ML11286A094
| ML11286A094 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/13/2011 |
| From: | Brownson D, Reza M AREVA |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F1011-05 86-9167251-001 | |
| Download: ML11286A094 (29) | |
Text
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 /LICENSE NUMBER DPR-72 ENCLOSURE 2 AREVA 86-9167251-001 -
SUMMARY
OF CR3 EPU INADVERTENT PRESSURIZER RELIEF VALVE OPENING
0402-01-FO1 (Rev. 016, 03/31/2011)
A CALCULATION
SUMMARY
SHEET (CSS)
AREVA Document No. 86 - 9167251 - 001 Safety Related: N Yes [No Title Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening PURPOSE AND
SUMMARY
OF RESULTS:
This document summarizes the inputs and results of an analysis of the Inadvertent Pressurizer Relief Valve Opening (IPRVO) accident performed for CR-3 at an Extended Power Uprate (EPU) rated thermal power level of 3014 MWt (plus 0.4% heat balance uncertainty). The IPRVO analysis is summarized in Reference [1].
Reference [2] is the analysis input summary document for the IPRVO analysis.
All acceptance criteria for the IPRVO accident are met. The total power increase throughout the transient is <3%.
Thermal power remains less than the 112% of full power for the duration of the event; therefore, fuel cladding integrity is maintained. The peak RCS pressure is not challenged during this event, which is a depressurization event.
THE DOCUMENT CONTAINS ASSUMPTIONS THAT SHALL BE THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: VERIFIED PRIOR TO USE CODENERSION/REV CODENERSION/REV R YES N/A Z NO Page 1 of 28
A AR EVA 0402-01-F01 (Rev. 016, 03/31/2011)
Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening Review Method: M Design Review (Detailed Check)
D] Alternate Calculation Signature Block P/R/A Name and Title and Pages/Sections (printed or typed) Signature LP/LR Date Prepared/Reviewed/Approved Douglas Brownson P All Supervisor, B&W 'A Safety Analysis Mohsin Reza R All Engineer IV 93-2.-1 T' I Keith Higar _.2 A n All - Reviewer Independence Manager Note: P/R/A designates Preparer (P), Reviewer (R), Approver (A);
LP/LR designates Lead Preparer (LP), Lead Reviewer (LR)
Project Manager Approval of Customer References (N/A if not applicable)
Name Title (printed or typed) (printed or typed) Signature Date N/A Mentoring Information (not required per 0402-01)
Name Title Mentor to:
(printed or typed) (printed or typed) (P/R) Signature Date N/A Page 2
A 0402-01-F01 (Rev. 016, 03/31/2011)
AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening Record of Revision Revision Pages/Sections/Paragraphs No. Changed Brief Description / Change Authorization 000 All Initial Release 001 Section 2.0 Removed Figures 2-1 through 2-4 (proprietary issue)
Section 3.1 Removed sentence comparing IPRVO event to an SBLOCA event Section 3.2 Removed sentence regarding availability of HPI. Removed discussion regarding core uncovery aspects of event being bounded by the SBLOCA event.
I- -4 4- -f
- 4. .4
- 4. .4 I. -4 Page 3
A AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening Table of Contents Page SIG NATURE BLOCK ................................................................................................................................ 2 RECO RD O F REVISIO N .......................................................................................................................... 3 LIST O F TABLES ..................................................................................................................................... 5 LIST O F FIG URES ................................................................................................................................... 6 1.0 ASSUM PTIO NS ............................................................................................................................ 7 1.1 Unverified Assumptions ........................................................................................................... 7 1.2 Justified Assumptions ............................................................................................................. 7 1.3 Modeling Simplifications ........................................................................................................... 7 2.0 DESIG N INPUTS .......................................................................................................................... 8 3.0 ANALYSIS SUM MARY ............................................................................................................... 11 3 .1 Ev e nt De sc riptio n ........................................................................................................................... 11 3.2 Applicable Acceptance Criteria .................................................................................................. 11 3 .3 Meth o d o lo g y ................................................................................................................................... 12 3.4 Steady-State Initialization .......................................................................................................... 12 3.5 Transient Analysis .......................................................................................................................... 13
4.0 REFERENCES
............................................................................................................................ 28 Page 4
A AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening List of Tables Page Table 2-1: K ey Input P aram eters ................................................................................................... 8 Table 2-2: Scram C urve > 15% FP ........................................................................................ ..... 10 Table 3-1: Steady-State Verification Results .................................................................................... 12 Page 5
A AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening List of Figures Page Figure 3-1: RCS Pressure ...................................................................................................................... 14 Figure 3-2: Reactor Power ..................................................................................................................... 15 Figure 3-3: Primary System Temperatures ....................................................................................... 16 Figure 3-4: Primary System Flow ........................................................................................................... 17 Figure 3-5: Indicated Pressurizer Level ............................................................................................ 18 Figure 3-6: Core Average Fuel Temperature .................................................................................... 19 Figure 3-7: SG Secondary Side Liquid Level .................................................................................... 20 Figure 3-8: SG Secondary Side Inventory ......................................................................................... 21 Figure 3-9: SG Operating Range ........................................................................................................... 22 F igure 3-10 : R e a ctiv ity ........................................................................................................................... 23 Figure 3-11: Main Feedwater Flow and Main Steam Flow ............................................................... 24 Figure 3-12: Energy Transferred ............................................................................................................ 25 Figure 3-13: Total RCS Flow ................................................................................................................. 26 Figure 3-14: PCSV Flow ........................................................................................................................ 27 Page 6
A AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening 1.0 ASSUMPTIONS 1.1 Unverified Assumptions There are no unverified assumptions associated with the analysis.
