scope 03/06/08 06/06/08 09/08/08Reliability Program (D-RAP) will be performedAssurance during the detailed design and PurposeProgram equipment specification phase prior

to initial fuel load. The D-RAP Objectiveevaluates and prioritizes theStructures, systems and SSCs Identification/Prioritizationcomponents (SSCs) in the designbased on risk significance. Failure Evaluation of Significant SSCsmodes, key assumptions, and risk 0 System descriptioninsights for the risk-significant SSCs * System operationwill be identified. 0 Major Difference from operating

BWRsThe D-RAP purpose is to provide * System fault treesreasonable assurance that the plant * System design responsedesign proceeds in a manner that isconsistent with the original bases Referencesand design assumptions. The D-RAP scope includes risk-significantSSCs as determined byprobabilistic, deterministic, or othermethods used for designcertification.

This LTR will address the list ofSSCs based on the certified designwith additional selected SSCsbased on site-specific PRA results.

The guidance described in DCDsubsection 17.3.11 and DCD 19KTables will be implemented.

The LTR will provide confirmation ofDCD/Tier I Section 3.6 ITAAC.

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