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LaSalle Unit 2 Cycle 9 Core Operating Limits Report, Amendment … · 2012-11-18 · LaSalle Unit 2...
Transcript of LaSalle Unit 2 Cycle 9 Core Operating Limits Report, Amendment … · 2012-11-18 · LaSalle Unit 2...
EMF-2440
LaSalle Unit 2 Cycle 9 Revision 0
Plant Transient Analysis Page 4-1
4.0 Transient Analysis for Thermal Margin - Extended Operating Domain
This section describes the development of the MCPR and LHGR limits to support operation in
the following extended operating domains:
* Increased core flow (ICF) to 105% of rated flow.
* Power cdastdown to 40% of rated power.
* Final feedwater temperature reduction (FFTR) of up to l 000 F and with ICF. Since FFTR is typically used in connection with coastdown, analyses were performed to support combined FFTR/coastdown operation.
Results of the limiting transient analyses are used to determine appropriate MCPR• limits and
LHGRFACp multipliers for ATRIUM-9B and GE9 fuel to support operation in the EOD scenarios.
MCPRP limits are established for'both ATRIUM-9B and GE9 fuel while LHGRFACp multipliers
are only established for the ATRIUM-9B fuel.
As discussed in Reference 9, the MCPR safety limit analysis for the base case remains valid for
operation in the EODs discussed below. Also, the flow-dependent MCPR and LHGR analyses
described in Section 3.4 were performed such that the results are applicable for all the EODs.
4.1 Increased Core Flow
The base case analyses presented in Section 3.0 were performed to support operation in the
power/flow domain presented in Figure 1.1, which includes operation in the ICF region. The
coastdown and combined FFTRPcoastdown analyses are performed in conjunction with ICF to
conservatively maximize the exposure at which a given power level can be attained. As a result,
the analyses performed support operation in the ICF extended operating domain for all
exposures.
4.2 -Coastdown Analysis
Coastdown analyses were performed to ensure that appropriate MCPRP limits and LHGRFACp
multipliers are applied to support coastdown operation. The analyses were performed for
coastdown operation to 40% of rated power using a conservative coastdown rate equivalent to a
10% decrease in rated power per 1000 MWd/MTU increase in exposure. An additional
1000 MWdMTU was added to the EOFP exposure prior to the start of coastdown to provide
operation support for operation at up to 10% of rated power above the equilibrium xenon
coastdown power level. The MCPRP limits and LHGRFACý multipliers are based on results of
c;-a. IA~ gP NA"g'w
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 4-1..
LRNB and FWCF analyses. The analyses were performed at cycle exposures consistent with
the assumed coastdown rate. This corresponds to the highest exposure at which the power can
be obtained. The base case coastdown ACPRs for both the ATRIUM-9B and GE9 fuel as well
as the ATRIUM-9B LHGRFACp results are presented in Table 4.1 for the indicated power/flow conditions. The ATRIUM-9B MCPRp limits and LHGRFACý multipliers for coastdown operation
are presented in Figures 4.1 and 4.2. The GE9 coastdown MCPRp limits are presented in
Figure 4.3.
4.3 Combined Final Feedwater Temperature ReductionlCoastdown
Analyses were performed to support FFTR with thermal coastdown to ensure that appropriate MCPR•, limits and LHGRFACp multipliers are established. The combined FFTRPcoastdown analysis used a 100*F feedwater temperature reduction applied at EOFP to extend full thermal power operation. The coastdown exposure extension discussed in Section 4.2 (1000 MWd/MTU to support operation at up to 10% of rated power above the equilibrium xenon power level) was then applied. LRNB and FWCF analyses were performed to establish MCPRP, limits and , "
LHGRFACp multipliers. TheCycle 9 FFTRlcoastdown ACPR results for both ATRIUM-9B and
GE9 fuel as well as the LHGRFACp results are presented in Table 4.2 for the indicated power flow conditions. The ATRIUM-9B MCPR, limits and LHGRFACp multipliers for combined
FFTR/coastdown operation are presented in Figures 4.4 and 4.5. The GE9 coastdown MCPRp
limits are presented in Figure 4.6.
LaSalle Unit 2 Cycle 9 C)Imnf *rr~nermnn Anni ic
EMF-2440 Revision 0
Pame 4-3
Table 4.1 Coastdown Operation I Transient Results
Power/Flow ATRIUM GE9 (% rated I
Event % rated) ACPR LHGRFACp ACPR
LRNB 100 /105 0.31 1.00 0.41
LRNB 80 /105 0.32 1.00 0.35
LRNB 60 /105 0.31 0.99 0.35
LRNB 40 / 105 0.31 0.96 0.31
LRNB 25 /105 0.19 1.13' 0.19
FWCF 100 / 105 0.26 1.08- 0.32
FWCF 80 / 105 0.29 1.08 0.31
FWCF 60 /105 0.34 1.08- 0.36
FWCF 401105 0.44 1.12 0.44
FWCF 25 / 105 0.86 1.08 0.88
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
LRNB 60/105 0.27 1.01 0.28
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Page 4-4
Table 4.2 FFTRlCoastdown Operation Transient Results
Power/ Flow ATRIUM GE9 (% rated I
Event % rated) ACPR LHGRFACJ ACPR
LRNB 100D1 105 0.26 1.04 0.29
LRNB 80 / 105 0.25 1.04 0.30
LRNB 40 1 105 0.25 0.99 0.25
LRNB 25/105 0.14 1.18 0.15
FWCF 100/105 0.26 1.09 0.28
FWCF 80 /105 0.30 1.09 0.33
FWCF 60 /105 0.37 1.09 0.40
FWCF 40 / 105 0.50 1.07 0.50
FWCF 25/105 1.10 0.95 1.12
�4( '�
N -I
J
LaSalle Unit 2 Cycle 9EMF-2440 Revision 0
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0 10 20 30 40 so To so 7goo• 110 POWN(%of Pmmd)
Power MCPRN ... (%) , Limit
.. 100 - 1.42 60 1.48
-25 ----- 2.05 -. 25 ... 2.20 -- 0' 2.70
"Figure 4.1 Coastdown Power-Dependent MCPR Limits fo"r ATRUM-9B Fuel
2M5
2.
2.m5
225
2.15
a.m 62A5
4D3I 39131101GL •lýl Zi
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
L
a,.
0 10 20 30 40 50 so 70 so 90 100 110
PowofC% of~ad
Power LHGRFACý (%) Multiplier
100 1.00 60 0.99 25 0.75 25 0.75 0 0.75
Figure 4.2 Coastdown Power-Dependent LHGR Multipliers for ATRUM-SB Fuel
Siemens Power Corporatfn
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I (z ,
LaSalle Unit 2 Cycle 9 •1• n'a•wt• JJ•q4A -'~ hI .;
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Paoe 4-7
0 10 20 30 40 50 " s 70 so so 100 110
Vower (%f RzOM
Power MCPRp
(%): Limit
100 1.52
60- 1.54
25 2.05
25. 2.20
0 2.70
Figure 4.3 Coastdown Power-Dependent 'MCPR Limits for GE9 Fuel
m. OK
rl, l9l" 14 Ibl~ C IZ C ~ l i •O l•- O
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Pac e4-8
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
285
2.65
2M•
2145
2.2M
2.15
105 t 2.a5,
S1JI5
1.115
1.753
1AS"
1.25
1.15
0 10 20 30 40 50 0
P-W(m %o raft)
70 W0 !0 100 110
Power MCPRN (%) Limit 100 1.42 60 1.56 25 2.30 25 2.35
0 2.85
Figure 4.4 FFTRPCoastdown Power-Dependent MCPR Limits for ATRUM-9B Fuel
U
AmRmng Piwmr Cormtfrfi
LaSalle Unit 2 Cycle 9r l V. i|. i i "- i i1; i i&'P ii h
EMF-2440 Revision 0 Pae 4-9
a 10 m 30 40 so0 70 so 90 100 1110
Puinr(M.of poe
Power LHGRFACý (%) Muttiplier
100 1.00 -60 0.97
-25 -.- 0.65
.-25 0.65 _ _ _0 0.65
Figure 4.5 FFTRlCoastdown Base Cise Power-Dependent LHGR Multipliers for ATRUM-9B Fuel
I
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page 4-10
0 10 2D W0 40 W0 50 so W0 150 110
Pufm rA of Poe
Power MCPRp (%) Limit
100 1.52 60 1.59 25 2.30 25 2.35
0 2.85
Figure 4.6 FFTR/Coastdown Power-Dependent MCPR Umits for GE9 Fuel
2.75
2.45
2.2M
12.5 2.15
~1J5 tIM
1.75
.AS
1."5
1.15
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-1
5.0 Transient Analysis for Thermal Margin- Equipment Out-of-Service
This section describes the development of the MCPR and LHGR operating limits to support
operation with the following EOOS scenarios:
* Feedwater heaters out-of-service (FHOOS) - 100°F feedwater temperature reduction. * 1 recirculation pump loop (SLO). * Turbine bypass system out-of-service (TBVOOS). * Recirculation pump trip out-of-service (No RPT). * Slow closure of I or more turbine control valves.
Operation with I SRV out-of-service, up to 2 TIPOOS (or the equivalent number of TIP
channels) and up to 50% of the LPRMs out-of-service is supported by the base case thermal
limits presented in Section 3.0. No further discussion for these EOOS scenarios is presented in
this section. The EOOS analyses presented in this section also include the same EOOS
scenarios protected by the base case limits.
Results of the limiting transient analyses are used to establish appropriate MCPRp limits and
LHGRFACp multipliers to support operation in the EOOS scenarios. All EOOS analyses were
performed with TSSS insertion times.
As discussed in Reference 9, the base case MCPR safety limit for-two-loop operation remains
applicable for operation in the EOOS scenarios discussed below with the eXception of single
loop operation. Also, the flow-dependent MCPR and LHGR analyses'described in Section 3.4
were performed such that the results are applicable in all the EOOS scenarios.
5.1 Feedwater Heaters Out-of-Service (FHOOS)
The FHOOS scenario assumes a 1000F reduction in the feedwater temperatubre. Operation with
FHOOS is similar to operation with FFTR except that the reduction in feedwater temperature
due to FHOOS can occur at any time during the cycle. The effect of the reduced feedwater
temperature is an increase in'the core subcooling which can 6hange the power shape and core
void fraction'.'Whike the LRNB event is leis severe due to the decrease in steam flow, the FVVCF
event can get worse due to the iricrease in core inlet SzUbcooling.'FWCF analyses were
performed for Cycle 9 to determine thermal limits to support operation with' FHOOS. The ACPR
and LHGRFACý results used to develop the EOC operating limits with FHOOS are presented in
Table 5.1. The EOC MCPRP limits and LHGRFAC6 multipliers for ATRIUM-9B fuel for FHOOS
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Paoe 5-2
operation are presented in Figures 5.1 and 5.2, and the EOC FHOOS GE9 MCPR: limits are
presented in Figure 5.3.
5.2 Single-Loop Operation (SLO)
5.2.1 Base Case operation
The impact of SLO at LaSalle on thermal limits was presented in Reference 9. The only impact
is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation safety limit is
0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The base case ACPRs
and LHGRFACp multipliers remain applicable. The net result is an increase to the base case
MCPRp limits of 0.01 as a result of the increase in the MCPR safety limit.
5.2.2 Idle Loop Startup
The MCPRp limits and LHGRFACp multipliers for the startup of an idle recirculation pump are
based on the results of the abnormal startup of the idle recirculation loop analysis and the SLO
MCPR safety limit analysis. As discussed in Section 3.2, the single-loop operation safety limit is
1.12 or 0.01 higher than the two-loop operation limit. The process used for the abnormal stari4j
of the idle recirculation loop analysis for L2C9 is presented in Reference 20. The responses of
the system parameters for the L2C9 analysis are consistent with those presented in Reference
20. The Reference 20 results demonstrated that the lowest power (35%P/47%F) conditions
provide conservative results. Subsequently, the L2C9 analyses were performed at 35%P/47%F.