1.2 Justified Assumptions There are no justified assumptions associated with the analysis.
1.3 Modeling Simplifications There are no modeling simplifications associated with the analysis.
Page 7
A AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening 2.0 DESIGN INPUTS Reference [2] provides a detailed description of the inputs to the IPRVO analysis. The input is summarized in Table 2-1 of this document.
Table 2-1: Key Input Parameters Parameter Value RCS Conditions Core Power, MWt 3026.1 Decay Heat I.0*ANS71+B&W actinides RCP Power, MWt per pump 4.1 Tave, 'F 582 RCS Pressure, psia 2170 (Note 1)
Total RCS Flow Rate, gpm 374,880 Core Bypass Flow Fraction, % 7.5 Pressurizer Initial Indicated PZR Level, in 220 Number of Pressurizer Code Safety Valves (PCSVs) N/A PCSV Nominal Setpoint, psig N/A PCSV Setpoint Tolerance, % N/A PCSV Blowdown, % N/A PCSV Capacity, lbm/hr/valve 317,973 @ 2750 psig PORV Capacity, lbm/hr/valve The analysis conservatively uses the capacity of a single PCSV in place of the PORV capacity.
Pressurizer Heaters Not Modeled Pressurizer Spray N/A MFW and Steam Generator Tube Plugging MFW Temperature, 'F 460 (Note 2)
MFW Flow, lbm/s per SG (Note 2)
SG Tube Plugging - average % 0 SG Level - operate range, % -70 EFW Flow, gpm per SG N/A Temperature, 'F N/A Page 8
A.
AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening Parameter Value Turbine & Main Steam System Turbine Header Pressure, psia 930 (Note 2)
Turbine Trip Delay Time, seconds 0.0 (at time of reactor trip)
TSV Stroke Time, sec 0.2 MSSV Nominal Setpoint per SG, psig 2 @ 1050 psig (one assumed out of service) 2 @ 1070 psig 2 @ 1090 psig 2 @ 1100 psig (Note 3)
MSSV Capacity per SG, ibm/hr/valve 7 @ 845,759 Ibm/hr at 1169.7 psia 1 @ 583,574 ibm/hr at 1169.7 psia (Note 3)
MSSV Setpoint Tolerance, % +3.0 MSSV Accumulation, % +3.0 MSSV Blowdown, % -5.0 Reactivity Control Moderator Temperature Coefficient, Ak/k/°F +0.75E-04 Doppler Reactivity (Ak/k/0 F) -1.30E-05 Prompt Neutron Generation Time (us) 24.8 Effective Delayed Neutron Fraction 0.0070 Shutdown Margin, %Ak/k 1.000 Scram Curve Table 2-2 Reactor Protection System Low RCS Pressure Setpoint (psia) 1894 (Note 1)
Low RCS Pressure Response Time (s) 0.610 Miscellaneous Offsite Power Available Single Failure None Operator Actions None Credited Notes:
- 1. As measured at the hot leg pressure tap.
- 2. The MFW temperature and flow as well as the turbine header pressure were varied to achieve the desired RCS and SG conditions for the heat load of the event.
- 3. The 1 MSSV per SG that has a capacity of 583,574 Ibm/hr at 1169.7 psia is at a nominal setpoint of 1100 psig.
