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

AGENDA AGENDA Introduction/Purpose Jon Franke Power Uprate Mod Overview Ted Williams B&W NSSS Design Features Dave Porter g

Key EPU Modifications Dave Porter EPU LAR Focus Areas Ken Wilson EPU LAR Focus Areas Ken Wilson Conclusion/Q&A Jon Franke 2

INTRODUCTIONS INTRODUCTIONS Jon Franke Site VP T d Willi EPU E i

i Ted Williams EPU Engineering Dave Porter Operations Support Ken Wilson Project Licensing Larry Sexton EPU Eng/LAR PM Dan Westcott CR3 Licensing Lewis Wells Safety Analysis Lewis Wells Safety Analysis Bob Muzzi EPU Engineering 3

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

NSSS Design Briefly describe key of the CR3 EPU difi ti modifications 4

CR3 EPU Project Philosophy 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 CR3 EPU Project Philosophy Utilized recently approved methodology for reactivity insertion (rod ejection) y

(

j

)

Improved accident mitigation capability through physical plant changes g

y g

Reduced operator burden Utilized previously approved Alternate Source Utilized previously approved Alternate Source Term 6

Phased Approach Phased Approach Phase I Phase I -- MUR MUR LEFM 1.6%

15R, (2007)

, (

)

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

Phased Approach Phased Approach Phase III Phase III Replace many additional secondary side p

y y

components Modify Emergency Core Cooling systems Reactor power increased by 15.5%

NRC license amendment required

CR3 EPU LAR Philosophy CR3 EPU LAR Philosophy FORMAT 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

l i

fl t

t d SE t

t Conclusion reflects expected SE content Includes appendices detailing key conceptual designs designs 9

Phase I Phase I Phase I Phase I Refuel 15 (MUR)

Refuel 15 (MUR)

Refuel 15 (MUR)

Refuel 15 (MUR)

Phase II Phase II Phase II Phase II

PLANT MODIFICATIONS PLANT MODIFICATIONS Phase II Phase II - Turbine Plant Efficiencies Turbine Plant Efficiencies

Turbine Bypass Valves Replacement

Moisture Separator Reheater (MSR)

Replacement Phase II Phase II Turbine Plant Efficiencies Turbine Plant Efficiencies 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

Isophase Bus Duct Cooler

Condensate Heat Exchangers

Secondary Services Closed Cycle System Heat Exchangers

Secondary Cooling Pumps and Impellers

Fiber Optic Backbone

Fiber Optic Backbone

ICS rescaling

16

17

18

19

20

21

EPU Phase III ECs EPU Phase III ECs Total of 30 Engineering Changes Focus on 6 ECs EC 70732 EC 70732 Emergency Feedwater System Upgrades EC 71855 Atmospheric D mp Val es/Fast Cooldo n S stem Atmospheric Dump Valves/Fast Cooldown System 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 HPI Modifications 24

B&W NSSS B&W NSSS Design Features Design Features g

25

REACTOR COOLANT SYSTEM FLOWPATH REACTOR COOLANT SYSTEM FLOWPATH 26

REACTOR COOLANT INLET REACTOR COOLANT INLET CO CO REACTOR VESSEL REACTOR VESSEL CORE CORE FLOOD FLOOD LINE LINE 14 28 28 28 Cold Leg 28 Cold Leg 36 Hot Leg 36 Hot Leg REVERSE FLOW RESTRICTOR REACTOR REACTOR REACTOR REACTOR COOLANT COOLANT OUTLET OUTLET COOLANT COOLANT OUTLET OUTLET CORE CORE 14 28 Cold Leg 28 Cold Leg CORE CORE FLOOD FLOOD LINE LINE REACTOR COOLANT INLET REACTOR COOLANT INLET 27

139 FT 6 IN REACTOR VESSEL REACTOR VESSEL 11 FT 6 IN CL COLD COLD 129 FT 6 IN 128 FT HOT LEG HOT LEG DHR LEG LEG 124 FT 7 IN TOP OF DHR Drop-Line FUEL High Pressure Injection Line 104 FT 28

