ML040630431

Powerpoint Presentation Slides for Meeting with Florida Power & Light Company Regarding Planned Power Uprate Request for Seabrook Station, Unit No. 1

ML040630431
Person / Time
Site:	Saint Lucie, Seabrook
Issue date:	03/03/2004
From:	Licata L NRC/NRR/DLPM/LPD1
To:	Darrell Roberts NRC/NRR/DLPM/LPD1
References
Download: ML040630431 (29)

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,:1 SEABROOK STATION

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. POWER UP..- R A STRETCH POWER UPRATE FPL ENERGY, SEABROOK - NRC MEETING March 3, 2004 1

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F 9 SEABROOK STATION

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HIntroduction UDiscussion of Proposed Submittal HClosing Remarks 2

_ INTRODUCTION

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• AC UPRATE TEAM lilCombined FPL/Seabrook team with over 150 years of nuclear experience rx-Operations FExEngineering FxLicensing IMaintenance FIxconstruction FISpecific experience at St, Lucie and Turkey Point related to power uprates 3

_ INTRODUCTION AUPRATE TEAM (cont.)

EIWestinghouse Fx-Mnvolved with all uprates of Westinghouse units KParticipated in Seabrook feasibility studies rZAdopting Best Estimate LOCA for Seabrook IJStone and Webster xI-Knvolved with many uprates including a majority of Westinghouse units EIHas performed extended power uprate evaluations xProven process for system evaluations 4

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INTRODUCTION

.. . .a STEAM MEMBERS El/Steve Hale - Project Manager I/\Greg Myers - Accident Analysis Lead E]Tom Abbatiello - Environmental Lead 1EIan Watters - Technical Lead ElTony Menocal - Balance of Plant Lead ME Laird Bruster - Shaw (Stone & Webster)

ElDave Dominicis - Westinghouse 5

___ INTRODUCTION HNRC GUIDANCE E1NRC Review Standard RS-001 for extended power uprates FxApplying the guidance for Seabrook Station Stretch Power Uprate (SPU) License Amendment Request ElDuring Initial drop-by meeting in May 2003 discussed plan and NRC provided feedback on format/content EIRequested follow-up meeting 1 month prior to submittal 6

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., INTRODUCTION 4- t4 , - .- ..-- 'rb * .- - - .-

nUndustry F1Using recent amendments/NRC SERs as input xKewaunee 1EBeaver Valley IByron/Braidwood xPalo Verde xVermont Yankee E1Indian Point EIReviewing and incorporating NRC RAI responses where applicable and appropriate 7

_ .- INTRODUCTION HIndustry (cont.)

EJLessons learned from power uprates xILessons learned addressed as part of uprate analyses and evaluations xIncorporated lessons learned into specifications and scoping documents FIxSystem Engineering Reports specifically address issues

[x-Stone and Webster, Westinghouse, and FPLE attended industry working group meeting in 2003 JImplementing draft guidance generated from the meeting 8

INTRODUCTION HAII work, both in-house and contracted, performed in accordance with 10 CFR 50, Appendix B QA Program HAII inputs provided to Westinghouse and Stone and Webster for analyses and evaluations are documented in verified engineering evaluations 9

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REQUESTED UPRATE

"' d Amendment Accident Current Request Analyses Licensed Core Power 3411 MWt 3587 MWt 3659 MWt NSSS Thermal Power 3429 MWt 3605 MWt 3678 MWt Stm Gen Tube Plugging 8% 0 to 10%0/ 0 to 10%

Thermal Design Flow/Loop 95,700 gpm 93,600 gpm 93,600 gpm Core Bypass Flow 6.30/b 8.3%/o 8.30/b RCS TAVG 588.50 F 5710 F to Range +/-

589.10 F Uncertainty Feedwater Temperature 4420 F 3900 F to 3900 F to 452.40 F. 452.40 F 10

AMENDMENT REQUEST IE1Attachment 1 - Technical Assessment IE\Attachment 2 - Marked up Facility Operating License and Technical Specification pages EIAttachment 3 - Retyped Facility Operating License and Technical Specification pages EAttachment 4 - List of Regulatory Commitments ElAttachment 5 - Proposed Schedule for License Amendment and Implementation FIAttachment 6 - No Significant Hazards Consideration Determination 11

AMENDMENT REQUEST dTechnical Assessment ElSection 1-Introduction FESection 2-Nuclear Steam Supply System Parameters FElSection 3-Design Transients ESection 4-Nuclear Steam Supply System IlSection 5-NSSS Components F-iSection 6-Accident Analyses FJSection 7-Nuclear Fuel 12

AMENDMENT REQUEST

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HTechnical Assessment (Cont.)