The limiting exposure was determined to be BOC. The ACPR and LHGRFAC, results for the
abnormal startup of the idle recirculation loop are presented in Table 5.2. Figures 5.4 and 5.5
Spresent the ATRIUM-9B MCPRp limits and LHGRFACp multipliers for idle loop startup. The GE9
MCPRP limits for idle loop startup are presented in Figure 5.6.
5.3 Turbine Bypass Valves Out-of-Service (TBVOOS)
The effect of operation with TBVOOS is a reduction in the system pressure relief capacity,
which makes the pressurization events more severe. While the base case LRNB event is
analyzed assuming the turbine bypass system out-of-service, operation with TBVOOS has an
effect on the FWCF evenL The FWCF event was evaluated for LaSalle Unit 2 Cycle 9 to support
operation with TBVOOS. The ACPR and LHGRFACp results used to develop the EOC operatirw"
limits with TBVOOS are presented in Table 5.3. The EOC MCPRp limits and LHGRFACp II
0 L-- ch- P
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-3
multipliers for ATRIUM-9g fuel for TBVOOS operation are presented in Figures 5.7 and 5.8, and
the EOC TBVOOS GE9 MCPRp limits are presented in Figure 5.9.
5.4 Recirculation Pump Tip Out-of-Service (No RP7)
This section summarzes the development of the thermal limits to support operation with the
EOC RPT inoperable. When RPT is inoperable, no credit for tripping the recirculation pump on
TSV position or TCV fast closure is assumed. The function of the RPT feature is to reduce the
severity of the core power excursion caused by the pressurization transient. The RPT
accomplishes this by helping revoid the core, thereby reducing the magnitude of the reactivity
insertion resulting from the pressurization transient. Failure of the RPT feature can result in
higher operating limits because of the higher positive reactivity in the core at the time of control
rod insertion.
Analyses were performed for LRNB and FWCF events assuming no RPT. The ACPR and
LHGRFACý results used to develop the EOC operating limits with no RPT are presented in
Table 5.4. The EOC MCPRp limits and LHGRFACý multipliers for ATRIUM-9B fuel for operation
with no RPT are presented in Figures 5.10 and 5.11, and the EOC no RPT GE9 MCPRF limits are
presented in Figure 5.12.
5.5 Slow Closure of the Turbine Control Valve
LRNB analyses were performed to evaluate the impact of a TCV slow closure. Analyses were
performed closing 3 valves in the normal fast closure mode and 1 valve in 2.0 seconds. Results
provided in Reference 23 demonstrate that performing the analyses with I TCV closing in
2.0 seconds protects operation with up to 4 TCVs closing slowly. Sensitivity analyses below
80% power have shown that the pressure relief provided by all 4 TCVs closing slowly can be
sufficient to preclude the high-flux scram set point from being exceeded. Therefore, credit for
high-flux scram is not taken for analyses at 80% power and below. The 80% power TCV slow
closure analyses were performed both with and without high-flux scram credited. The ACPR and
LHGRFACp results of the analyses performed are presented in Table 5.5.
The MCPRp limits and LHGRFACp multipliers are established with a step change at 80% power.
At 80% power, the lower-bound MCPR, limits and upper-bound LHGRFACp multipliers are based on the analyses which credit high-flux scram; the upper-bound MCPRp limt and lower
bound LHGRFACp multipliers are based on analyses which do not credit high-flux scram. While
~m.,eDine .r1mtFIM
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-4
the TCV slow closure analysis is performed without RPT on valve position, it does not
necessarily bound the LRNB no RPT or FWCF no RPT events at all power levels because the
slow closing TCV provides some pressure relief until it completely closes. Therefore, the MCPRp
limits and LHGRFACp multipliers for the TCV slow closure EOOS scenario are established using
the limiting of the no RPT results reported in Section 5.4 and the TCV slow closure results.
The EOC MCPRp limits and LHGRFACp multipliers for ATRIUM-9B fuel for operation with TCV
slow closure are presented in Figures 5.13 and 5.14 and the EOC TCV slow closure GE9
MCPRp limits are presented in Figure 5.15. The limits presented in Figures 5.13 through 5.15
protect the scenario of all 4 TCVs closing slowly.
5.6 Combined FHOOS/TCV Slow Closure and/or No RPT
MCPi• limits and LHGRFACp multipliers were established to support operation with FHOOS,
TCV slow closure and/or no RPT. The TCV slow closure ACPR and LHGRFACý results with
FHOOS become less limiting than the TCV slow closure event with nominal feedwater
temperature since the initial steam flow with FHOOS is lower and produces a less severe j r
pressurization event. Subseque'ntly, no TCV slow closure with FHOOS analyses were
performed. The TCV slow closure results with nominal feedwater temperature are considered in
determining the combined FHOOS/TCV slow closure and/or no RPT MCPRp limits and
LHGRFACp multipliers. The limits were developed based on the limiting of either the TCV slow
closure analysis results discussed in Section 5.5 or the analyses with both FHOOS and no RPT
presented in Table 5.6.
The EOC MCPRp limits and LHGRFAC, multipliers for ATRIUM-9B fuel with FHOOS/TCV slow
closure and/or no RPT are presented in Figures 5.16 and 5.17, and the EOC GE9 MCPRp limits
for the same EOOS scenario are presented in Figure 5.18. The limits presented in Figures 5.16
through 5.18 protect the scenario of all 4 TCVs closing slowly.
EMF-2440 Revision 0
Page 5-5LaSalle Unit 2 Cycle 9 r DEI " Ir *ann Anal i
Table 5.1 EOC Feedwater Heater Out-of-Service Analysis Results
Power/ Flow . ATRIUM GE9 (% rated/
Event % rated) ACPR LHGRFACý &CPR
FWCF 100/105 0.26 1.08' 0.31
FWCF 100181 0.23 1.11 0.28
FWCF 801105 0.30 1.03" 0.36
FWCF 60/ 105 0.40' 0.97* 0.46'
FWCF 401105 0.62' 0.87* 0.69*
FWCF 25 /105 1.03° 0.69' 1.11°
° The analysis results presented are from an ealier cycle exposure. The ACPR and LHGRFAC, results are conservatively used to establish the thermal limits.
a 10110 Z=
LaSalle Unit 2 Cycle 9l-ioll i IdFIWSIeL AI Idliy*a
EMF-2440 Revision 0 Paoe 5-6
0
Table 5.2 Abnormal Recirculation Loop Startup Analysis Results
Power I Flow FCV ATRIUM-9B (% rated I Position % rated) ACPR• LHGRFACý
35147 27% open 1.46t 0.421
& ACPR results for ATRIUM-9B fuel are conservatively applicable for GE9 fuel. SThe analysis results presented are from an earlier cycle exposure. The .CPR and LHGRFACp
results are conservatively used to establish the thermal limits.
EMF-2440 Revision 0 Page 5-7LaSalle Unit 2 Cycle 9
01 4r ~emarn Anol ;ee
Table 5.3. EOC Turbine Bypass Valves Out-of-Service Analysis Results
Power / Flow ATRIUM GE9 (% rated !
Event % rated) ACPR LHGRFAC - ACPR
FWCF 10 0/105 .0.32 v1.02 0.41
FWCF 100181 0.31 -0.99- 0.41
FWCF 80/105 0.35 1.00' 0.45
FWCF 80157.2 0.31 1.05 0.41
-FWCF. 60/105 0.41. -' 0.97- 0.51
FWCF 60/35.1 0.15 1.14 0.25
FWCF 40 / 105 0.58' .0.90r 0.65'
FWCF 25/105 0.87* 0.76' 0.97*
" The anatyss results presented are from an earlier cycle exposure. The ACPR and LHGRFACý resuht are conservatively used to establish the thermal limits.
LaSalle Unit 2 Cycle 9Md"IIi I rdansIeIIL "63 ma il
EMF-2440 Revision 0
Paoe 5-8
<9
Table 5.4 EOC Recirculation Pump Trip Out-of-Service Analysis Results
Power I Flow ATRIUM GE9 (% rated I
Event % rated) ACPR LHGRFAC, ACPR
LRNB 100 /105 0.40 0.89 0.50
LRNB 100/81 0.32 0.91 0.47
LRNB 801105 0.35 0.94 0.47
LRNB 80157.2 0.30 0.97 0.44
LRNB 601105 0.32 0.99 0.44
FWCF 100/105 0.31 0.97 0.40
FWCF 100181 0.26 0.99 0.35
FWCF 80/105 0.33 1.00* 0.43
FWCF 60/105 0.38 0.97' 0.48
FWCF 40/ 105 0.51' 0.91" 0.59*
FWCF 25/105 0.78' 0.79* 0.87'
" The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC, results are conservatively used to establish the thermal limits.
EMF-2440 Revision 0
Pawe 5-9LaSalle Unit 2 Cycle 9
Table 5.5, EOC Turbine Control Valve Slow Closure Analysis Results
Slow Power I Flow ATRIUM-9B GE9 Valve (% rated I
Event Characteristics % rated) &CPR LHGRFACý ACPR
LRNB 1 TCV dosing at 2.0 sec 100 / 105 0.42 0.93 0.52
LRNB 1 TCV dosing at 2.0 sec 100 8.1... 0.33 0.97 0.49
LRNB 1 TCV dosing at 2.0 sec, 801 105" 0.40 0.96 0.49
LRNB I TCV closing at 2.0 sec B0 / 57.21 0.50 0.97 0.73
LRNB 1 TCV closing at 2.0 sec 801 105't 0.52? 0.86* 0.62
LRNB I TCV, closing at 2.0 sec 80 1 57.2! 0.58 0.92? 0.84
LRNB I TCV closing at 2.0 sec 60/1051 0.61$ 0.83* 0.71S
LRNB I TCV dosing at 2.0 sec 601 35.11 0.63W 0.940 0.86
LRNB I TCV closing at 2.0 sec 40 /I 105t 0.78 0.77* 0.84
LRNB -TCV dosing at 2.0 sec 25/ 1051 0.99 0.70e 0.97$
Scram initiated by high-neutron flux. Scram initiated by high dome pressure
The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFACP resutts are conservatively used to establish the thermal limits.-
$
Mant I ransient Pnaiyz
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page 5-10
7-i
Table 5.6 EOC Recirculation Pump Trip and Feedwater Heater Out-of-Service Analysis Results
Power I Flow ATRIUM-9B GE9 (% rated I
Event % rated) ACPR LHGRFACp ACPR
FWCF 100/105 0.30 0.98 0.39
FWCF 100181 0.25 1.03 0.33
FWCF 801105 0.35 0.98* 0.43
FWCF 60/105 0.42 0.94" 0.51
FWCF
FWCF
40/105 0.61* 0.85*t *1.
25/105 1.01* 0.68*I J.
0.70"
1.09*
The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
LaSaI eUnit 2 Cycle 9 I~3 l.... "r.. .-u a�a n f A V, .1ei u
2.15
2'is t=u=
1.76"
IAS
1.35'
1.25
EMF-2440 Revision 0 Page 5-11
0 10 20 30 40 s0 s0 _ 70 s0 90 100 110
Pwf" N d ftMr)
Power- MCPRP
(%). Limit
100 1.41 60 1.51 25 2.14 25 2.35
0 2.85
Figure 6.1 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR Uimits for ATRIUM-9B Fuel
IaiIIf I Ol i843 ;I i 0 i4 iRZuya;
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page 5-12
0 10 20 40 50 so 70 60 90 10 110
powmr(% ofRmhom
Power LHGRFACý (%) Multiplier
100 1.00 60 0.97 25 0.69 25 0.69
0 0.69
Figure 5.2 EOC Feedwater Heaters Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
0. U
a'.