Page 9
A AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening Table 2-2: Scram Curve > 15%FP Time After Reactivity Reactor Trip Insertion sec %
0.0 0.00 0.2 0.58 0.3 0.99 0.4 1.83 0.6 5.29 0.8 12.33 1.0 21.41 1.2 33.09 1.4 50.75 1.6 72.96 1.8 91.30 2.0 99.26 2.2 99.99 2.3 100.00 Page 10
A' AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening 3.0 ANALYSIS
SUMMARY
3.1 Event Description The inadvertent opening of a primary system pressure relief valve results in a decrease in reactor coolant inventory and Reactor Coolant System (RCS) pressure, since the loss of inventory will be in excess of the capability of the makeup system. The event is initiated by a spurious electrical signal or operator error. This type of initiating event could only occur with the Pilot Operated Relief Valve (PORV). However, the analysis will conservatively model a break flow consistent with a single PCSV, since the PCSV has a larger capacity. The decrease in pressure affects neutron flux via moderator density feedback. For this event, feedback is based on a positive moderator temperature coefficient such that the result of the feedback is an increase in core power. The RCS continues to depressurize until the low RCS pressure RPS setpoint is reached. The resulting insertion of scram reactivity ends the power excursion and negates further challenge to the core Departure from Nucleate Boiling (DNB) limits. For the IPRVO event, it is anticipated that the operator would have ample time to isolate the relief valve prior to any concerns with core uncovery.
3.2 Applicable Acceptance Criteria The IPRVO analyses will demonstrate compliance with the acceptance criteria for the evaluation of this accident.
Per Section 15.6.1 of the Standard Review Plan (SRP) [5], the applicable acceptance criteria for this event are:
- 1) Pressure in the reactor coolant and main steam systems should be maintained below 110 percent of the design values.
- 2) Fuel cladding integrity is maintained if the minimum departure from nucleate boiling ratio (DNBR) remains above the 95/95 DNBR limit.
- 3) An AOO should not develop into a more serious plant condition without other faults occurring independently.
The first acceptance, criterion will not be challenged, since the RCS is depressurizing and the event does not challenge the secondary plant response.
The second criterion will be shown to be met by demonstrating that thermal power remains less than 112% of full power for the duration of the event.
As explained in Section 6.0 of Reference [2], the equivalent break size of a fully opened PCSV is at the lowest end of the spectrum for small break loss-of-coolant accidents (SBLOCA). For the IPRVO event, there is ample time for operator action to isolate the break long before core uncovery is a concern. Therefore, the event will not evolve into a different classification.
Page 1 1
A AREVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening 3.3 Methodology The IPRVO analysis uses the approved methodology in Reference [3]. Where possible, this methodology utilizes the plant design bases to establish acceptance criteria and input boundary conditions. The approved methodology includes the manner for determining the responses of the primary system, the secondary system, and the core to postulated accidents. In addition, the methodology requires the use of conservative setpoints, valve and pump capacities, and reactivity coefficients to demonstrate adequate margin to the applicable limits.
The analysis is performed using the RELAP5/MOD2-B&W computer code. This code has been approved by the NRC for use in non-LOCA safety analyses [3] [4]. The code simulates RCS and secondary system operation. The reactor core model is based on a point kinetics solution with reactivity feedback for control rod assembly insertion, fuel temperature changes, and moderator temperature changes. The RCS model provides for heat transfer from the core, transport of the coolant to the SGs, and heat transfer to the SGs. The secondary model includes a detailed depiction of the main steam system, including steam relief to the atmosphere through the MSSVs, TBVs, and simulation of the TSVs. The secondary model also includes the delivery of feedwater, both main and emergency, to the SGs.
3.4 Steady-State Initialization The analysis in Reference [1] began by creating a steady-state input model that targeted the conditions in Table 2-1. Table 3-1 demonstrates the comparison between the targeted conditions and the conditions achieved by the steady-state input model.
Table 3-1: Steady-State Verification Results Parameter Target Steady-State Value Core Power, MWt 3026.1 3026.1 RCS Tare, -F 582 581.94 RCS Pressure, psia 2170 2169.7 RCS Flow Rate, gpm 374,880 374,866 Core Bypass Flow, % 7.5 7.5030 RCP Heat, MWt 16.4 16.522 PZR Level, in 220 220.22 72.567 (SG A)
SG Level - operate range, % span 70 72.7 (SG B) 72.754 (SG B)
Turbine Header Pressure, psia 930 883.30 With the exception of the turbine header pressure, the parameters are reasonably close to the targeted conditions.
