ML11123A042

4/21/11 Crystal River Unit 3 Meeting Slides Regarding EPU Pre-Application

ML11123A042
Person / Time
Site:	Crystal River
Issue date:	04/21/2011
From:	Progress Energy Florida
To:	Siva Lingam Plant Licensing Branch II
Lingam S
References
TAC ME3949
Download: ML11123A042 (79)

Text

CRYSTAL RIVER 3 EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST FINAL PRE-PRE-APPLICATION MEETING APRIL 21, 2011

AGENDA Introduction/Purpose Jon Franke Power Uprate Mod Overview Ted Williams B&W NSSS Design g Features Dave Porter Key EPU Modifications Dave Porter EPU LAR Focus Areas Ken Wilson Conclusion/Q&A Jon Franke 2

INTRODUCTIONS Jon Franke Site VP T d Williams Ted Willi EPU E Engineering i i Dave Porter Operations Support Ken Wilson Project Licensing Larry Sexton EPU Eng/LAR PM Dan Westcott CR3 Licensing Lewis Wells Safety Analysis Bob Muzzi EPU Engineering 3

PURPOSE CR3 EPU LAR development reaching final stages Provide some background for NRC staff Highlight changes since previous meetings Briefly describe unique aspects of the B&W NSSS D Design i

Briefly describe key of the CR3 EPU modifications difi ti 4

CR3 EPU Project Philosophy Thoroughly evaluated appropriate operating and design margins Proposed modifications to maintain or increase nuclear safety margin and operating margin as much as possible Relied on approved codes and standards applied on a plant specific basis Significantly updated and upgraded thermal hydraulic and other design basis calculations 5

CR3 EPU Project Philosophy Utilized recently approved methodology for reactivityy insertion ((rod ejection) j )

Improved accident mitigation capability through g physical y plant changes g

Reduced operator burden Utilized previously approved Alternate Source Term 6

Phased Approach Phase I - MUR LEFM 1.6% 15R,, (2007)

( )

Phase II Steam plant efficiencies Replaced Electrical generator internals/Exciter Increased secondary side cooling capacities

Phased Approach Phase III Replace p manyy additional secondary y side components Modify Emergency Core Cooling systems Reactor power increased by 15.5%

NRC license amendment required

CR3 EPU LAR Philosophy FORMAT Consistent with RS-001 Guidance Compares pre- and post-EPU Regulatory evaluation clearly articulates regulatory standard expectations and current licensing basis Technical evaluation includes summary and d t il details Actual results (tables, graphs, etc.) provided C

Conclusion l i reflects fl t expectedt d SE content t t Includes appendices detailing key conceptual designs 9

Phase I Refuel 15 (MUR)

Phase II PLANT MODIFICATIONS Phase II - Turbine Plant Efficiencies Turbine Bypass Valves Replacement Moisture Separator Reheater (MSR)

Replacement MSR Shell Drain Heat Exchangers Heater Drain Valves and Piping Upgrade of Main Generator/Exciter Turbine Generator Lube Oil Tube Bundle Isophase Bus Duct Cooler Condensate Heat Exchangers Secondary Services Closed Cycle System Heat Exchangers Secondary Cooling Pumps and Impellers Fiber Optic Backbone ICS rescaling

16 17 18 19 20 21

EPU Phase III ECs Total of 30 Engineering Changes Focus on 6 ECs EC 70732 Emergency Feedwater System Upgrades EC 71855 Atmospheric Dump D mp Val Valves/Fast es/Fast Cooldown Cooldo n System S stem EC 73934 LPI Cross-Tie and Hot Leg Injection Addition EC 75574 SPDS Upgrades EC 76340 Inadequate Core Cooling Mitigation System (ICCMS)

EC79352 HPI Modifications 24

B&W NSSS Design g Features 25

REACTOR COOLANT SYSTEM FLOWPATH 26

REACTOR VESSEL REACTOR COOLANT INLET CO CORE FLOOD LINE 14 28 28 Cold Leg Cold Leg REVERSE FLOW RESTRICTOR 36 36 Hot Leg Hot Leg REACTOR REACTOR COOLANT COOLANT OUTLET 28 28 OUTLET Cold Leg Cold Leg 14 CORE FLOOD LINE REACTOR27 COOLANT INLET

REACTOR VESSEL 139 FT 6 IN 11 FT 6 IN 129 FT 6 IN C

L 128 FT COLD HOT LEG LEG 124 FT 7 IN TOP OF DHR High Pressure FUEL Drop-Line Injection Line 104 FT 28