ElSection 8-Balance of Plant

/IKSection 9-Programs l7JSection 10-Miscellaneous Topics FlSection 11-Impact on Operations FlSection 12-Testing FElSection 13-Environmental Evaluation 13

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AMENDMENT REQUEST AOther Features IlIThe SPU submittal relies on NRC approval of LAR No. 03-02 submitted on October 6, 2003 to adopt Alternate Sou rce Term (AST) methodology for Seabrook Station - AST analyses were performed at a core power level of 3659 MWt F-Large break LOCA analysis performed for the SPU utilizes NRC approved best estimate methodology 14

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AMENDMENT REQUEST NOther Features (Cont,)

IEContainment analyses utilize the GOTHIC code for comparison purposes EISPU LAR Table 1.2-1 in Section 1 of Attachment 1 includes a table of computer codes utilized for the SPU and whether they have been previously used for Seabrook Station 15

I---Ad AMENDMENT REQUEST H"Use of NRC Review Standard RS-OO1 ESPU LAR Tables 1.3-1 through 1.3-13 in Section 1 of Attachment 1 provide cross references between the topical areas in each RS-OO1 matrix to the specific sections in the SPU LAR where those topics are discussed and evaluated 16

AMENDMENT REQUEST

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= i TABLE 1.. -i -,k NRC REVIEW STANDARD RS-001 MATRIX 8 REACTOR SYSTEMS LAR SECTION Fuel System Design 5.3 Fuel Assembly Structural Analysis Nuclear Design 7.2 Core Design 7.3 Fuel Rod Design and Performance Thermal and Hydraulic Design 7.1 Core Thermal-Hydraulic Design Functional Design of Control Rod Drive System 5.4 Control Rod Drive Mechanisms Overpressure Protection during Power Operation 4.1 NSSS Fluid Systems 4.3.3 Control Systems 5.6 Pressurizer 6.3.3 Decrease in Heat Removal by the Secondary System Overpressure Protection during Low 4.3.4 Cold Overpressure Mitigation System Temperature Operation Reactor Core Isolation Cooting System (BWR) N/A Residual Heat Removal System 4.1.4.3 Residual Heal Removal System Emergency Core Cooling System 4.1.44 Salety Injection System Standby liquid Control System (BWR) N/A Decrease in Feedwater Temperature. Increase in 8.3.2 Increase I Heat Removal Feedwater Flow. Increase In Steam Flow, and Inadvertent Opening of a Steam Generator Reliet or Salely Valve Steam System Piping Failures Inside and 6.3.2 Increase in Heat Removal Outside Containment 6.4 Containment Response 6.5 Steamline Break Outside Containment 10.4 High Energy Une Break /Jet Impingement Loss of External Load. Turbine Trip. Loss at 63.3.1 Loss ot External Load/Turbine Trip Condenser Vacuum, and Steam Pressure Regulator Failure (Closed)

Loss of Non-emergency AC Power to Station 6.3.3.3 Loss at Nonemergency AC Power to Plant Auxiliaries Auxiliaries Loss of Normal Feedwater Flow 6.3.3.2 Loss of Normal Feedwaler Feedwater System Pipe Breaks Inside and 6.3.3.4 Feedwater System Pipe Break Outside Containment Loss of Forced Reactor Coolant Flow Including 6.3.4.1 Partial Loss of Reactor Coolant Flow /

Trip of Pump Motor and Flow Controller Complete Loss of Reactor Coolant Flow Mallunctions Reactor Coolant Pump Rotor Seizure and 6.3.4.2 Reactor Coolant Pump Locked Rotor/Shalt Reactor Coolant Pump Shalt Break Break Uncontrolled Control Rod Assembly Withdrawal 6.3.5.1 Uncontrolled Rod Control Cluster Assembly from a Sub-critical or Low Power Condition Bank Withdrawal trom Subcritical Uncontrolled Control Rod Assembly Withdrawal 6.3.5.2 Uncontrolled Rod Control Cluster Assembly at Power Withdrawal at Power 17

--= AMENDMENT REQUEST

.,.. A=4 I 0 HCNSSS and BOP Evaluations IESystems and components were evaluated for flows, temperatures, and pressures based on an NSSS thermal output of 3678 MWt (accident analysis value) with comparable electrical output of 1314 MWe (gross)

-EHxpected gross electrical output at the proposed licensed SPU power level is 1287.5 MWe 18

AMENDMENT REQUEST 1BOP Evaluations (Cont.)

