ANP-3052Revision 0

October 2011

CR-3 EPU Feedwater Line Break.Analysis with Failure of First Safety Grade Trip

AREVA Inc.

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Record of Revision

Revision PageslSectionslParagraphs

No. Changed Brief Description I Change Authorization

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Table of Contents

1.0 Introduction ........................................................................................................................................ 72.0 Analytical Methodology ............................................................................................................. 83.0 Analysis Inputs .................................................................................................................................. 94.0 Results / Conclusions ...................................................................................................... 125.0 References ...................................................................................................................................... 29

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List of Tables

Table 3-1: Input to Feedwater Line Break Analysis with First Trip Failed ............................................ 10Table 4-1: Sequence of Events for FWLB with First Trip Failed .......................................................... 13Table 4-2: Results for FWLB with First Trip Failed ............................................................................... 13

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List of Figures

Figure 4-1: FWLB with Fail First Trip - RCS Pressure ............................................................... 14Figure 4-2: FWLB with Fail First Trip - Reactor Power ........................................................................ 15Figure 4-3: FW LB with Fail First Trip - Reactivity ................................................................................ 16Figure 4-4: FWLB with Fail First Trip - Primary System Temperatures ............. ...................... 17Figure 4-5: FWLB with Fail First Trip - Indicated Pressurizer Level ...................................................... 18Figure 4-6: FWLB with Fail First Trip - Pressurizer Collapsed Liquid Level ......................................... 19Figure 4-7: FWLB with Fail First Trip - Pressurizer Surge Line Flow ...................................... 20Figure 4-8: FWLB with Fail First Trip - RCS Volumetric Flow Rate ............................................. 21Figure 4-9: FWLB with Fail First Trip - Pressurizer Safety Valve Flow ....................... 22Figure 4-10: FWLB with Fail First Trip - SG Secondary Side Liquid Level ................................. 23Figure 4-11: FWLB with Fail First Trip - SG Secondary Side Inventory ........................... 24Figure 4-12: FWLB with Fail First Trip - SG % Operating Range ............................................. 25Figure 4-13: FWLB with Fail First Trip - SG Pressure .................... ................................. 26Figure 4-14: FWLB with Fail First Trip - EFW Flow ..................... ................................... 27Figure 4-15: FWLB with Fail First Trip - Integrated MSSV Flow .......................................... 28

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ANP-3052Revision 0

Nomenclature

Acronym Definition

CR-3 Crystal River Unit 3

DSS Diverse Scram System

EFIC Emergency Feedwater Initiation and Control

EFW Emergency Feedwater

EPU Extended Power Uprate

FWLB Feedwater Line Break

LAR Licensing Amendment Request

LOOP Loss of Offsite Power

MFW Main Feedwater

MSSV Main Steam Safety Valves

NRC Nuclear Regulatory Commission

PORV Pilot Operated Relief Valve

PSV Pressurizer Safety Valve

RCP Reactor Coolant Pump

RCPB Reactor Coolant Pressure Boundary

RCS Reactor Coolant System

RPS Reactor Protection System

SG Steam Generator

TSV Turbine Stop Valves

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1.0 INTRODUCTION

The Nuclear Regulatory Commission (NRC) Reactor Systems Branch staff requested an additionalanalysis be performed to support the review of the Crystal River Unit 3 (CR-3) extended power uprate(EPU) licensing amendment request (LAR). In particular, the staff requested an analysis of the feedwaterline break (FWLB) transient assuming that the first safety grade reactor protection system (RPS) tripfunction fails to trip the reactor. This report documents the results of the requested analysis.

The analysis documented in this report assumes that the RPS high reactor coolant system (RCS)pressure trip function fails to trip the reactor. This analysis models the non-safety grade diverse scramsystem (DSS) trip, which inserts the regulating control rod banks upon reaching the DSS high RCSpressure trip setpoint. The peak RCS pressure during the FWLB transient is reported and compared toan acceptance criterion of 120% of the reactor coolant pressure boundary (RCPB) design pressure (1.20* 2500 = 3000 psig).

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2.0 ANALYTICAL METHODOLOGY

The thermal-hydraulic analysis of the FWLB analyses at the CR-3 EPU power level with the first safetygrade trip failed is performed using the RELAP5/MOD2-B&W computer program (Reference [1]). Thecode simulates RCS and secondary system operation. The reactor Core model is based on a pointkinetics solution with reactivity feedback for control rod assembly insertion, fuel temperature changes,moderator temperature changes, and changes in boron concentration. The RCS model provides for heattransfer from the core, transport of the coolant to the steam generators (SG), and heat transfer to thesteam generators. The secondary model includes a detailed depiction of the main steam system,including steam relief to the atmosphere through the main steam safety valves (MSSVs) and simulation ofthe turbine stop valves (TSVs). The secondary model also includes the delivery of feedwater, both mainand emergency, to the steam generators.