Normal Feedwater System Flow Path PRIMARY INLET MANWAY UPPER TUBESHEET UPPER SHROUD STEAM OUTLET MAIN LOWER FEEDWATER SHROUD HEADER ORIFICE PLATE LOWER TUBESHEET MANWAY 29 OUTLET NOZZLES

EFW System Flow Path after an EFW Actuation PRIMARY INLET MANWAY UPPER TUBESHEET EMERGENCY FEEDWATER HEADER UPPER SHROUD STEAM OUTLET EFW FLOW RATE of 660 GPM MAIN LOWER FEEDWATER SHROUD within 40 seconds HEADER ORIFICE PLATE LOWER TUBESHEET MANWAY 30 OUTLET NOZZLES

Feedwater and Emergency FW System Flow Paths 31

Flow Paths During Natural Circulation EMERGENCY FEEDWATER HEADER 32

Elevation Relationships for Natural Circulation 33

Reflux Cooling 34

HIGH PRESSURE INJECTION SYSTEM 35

CORE FLOOD TANKS 36

LOW PRESSURE INJECTION SYSTEM 37

Phase III 38

Core Load for EPU Normally replace 76 fuel assemblies each refuel outage Will replace 88 for EPU Will be designed with higher enrichment 4.95% uranium enriched 39

REACTOR VESSEL FLOWPATH Current Thot Temp. Current Tcold Temp.

602°F 556°F N

New EPU Thot Temp.

T N New EPU Tcold Temp.

T 609°F 555°F Current Tave Temp.

579°F N

New EPU Tave Temp.

T 582°F 40

STEAM GENERATOR FLOWPATH Currentt OTSG C

Pressure 885 psig EPU OTSG Pressure 915 psig Current Feedwater Fl Flow per OTSG 5.4 Mlb/hr EPU Feedwater Flow per OTSG 6.4 Mlb Mlb/hr

/hr OTSG Adjustable Orifice Plate 41

Emergency E mergency Feedwater System S

42

Emergency Feedwater System For EPU Conditions:

Additional system modifications are necessary for successful mitigation of Design Basis Accidents Changeg EFW flow requirements q from:

550 GPM within 60 seconds after actuation to 660 GPM within 40 seconds after actuation 43

EFW changes for EPU Install new safety related recirculation isolation EFV-33 EFV-57 valves for EFP-2 and EFP-3 EFV EFV-146 Recirculation isolation EFP--3 EFP EFV-14 EFV-58 valves CLOSE when the A OTSG flow to the SG exceeds the EFV-7 EFV-13 minimum recirculation flow EFV-12 B OTSG requirements EFV-11 EFV-56 Closure will stop the EFV-8 recirculation flow normally EFP--2 EFP aligned to the EFT EFV-32 EFV-55 R di t allll EFW to Redirects t the th SGs SG 44

ADV/Fast Cooldown System 45

Fast Cooldown System (FCS)

Provides additional core Inventory/cooling Backup for a single HPI train failure Depressurizes the RCS Improve ECCS flow into the core Allows partial injection of the core flood tank into the RCS Fast Cooldown System will depressurize the secondary side of the OTSGs to maintain < 350 psig Remove the stored heat from the OTSGs preventing them from becoming a heat source 46

Fast Cooldown System (FCS)

Fast Cooldown System will maintain acceptable peak clad temperatures (PCTs) and ultimately reduces PCT and time at elevated PCT SBLOCA demonstrated to be well below 10 CFR 50.67 dose limits All aspects of FCS must be independent of HPI 47

Fast Cooldown System (FCS)

FCS subsystem components New Atmosphere Dump valves (ADVs)

Separate instruments and controllers from normal ADV control Backup air supply DC electrical supply system Two battery banks per train, each 100% capacity Allows maintenance/testing without LCO All FCS components are train separated, safety related, seismic and EQ qualified 48

Simplified FCS Actuation Circuit ISCM/HPI Relays A 3 FCS Switch Position FCS DC POWER B 2 R1 R1 seal in VBDP A TRAIN R1 BATTERY 4 - 20 ma EFIC A A ADV MS-106

-PT R1 FCS Train A Actuated 4 - 20 ma Switch Position NEW NEW Auto

1) BYP - open Bypass Actuate PT-122 CONTROLLER 2) AUTO - closed

3) ACT - closed Currently 3 position Manual and Maintains contact FCS

- same power as DC POWER R1 relay 49

Fast Cooldown System Controls Automatic Actuation Reactor Trip confirmed AND Inadequate SCM AND Less than adequate HPI flow THEN automatically actuates FCS within 10 minutes Actuation comes from new Inadequate q Core Cooling g