As noted in Section 7.4.1 of Reference [2], the turbine header pressure was adjusted as needed to achieve the targeted Tave, and is therefore acceptable.
Page 12
A AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening 3.5 Transient Analysis The plots associated with the transient are provided in Figures 3-1 through 3-14.
The IPRVO event is initiated by assuming that one PCSV opens suddenly during power operation and remains open during the event. The PCSV Flow Rate reaches 63.2 Ibm/s at t=ls, and decreases slowly to reach 54 Ibm/s before reactor trip due to RCS depressurization. The valve opening causes loss of reactor coolant system (RCS) inventory, rapid RCS depressurization, and decrease in fluid density. Pressurizer heaters are assumed to be off for this event and the RCS pressure continues to decrease, leading to a rapid change in density. RCS flow is maintained by the running reactor coolant pumps (RCPs). The reduction in moderator density causes positive reactivity to be inserted as a result of the positive moderator temperature coefficient. Consequently, the core power increases. As the depressurization continues, the Reactor Protection System (RPS) automatically functions at 45 seconds, causing a reactor trip on Low RCS Pressure (P<1894 psia). The reactor trip automatically trips the turbine. The resulting insertion of scram reactivity ends the power excursion and negates further challenge to the core DNB limits. Hence, the event is considered terminated.
The total neutron power increases from 3026.10 to 3100.92 MWt at 45 s, and as can be seen in Figure 3-2. This is an increase of 2.5%, and is 2.9% higher than the rated thermal power of 3014 MWt. The total neutron power increase bounds the thermal power; therefore, thermal power remains less than 112% of full power for the duration of the event. Since the thermal power remains below 112% of the rated thermal power, the fuel cladding integrity is maintained.
Figure 3-1 shows that the RCS pressure is constantly decreasing until reactor trip, and is always less than the initial value. Therefore, the peak RCS pressure acceptance criteria is not challenged during the IPRVO event.
Based on the analysis results, all acceptance criteria are met.
Page 13
Figure 3-1: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 2200
-- Hot Leg 1 (CV 110-4)
-- Hot Leg 2 (CV 210-4)
-A Core Exit (CV 352-01)
-< Top of Pressurizer (CV 405-01) 2100 -----------
-- --------- -- ----- -------
-------
2000 --------------- ------------- -----------------------------
U 1900 -------- --------------- I ---------------
------------- ---------------
1800 --------------- ............ ---------------
-- ---------
00 1700 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s)
_l
Figure 3-2: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 3200
---ETotalRX Power (CVAR 370 3 140 . . . . . . . .. .. . . . . . . .. . . . . .. . . . . . .. .. . . . . .. . . . .. .. . . . . . .. . . . . . . . .. . . . .. . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . .. . . . . .. . . . . . . . . .. . . . . .. . . . . .. . . . . .. . . . . . .. . . . . . . . . . . . . .. . . . . .. . . . . .. . . .. . . . . . . .. .
30 80 . . . . . . . . . . . . . ------- . . . . . . . k -. .-- ------. --------. . . . .-.-..
.. . . .. . . . . . . . . . .. .-.. . . . . . . . . . . . . . . . .. - ----- .. . .. . . . . . . . . . . . .. . . . . . . . .
-- --
3020 ----- ---------- --------
278 2 842 4 -------.. ... ....- -----.- ----- -------------.- --- ---. L.- ---------- -------.- -------.- -----------.- ----------.- . .--.-.--..---.--- . . -..---.--.-.--.-.--. .-.--
.. --.- . . -. .-- . .-. -.. . . . . . . . .
(A :
00 2600 0 5 10 15 20 25 30 35 40 45 50 55 60 t~
Time (s)
_2
Figure 3-3: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 630 -
-- RCS Ave Temp (CVAR 900)
-0 Loop 1 Hot Leg (CV 110-4)
-A Loop 2 Hot Leg (CV 210-4) 620 --< Loop 1A Cold Leg (CV 160-4)
-- V Loop 1 B Cold Leg (CV 180-4)
-D, Loop 2A Cold Leg (CV 260-4)
-- Loop 2B Cold Leg (CV 280-4) 610 - ---- - -------- ------
600 -
59 0 .------.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..-..
.-.-------------.-------- .. . . .
] ' * [ - --- - - - - - -- - - -- - -
[ -- - -- - -- ---------------
5 0 - - - ---
E3 E0 E B E3 E3 CIO 530 530-.