The RELAP5/MOD2-B&W code has been approved by the NRC for use in non-LOCA safety analyses(Reference [2]). The analysis documented in this report is consistent with Reference [2] except that thefirst safety grade trip is not credited. Instead, this analysis credits the next available trip, which is thenon-safety grade DSS trip on high RCS pressure.

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3.0 ANALYSIS INPUTS

The FWLB analysis with the first safety grade trip failed uses input that is consistent with the FWLBanalysis without pressurizer spray performed to support Section 2.8.5.2.4 of the CR-3 EPU LAR, with afew notable exceptions. The changes include:

1. The RPS high RCS pressure trip function is disabled.

2. The DSS high RCS pressure trip function is modeled. The DSS trip setpoint is modeled as 2465psia. The DSS high RCS pressure trip setpoint includes margin to bound possible changes in thecontainment pressure during a FWLB. The DSS trip delay time is modeled as 1.23 seconds.Finally, the rod worth available to the DSS system is modeled as only 2.0 %Ak/k, since the DSSsystem only inserts the regulating control rod groups.

Table 3-1 summarizes all of the key input to the FWLB analysis with the first safety grade trip failed,including the changes highlighted above.

The peak RCS pressure is reached shortly after reactor trip before any active components such asemergency feedwater (EFW) are credited to mitigate the results. Therefore, there are no single failureassumptions that would result in a more limiting peak RCS pressure. However, the FWLB overpressureprotection analysis with the first safety grade trip failed assumes the same single failure assumption asthe FWLB analysis performed to support Section 2.8.5.2.4 of the CR-3 EPU LAR. The single failureassumption modeled is the failure of one train, of Emergency Feedwater Initiation and Control (EFIC) suchthat EFW flow is not initiated automatically in one train. Consequently, only one of the two EFW pumps isassumed available to provide flow to the SGs. This single failure assumption produces a conservativelong-term transient response after EFW is assumed to reach the SGs.

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Table 3-1: Input to Feedwater Line Break Analysis with First Trip Failed

Parameter Value

RCS Conditions

Core Power, MWt 3014 * 1.004 = 3026.1

Decay Heat 1.0*ANS71 plus B&W Actinides

Total Net Reactor Coolant Pump (RCP) Heat, MWt 16.4

Average RCS Temperature, °F 582

Initial Hot Leg Pressure, psia 2170

Total RCS Flow Rate, gpm 374,880

Pressurizer

Initial Indicated Pressurizer Level, in 240

Pressurizer Spray Not Modeled

Pressurizer Heaters Not Modeled

Pilot Operated Relief Valve (PORV) Not Modeled

Pressurizer Safety Valve (PSV) Setpoints, psig 2500 * (1 + 0.03) (open)2500 * (1 - 0.04) (close)

Total PSV Rated Capacity, Ibm/hr 2 * 317,973 @ 2750 psig

Secondary Side

Initial Main Feedwater (MFW) Temperature, OF 460 OF

Tube Plugging, % 5

Initial SG Level, %OR < 70

EFW Temperature, OF 120

EFW Minimum Required Flow, gpm 550

EFW Delay Time, sec 60

Turbine Trip Delay Time, s 0.0

TSV Stroke Time, s 0.2

Number of Main Steam Safety Valves (MSSVs) per SG 8

MSSV Capacity per SG 7 @ 845,759 Ibm/hr1 @ 583,574 Ibm/hr

MSSV Nominal Setpoints 2 @ 1050 psig2 @ 1070 psig2 @ 1090 psig

2 @ 1100 psig including small MSSV

MSSV Setpoint Tolerance +3%

MSSV Accumulation +3%

MSSV Blowdown -5%

Core Kinetics Parameters

Doppler Temperature Coefficient (Ak/k/°F) -1.30 E-5

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Parameter Value

Moderator Temperature Coefficient (Ak/°kIF) 0.0 E-4

Prompt Neutron Generation Time, (ps) 24.8

Effective Delayed Neutron Fraction 0.0070

DSS Insertable Rod Worth, %Ak/k 2.000

RPS High RCS Pressure Trip Assumed Failed

DSS High RCS Pressure Trip Setpoint, psia 2465

DSS Trip Delay Time, s 1.23

Miscellaneous

Offsite Power Available

Single Failures One Train of EFIC

Operator Actions None

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4.0 RESULTS I CONCLUSIONS

The sequence of events for the FWLB accident with the first safety grade trip failed is listed in Table 4-1and the calculated results are tabulated in Table 4-2. Plots that demonstrate the transient responsefollowing a FWLB are provided in Figures 4-1 through 4-15.