Mitigation System (ICCMS)

Automatic actions can be manually actuated from M i C Main Control t lB Board d FCS not required once sufficient flow from HPI pumps established to remove core decay heat 50

Safety Parameter Display System (SPDS)

( )

51

SPDS Monitor for Subcooling Margin 52

SPDS Monitor and Display for ISCM 53

SPDS Display with Adequate SCM and HPI flow Margin

+20°SCM EFW FLOW 0 GPM HPI FLOW 400 GPM UNACCEPTABLE ACCEPTABLE UNACCEPTABLE REGION ACCEPTABLEREGION REGION REGION 0 200 300 400 500 600 700 800 900 1000 2167 917 564 602 54

SPDS Display with Inadequate HPI flow Margin

- 12°SCM EFW FLOW 325 GPM HPI FLOW 300 GPM UNACCEPTABLE ACCEPTABLE UNACCEPTABLE REGION ACCEPTABLEREGION REGION REGION 0 200 300 400 500 600 700 800 900 1000 1535 1025 610 612 Inadequate HPI Flow 04:26 55

Inadequate q Core Cooling Mitigation System (ICCMS) 56

ICCMS Functions Provides Post Accident Monitoring Indication Subcooling Margin HPI flow margin Two trains Safety related Class 1E Complies with RG 1.97 requirements 57

ICCMS Functions Automatic RCP trip signal within 1 minute following Loss of SCM Automatic selection of EFIC ISCM level setpoint within 10 minutes following Loss of SCM Eliminates two currently licensed manual operator actions Automatic Actuation Reactor Trip confirmed AND Inadequate SCM Automatic actions can be manually actuated from Main Control Board 58

ICCMS Functions A t Automatically ti ll actuates t t FCS within ithi 10 minutes i t Automatic Actuation R

Reactor t Trip T i confirmed fi d AND Inadequate q SCM AND Less than adequate HPI flow C be manually actuated ffrom Main Control Can C Board 59

Inadequate Core Cooling Mitigation The system is used to mitigate the consequences of a range of small break LOCAs with a protection system similar to the Engineered Safeguards system Three (3) channel arrangement with independent analog g input p signals g to each channel with a 2 out of 3 logic scheme to actuate Adding an additional channel of sensing devices for third channel CRD Breaker position RCS pressure Incores HPI flow 60

High Pressure Injection System 61

HIGH PRESSURE INJECTION SYSTEM 62

High Pressure Injection System Ensures FCS actuates only when necessary Provides additional margin between single and dual HPI pump flows Increases HPI flow to core for many SBLOCA events 63

Low Pressure Injection System C

Cross-Cross -Tie Ti 64

DHV-69 DHV-70 DHV-6 DHV-111 DHV-11 DHV-12 A CFT DHV-2 CFV-1 DHV-10 DHV-7 DHV-9 MAKEUP SF PREFILTERS RX DHV-211 DHV 211 BORATED O WATER STORAGE TANK DHV-8 DHV-210 CFV-3 DHV-1 DHV-105 DHV-106 B CFT DHV-5 DHV-110 B HOT LEG DHHE-1A DHHE-1B PZR MUPs DHV-91 SPRAY DHV-3 DHV 3 DHV-34 DHV-35 DHV-4 DHV-41 DHP-1A DHP-1B DHV-42 DHV-21 DHV-32 BSPs DHV-39 DHV-75 MAKEUP SF POST FILTERS RB SUMP DHV-40 DHV-76 DHV-43 65 ES Actuation

B CF Line Break, B Train Fails DHV-69 DHV-70 DHV-6 DHV-111 DHV-11 DHV-12 A CFT DHV-2 CFV-1 DHV-10 DHV-7 DHV-9 MAKEUP SF PREFILTERS BORATED WATER RX DHV-211 DHV 211 STORAGE TANK DHV-8 DHV-210 CFV-3 DHV-1 DHV-105 DHV-106 B CFT DHV-5 DHV-110 B HOT LEG DHHE-1A DHHE-1B PZR MUPs DHV-91 SPRAY DHV-3 DHV 3 DHV-34 DHV-35 DHV-4 DHV-41 DHP-1A DHP-1B DHV-42 DHV-21 DHV-32 BSPs DHV-39 DHV-75 MAKEUP SF POST FILTERS RB SUMP DHV-40 DHV-76 DHV-43 66 ES Actuation