0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s) .
_3
Figure 3-4: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 12000Loop 1A Flow Rate (JUN 170)
-- Loop 1B Flow Rate (JUN 190)
Loop 2A Flow Rate (JUN 270) 11600 ---------------- ..-------------- .--------------- ..---------- .-.----------------- ----------- .--- .----------- .---.---...---- ...-- Lo op 2 B F lo w Ra te (J UN 29 0 ) .......
11200 ------------. --- .---------------.--.-..-.-.-.--.--.-.-------. ---. -----------.----------- .--- .------- ........ ..........................
10400 ...................................... .....................................................................---.................... ...............................
108000 ------ - ---- - - -- - - --- --
S10400- --
10000-- ---------------....--- ------------
t 960 0 .... ... ... --- . --
- .. ---------
................. ------ - ......... .. ...- ------------ --
9 20 0 . . . . .. . . . . . .. . . . . . . . . . . . . .. . . -
. --- .-. --.. . -
..- . -----.-.-.-.- . . . . . . . . .. . .-.-.-. ..--.--.-
---.-.-.-.- . . . . . . .. . .-
. . . .-.-..--.-.. . . . . . . . . . . . .. ....... . . .--.- . . . . . . . . . .
88 0 0 . . . .. . . . . . . . .. .. . . . .. . . . .. .. . .. . .. . . . . . .. . . . . . .. . . . . . . .. . . . . .. .. . . . . . .. . . . . .. . . . . . .. . . . .. . . . . . .. . . . . . . . .. . . . . . .. . . .. . . . . . . . .. . . . . . .. . . . . . .. . . . . .. . . . . . . .. . . . . . . . . . . . .. . . . . . . . .. . . . . . .
8400-8000, 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s) -
_4
Figure 3-5: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 240 I- CVAR 409 2310 --- - - -------------- --- - -- - - .. . . . . . .. . . . .. . . . . . . . .. . . . . .. .. . . . . ---
..220 S 190 --- - --.-- - --- -- --- -- - --- - ---... ......-- -- - --- -I-.--- --- ----- -- - -...--- - - --.-- ---- -- - --- - - ---- - ---- - -
2000 190 180 __ _ _ _ __ _ _ _ __ _ _ _ -.4__
0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s) -
00.-
_5
Figure 3-6: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 1430 I43 Volume Weighted (CVAR 56) 1426 1428 ---- --------- ------------------------------- --"-- --- ---------- ------------------
1424 1420 S 14184 -
S 1416---
1414------
H :
S 1412 -------------- --------------------- --- -----
14 14.-.-------------.-.---------.-- . ..............---------------.-----------------------.-------.---------- -------------------- ----------.---- --------- .-------------.------------
1402
------ --
- ---- ----
14 0 0 --------
0510 15 20 25 30 35 40 45 50 55 60 b Time (s)
_6
Figure 3-7: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 16
-- SG 1 (CVAR 614)
-- SG 2 (CVAR 714) 14 ---------- -. - . , .-
---. ----------. --------
.-- -----. -------------.
..-- . ..-- . ..--
. --- --. -------------. ---.
..-- .-- . ..-- . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . . . . .. .
12 ----- ------
. . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . .. . .. .. .. .. .
. --. . ---. -----------. . . . . . . . . .. . . . . . . . . . .
8 .-.- . . . . . . . . . . . . . . . . . . . . . . . .
-e 8 00 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s)
_7
Figure 3-8: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening at 3026.1 Relief Valve Full Power OpeningMWt Inadvertent Figure Pressurizer 3-8:CR-3 -ESC 64000 2 ( V M bU(CVAR707) ........... .....-
---
- -- -- --
--.-. -------- -- .-.-
-------. --- .- ---------
62000 60000
. -. . ------- ------------
--. . . . . . .. . . . .
58000 E ------------------- ---------------
56000
- 4. -- - - - - - - . ---
--- --- . . ---
. --- --- --- --
54000 52000
-------------
50000 0
48000
-- ------- -------
46000 44000 42000 00 40000 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s)
_8
Figure 3-9: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 100
-- c SG 1 (CVAR 612)
-SG 2 (CVAR 712) 90 80 80 --- -- - -...........
--- - - - ...
-- - . .... ..... ----- ------------------....