The transient progression is similar to the FWLB transient described in Section 2.8.5.2.4 of the CR-3 EPULAR. The trip setpoint is reached at 9.025 seconds instead of 8.802 seconds because the DSS high RCSpressure setpoint is higher than the RPS high RCS pressure setpoint. In addition, because the delay timemodeled for the DSS trip is longer than the delay time associated with the RPS, control rod insertion doesnot begin until 10.258 seconds compared to 9.415 seconds in the FWLB analysis in LAR Section2.8.5.2.4. The longer time to reactor trip contributes to a higher peak RCS pressure. The peak RCSpressure is also higher for the analysis with the first safety grade trip failed because DSS only inserts theregulating control rod banks, and therefore has less inserted rod worth than the analysis modeling theRPS trip function.

The peak RCS pressure (2950.9 psia) occurred in the lower downcomer region of the reactor vessel anddid not exceed 120% of the RCPB design pressure of 2500 psig (3000 psig).

As explained in Section 2.8.5.2.4 of the CR-3 EPU LAR, the FWLB event is sufficiently severe that thepressurizer fills., As a result, the PSVs begin to pass single-phase liquid. The PSVs of the type installedat CR-3 achieve satisfactory performance for fluid temperatures greater than -550'F. An additionalcheck is performed to show that the PSV fluid inlet temperature remains greater than 600 OF to ensurethat the PSVs operate as intended. Figure 4-4 demonstrates that at all times throughout the FWLBtransient, the liquid temperature at the top of the pressurizer remains above 600 OF.

A sensitivity study was performed modeling the FWLB transient with the first safety grade trip failed and aloss of offsite power (LOOP). The LOOP is conservatively considered to occur coincident with the turbinetrip that follows reactor trip. The case with a LOOP included the insertion of the safety control rod bankson LOOP. The sensitivity study determined that the peak RCS pressure from a LOOP case (2921.9 psia)is less limiting than the peak RCS pressure without a LOOP. Therefore, the FWLB evaluation using theDSS trip function and no LOOP is the bounding case.

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Table 4-1: Sequence of Events for FWLB with First Trip Failed

Parameter Time, sec

Transient Initiated 0.0

MFW to both SGs Interrupted 1.OE-6

EFIC Actuated on Low SG-B Level 6.515

Peak Thermal Power Occurs 6.523

DSS High RCS Pressure Trip Setpoint Reached 9.025

Regulating Control Rod Groups Begin to Insert 10.258

Turbine Trip, TSVs Begin to Close 10.260

Initial PSV Lift -12

Peak RCS Pressure occurs 13.518

Affected SG depressurization complete -36

EFW to Unaffected SG Begins 66.520

Final PSV closure -282

Peak Tave occurs -404

Transient Analysis Ends 600

Table 4-2: Results for FWLB with First Trip Failed

Parameter Value

Peak RCS pressure (psia) 2950.9

Peak thermal power (%RTP) 100.49

Peak Tave (OF) 630.54

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Figure 4-1: FWLB with Fail First TripRCS Pressure

3000-- Hot Leg 1 (CV 110-4)-- Hot Leg 2 (CV 210-4)-A Core Exit (CV 352-01)

.... .< Top of PZR (CV 405-01)-v Lower RV Downcomer (CV 324-04)

------------------------------------------------------------------------

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420 480 540 600

Time (s)

I

Figure 4-2: FWLB with Fail First TripReactor Power

3200 --- Total Reactor Power (CVAR 370)-- Thermal Power (CVAR 379)

24 0 -.-------........................ I -------------------- .... ........--..... .....--............................. ---------- ------------------ -------- -----------.... r ------------------

20------------------

I 10- - - - - - - - - - - --------- ---------------- --

800

0 60 120 180 240 300 360 420 480 540 600Time (s)

_2

Figure 4-3: FWLB with Fail First TripReactivity

0

0.010

0.000

-0.010

-0.020

-0.030

-0.040

-0.050

CDo ýS0

0 300Time (s)

3

Figure 4-4: FWLB with Fail First TripPrimary System Temperatures

720-- RCS Ave Temp (CVAR 900)-o Loop 1 Hot Leg (CV 110-4)

Loop 2 Hot Leg (CV 210-4)700......... - Loop IA Cold Leg (CV 160-4)7v Loop 1 B Cold Leg (CV 180-4)

Loop 2A Cold Leg (CV 260-4)-+ Loop 2B Cold Leg (CV 280-4)

680 .................. - x Top of Pressurizer Liquid Temperature (CV 405) ------------------660 --- ..... ... ...........