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

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

Feedwater and Emergency FW Feedwater and Emergency FW System Flow System Flow Paths Paths 31

Flow Paths During Natural Circulation Flow Paths During Natural Circulation EMERGENCY EMERGENCY FEEDWATER FEEDWATER FEEDWATER FEEDWATER HEADER HEADER 32

Elevation Relationships Elevation Relationships for for Natural Circulation Natural Circulation Natural Circulation Natural Circulation 33

Reflux Cooling Reflux Cooling 34

HIGH PRESSURE INJECTION SYSTEM HIGH PRESSURE INJECTION SYSTEM 35

CORE FLOOD TANKS CORE FLOOD TANKS 36

LOW PRESSURE INJECTION SYSTEM LOW PRESSURE INJECTION SYSTEM 37

Phase III Phase III Phase III Phase III 38

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

REACTOR VESSEL FLOWPATH REACTOR VESSEL FLOWPATH Current Thot Temp.

602°F Current Tcold Temp.

556°F N

EPU T T

N EPU T T

New EPU Thot Temp.

609 609°F New EPU Tcold Temp.

555 555°F Current Tave Temp.

579°F N

EPU T T

New EPU Tave Temp.

582 582°F 40

STEAM GENERATOR FLOWPATH STEAM GENERATOR FLOWPATH C

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

/hr OTSG Adjustable Orifice Plate 41

Emergency Emergency S

Feedwater Feedwater System System 42

Emergency Feedwater System Emergency Feedwater System For EPU Conditions:

For EPU Conditions:

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

g q

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

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

ll EFW t th SG EFV-32 EFV-8 EFP EFP--2 EFV-55 Redirects all EFW to the SGs 44

ADV/Fast ADV/Fast Cooldown Cooldown System System 45

Fast Cooldown System Fast Cooldown System (FCS)

(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 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 Fast Cooldown System (FCS)

(FCS)

Fast Cooldown System will maintain acceptable peak clad temperatures (PCTs) and ultimately reduces PCT and time at elevated 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)

Fast Cooldown System (FCS)

FCS subsystem components FCS subsystem components New Atmosphere Dump valves (ADVs)

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 Simplified FCS Actuation Circuit ISCM/HPI ISCM/HPI Relays Relays 3

A R1 R1 FCS DC POWER Relays Relays R1 seal in R1 seal in 3

2 A

B FCS Switch FCS Switch Position Position ADV ADV EFIC A EFIC A R1 R1 BATTERY VBDP A TRAIN 4 - 20 ma R1 seal in R1 seal in ADV ADV EFIC A EFIC A MS-106

-PT Auto Auto R1 R1 NEW NEW NEW NEW 4 - 20 ma FCS Train A Actuated Switch Position Auto Auto Bypass Actuate Bypass Actuate NEW NEW CONTROLLER CONTROLLER NEW NEW PT-122 Currently 3 position Manual and Maintains contact

1) BYP - open

2) AUTO - closed

3) ACT - closed

- same power as R1 relay FCS DC POWER contact 49

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

g Mitigation System (ICCMS)

Automatic actions can be manually actuated from M i C

t l B d

Main Control Board FCS not required once sufficient flow from HPI pumps established to remove core decay heat pumps established to remove core decay heat 50

Safety Parameter Safety Parameter Display System Display System (SPDS)

(SPDS)

(

)

(

)

51

SPDS Monitor for Subcooling Margin SPDS Monitor for Subcooling Margin 52

SPDS Monitor and Display for ISCM SPDS Monitor and Display for ISCM 53

SPDS Display with Adequate SCM SPDS Display with Adequate SCM and HPI flow Margin and HPI flow Margin HPI FLOW 400 GPM EFW FLOW 0 GPM

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

SPDS Display with Inadequate HPI flow Margin SPDS Display with Inadequate HPI flow Margin 12°SCM HPI FLOW 300 GPM EFW FLOW 325 GPM