LPI System Cross- Cross-tie Modifications DHV-69 DHV-70 DHV-6 DHV-111 DHV-11 DHV-12 A CFT DHV-2 600 DHV-10 CFV-1 601 DHV-7 DHV48 DHV--9 DHV MAKEUP SF PREFILTERS BORATED WATER RX DHV STORAGE TANK 610 DHV-8 DHV-211 DHV-DHV-501 510 DHV-210 CFV-3 DHV-1 DHV-105 DHV-106 B CFT 500 DHV-5 DHV-110 B HOT LEG DHHE-1A DHHE-1B PZR MUPs DHV-91 SPRAY DHV-3 DHV 3 DHV-34 DHV-35 DHV-4 DHV-41 DHP-1A DHP-1B DHV-42 DHV-21 DHV-32 BSPs DHV-39 DHV-75 MAKEUP SF POST FILTERS RB SUMP DHV-40 DHV-76 DHV-43 67

Low Pressure Injection System Cross--Tie Cross Similar to other B&W fleet designs I

Improves safety f t margin i for f Core C Flood Fl d line li bbreaks k

Totally passive system No operator action required 68

Boron Precipitation 69

Boron Precipitation 139 FT 6 IN 11 FT 6 IN 129 FT 6 IN C

L 128 FT COLD HOT LEG LEG 124 FT 7 IN TOP OF High Pressure FUEL DHR Drop-Line filled from Injection Line Boron Precipitation Line 104 FT 70

Hot Leg Injection (Boron Precipitation Line) DHV-69 DHV-70 DHV-6 DHV-111 DHV-11 DHV-12 A CFT DHV-2 600 DHV-10 CFV-1 601 DHV-7 514 DHV-48 DHV-9 SF DHV-610 DHV 610 BORATED O WATER RX STORAGE TANK 614 DHV-8 611 DHV-510 501 612 CFV-3 DHV-1 500 B CFT DHV-5 DHV-110 615 DHHE-1A DHHE-1B PZR MUPs B HOT LEG DHV-91 SPRAY DHV-3 DHV 3 DHV-34 DHV-35 DHV-4 DHV-41 DHP-1A DHP-1B DHV-42 BSPs DHV-39 SF RB SUMP DHV-40 DHV-43 71

Hot Leg Injection (Boron Precipitation Line)

Improvement over current license conditions Reduces Operator burden and reduces complexity to implement Single failure proof 72

EPU LAR FOCUS AREAS SPENT FUEL POOL CRITICALITY RS-001 does not require addressing subject if fuel design is not changed to support EPU CR3 EPU does NOT require any change in fuel design CR3 discussed approach with Reactor Systems in late 2009 and again recently EPU LAR will include ITS changes to require refueling refueling boron concentration concentration at all times Separate, later LAR will reduce this excessive conservatism by fully addressing EPU impacts and operational considerations 73

EPU LAR FOCUS AREAS EQ analysis complete New Pressure,, Temperature p and Dose Profiles Generated Compared p to current qqualification p profiles No modifications required BOP piping i i evaluation l ti complete l t Hydraulic loading evaluation of Turbine Stop V l closure Valve l completed l t d Resultant loads included in LAR Required support upgrades fully scoped 74

EPU LAR FOCUS AREAS Vibration Monitoring Installing extensive vibration monitoring equipment Developing robust program Testing Pre- and Post EPU Robust Start Start-up up Plans Consistent with ASME OM-S/G 2007 standard Large Transient Testing Worked with AREVA to apply and benchmark Digital Power Train model Thoroughly g y modeled transient response p Proposes limited testing Turbine Trip from <40% RTP R id P Rapid Power T Transitions, iti IIncreases and dDDecreases 75

EPU LAR FOCUS AREAS Concurrent NFPA-NFPA-805 LAR Envisioned as part of NEI Proposed Phase II EPU LAR based on Appendix R PSA Models being merged None presume outcome of the other TSTF 493 Unique q challengeg of applying pp y g to curve based LSSS Utilized appropriate form of Option A Input as found/as left tolerances consistent with curve inputs 76

REQUESTED NRC APPROVALS Fast Cooldown System Design features and applications Alternate means of mitigating boron precipitation Mitigation addressed in License Condition Eliminates need for single failure exemption Boron Credit to mitigate Spent Fuel Pool Criticality 77

REQUESTED NRC APPROVALS Several Related ITS Changes ADV/FCS ICCMS Post-Accident Monitoring g Table Lowered DEI Increased Shutdown Margin Spent Fuel Pool Boron Credit 78

CONCLUSION EPU LAR Submittal May/June 2011 Amendment Issuance December 2012 79