FlThe electrical generator evaluation and ISO New England Grid stability studies demonstrate acceptable performance up to a gross electrical output of 1295 MWe without plant modifications 19

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TECH SPEC CHANGES I . ~ --

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DESCRIPTION OF CHANGE AFFECTED TS RATED THERMAL POWER increase from 3411 MWt to 3587 MWt Operating License, TS Definition 1.28 Reactor Core Safety Limits revised to reflect increased RATED THERMAL POWER TS Figure 2.1-1 Steam Generator Low-Low water level reactor trip/EFW actuation setpoint increased from current 14.0% to 20.0% TS Table 3.3-4 Correction of typographical errors TS Table 2.2-1 Notes 1 and 3 Heat Flux Hot Channel Factor Fq(Z) Surveillance Limits 4.2.2.2c, 4.2.2.2e & 4.2.2.2f are applicable in the core region TS 4.2.2.2g from 10% to 90% versus the current 15% to 85%

The following DNB parameters change:

• RCS Thermal Design Flow reduced to 374,400 gpm TS 3.2.5

• RCS Minimum Measured Flow reduced to 383,800 gpm Steam Generator Hi-Hi level turbine trip/feedwater isolation Increased from current 86% to 90.8% TS Table 3.3-4 Reduced maximum allowable power range for inoperable MSSVs TS Table 3.7-1 Various changes to COLR analytical methods listed in the Administrative Controls section TS 6.8.1.6b Changes to bases for hot channel factors TS Bases 3/4.2.2, 3/4 2.3 Changes to bases for main steam code safety valves TS Bases 3/4.7.1.1 20

SCHEDULE

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USubmittal to NRC by the end of March 2004 RRequest a 9 month NRC review XLicensed operator training-First 3 months of 2005 HImplementation of modifications-Spring 2005 refueling outage UPerformance testing on return to power N Power Ascention Test report to NRC 90 days from return to power (Tech Spec 6.8.1.1) 21

Em= MODIFICATIONS Modifications to support the safety analyses:

ElOvertemperature and overpower AT setpoints ElAuctioneered high Tavg to average Tavg FlSteam generator high-high and low-low level setpoints E1Re-span steam generator level transmitters IEIPressurizer level control program FlScaling for turbine impulse pressure to power EILoss of load interlocks, automatic rod control, permissives, and steam dump control 22

MODIFICATIONS HModifications to improve plant performance, margins and efficiency:

FIReplace the high pressure turbine rotor and fixed diaphragms EJReplace the moisture separator reheater internals with a new four pass system Fl Modify drain piping from the #5 feedwater heaters and vent piping from the heater drain tank 23

_ MODIFICATIONS HIModifications to improve plant performance, margins and efficiency (Cont.):

IEIModify the condensate pumps to provide additional operating margin for the Condensate/Feedwater Systems FEJlEnhance condensate supply to the Condenser FIModify the main feedwater pump turbine speed controllers to maintain feedwater regulating valve control margin 24

MODIFICATIONS IModifications to improve plant performance, margins and efficiency (Cont.):

FlChange the condensate pump recirculation valve setpoint El Re-span steam flow transmitters FlRe-band the main steam and feedwater flow indication in the Control Room normal operating (green band) band FiModify scaling and indicator for generator megawatt meter on main control board 25

MODIFICATIONS HModifications to improve plant performance, margins and efficiency (Cont.):

FJModify generator step-up transformer cooling to increase operating margin and transformer life 26

-=l-SAAFFE -- CTE AREAS

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CInstrumentation modifications to be performed in the control room cabinets and locally at the instruments FlNo special facilities required beyond normal calibration and maintenance practices during refueling outages 27

AFFECTED AREAS UModifications to cooling for the generator step-up transformers will be performed at the transformers in the yard ElSupport requirements will include scaffolding, but no special facilities beyond those used for normal refueling outages 28

AFFECTED AREAS

.. ni..- -. ,,t>' fK d AModifications to the high pressure turbine, moisture separator reheaters, and condensate system will be performed in the Turbine Building E1Support requirements will include scaffolding and portable cranes, but no special facilities beyond those used for normal refueling outages 29