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

Inadequate Core Inadequate Core q

Cooling Mitigation Cooling Mitigation System (ICCMS)

System (ICCMS) 56

ICCMS Functions ICCMS Functions Provides Post Accident Monitoring Indication Provides Post Accident Monitoring Indication

Subcooling Margin

Subcooling Margin

HPI flow margin Two trains Two trains Safety related Class 1E Class 1E Complies with RG 1.97 requirements 57

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

ICCMS Functions ICCMS Functions A t ti ll t

t FCS ithi 10 i

t ithi 10 i

t Automatically actuates FCS within 10 minutes within 10 minutes Automatic Actuation R

t T i fi d

Reactor Trip confirmed AND

Inadequate SCM q

AND

Less than adequate HPI flow C

f C

Can be manually actuated from Main Control Board 59

Inadequate Core Cooling Mitigation 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 system similar to the Engineered Safeguards system Three (3) channel arrangement with independent analog input signals to each channel with a 2 out of 3 g

p g

logic scheme to actuate

Adding an additional channel of sensing devices for third channel third channel CRD Breaker position RCS pressure Incores HPI flow 60

High Pressure High Pressure Injection System Injection System 61

HIGH PRESSURE INJECTION SYSTEM HIGH PRESSURE INJECTION SYSTEM 62

High Pressure Injection System High Pressure Injection System Ensures FCS actuates only when necessary

Provides additional margin between single and dual HPI pump flows HPI pump flows Increases HPI flow to core for many SBLOCA events 63

Low Pressure Low Pressure Low Pressure Low Pressure Injection System Injection System Injection System Injection System C

Ti Ti Cross Cross--Tie Tie 64

A CFT DHV-2 DHV-6 DHV-111 DHV-11 DHV-12 DHV-69 DHV-70 CFV-1 SF DHV-7 DHV-10 DHV-9 MAKEUP PREFILTERS DHV-211 RX RX BORATED WATER CFV-3 DHV-1 DHV-8 DHV-210 DHV 211 DHV-105 DHV-106 RX RX O

STORAGE TANK B CFT B HOT LEG DHV-3 PZR SPRAY DHV-91 DHHE-1A DHV-110 DHV-5 DHHE-1B MUPs DHV 3 DHV-4 DHP-1A DHV-41 DHP-1B DHV-34 DHV-35 DHV-42 DHV-39 SF DHV-75 DHV-21 MAKEUP POST FILTERS DHV-32 BSPs DHV-43 RB SUMP DHV-40 DHV-76 POST FILTERS ES Actuation ES Actuation 65

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

DHV-69 DHV-70 A CFT DHV-6 DHV-111 DHV-11 DHV-12 LPI System Cross LPI System Cross--tie Modifications tie Modifications DHV-2 SF DHV-7 DHV-10 DHV DHV--9 MAKEUP PREFILTERS RX RX 601 601 BORATED WATER 600 600 CFV-1 DHV48 DHV48 DHV-8 DHV-105 DHV-106 RX RX 501 501 DHV DHV--

510 510 DHV DHV 610 610 STORAGE TANK DHV-210 DHV-211 CFV-3 DHV-1 B CFT B HOT LEG DHV-3 PZR SPRAY DHV-91 DHHE-1A DHV-110 DHV-5 DHHE-1B MUPs 500 500 DHV 3 DHV-4 DHP-1A DHV-41 DHP-1B DHV-34 DHV-35 DHV-42 DHV-39 SF DHV-75 DHV-21 MAKEUP POST FILTERS DHV-32 BSPs DHV-43 RB SUMP DHV-40 DHV-76 POST FILTERS 67

Low Pressure Injection System Low Pressure Injection System Cross Cross-Tie Tie Cross Cross Tie Tie