EMF-2440 Revision 0 Paqe 5-13LaSalle Unit 2 Cycle 9
ý0I1 .4 "r,-I M=n Arnhteic
0 10 20 30 40 so so 70 50 90 ¶00 110
pa"I (% d Rd)69
Power MCPRP (%) UIt
100' 1.51
60 1.57 25 2.22 25 2.35
0 9 2.85
Figure 5.3 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
B.
4M 443410 --
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
VK%
U U.
z" I
225
213,
2.105
125.
1.75.
1.85"
1AS"
135
12S
1.150 10 20 30 40 50 60
Pm I% of Ratd)
70 s0 9O 100 110
Power MCPRp
(%) Limit
100 2.60 60 2.60 25 2.60 25 2.60
0 2.60
Figure 5.4 Abnormal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for ATRIUM-96 Fuel
xJ.
EMF-2440 Revision 0 Page 5-14
Lkft LO .Reala
EMF-2440 Revision 0 oPage 5-15LaSalle Unit 2 Cycle 9
11d1 10" V"@ a~~ 31Fe aYO
I *LOOsRoP Re I LHGRFAOP
10 20 30 40 50 60
Power (% of Raed)
1.30
1.25 1.20'
1.15.
1.10
1.05,
1.00 OAS
OmO
0.75
0.70
O.050.60
0.45 j
0431
Power- LHGRFACp (%) Multiplier
100 . .. . 0.40
60-- -0.40
25 --.. 0.40 25 .. .0 _0 . ..... 0.40
Figure 5.5 Abnormal Idle Recirculation Loop Startup Power-Dependent LHGR Multipliers for ATRIUM-91 Fuel
E.
70 W0 90 100 1100
C6._..ftW cv."Or t'*fW"nrAfinn
. I I !I ! I
i
LaSalle Unit 2 Cycle 9*o..s . *e**e5�s*t �
-3 t~
2.45
2452.35'
225
2.15'
2.05
~1AS
1.75
1.A
1.5S
1.45
15
1.25
1.150 10 20 30 40 50 so
Power 1% d R20
70 s0 90 1M 110
Power MCPRI (%) Umit
100 2.60 60 2.60 25 2.60 25 2.60
0 2.60
Figure 5.6 Abnormal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for GE9 Fuel
EMF-2440 Revision 0 Pace 5-16
£f wpRa
K iAMP
EMF-2440 Revision 0 Page 5-17LaSalle Unit 2 Cycle 9
Plant Transient Analysis
0 10 20 30 40 so OD To OD 90 1OD 110
POinr M% d Rabd
Power MCPRq (%) Umit
100 - -..••_ . .1.43
60 -1.52
25 V 1.98
25 2.20
0 2.70
Figure 5.7 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel
a
EMF-2440 Revision 0 Paoe 5-18
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
a. U
0 10 20 30 40 so 60
Pom •(%of Ramd)
Power LHGRFACp
(%) Multiplier
100 0.99
60 0.97
25 0.76
25 0.76
0 0.76
Figure 5.8 EOC Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
70 80 90 100 110
Paae 5-18
LaSalle Unit 2 Cycle 9 £•II•..lA "' -• .,I, A1 .•.J •.
IIIL I l-ans "L a l o-i l -.
EMF-2440 Revision 0 Paoe 5-19
0 10 2 0 40 50 60 70 so o 100 110
POWA f cIamm
Power MCPRP
(%) Limit
:100 1.52
60 1.62
25 2.08
25 2.20 0 2.70
Figure 5.9 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPRL'Umits for GES Fuel
1.35
125
LaSalle Unit 2 Cycle 9rldnl I I a2 1 M " 0" cIzy--,
2.o5
1.75'
1.85. I.M 1.55'
IA5'
1.Ms
EMF-2440 Revision 0 Paoe 5-20
0 10 20 30 40 50 60 70 80 so 100 110
Power MCPRP
(%) Limit
100 1.51
60 1.51 25 1.91 25 2.20
0 2.70
Figure 5.10 EOC Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel
K)j
LaSalle Unit 2 Cycle 9 01 "lrrsnei&nM Ar~nst*se
a IZ~ a.e..r5,.2
i 4%n
120*
1.15�
1.10
U IL
0J.90
am I
0.U0
COS -
0.70,
am65
0.60
0 10 20 30 40 s0 6o PC"r (M)
7D W0 90 100 110
Power LHGRFACp
(%) Multiplier
100 0.89
60 0.89
25 0.78
25 0.78
0 0.78
Figure 5.11 EOC Recirculation PumpTrip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-98 Fuel
EMF-2440 Revision 0 Pacne 5-21
a a1
*
U
* FVCF
I_•11
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
2.85'
2.55
24S.
2.35
22S
125, 2.15'
2.05
I1.9
lAs
1.75
lAs
1.55
145'
1.35
1.25
1.IS �*
0 10 20 30 40 50 so
POW" (% of RONDO70 s0 90 1W 110
Power MCPRP (%) Limit 100 1.61
60 1.61 25 1.99 25 2.20
0 2.70
Figure 5.12 EOC Recirculation PumpTrip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
U
EMF-2440 Revision 0 Page 5-22
&
d FVCF -C o:P
U
U
a UU
EMF-2440 Revision
0
Parle
5-22
EMF-2440 Revision 0 Page 5-3LaSalle Unit 2 Cycle 9
FIOIIL I I�5I�'��.
0 10 20 3D 40 so so To ao 90 100 110
F~m M% of Ubft
Power MCPRF
(%) Limit
100 1.53
80 1.61
80 1.69
25 2.10 25 2.20
0 2.70
Figure 5.13 EOC Turbine Control Valve Slow Closure and/or -Recirculation Pump Trip Out-of-Service Power-Dependent
MCPR Limits for ATRIUM-98 Fuel
LaSalle Unit 2 Cycle 9r 3C1 IL I V 1 " i& r- ., .
S1.00
0 0.95n
0 10 20 30 40 50 s0 70 s0 go 100 11I
Power LHGRFACp
(%) Multiplier
100 0.89
80 0.89 80 0.86 25 0.70 25 0.70
0 0.70
Figure 5.14 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
LHGR Multipliem for ATRIUM-9B Fuel
J
EMF-2440 Revision 0 Paae 5-24
K)
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
3. a., U=
EMF-2440 Revision 0 Page 5-25
0 10 40 s s 70 s0 so 100 110
Pwut(%of 4bMd
Power MCPRp (M) Limit
100 1.63
"80 1.84
80 o-. 1.95 25 - 2.10
-25 2.20 0 --2.70
Figure 5.15 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent
MCPR Umits for GE9 Fuel
Siemens Power Corooration
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
2.85
2.75'
zw I
1.15• 1.15
7AS
1.tz
4 4�.
0 10 20 30 40 OD OD
Pomr 1% d FW04
70 s0 9o 100 110
Power MCPR, (%) Limit
100 --1.53
80 1.61 80 1.69 25 2.14 25 2.35
0 2.85
Figure 5.16 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service
Power-Dependent MCPR Limits for ATRIUM-9B Fuel
4
EMF-2440 Revision 0 Page 5-26
K-
SI • FVCFNr WT"ftFH= KoF RTmcV I XMRVO6x
EMF-2440 Revision 0 Page 5-27LaSalle Unit 2 Cycle 9
125 120
1.15
1.10
.• 1.00 U I
S0.95
0J•
0.75.
0.70'
O.65
. *R I0 10 20 30 40 so s0
Paws( M cRtMd)
70 so 9o 100 110
Power LHGRFACp
(%) Multiplier
100 0.89
80 0.89
80 z 0.86
25 0.68
25 0.68
0 0.68
Figure 5.17 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service
Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
• FVC• No FT v ft FHOOS
* U
011L Jc"Q-_ Z=
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
I.
a 10 2D 30 40 50 so 70 s0 90 100 110
Pur (% of fd)
Power MCPRp (%) Umit 100 1.63
80 1.84 80 1.95 25 2.22 25 2.35
0 2.85
Figure 5.18 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service
Power-Dependent MCPR Limts for GE9 Fuel
EMF-2440 Revision 0 Paoe 5-28
K)
U
Paoe 5-28
EMF-2440
LaSalle Unit 2 Cycle 9 Revision 0
Plant Transient Analysis Pae 6-1
6.0 Transient Analysis for Thermal Margin - EODIEOOS Combinations
This section describes the transient analyses perform. ed to determine the, MCPR and LHGR
operating limits to support operation in the coastdown and combined FFTR/coastdown extended
operating domains in conjunction with the following EOOS scenarios:
* Feedwater heaters out-of-service (FHOOS) - 100 F feedwater temperature reduction.
* 1 recirculation pump loop (SLO). * Turbine bypass system out-of-service (TBVOOS). * Recirculation pump trip out-of-service (no RPT). * Slow closure of I or more turbine control valves andlof no RPT.
Each of the EOOS scenarios presented also includes the failure of 1 SRV.
Results of the limiting transient analyses are used to establish MCPR: limits and LHGRFACp
multipliers to support operation in the combined EOD/EOOS scenarios. All combined
EODIEOOS analyses were performed with TSSS insertion times.
As discussed in Reference 9, the base case MCPR safety limit for two-loop operation remains
applicable for operation in the combined EODIEOOS scenarios with the exception of single-loop
operation. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 remain
applicable in all the combined EODIEOOS scenarios.
6.1 Coastdown With EOOS
The impact of EQOS scenarios on coastdown operation is discussed below. The MCPRp limits
and LHGRFACp values established for.nominal coastdown operation remain applicable for
coastdown operation with 1 safet,/relief'valve out-of-service, up to 2 TIPOOS (or the equivalent
number of TIP channels) and up to 50% of the LPRMs out-of-serivice (Reference 9).
6.1.1 Coastdown With Feedwater Heaters Out-of-Service
The discussion and results presented in Section 4.3 for combined FFTR/coastdown operation
are applicable to coastdown operation with FHOOS.
6.1.2 Coastdown With One Recirculation Loot
The impact of SLO at LaSalle on thermal limits was presented in-Reference 9. The only impact
is on the MCPR safety limit. As presented in'Section 32, the single-loop operation safety limit is
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-2
0.01 greater than the to-loop operating limit (1.12 compared to 1.11). The base case
coastdown ,CPRs and LHGRFACý multipliers remain applicable. The net result is an increase
to the base case coastdown MCPRp limits of 0.01 as a result of the increase in the MCPR safety
limit.
6.1.3 Coastdown With TBVOOS
The exposure extension during coastdown can make the effects of the pressurization transients
more severe. The TBVOOS assumption also increases the severity of pressurization events.
The nominal coastdown analysis for the load rejection event is performed assuming the turbine
bypass system is inoperable. Therefore, the impact of the TBVOOS on the load rejection event
is included in the nominal coastdown results.
The FWCF event was evaluated to ensure appropriate MCPRp limits and LHGRFACpvalues are
established to support coastdown operation with TBVOOS. The results of the Cycle 9
coastdown FWCF with TBVOOS analyses for both ATRIUM-9B and GE9 fuel are presented in
Table 6.1. Figures 6.1 and 6.2 show the ATRIUM-9B MCPRF limits and LHGRFACp multipliers
that support coastdown operation with TBVOOS. The coastdown with TBVOOS MCPRp limigs')
for GE9 fuel are presented in Figure 6.3.
6.1.4 Coastdown Wrth No RPT
To ensure that appropriate MCPRp limits and LHGRFACp multipliers are established to support
coastdown operation with no RPT, analyses were performed for LRNB and FWCF events with
RPT assumed inoperable. The results of the Cycle 9 coastdown no RPT analyses for both
ATRIUM-9B and GE9 fuel are presented in Table 6.2. Figures 6.4 and 6.5 show the
ATRIUM-9B MCPRp limits and LHGRFACp multipliers that support coastdown operation with no
RPT. The coastdown with no RPT MCPRp limits for GE9 fuel are presented in Figure 6.6.