--- --- - -------
601 1ý 0 0 ------
60 30 00 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s)-
9
Figure 3-10: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 0.00
-0.10
-0.20
-0.30
-0.40
-0.50
-0.60
-0.70
-0.80
-0.90
-1.00
-1.10
-1.20
-1.30
-1.40
°0-
-1.50
-1.60
-1.70
-1.80
-1.90
-2.00
-2.10
-2.20
-2.30
-2.40
-2.50
-2.60
-2.70 00
-2.80
-2.90
-3.00 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s) t-)
10
Figure 3-11: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 4000
-- Main Feedwater Flow (JUN 602 + JUN 702)
-- Steam Flow (JUN 511)
------------
3900
.......... ----------
3800 3700 ---------- -----------
CIO 3600 3500 -----------
3400 3300 -----------
3200 -----------
3100 --------
--
00 3000 t'Q 0 5 10 15 20 25 30 35 40 50 55 60 Time (s)
IlI
Figure 3-12: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve 3026.1 MWt Power Relief at Opening Valve Opening 1000 Full Pressurizer Figure3-12:CR-3 Inadvertent -- 0 Energy Into + Energy Out SG1 (CVAR 5 + CVAR 85)
-0 Energy Into + Energy Out SG2 (CVAR 6 + CVAR 86)
-- -----------
.......... ---------------
800 600 -----------
400 ------------- --------------
---------
200 -------------
-------- --
cd~ 0 R - ----R ()----H --- HU -~ - - - -I r'i U
I I L!j H
-200 --
---------------
LI~
-400 -- ------------
---------
-600 --------------
.......... ---------
.........
-800 ----------
00 ON ON
-1000 -~1 0 5 10 15 20 25 30 35 40 45 50 55 60 Time (s) k) 0 0
12
Figure 3-13: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 390000
[ CVAR 332 3 8 5 000 --------- -------. -- - - -- - - ----------- .-. ----
. . . -. --.. - . . --
.. - . .. .. . .. .. . --- - --- - - ..--
. --.-. -- .-
..---. --..-.-.-. - . . . -. -
. . -- . - .. -
.-. - ..- -. . -- . . --- --- -- --- -- --
. . -- . -- . -. -
. ..- . -- -- -- - ---
3 8 0 00 0 . . . .. . . . . . .. . . . . . . . . .. . . . . . .. . . . . . .. . . . . . . . . . . . .. . . . .. . . . . . . .. . . . . . . .. . --- ---- ----------
. . . . .. . . . .. . . . . . .. . . . .. . . . . . . . . . . . .. . . . . . . . .. . . . . . . .- -- -- --- .. . . . . . . .. .
--..
~ .. ~..
375000
... ~ ~ . ~ .....~ ..~ . P -- . .- -. : a .--- . .--.-- . :n.. --. .- .- .- .- .--
. ---......
- ........ . . . . .[ D. R . . . . .* -
0 ct~
375000 ------- a a- ~------------------ - a--
00 360000 55--- 60-0 5 10 15 20 25 30 35 40 45 50556 Time (s)
O7 13
Figure 3-14: CR-3 Full Power at 3026.1 MWt Inadvertent Pressurizer Relief Valve Opening 80 PCSV Flow (JUN 492 70 ---------- ---------------
--------------------------------
---------------
4 --------------- ---------------
-- ------------ ----------------------------
4 -------------
- --- -----------
60 50 -----------------------------
I---------------
......
- -------
-- ------------
40 - ------------- --------------------------
-------------------------- ---------------
.............--------------
U 30 ------
--------------- --------------
---------
-------------
20 ------------............... --------------------------
- - -- ----- ---
1.
10 ------------------------- ---------
---------------
00 ON IN 0 5 10 15 20 25 30 35 40 45 50 55 60 0o Time (s) 14
.AR EVA Document No. 86-9167251-001 Summary of CR3 EPU Inadvertent Pressurizer Relief Valve Opening
4.0 REFERENCES
- 1) AREVA Document 32-9086732-000, "CR-3 EPU Inadvertent Pressurizer Relief Valve Opening."
- 2) AREVA Document 51-9083076-000, "CR-3 EPU Inadvertent Pressurizer Relief Valve Opening AIS."
- 3) AREVA Document 43-10193PA-00, "RELAP5/MOD2-B&W for Safety Analysis of B&W-Designed Pressurized Water Reactors."
- 4) AREVA Document 43-10164PA-06, "RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis."
- 5) NUREG 0800, Section 15.6.1, "Inadvertent Opening of a PWR Pressurizer Pressure Relief Valve or a BWR Pressure Relief Valve," US NRC, Rev. 2, 03/2007.
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