S 6 6 0 -- ........ ......-- ---- --- .... ... ... ....-- ... ... .... ....--... ... ... ... ..- ................... I ------------------- -- ----- ----------------------

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0 W520 = 00 60 120 180 240 300 360 420 480 540 600 0 to

Time (s)

_4

Figure 4-5: FWLB with -Fail First TripIndicated Pressurizer Level

400

380

360

340

320

300

• 280

260

240

220

200

............

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Figure 4-5: FWLB with.Fail

First

Trip

Indicated Pressurizer

Level

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Time (s)360 420 480 540 600

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Figure 4-6: FWLB with Fail First TripPressurizer Collapsed Liquid Level

-o

44

42

40

38

36

34

32

30

28

26

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oLAt"00 60 120 180 240 300

Time (s)360 420 480 540 600

_6

Figure 4-7: FWLB with Fail First TripPressurizer Surge Line Flow

500

250

C

-250

-500

-750

--------

------ -- - -- -

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-1000

-1250

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t0

-15000 60 120 180 240 300

Time (s)360 420 480 540 600

_7

Figure 4-8: FWLB with Fail First TripRCS Volumetric Flow Rate

- aCVAR 332R400000

350000

300000

.................. -------

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250000

0 200000

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1500001 .

100000 1. .................

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50000

0

ýo ý0 0j

0 60 120 180 240 300Time (s)

360 420 480 540 600

8

Figure 4-9: FWLB with Fail First TripPressurizer Safety Valve Flow

500

450

400

350

Figure 4-9: FWLB with .Fail First TripPressurizer

Safety Valve Flow

...............

................

................

0

300

250

200

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150

100

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50 .-----

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0 0-0-------------- -

120 180 240 360 420 480 540

Time (s)

_9

Figure 4-10: FWLB with Fail First TripSG Secondary Side Liquid Level

12 - q 9

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0 60 120 180 240 3T0Time (s) 360 600

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Figure 4-11: FWLB with Fail First TripSG Secondary Side Inventory, Ibm

80000 I

70000 1 ------------- ----------- ............ ------

------------------ -------------------

--- SG-A (CVAR 607)-o SG-B (CVAR 707)

60000 1-

S

0

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0

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20000 --- ------------- ---

10000 ......

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0 00 180 240 300Time (s)

360 420 480 540 600

11

Figure 4-12: FWLB with Fail First TripSG % Operating Range

1oo

90

80

.....................

---------------------

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---------- ........

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C0#

60

50

40

30

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-- SG-A (CVAR 612)-- i SG-B (CVAR 712)

. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . .

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0 60 120 180 240 300Time (s)

360 420 480 540 600

12

Figure 4-13: FWLB with Fail First TripSG Pressure, psia

1200--n Unaffected (CV648-1)-* Affected (CV 748-1)1100 .- "

1000 ---- --- .. ......... - - -- ------....

100 0 --- .----- .------ . -----------. ------- -----------. --------- --------- .------- ........... I .---------- -------.------------ -- .-- .--------------- --- .---------------- --.-----------------

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2 0 o -- . . . . ........- ------- ------- ..... : ----------

400

0 60 1.20 180 240 300 360 420 480 540 600

Time (s)

13

Figure 4-14: FWLB with Fail First TripEFW Flow

I0

100

90

80

70

60

50

40

30

20

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--s To Unaffected SG (JUN 626)--- To Affected SG (JUN 726)

------------

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--- --------10

0 W010

-- jA A R A @ - , - - - 0.0 0 0,0 0-- - 1 0 0 0 0 1ý 0 0-0 0 ý 0 - I.- - 0 0 0 0 0 0 0 0.

P 60 120 180 240 300Time (s)

360 420 480 540 600

-.1

14

Figure 4-15: FWLB with Fail First TripIntegrated MSSV Flow

100000-- Unaffected SG (OVAR 659),-- Affected SG (CVAR 660)

90000------------------------------------------------------------------- ------------------ --------- ..------------------- ------------------

7 0 0 0 0 ------. -. ------. . . . . . . . . . . . . . . . . . . . .. --. ------------------- -------------------- ------------------. --. ---------------. --. ---------------. .................... --.. . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .8 0 0 0 0 - - -- - - - - --

70000 ---- -

36 0 0 0 0 - -- -------------------.- ------------------.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .C

-Er

200050000 --------------- ----- 1 -------------------------

10000

.• o. . o0 60 120 180 240 300 360 420 480 540 600 0

Time (s).t0

15

ANP-3052Revision 0

5.0 REFERENCES

1. BAW-10164PA-06, "RELAP5/MOD2-B&W - An Advanced Computer Program for Light WaterReactor LOCA and Non-LOCA Transient Analysis."

2. BAW-10193PA-00, "RELAP5/MOD2-B&W for Safety Analysis of B&W-Designed PressurizerWater Reactors."

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