6.1.5 Coastdown Withl Slow Closure of the Turbine Control Valve
The slow closure of the turbine control valve event changes the characteristics of the LRNB
event in that no direct scram or RPT occurs on valve position. The effect of the increase in
exposure resulting from coastdown operation can make the event more severe. The ACPR and
LHGRFACý results are presented in Table 6.3. While the TCV slow closure analysis is performr
without RPT on valve position, it does not necessanily bound the LRNB no RPT or FWCF no RPT'
events at all power levels because the slow closing TCV provides some pressure relief until it
EMF-2440
LaSalle Unit 2 Cycle 9 Revision 0
Plant Transient Analysis Page 6-3
completely closes. Therefore, the MCPRp limits and LHGRFACP multipliers for the coastdown with
TCV slow closure scenario are established using the limiting of the coastdown no RPT results
reported in Section 6.1.4 or the TCV slow closure results.
Figures 6.7 and 6.8 present the ATRIUM-9B coastdown with TCV slow closure and/or no RPT
MCPRt rrnits and LHGRFACý multipliers and Figure 6.9 presents the coastdown with TCV slow
closure and/or no RPT GE9 MCPRP limits.
6.2 Combined FFTRICoastdown With EOOS
The impact of EOOS scenarios on combined FFTR/coastdown operation is discussed below.
The FFTR/coastdown MCPRp limits and LHGRFAC, values established for combined
FF'RJcoastdown operation remain applicable for FFTR/coastdown operation with I safetylrelief
valve out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50%
of the LPRMs out-of-service (Reference 9).
6.2.1 Combined FFTR/Coastdown With One Recirculation Loon
The impact of SLO at LaSalle on thermal limits was presented in Reference 9S.The only impact
is on the MCPR safety limit. As presented in Section 3.2, the'single-loop operation safety limit is
0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The base case
FFTRPcoastdown ACPRs and LHGRFACp multipliers remain applicable. The net result is an
increase to the base case FFTRicoastdown MCPRp limits of 0.01 as a result of the increase in
the MCPR safety limit.
6.2.2 Combined FFTRPCoastdown With TBVOOS
The exposure extension and decrease in core inlet enthalpy during combined FFTR/coastdown
operation can make the effects of the pressurization transients more severe. The TBVOOS
assumption also increases the severity of pressurization events. The nominal FFTR/coastdown
analysis for the load rejection event is performed assuming the turbine bypass system is
inoperable. Therefore, the impact of the TBVOOS on the load rejection event is included in the
nominal FFTR/coastdown results.
The FWCF event was evaluated to ensure appropriate MCPRP limits and LHGRFACý values are
established to support combined FFTR/coastdown operation with TBVOOS. The results of the
Cycle 9 FFTR/coastdown FWCF with TBVOOS analyses for both ATRIUM-9B and GE9 fuel are
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-4
K) presented in Table 6.4. Figures 6.10 and 6.11 show the ATRIUM-9B MCPRp limits and
LHGRFACý multipliers that support combined FFTR/coastdown operation with TBVOOS. The
FFTR/coastdown with TBVOOS MCPRp limits for GE9 fuel are presented in Figure 6.12.
6.2.3 Combined FFTRPCoastdown With No RPT
To ensure that appropriate MCPRr, limits and LHGRFACp multipliers are established to support
FFTPIcoastdown operation with no RPT, analyses were performed for LRNB and FWCF events
with RPT assumed inoperable. The results of the Cycle 9 FFTR/coastdown no RPT analyses for
both ATRIUM-99 and GE9 fuel are presented in Table 6.5. Figures 6.13 and 6.14 show the
ATRIUM-9B MCPRP limits' and LHGRFACI multipliers that support combined FFTRPcoastdown
operation with no RPT. The FFTRlcoastdown with no RPT MCPRp limits for GE9 fuel are
presented in Figure 6.15.
6.2.4 Combined FFTRlCoastdown With Slow Closure of the Turbine Control Valve
Slow closure of the turbine control valve changes the characteristics of the LRNB event in that
no direct scram or RPT occurs on valve position. While the decrease'in steam flow due to the • "
FFTR tends to lessen the severity of the event, the FFTR/coastdown exposure extension may
have the opposite effect. The iCPR and LHGRFACp results are presented in Table 6.6. While the
TCV slow closure analysis is performed without RPT on valve position, it does not necessarily
bound the LRNB no RPT or FWCF no RPT events at all power levels because the slow closing
TCV provides some pressure rerief until it completely closest.Therefore, the MCPRP limits and
LHGRFACp multipliers for the combined FFTR/coastdown with TCV slow closure scenario are
established using the limiting of the FFTR/coastdown no RPT results reported in Section 6.2.3 or
the TCV slow closure results.
Figures 6.16 and 6.17 present the ATRIUM-9B combined FFTR/coastdown with TCV slow
closure and/or no RPT MCPR, limits and LHGRFACp multipliers and Figure 6.18 presents the
FFTR/coastdown with TCV slow closure and/or no RPT GE9 MCPRp limits.
a-.- F r6===M.=k1.
EMF-2440 Revision 0 Pae 6-5
LaSalle Unit 2 Cycle 9 Diftnt Tr-Jinnt An.l is
Table 6.1 Coastdown Turbine Bypass Valves Out-of-Service'Analysis Results
Power I Flow ATRIUM GE9 (% rated /
Event % rated) ACPR LHGRFACP &CPR
FWCF 100/105 0.33 1.01 0.42
FWCF 801105 0.37 1.01 0.40
FWCF 601105 0A2 1.00 0A6
FWCF 40/105 0.54 1.00 0.55
FWCF 251105 0.86 1.08 0.88
dL=
LaSalle Unit 2 Cycle 9l'ld11, I i0 ioi•Pia 6-u- y6i-
EMF-2440 Revision 0 Paae 6-6
I
Table 6.2 Coastdown Recirculation Pump Trip Out-of-Service Analysis Results
Power I Flow ATRIUM GE9 .(% rated /
Event % rated) ACPR LHGRFACý ACPR
LRNB 100 /105 0.44 0.89 0.56
LRNB 80/105 0.42 0.91 0.45
LRNB 601105 0.39 0.91 0.47
LRNB 401105 0.39 0.87 0.41
LRNB 251105 0.29 1.01 0.28
FWCF 1001105 0.32 0.96 0.42
FWCF 80/105 0.35 0.98 0.38
FWCF 60/105 0.39 0.99 0.44
FWCF 40/105 0.47 0.97 0.48
FWCF 251105 0.86 1.06 0.88
--- N
4
.1
LaSalle Unit 2 Cycle 9 DI,.,1 "4 p••ent Anniv c
EMF-2440 Revision 0
Paoe 6-7
Table 6.3 Coastdown Turbine Control Valve Slow Closure Analysis Results
Slow Power / Flow ATRIUM-9B GE9 Valve (% rated I
Event Characteristics % rated) ACPR LHGRFACp ACPR
LRNB I TCV dosing at 2.0 sec 100/ 105' 0.44 0.93 0.55
LRNB 1 TCV closing at 2.0 sec 80/105' 0.45 0.94 0.48
LRNB 1 TCV closing at 2.0 sec 80/ 105, 0.52 0.95 0.55
LRNB 1 TCV closing at 2.0 sec 601 1051 0.59 0.96 0.61
LRNB 1 TCV closing at 2.0 sec 4011051 0.79 0.87 0.78
LRNB 1 TCV closing at 2.0 sec 25/1051 0.99 0.74 0.93
Scram initiated by high-neutron flux Scram initiated by high dome pressure
0
¶
a 193" z
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
Table 6A FFTR/Coastdown Turbine Bypass Valves Out-of-Service Analysis Results
Power I Flow ATRIUM GE9 (% rated i
Event % rated) ACPR LHGRFACý ACPR
FWCF 100/105 0.32 1.03 0.35
FWCF 801 105 0.36 1.03 0.40
FWCF 601105 0.44 1.01 0.47
FWCF 40/105 0.60 1.07 0.59
FWCF 25/105 1.10 0.95 1.12i a h
EMF-2440 Revision 0
Pacie 6-8
i
I-
EMF-2440 Revision 0 Paqe 6-9
LaSalle Unit 2 Cycle 9
Table 6.5 FFTRPCoastdown Recirculation Pump Trip Out-of-Service Analysis Results
Power i Flow ATRIUM GE9 (% rated i
Event % rated) ACPR LHGRFACp ACPR
LRNB 100I1 105 0.39 0.92 0.41
LRNB 80/105 0.38 0.94 0.44
LRNB 601105 0.40 0.92 0.41
FWCF 100/105 0.32 0.97 0.34
FWCF 801105 0.36- 0.98 0.41
FWCF 601105 0.43 0.96 0.46
FWCF 401105 0.56 0.91 0.56
FWCF 25/105 1.10 0.95 1.12
D ian#| r-n tn |A|n1a1|• l, lu Isv
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page 6-10. K)
Table 6.6 FFTR/Coastdown Turbine Control Valve Slow Closure Analysis Results
Slow Power I Flow ATRIUM-gB GE9 Valve (% rated I
Event Characteristics % rated) ACPR LHGRFACý ,CPR
LRNB I TCV dosing at 2.0 sec 100 105' 0.39 0.96 0.40
LRNB 1 TCV dosing at 2.0 sec 80 105* 0.38 0.98 0.42
LRNB 1 TCV dosing at 2.0 sec 80 105t 0.49 0.98 0.52
LRNB 1 TCV dosing at 2.0: sec 60/ 1105 0.60 0.94 0.58
LRNB 1 TCV dosing at 2.0 sec 40 1105t 0.72 0.83
LRNB I TCV closing at 2.0 sec 2511 05t 0.98 0.76 0.83
Scram initiated by high-neutron flux. Scram inifiated by high dome pressure
0
EMF-2440 Revision 0 Pane 6-11LaSalle Unit 2 Cycle 9
-. ~ A .......
0 10 20 30 40' so 6 70 so 90 100 110
Pm M oftflMd)
Power MCPRp
S(%) Limit
100 1.44 60 1.55
-25 - 2.05
-25' 2.20 0-, 2.70
Figure 6.1 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR'Limits for ATRIUM-9B Fuel
E S.
P-lant, I ransien P, naysis
LaSalle Unit 2 Cycle 9 Dl,-nt Tmneiant Analvmis
EMF-2A40 Revision 0 Panae 6-12
0 10 20 30 40 so 60 70 s0 90 100 110
Power (% of Rtd)
Power LHGRFACp
(%) Multiplier
100 0.99
60 0.97
25 0.73
25 0.73
0 0.73
Figure 6.2 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
>9
I %A
1.15
1.10
1.5
CL 1.00
0.35
0.30
0.75
0.70
0.5
L VWF ULGFAP
nI WI
EMF-2440 Revision 0 Page 6-13LaSalle Unit 2 Cycle 9
ManII I *,I~~ au is e Z.2*
1.15
0 10 20 30 40 so s0 70 so 90 100 110
POW .r(%Ctfmd
Figure 6.3 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
LaSalle Unit 2 Cycle 94"Illi I Idllbl~II IW" "a*7 =
2.05'
2.5
2MS'
2.06' L2MS
1.05
1.45
1.150 io 1 0 2DO 40 50 70 so so 100 110
PWrM % ce iMf)
Power MCPRI
(%) Umit
100 1.55
60 1.55 25 2.05 25 2.20
0 2.70
Figure 6.4 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel
EMF-2440 Revision 0 Paae 6-14
'<91
EMF-244D Revision 0
LaSalle Unit 2 Cycle 9 01 .~4 T.r esiant Anal k IDSEUu~. .
q �I I
IM I
1.20I1.15�
s-la,
U IL
-JOm0
tos
�u. �75.