Similar to other B&W fleet designs I

f t i

f C

Fl d li b

k

Improves safety margin for Core Flood line breaks

Totally passive system

No operator action required

No operator action required 68

Boron Precipitation Boron Precipitation 69

139 FT 6 IN Boron Precipitation Boron Precipitation 11 FT 6 IN CL COLD 129 FT 6 IN 128 FT HOT LEG LEG 124 FT 7 IN TOP OF DHR Drop-Line filled from Boron Precipitation Line FUEL High Pressure Injection Line 104 FT 70

DHV-69 DHV-70 A CFT DHV-2 DHV-6 DHV-111 DHV-11 DHV-12 Hot Leg Injection (Boron Precipitation Line)

Hot Leg Injection (Boron Precipitation Line)

CFV-1 SF DHV-7 DHV-10 DHV-610 BORATED WATER RX RX 601 600 514 DHV-9 DHV-48 CFV-3 DHV-8 DHV-510 DHV 610 O

STORAGE TANK RX RX 501 611 612 614 DHV-1 B CFT B HOT LEG DHV-3 PZR SPRAY DHV-91 DHV-110 DHV-5 MUPs 500 615 DHHE-1A DHHE-1B DHV 3 DHV-4 DHP-1A DHV-41 DHP-1B DHV-34 DHV-35 DHV-42 DHV-39 SF BSPs DHV-43 RB SUMP DHV-40 71

Hot Leg Injection Hot Leg Injection (Boron Precipitation Line)

(Boron Precipitation Line)

(Boron Precipitation Line)

(Boron Precipitation Line)

Improvement over current license conditions

Reduces Operator burden and reduces complexity to implement

Single failure proof 72

EPU LAR FOCUS AREAS EPU LAR FOCUS AREAS SPENT FUEL POOL CRITICALITY SPENT FUEL POOL CRITICALITY SPENT FUEL POOL CRITICALITY SPENT FUEL POOL CRITICALITY

RS-001 does not require addressing subject if fuel design is not changed to support EPU design is not changed to support EPU

CR3 EPU does NOT require any change in fuel design design

CR3 discussed approach with Reactor Systems in late 2009 and again recently late 2009 and again recently

EPU LAR will include ITS changes to require refueling boron concentration at all times refueling boron concentration at all times

Separate, later LAR will reduce this excessive conservatism by fully addressing EPU impacts and conservatism by fully addressing EPU impacts and operational considerations 73

EPU LAR FOCUS AREAS EPU LAR FOCUS AREAS

EQ analysis complete EQ analysis complete

New Pressure, Temperature and Dose Profiles p

Generated

Compared to current qualification profiles p

q p

No modifications required BOP i i l

ti l t BOP i i l

ti l t

BOP piping evaluation complete BOP piping evaluation complete

Hydraulic loading evaluation of Turbine Stop V l l

l t d Valve closure completed

Resultant loads included in LAR

Required support upgrades fully scoped 74

EPU LAR FOCUS AREAS EPU LAR FOCUS AREAS

Vibration Monitoring Vibration Monitoring

Installing extensive vibration monitoring equipment

Installing extensive vibration monitoring equipment

Developing robust program Testing Pre-and Post EPU Robust Start up Plans Robust Start-up Plans Consistent with ASME OM-S/G 2007 standard

Large Transient Testing Large Transient Testing

Worked with AREVA to apply and benchmark Digital Power Train model

Thoroughly modeled transient response g y p

Proposes limited testing

Turbine Trip from <40% RTP R

id P T

iti I

d D

Rapid Power Transitions, Increases and Decreases 75

EPU LAR FOCUS AREAS EPU LAR FOCUS AREAS Concurrent NFPA Concurrent NFPA--805 LAR 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 TSTF 493 Unique challenge of applying to curve based LSSS q

g pp y g Utilized appropriate form of Option A Input as found/as left tolerances consistent with curve Input as found/as left tolerances consistent with curve inputs 76

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

REQUESTED NRC APPROVALS REQUESTED NRC APPROVALS Several Related ITS Changes Several Related ITS Changes

ADV/FCS

ICCMS

Post-Accident Monitoring Table g

Lowered DEI

Increased Shutdown Margin

Spent Fuel Pool Boron Credit 78

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