G."70
am ,"aid
0 10 20 30 40 so I60
Powim % of Rd)
Power' LHGRFAC,ý (%) Multiplier
100 0.88 60 0.88 25 07 25 - 0.75 0 0.75
Figure .6 Coastdoin Re'cir'ulatio-n Pump Trip Out-of-Service Power-Dependent LHGR Multpliers for ATRIUM-9B Fuel
FVRF
a aRAC
"70 so so 100 11
a 1=" Z.= -
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
CL IL.
0 10 20 30 40 50 60
Po• .(%of Ram)
Power MCPRP (%) Limnit
100 1.67
60 1.67
25 2.05
25 2.20
0 2.70
Figure 6.6 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
EMF-2440 Revision 0
Pace 6-16
0
lie,70 so 60 100 110
EMF-2440 Revision 0 Page 6-17
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
245
2.M5
2.15
2.05
IM
1.75
1.65
IAS
1.35
1.150 10 20 30 40 50 so
P•,.% ,of Rat)
70 s0 90 100 110
Power MCPRP (%) Limit
100 - - 1.55
80 ... 1.62 "80 .. 1.70 25 2.15 25 - 2.20
0 2.70
Figure 6.7 Coastdown Turbine Control Valve Slow Closure and/or Recirculation'Pump Trip Out-of-Service Power-Dependent
MCPR Limits for ATRIUM-SB Fuel
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page6-18
0 10 20 30 40 50 s0 70 so 90 100 110
Power (% of Rawd)
Power LHGRFACp
(%) Multiplier
100 0.88
80 0.88 80 0.85 25 0.68 25 0.68
0 0.68
Figure 6.8 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
LHGR Multipliers for ATRIUM-9B Fuel
1.30
12.
1~.2
1.15
1.10
C. 1.00'
M1S
0.90
0.50
0.50
0.7S
0.70
0.65
0.60
LaSalle Unit 2 Cycle 9rPWdl Ir | sI'eI L ,rn Inyioi
EMF-2440 Revision 0 Paoe 6-19
0 10 M 30 40 so 00 70 so s0 10 110
POWMM of Room
Power MCPRN
(%) Limt
100 1.67
80 1.85 80 1.96
25 2.15 25 2.20
0 2.70
Figure 6.9 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
MCPR Umits for GE9 Fuel
LaSalle Unit 2 Cycle 9 r I.l 4,,% *rl,,,lli. i l.# A .. "lIv~
a" I O 'a1 W"ala I " - .2 -a
EMF-2440 Revision 0 Paae 6-20
�Y
0 10 20 30 40 50 so 70 80 sO 1W0 110
Power MCPRp
(%) Limit
100 1.44 60 1.57 25 2.30 25 2.35
0 2.85
Figure 6.10 FFTR/Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel
�yJ�
245
115.
IM.
1.75.
IAS
1.25
1.M
LaSalle Unit 2 Cycle 9r aI.SL 0" 1=
a. ¶.W U
�OJ5
-a �
D.AO
EMF-2440 Revision 0 Page 6-21
0 1o 20 30 40 50 go 70 so o0 100 110
Pow*(% of ad)
Power LHGRFACp (%) Multiplier
100 0.99
60 0.97
25 0.65
25 0.65
0 0.65
Figure 6.11 FFTRlCoastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
z"5' 2.75'
2.55'
2. 5
0. 2AS
S2.05'
* 1.35,
1m.5 1.75
1.55 1J45
EMF-2440 Revision 0 Page 6-22
K.)
'U0 10 20 30 40 so 70 so g0 10 110
POUsr(%of Room
Power MCPRq
(%) Umft
100 1.53 60 1.64 25 2.30 25 2.35
0 2.85
Figure 6.12 FFTR/Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
�y-)
LaSalle Unit 2 Cycle 9
:IM•
215
1IM"
1LO5"
1-!5.
lAS'
1L25•
EMF-2440 Revision 0 Pane 6-23
a 10 30 40 W W 70 so W 10 110
Pow" (%o yEwo
Power MCPRO
(%) Limit
100 1.55
60-- 1.56 25 2.30 25 2.35
0 2.85
Figure 6.13 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel
Mani |I~l~l~ I L wi i 't4 "a lyr
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
1.30
1.25
1.20
1.15
1.10
1.00
a."
o
0.75
0.70
0.05
0 10 20 30 40 so 60 70 so 90 100 110
Pvwrf% of ra"
Power LHGRFACp.
(%) Multiplier
100 0.88
60 0.88
25 0.65
25 0.65
0 0.65
Figure 6.14 FFTR/Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel
q
EMF-.2440 Revision 0 Page 6-24
)EMF-2440 Revision
0
Page
6-24
EMF-2440 Revision 0 Page 6-25LaSalle Unit 2 Cycle 9
Plant Transient Analysis
225
2.15
2015
1.735
us55
IAS
IM.
0 10 20 W0 40 s0 s0 70
PMrAr fM*Mb)
Power MCPRi (%) iUmit
100 1.67
60 1.67
25 2.30 25 2.35
0 2.85
Figure 6.16 FFTR/Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel
80 s0 100 110
EMF-2440 Revision 0 Page 6-26LaSalle Unit 2 Cycle 9
Mant ran [ en Z2~I
29551 2.75] 2.65
2M55
245
2M' 2.25~
21S
2.05
S1.95
1.85
1.75
.AS
1.45
1.35-
1.15
0 10 2 30 40 50 0 70 00 go 100 110 PowmCrAof d)
Power MCPR• (%) Umit
100 1.55
80 1.62
80 1.70
25 2.30 25 2.35
0 2.85
Figure 6.16 FFTRlCoastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
MCPR Limits for ATRIUM-9B Fuel
I*SaruvTCVcakuu *LRMNo MyT •F•€:F Noi WPT
U
0
U,
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
1.
1.15.
1.10
1.05,
,L 1.0 U
OAS
0.•5
0.70
0.15
0-go'0 10 20 30 40 so 60
POW8 f% of Ad
70 • s o 10 100 110
Power LHGRFACp (%) M Multiplier
100 0.88 80 0.88 80 0.85 25 0.65 25 - 0.65
0 - 0.65
Figure 6.17 FFTR/Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
LHGR Multipliers for ATRIUM-9B Fuel
--.. ,. b4ha# It"WMW6,.,;
EMF-2440 Revision 0 Page 6-27
*LRH No RPT
* FVCF No RT
LHGRPMACP
%M
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
Ix
0 10 20 30 40 50 so 70 s0 so 100 110
POW- r, of .M;
Power MCPRp (%) Limit
100 1.67
80 1.85 80 1.96 25 2.30 25 2.35
0 2.85
Figure 6.18 FFTRlCoastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent
MCPR Limits for GE9 Fuel
Siemens Power Comoration
EMF-2440 Revision 0
Paae 6.28
0
K
Ip .
EMF-2440
LaSalle Unit 2 Cycle 9 - Revision 0 Plant Transient Analysis - Page 7-1
7.0 Maximum Overpressurization Analysis
This section describes the maximum overpressuri-ation analyses performed to demonstrate
compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the
safety/relief valves at LaSalle Unit 2 have sufficient capacity and performance to prevent the
pressure from reaching the pressure safety limit of 110% of the design pressure.
7.1 Design Basis
The MSIV closure analysis was performed with the SPC plant simulator code COTRANSA2
(Reference 4) at a powertfnow state point of 102% of uprated power/1 05% flow. Reference 9
indicates that an EOFP + 1000 MWdWMTU exposure is limiting for the overpressurization
analysis. The following assumptions were made in the analysis.
The most critical active component (direct scram on valve position) was assumed to fail. However, scram on high-neutron flux and high-dome pressure is available.
At ComEd's request, analyses were performed to determine the minimum number of the highest set point SRVs required to meet the ASME and Technical Specification pressure limits. It was determined that having the 10 highest set point SRVs operable will meet the ASME and Technical Specification pressure limits. In order to support operation with I SRV out-of-service, the plant configuration needs to include at least 11 SRVs. As per ASME requirements, the SRVs are assumed to operate in the safety mode.
TSSS insertion times were used.
The initial dome pressure was set at the maximum allowed by the Technical Specifications (1035 psia).
* An MSIV closure time of 1.1 seconds was assumed in the analysis.
EOC RPT is assumed inoperable; ATWS (high-dome pressure) RPT is available.
7.2 Pressurization Transients
Results of analysis for the MSIV closure event initiated at 102% power/1 05% flow are presented
in Table 7.1. Figures 7.1-7.5 show the response of various reactor plant parameters to the
MSIV closure event. The maximum pressure of 1346.2 psig occurs in the lower plenum at
approximately 4.4 seconds. The maximum dome pressure of 1319.9 psig occurs at
4.6 seconds. The results demonstrate that the maximum vessel pressure limit of 1375 psig and
dome pressure limit of 1325 psig are not exceeded.
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0 Page 7-2 0©
Table 7.1 ASME Overpressurization Analysis Results 102%PI105%F
Peak Peak Maximum Maximum Neutron Heat Vessel Pressure Dome
Flux Flux Lower-Plenum Pressure Event (% rated) (% rated) (psig) (psig)
MSIV closure 373.7 136.6 1346.2 1319.9
'0>
m.ni,•v Prmar Cbrnratinn
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
a W
I.z
0 9.z
UJ W LaJ
TWE.. SECONDS
Figure 7.1 Overpressurization Event at 1021105 MSIVClosuie Key Parameters
Siemens Power Comoration
EMF-2440 Revision 0
Page 7-3
La
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
4.0 1 TDAE, SECONDS
Figure 7.2 Overpressurization Event at 102/105 MSIV Closure Vessel Water Level
EMF-2440 Revision 0
Page 7-4
0 II w N
.z tbJ w
0 m
z
w w L&J w
W (.
in, W I-
..J UJ U)
LaSalle Unit 2 Cycle 9 M Tr neint Analv~
TIE, SECONDS
Figure 7.3 Overpressurization Event at 1021105 --MSIV Closure Lower-Plenum Pressure
a"11 @ai L=**~ Y~*
EMF-2440 Revision 0 Peae 7-5
UI)
w
D z
w
0 Li
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
V. IAJ In
0
D
EMF-2440 Revision 0
Page 7-6 U
4.0 TIME, SECONDS
Figure 7.4 Overpressurization Event at 102/105 MSIV Closure Dome Pressure
IL.
EMF-2440 Revision 0 Page 7-7LaSalle Unit 2 Cycle 9
.an i l-a n iL le U ilaiy
1500.0
U)
00 .J
0
L
i/)
500.0,
n0
.0 1.0 2.A0 . _4.0 TIME,- SECONDS
5D06. 7.0
Number off Opening
Bank _________ SRVs - Pressure (psia)
01 "'__NA'
2 2'" 1235.3
3 4 1245.6 -4 4 1255.9
5 .. . _ _ NA
Figure 7.5 Overpressurization Event at 1021105MSIV Closure Safety/Relief Valve Flow Rates
SRV BANK 1 SRV BANK 2 SRV BANK 3 SRV BANK 4 SRV BANK 5
- "--- ------- ----ii
:I ...
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 8-1
8.0 References
1. Letter, D. E. Garber (SPC) to R. J. Chin (CornEd), "LaSalle Unit 2 Cycle 9 Calculation Plan,* DEG:00:031, February 25,2000.
2. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
3. XN-NF-80-19(P)(A) Volume 1 Supplement 3, Supplement 3 Appendix F, and Supplement 4, Advanced Nuclear Fuels Methodology for Boiling Water Reactors: Benchmark Results for the CASMO-3G/MICROBURN-B Calculation Methodology, Advanced Nuclear Fuels Corporation, November 1990.
4. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation. August 1990.
5. ANF-524(P)(A) Revision 2 and Supplements I and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
6. ANF-1125(P)(A) and Supplement I and 2, ANFB Critical Power Correlation, Advanced Nuclear Fuels Corporation, April 1990.
7. XN-NF-80-1 9(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
8. EMF-2323 Revision 0, LaSalle Unit 2 Cycle 9 Principal Transient Analysis Parameters, Siemens Power Corporation, March 2000.
9. EMF-95-205(P) Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis for A TRIUMT-gB Fuel, Siemens Power Corporation, June 1996.
10. EMF-95-049(P), Application of the ANFB Critical Power Correlation to Coresident GE Fuel at the Quad Cities and LaSalle Nuclear Power Stations, Siemens Power Corporation, October 1995.
11. XN-NF-84-105(P)(A) Volume 1 and Volume I Supplements I and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
12. EMF-1 125(P)(A) Supplement 1 Appendix C, ANFB Critical Power Correlation Application for Co-Resident Fuel, Siemens Power Corporation, August 1997.
13. XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Therrna( Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
EMF-2440
LaSalle Unit 2 Cycle 9 Revision 0
Plant Transient Analysis Page 8-2
8.0 References (Continued)
14. LaSalle County Nuclear Station Unit 2 Technical Specifications. as amended.
15. EMF-2437 Revision 0, LaSalle Unit 2 Cycle 9 Reload AnalysiS, Siemens Power
Corporation, October 2000.
16. EMF-1903(P) Revision 3, Impact of Failed/Bypassed LPRMs and TIPs and Extended
LPRM Calibration Interval on Radial Bundle Power Uncertainty, Siemens Power
Corporation, March 2000.
17. ANF-1 125(P)(A") Supplement 1, Appendix E, ANFB Critical Power Correlation
Determination of ATRIUMT"-9B Additive Constant Uncertainties, Siemens Power
Corporation, September 1998.
18. ANF-1373(P), Procedure Guide for SAFLIM2, Siemens Power Corporation, February 1991.
19. Letter, D. E. Garber (SPC) to R. J. Chin (CornEd), "LaSalle Unit 2 Cycle 9 Transient Power History Data for Confirming Mechanical Limits for GE9 Fuel,, DEG:00:185, August 3, 2000D....
20. Letter, D. E. Garber (SPC) to R.-J. Chin (CornEd), 'LaSalle Unit 2 Cycle 8 Abnormal Idle
Recirculation Loop Startup Analysis,' DEG:99:070, March 8, 1999.
21. Letter, D. E. Garber (SPC) to R. J. Chin (CornEd), "Description of Measured Power Uncertainty for POWERPLEXo Operation Without Calibrated LPRMs,' DEG:00:061, March 7, 2000.
22. Letter, J. H. Riddle (SPC) to R. J. Chin (CornEd), "Scram Surveillance Requirements for MCPR Operating Limits," JHR:96:397, October 8, 1996.'
23. EMF-2277 Revision 1, LaSalle Unit I Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 1999.
24. Letter, D. E. Garber (SPC) to R. J. Chin (CornEd), "Extension of LPRM Calibration Interval to 2500 EFPH," DEG:00:088, April 17, 2000.
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page A-1
Appendix A Power-Dependent LHGR Limit Generation
The linear heat generation rate (LHGR) operating limit is established to ensure that the steady
state LHGR (SSLHGR) limit is protected during normal operation and that the protection against
power transient (PAPT) LHGR limit is protected during an anticipated operational occurrence
(AOO). To ensure that the LHGR operating limit provides the necessary protection during
operation at off-rated conditions, adjustments to the SSLHGR limits may be necessary. These
adjustments are made by applying power and flow-dependent LHGR multipliers (LHGRFACP and
LHGRFACI, respectively) to the SSLHGR limit. The LHGR operating limit (LHGROL) for a given
operating condition is determined as follows:
LHGROL = min [LHGRFACp x SSLHGR, LHGRFACf x SSLHGRJ
The power-dependent LHGR multipliers (LHGRFACp) are determined using the heat flux
excursion experienced by the fuel during AQOs. The heat flux ratio (HFR) is defined as the ratio
of the maximum nodal transient heat flux over the maximum nodal heat flux at the initiation of 'x
the transient. The HFR Provides a measure of the LHGR excursion during the transient. The
PAPT limit divided by the SSLHGR limit provides an upper limit for the HFR to ensure that the
PAPT LHGR limit is not violated during an AOO. LHGRFACp is set equal to the minimum of the
PAPTISSLHGR ratio over HFR, or 1.0. Based on the ATRIUM-9B LHGR limits presented in
Reference A-i, LHGRFACp is established as follows:
PAPT = 1.35
SSLHGR
HFR = Q,
LHGRFACP = min LHFR 'I"
In some cases, the established MCPR limit precludes operation at the SSLHGR limit. This
allows for a larger LHGR excursion during the transient without violating the PAPT LHGR 5mimkJ
This approach was used to provide less restrictive LHGRFACp multipliers for some cases.
EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page A-2
References
A.1 EMF-2404(P) Revision 1, Fuel Design Report for LaSalle 2, Cycle 9 ATRIUM'rA-9B Fuel Assemblies, Siemens Power Corporation, September 2000.
Siemen Pow Corvoration
LaSalle Unit 2 Cycle 9 Plant Transient Analysis
EMF-2440 Revision 0
Controlled Distribution
Richland
D. E. Garber (12 copies)
Uncontrolled Distribution
E-Mail Notification
D. G. D. B. O.C. M. E. J. M. J. G. R. R. P.D.
Carr McBumey Brown Garrett Haun Ingham Schnepp Wimpy
4'.'
Simens Power Corporation
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
Attachment 4
ARTS Improvement Program Analysis, Supplement 1 (Excerpts)
LaSalle Unit 2 Cycle 9 August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
TOP/MOP and MAPFACp Requirements
Equipment Out of Service
No EOOS RPT OOS TBV OOS No EOOS RPT OOS TBV OOS
TOP
24.9 30.3 28.7 50.1 57.1 62.7
MOP
25.2 30.6 30.0 52.0 59.0 64.5
Calculated MAPFACp
1.0 1.0 1.0
0.83 0.83 0.79
1.0 1.0 1.0
0.61 0.61 0.61
(a) Based on the GE9/10 LHGR Improvement Report, the MAPFACs are applied to LHGR (Reference 19)
Uý
LaSalle Unit 2 Cycle 9
Limiting AOO
LRNBP LRNBP FWCF FWCF FWCF FWCF
Power
100 100 100 25 25 25
Generic MAPFACp
August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
Attachment 5
TCV Slow Closure Analysis (Excerpts)
LaSalle Unit 2 Cycle 9 August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
Table 4. - TOP and MOP Values for the Off-rated Transient Events
LRNBP, One TCV Slow LRNBP, All TCV Slow Closure at 50%/s, 3 TCV Fast Closure at 19%/s
Closure
Calculated TOP 26.17 49.27
Calculated MOP 26.17 55.30
Adjusted MOP 60.83
Required MOP 38.0
Required MAPFAC 0.62
Limiting MACFAC 0.60 (a)
Note: (a) Based on Figure 3.2-2 in COLR.
(b) Based on the GE9/10 LHGR Improvement Report, the MAPFACs are applied to LHGR (Reference 19).
LaSalle Unit 2 Cycle 9 August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
?ITu culp, I
i6s.� i
5�
II1 [SIMI2
.II lta m , i1r eszcins
Figure 1. LRNBP from Rated Power, All TCV Fast Closure, Direct Scram, EOC-RPT
LaSalle Unit 2 Cycle 9
'U
S
a
I LEVEL( NcH.-N[i-S[P-$l] 2 VEss[R STEAifLOu 3 u ) I S I E I oAf LOWt
M~ 19.i U
August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
IlK ulLIKmsI IlK 151Cl13
I
Ill ISICOl9l 11K slgllli
Figure 2. LRNBP from Rated Power, One TCV Slow Closure(50O/6second)/mhree TCV Fast Closure, Flux Scram, EOC-RPT OOS
LaSalle Unit 2 Cycle 9
I-
!
August 2002
1I.8
m
i
S.
U
T1m 111111
Figure 3. LRNBP from 50% Power, One TCV S-low Closure(500/o/second)fIhree TCV Fast Closure, Flux Scram
LaSalle Unit 2 Cycle 9
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
I NEUrc 00 FLU3 2A SULRFCE PEAT FLU 3 COR I MT| FLOWl
I V1S I;EL PRESS PISIPS]) 2 SAF IT VALVE FLOM B REt IEF VALVE FLOW
0.I
RIK fugiml
IRK lUlM
80.4.
RIK 1"IM11
I Wt ) BE (ACTIVITY
D OP ILLAtl tAC I IVITY
AV Iff l flur;I?
9.0.
16.4i
August 2002
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
I NIEU 00 FLUX 2 AVE SURFACE HEA1 FLUX 5 COD . InL FLOiW
I"LIP
I LIV L4I1CH-R[F-SEP-SKWTI 2 VIS EL $TE&NFLCU I vUR UL S'iDRFLOI
• •. rrr jani~ ;, mu
e.0
III I Itg aIi
I
"I"
I rot I RACTIVITY 2 DOP Lfl REACTIVIZTY
L.II~~ SCR- LREACTIVIrTY ,
-u°1
-41.'
TIR IK91011111
Figure 4. LRNBP from 500/6 Power, All TCV Closure at 19%/second, Pressure Scram
LaSalle Unit 2 Cycle 9
m
U
I S •EL Pl SI E1S6IPSI3 2 SAF I1 VALVE FLmui 3 REL IF VALVE FLOW a gave cc€ wag r ri alU
August:2002
•D
UW.0
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
Attachment 6
LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity
LaSalle Unit 2 Cycle 9 August 2002
Framatome ANP Richland, Inc. Proprietary
FRAMATOME A-iIP
March 22, 2001 DEG:01:046
Dr. R. J. Chin Nuclear Fuel Services (Suite 400) Exelon Corporation 1400 Opus Place Downers Grove, IL 60515-5701
Dear Dr. Chin:
LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity
Ref: 1: LaSalle County Nuclear Station Unit 2 Technical Specifications, as amended.
Ref: 2: EMF-2440 Revision 0, LaSalle Unit 2 Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 2000.
Ref: 3: EMF-2437 Revision 0, LaSalle Unit 2 Cycle 9 Reload Analysis, Siemens Power Corporation, October 2000.
Ref: 4: Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 2 Cycle 9 Base Case Operating Umits for Proposed ITS Scram Times,* DEG:01:014, January 18, 2001.
Ref 5: Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "Transmittal of Condition Report 9191," DEG:01:038, February 27, 2001.
Exelon has proposed replacing the current Technical Specifications (Reference 1) with Improved Technical Specifications (ITS) during LaSalle Unit 2 Cycle 9 (L2C9) operation. The operating limits for L2C9 (References 2 and 3) are established consistent with the scram times presented in Reference 1 and are not consistent with the proposed ITS surveillance times. Exelon has requested that FRA-ANP perform analyses to support a mid-cycle transition to the ITS for base case operation and one equipment out-of-service (EOOS) scenario. Reference 4 described the determination of analytical scram times consistent with the ITS and provided base case operating limits. Reference 5 identifies an error in the fuel thermal conductivity used in the transient analyses for LaSalle, including the analyses provided in Reference 4.
Framatome ANP Richland, Inc.
2101 Horn Rapids Road Tel: (509) 375-8100 Richland, WA 99352 Fax: (509) 375-8402
Framatome ANP Richland, Inc. Proprietary
Dr. R. J. Chin DEG:01:046 March 22, 2001 Page 2
'-I
The attachment provides the L2C9 base case and slow TCV closure/FHOOS and or no RPT transient analysis results and operating limits using the analytical scram times and the corrected fuel thermal conductivity. The base case operation limits provided in the attachment supercede those transmitted in Reference 4.
Very truly yours,
David Garber
Project Manager
slg
Enclosure
cc: P. Kong
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-1 \J
LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected
Fuel Thermal Conductivity
Limiting Condition for Operation (LCO) 3.1.3.3 of the current LaSalle Unit 2 Technical Specifications
(Reference 1) specifies the average scram insertion times of all operable control rods. The average
control rod insertion times must not exceed the scram times f6r the requirements of LCO 3.1.3.3 to
be met. Exelon is planning to implement Improved Technical Specifications (ITS) for LaSalle Unit 2
during Cycle 9. The scram surveillance times in the proposed ITS are slightly more restrictive than
those presented in Reference 1. Additionally, the surveillance requirement for the ITS is that each
rod must meet the scram times. The LaSalle Unit 2 Cycle 9 (L2C9) operating limits (References 2
and 3) are based on the average scram times presented in Reference 1. Therefore, the limiting
transient analyses used to set the operating limits provided in References 2 and 3 must be
reanalyzed with revised scram times in order to support the mid-cycle implementation of the ITS.
FRA-ANP provided proposed ITS surveillance scram times to Exelon in Reference 4, Table 1. The
Reference 4 analytical scram times are presented in Table 1 for completeness.
FRA-ANP informed Exelon of an error in the fuel thermal conductivity used in COTRANSA2
calculations (Reference 5). The analysis results presented in Tables 2 and 3 include the effect of the
corrected fuel thermal conductivity.
Reference 9 provided a disposition of LOCA and UFSAR events for ITS scram times for LaSalle.
The Reference 9 disposition remains applicable.
Base Case Operation
Reference 4 provided base case operating limits for the proposed ITS scram times. After
Reference 4 was issued, FRA-ANP informed Exelon of an error in the fuel thermal conductivity used
in COTRANSA2 calculations (Reference 5). The analyses provided in Reference 4 have been
reanalyzed using the corrected fuel thermal conductivity. The results of these analyses are
presented in Table 2.
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-2
Figures 1 and 2 present the revised base case MCPRp limits for the ATRIUMTM-9B* and GE9 fuel,
respectively. The sum of the L2C9 safety limit MCPR (1.11 per Reference 2) and the ACPR results
from Table 2 are also presented in Figures 1 and 2.
The Reference 2 base case LHGRFACp multipliers and the LHGRFACp results from Table 2 are
presented in Figure 3. Review of Figure 3 shows that all of the ATRIUM-9B LHGRFACp results are
above the LHGRFACp multipliers, and therefore, the Reference 2 base'case LHGRFACp multipliers
remain applicable for the proposed ITS scram times.
TCV Slow Closure/FHOOS and/or No RPT
Exelon requested that FRA-ANP provide operating limits for the most limiting equipment out-of
service (EOOS) scenario provided in Reference 2. Review of the Reference 2 limits shows that the
most limiting two-loop operation EOOS scenario is TCV slow closure/FHOOS and/or no RPT.
The TCV slow closure/FHOOS and/or no RPT limits consider transient analysis results from.the
following scenarios: TCV slow closure (up to all four valves), EOC RPT OOS. FHOOS, and a
combination of FHOOS and EOC RPT OOS. (Note: TCV slow closure analyses with FHOOS are
bound by TCV slow closure analyses at nominal feedwater temperature, and therefore, no specific
analyses are required for this scenario.) In order to reduce the workscope required to establish new
limits, only a subset of the analyses reported in Reference 2 have been reanalyzed. 'Review of
Figures 5.16, 5.17 and 5.18 in Reference 2 show that the TCV slow closure analyses are limiting for
all power levels above 25% power, the FWCF no RPT with FHOOS is limiting at 25% power.
Additionally, these figures show that there is considerable margin between the analysis results and
the limits at power levels of 400 and 60%.
Table 5.5 of Reference 2 was reviewed to determine which specific TCV slow closure analyses
required reanalysis to establish the limits. Tables 5.1 (FHOOS) and 5.4 (EOC RPT OOS) of
Reference 2 were also reviewed since the limits are applicable for EOC RPT OOS or FHOOS only.
Table 3 presents the analysis results required to adequately establish the slow TCV closurefFHOOS
and/or no RPT limits.
Figures 4 and 5 present the revised slow TCV closure/FHOOS and/or no RPT MCPRp limits for the
ATRIUM-9B and GE9 fuel, respectively. The sum of the L2C9 safety limit MCPR (1.11 per
Reference 2) and the ACPR results from Table 3 are also presented in Figures 4 and 5.
ATRIUM is a trademark of Framatome ANP.
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-3
Figure 6 presents the revised slow TCV closure/FHOOS and/or no RPT LHGRFACp multipliers for
the ATRIUM-9B fuel.
The MCPR, limits and LHGRFACp multipliers provided in Figures 4-6 protect operation with up to
four TCVs closing slowly, EOC RPT OOS, FHOOS and any combination of up to four TCVs closing slowly, EOC RPT OOS and FHOOS. The only equipment out-of-service scenarios provided in Reference 2 not explicitly protected by the slow TCV closureIFHOOS and/or no RPT limits are single-loop operation (discussed below), turbine bypass valves OOS, and abnormal startup of an idle
loop.
Comparison of turbine bypass valves OOS and the TCV slow closure/FHOOS and/or no RPT limits in Table 2.2 of Reference 3 shows the TCV slow closure/FHOOS and/or no RPT limits clearly bound the turbine bypass valves OOS limits. Consequently, applying the TCV slow closure/FHOOS and/or no RPT limits will protect operation with the turbine bypass OOS.
No analyses were performed to address the abnormal startup of an idle loop limits with ITS scram times and the corrected fuel thermal conductivity.
Single-Loop Operation
Figures 1-3 provide the two-loop operation (T'LO) MCPRp limits and LHGRFACp multipliers for base case operation. Reference 7 indicates that the consequences of base case pressurization transients in single-loop operation (SLO) are bound by the consequences of the same transient initiated from
the same power/flow conditions in TLO and that the TLO base case ACPRs and the LHGRFACp multipliers remain applicable for SLO. Reference 2 indicates the L2C9 TLO safety limit MCPR is 1.11 and the SLO safety limit MCPR is 1.12. Since the TLO ACPR results are applicable to SLO, the
SLO ATRIUM-9B and GE9 MCPRp limits can be determined by adding 0.01 to the base case operation MCPRp limits provided in Figures I and 2 to account for the increase in safety limit MCPR.
The base case LHGRFACp multipliers shown in Figure 3 remain applicable for SLO.
The conclusion that TLO ACPR results generally bound SLO results has been demonstrated for both
base case operation and some equipment out-of-service scenarios for other BWRs. Although
specific L2C9 analyses for a combination of TCV slow closure/FHOOS'and/or no RPT in SLO have
not been performed, FRA-ANP expects the TLO operation ACPR results would remain applicable ini
SLO for this scenario. Therefore, SLO MCPRp limits for TCV slow closure/FHOOS and/or no RPT
can be determined by adding 0.01 to the TCV slow closure/FHOOS and/or no RPT MCPR, limits
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-4
reported in Figures 4 and 5 to account for the increase in safety limit MCPR. The Figure 6 TCV slow
closure/FHOOS and/or no RPT LHGRFACp multipliers remain applicable for SLO.
GE9 Mechanical Limits
Reference 6 provides an evaluation of the GE9gmechanical limits for L2C9. An evaluation of the GE9
mechanical limits for the rated power analyses reported in Tables 2 and 3 was performed. It has
been demonstrated that the maximum nodal power ratio history curve for the analyses are bound by
the previously approved L2C9 curve. Therefore, it is FRA-ANP's position that no further evaluation
of the GE9 mechanical limits is required.
References
1. LaSalle County Nuclear Station Unit 2 Technical Specdifications, as amended.
2. EMF-2440 Revision 0, LaSalle Unit 2 Cycle 9 Plant Transient Analysis, Siemens Power "Corporation, October 2000.
3. EMF-2437 Revision 0, LaSalle Unit 2 Cycle 9 Reload Analysis, Siemens Power Corporation, October 2000.
4. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 2 Cycle 9 Base Case Operating Limits for Proposed ITS Scram Times," DEG:01:014, January 18, 2001.
5. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), 'Transmittal of Condition Report 9191,' DEG:01:038, February 27, 2001.
6. Letter, D. E- Garber (SPC) to R. J. Chin (CornEd), "LaSalle Unit 2 Cycle 9 Transient Power History Data for Confirming Mechanical Limits for GE9 Fuel," DEG:00:185, August 3, 2000.
7. EMF-95-205(P) Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis forATRIUMh-9B Fuel, Siemens Power Corporation, June 1996.
8. EMF-2323 Revision 0, LaSalle Unit 2 Cycle 9 Principal Transient Analysis Parameters, Siemens Power Corporation, March 2000.
9. Letter D. E. Garber (SPC) to R. J. Chin (ComEd), "Evaluation of Improved Technical Specification Scram Times at Dresden, LaSalle and Quad Cities Station," DEG:99:195, July 26, 1999.
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-5
Table I Proposed ITS Scram Insertion Times
if 4
" The 0.20-second delay is considered a nominal value that cannot be verified by the plant Therefore, the transient analysis calculations are performed to bound a range of no delay (linear insertion from start signal to notch 45) to a delay value just before notch 45. This is consistent with the information provided in Reference 8.
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-6
Table 2 Base Case Transient Analysis Results With Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity
I Peak Peak Power ATRIUM-9B ATRIUM-9B GE9 Neutron Flux Heat Flux I Flow ACPR LHGRFACp-- ACPR (% rated) (% rated)
LRNB
FWCF - -
* The analysis results presented are from an exposure prior to EOC. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-'7 ,
Table 3 EOOS Transient Analysis Results With Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity
Slow TCV Closure
100/105" 1 TCV closing in 2.0 seconds 0.42
80 / 57.2* 1 TCV dosing in 2.0 seconds 0.51
80 / 105t 2 TCV dosing in 2.0 seconds 0.544
80 / 57.2t 2 TOY closing in 2.0 seconds 0.59
25 / 105"t 1 TCV closing in 2.0 seconds 1.00 9,LRNB
No RPT
100/105 iNA o0.40 0.89 0.51
FWCF With FHOOS
251105 I NA 1.06* 0.6813: 1.13:
FWCF No RPT With FHOOS
25/105 7 I NAI 1. 0.67* 1.11*
Scram initiated by high neutron flux. Scram initiated by high dome pressure. The analysis results presented are from an exposure prior to EOC. The'ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
t 4t -
Framatome ANP Richland, Inc. Proprietary
DEG:01:046
Z75
Z65
Z55
2-45
2.35
225
.15
a.205
S1.95
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CL 7O
1.65-
Attachment Page A-8
0 10 20 30 40 50 , 60 70 80 90 100 110
PMer(% of Rtd
Power MCPRp (%) •Limit
S.-100 1.41 60 1.48 25 1.93
25- -2.20 0 -2.70
Figure 1 EOC Base.Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel With Proposed ITS :Scram Times and
- Corrected Fuel Thermal Conductivity
Framatome ANP Richland, Inc. Proprietary
DEG:01:046
ZS•
24!
Z3M
Z2M
2.15
.Z05
1.95
Attachment Page A-9
0 10 20 30 40 so SO 70 80 90 100 110
Poer(%ofRMd)
Power MCPRp
(%) Limit
100 1.51
60 1.53
25 2.01
25 2.20
0 2.70
Figure 2 EOC Base Case Power-Dependent MCPR Limits for GE9 Fuel With Proposed ITS Scram Times and
Corrected Fuel Thermal Conductivity
Framatorne ANP Richland, Inc. Proprietary
DEG:01:046
1.3C
1.25
1.20
1.15
1.10
1.05
0. 1.00 ,.)
0 095
3non
Attachment Page A-10
0 10 20 30 40 50 60 70 60 90 100 110
Power (% of Rated)
Power LHGRFACp (%) Multiplier
100 1.00 60 1.00
25 0.77
25 0.77
0 0.77
Figure 3 EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel With Proposed ITS Sciram Times and'
Corrected Fuel Thermal Conductivity-
Framatome ANP Richland, Inc. Proprietary
DEG:01:046 Attachment Page A-1I
.,J
a.
0 10 20 30 40 50 60 70 80 90 100 110
Power MCPRp (%) Umit
100 1.53 80 1.62 80 1.70 25 2.17
25 2.35
0 2.85
Figure 4 EOC Slow TCV Closure/FHOOS and/or No RPT Power-Dependent MCPR Limits for ATRIUM-9B Fuel With Proposed ITS Scram Times and
Corrected Fuel Thermal Conductivity
L-
Framatome ANP Richland, Inc. Proprietary
DEG:01:046
245
2.85
2.7I Z15
1.55.
2.45"
2.35
2.25
1* 2.15
1.96'
1.85"
1.75" 1.855' 1.56"
1.45'
1.35"
1.15"
Attachment Page A-12
0 10 20 30 40 50 60
POW Mr( of RPadM
Power MCPRp
(%) Limit
100 1.63
80 1.86
80 1.96
25 2.24
25 2.35
0 -- 2.85
70 80 9o 100 110
Figure 5 EOC Slow TCV Closure/FHOOS and/or No RPT Power-Dependent MCPR Limits for GE9 Fuel With Proposed ITS Scram Times and
-Corrected-Fuel Therrtl Condutivity.. ,........
*LRNBNobF'TT
*FVCFNOFtPTvI~hFHOOS FVC WtFhU FHOOS
*Skw TCV ~o5uir
Framatome ANP Richland, Inc. Proprietary
DEG:01:046
1.
Attachment Page A-,4 '
0j
30 .
* LRM No RPT
F F•F NoW RPTi h RiOOS A FWCFWi -iOOS
SSlowCvcasure
ILUGRF
0 10 20 30 40 s0 60
Power (% ofRaadem
Power LHGRFACp (%) Multiplier
100 0.89 80 0.89 80 0.85 25 0.67
25 0.67
0 0.67
70 80 90 100 110
Figure 6 EOC Slow TCV Closure/FHOOS and/or No RPT Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel With Proposed ITS Scram Times and
Corrected Fuel Thermal Conductivity
1.15
1.10.
1.05
ۥ1.00 0
0.95
0.85'
0.75"
0.70
065"
0 0
0
1.
125-
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
Attachment 7
LaSalle Unit 2 Cycle 9 Equipment Out-of-Service Operating Limits
Using Nominal Scram Speed And
Exposure Limited to 14,000 MWd/MTU
LaSalle Unit 2 Cycle 9 August 2002
Framatome ANP, Inc. Proprietary
59FRAMAOME ANP
January 10, 2002 DEG:02:009
Mr. F. W. Trikur Exelon Nuclear Nuclear Fuel Management 4300 Winfield Road Warrenville, IL 60555
,' D'e
* "O',. 6t'•>
Dear Mr. Trikur.
LaSalle Unit 2 Cycle 9 Equipment Out-of-Service Operating Limits Using Nominal Scram Speed and Exposure Limited to 14,000 MWdlMTU
Reference: 1) Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity," DEG:01:046, March 22,2001.
2) Exelon Task Order, L2C9 TCV Slow Closure Analysis with NSS Insertion Times, NFM-MW-B040, Exelon, November 29, 2001.
Turbine control valve (TCV) testing at LaSalle Unit 2 indicated that some of the turbine control valves do not meet the fast closure criteria. Due to TCV slow closure, the plant must be operated using the more restrictive TCV slow closure equipment out-of-Service (EOOS) MCPRp limits provided in Reference 1. Based on the Reference 1 EOOS MCPRp limits, Exelon expects to run into MCPR margin problems in February 2002. Exelon requested FRAANP (Reference 2) to provide revised ATRIUM Tm-9B EOOS limits that will Improve MCPR margin to support continued operation until a mid-cycle outage to correct the TCV closure rate.
The attachment provides the L2C9 TCV slow closure/FHOOS and/or no RPT transient analysis results and operating limits based on nominal scram speed and a maximum cycle exposure of 14,000 MWd/MTU. The operating limits in the attachment provide significant additional margin as noted by comparison of the 100% power MCPRp limit of 1.42 versus 1.53 provided in Reference 1. The GE9 operating limits presented in Reference I remain applicable.
Please forward the attachment to Exelon at your earliest convenience.
Very truly yours,
D. E. Garber Project Manager
Framatome ANP, Inc.
Tel: (509) 375-8100 I-. sc-n .--
2101 H=m Rapids Road "8_6ý,,Ai, 1. 1 A f-,,"iiB .%•l
Framatome ANP, Inc. Proprietary
DEG:02:009 Attachment Page A-1
LaSalle Unit 2 Cycle 9 Equipment Out-of-Service Operating Limits for Nominal Scram Speed and
Exposure Limited to 14,000 MWd/MTU
Turbine control valve (TCV) testing at LaSalle Unit 2 indicated that some of the turbine control valves
do not meet the fast closure criteria. Due to TCV slow closure the plant must be operated using the
more restrictive TCV slow closure equipment out-of-service (EOOS) MCPRO limits provided in
Reference 1. Based on the Reference 1 EOOS MCPRp limits, Exelon expects to run into MCPR
margin problems in February 2002. Exelon requested Framatomre'ANP, Inc. (FRA-ANP)
(Reference 2) to provide revised ATRIUM1-9B* EOOS limits that will improve MCPR margin to
support continued operation until a mid-cycle outage to correct the TCV closure rate.
MCPR margin was gained in the EOOS operating limits by reanalyzing TCV slow closure/FHOOS
and/or no RPT analyses based on nominal scram speed (NSS) and limiting the cycle exposure over
which the limits are applicable to BOC - 14,000 MWd/MTU.
Scram times corresponding to NSS were taken from the LaSalle Unit 2 plant transient analysis
parameters document (Reference 3). The scram times used are presented in Table I for
informational purposes.
TCV Slow ClosureIFHOOS and/or No RPT
The TCV slow closure/FHOOS and/or no RPT limits consider transient analysis results from the
following scenarios: TCV slow closure (up to all four valves), EOC RPT OOS, FHOOS, and a
combination of FHOOS and EOC RPT OOS. (Note: TCV slow closure analyses with FHOOS are
bound by TCV slow closure analyses at nominal feedwater temperature, and therefore, no specific
analyses are required for this scenario.) In order to reduce the workscope required to establish new
limits, only a subset of the analyses reported in Reference 4 have been reanalized. The subset of
analyses reanalyzed is similar to the subset presented in Reference - and is based on results
presented in Reference 4. Review of Figures 5.16, 5.17, and 5.18 in Reference 4 shows that the
TCV slow closure analyses are limiting for all power levels above 25% power; the FWCF no RPT
with FHOOS Is limiting at 25% power. FWCF with FHOOS cases were included in this analysis
resulting in a slightly more limiting case at 25% power than the FWCF no RPT with FHOOS cases.
* ATRIUM Is a trademark of Framatome ANP.
Framatome ANP, Inc. Proprietary
DEG:02:009 Attachment . Page A-2j9
Cases at power levels of 40% and 60% were included in this analysis for completeness even though
Reference 4 shows considerable margin to the limits at these power levels.
Table 2 presents the analysis results used to establish the slow TCV closure/FHOOS and/or no RPT
limits. Figure 1 presents the revised slow TCV closure/FHOOS and/or no RPT MCPRp limits for the
ATRIUM-9B fuel. The sum of the L2C9 safety limit MCPR (1.11 per Reference 4) and the ACPR
results from Table 2 are also presented in Figure 1.
Figure 2 presents the revised slow TCV closure/FHOOS and/or no RPT LHGRFACp multipliers for
the ATRIUM-9B fuel.
The ATRIUM-9B MCPRp limits and LHGRFACp multipliers provided in Figures 1 and 2 protect
operation with any combination of up to four TCVs closing slowly, EOC RPT OOS, and FHOOS up to
a cycle exposure of 14,000 MWd/MTU (NEOC). The only equipment out-of-service scenarios
provided in Reference 4 not explicitly protected by the slowTCV closure/FHOOS and/or no RPT
limits are single-loop operation (discussed below), turbine bypass valves OOS (discussed below), "
and startup of an idle loop. The limits support scram speeds at least as fast as the NSS insertion
times presented in Table 1; the slower technical specification scram speed (TSSS) insertion times
are not supported by these limits.
Comparison of turbine bypass valves OOS and the TCV slow closure/FHOOS and/or no RPT limits
in Table 2.1 of Reference 4 shows the TCV slow closure/FHOOS and/or no RPT limits clearly bound
the turbine bypass valves OOS limits. Consequently, applying the TCV slow closure/FHOOS and/or
no RPT limits will protect operation with the turbine bypass OOS.
No analyses were performed to revise limits for startup of an idle loop.
Single-Loop Operation
Figures 1 and 2 provide the two-loop operation (TLO) MCPRp limits and LHGRFACp multipliers.
Reference 5 indicates that the consequences of base case pressurization transients in single-loop
operation (SLO) are bound by the consequences of the same transient initiated from the same
power/flow conditions in TLO and that the TLO base case ACPRs and the LHGRFACp multipliers
remain applicabie for SLO. The conclusion that TLO ACPR results generally bound SLO results hal-
been demonstrated for both base case operation and some equipment out-of-service scenarios for
other BWRs. Although specific L2C9 analyses for a combination of TCV slow closure/FHOOS and/or
no RPT in SLO have not been performed, FRA-ANP expects the TLO operation ,CPR results would
Framatome ANP, Inc. PrOprietary
DEG:02:009 Attachment Page A-3
remain applicable in SLO for this scenario. Reference 4 indicates the L2C9 TLO safety limit MCPR
is 1.11 and the SLO safety limit MCPR is 1.12. Therefore, SLO MCPRp limits forTCV slow
closure/FHOOS and/or no RPT can be determined by adding 0.01 to the TCV slow closure/FHOOS
and/or no RPT MCPRI limits reported in Figure 1 to account for the increase in safety limit MCPR.
The Figure 2 TCV slow closure/FHOOS and/or no RPT LHGRFACp multipliers remain applicable for
SLO.
References
1. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity," DEG:01:046, March 22, 2001.
2. Exelon Task Order, L2C9 TCV Slow Closure Analysis with NSS Insertion Times, NFM-MWB040, Exelon, November29, 2001
3. EMF-2323 Revision 0, LaSalle Unit 2 Cycle 9 Principal Transient Analysis Parameters, Siemens Power Corporation, March 2000.
4. EMF-2440 Revision 0, LaSalle Unit 2 Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 2000.
5. EMF-95-205(P) Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis for ATRIUMh' -9B Fuel, Siemens Power Corporation, June 1996.
Framatome ANP, Inc. Proprietary
DEG:02:009 Attachment Page A-4
Table I Nominal Scram Insertion Times (Reference 3)
Position NSS Time
(notch) (sec)
48 0.00
48 0.200*
45 0.380
39 0.680
25 1.680
5 2.680
0 2.804
The 0.20-second delay is considered a nominal value that cannot be verified by the plant Therefore, the transient analysis calculations are performed to bound a range of no delay (linear insertion from start signal to notch 45) to a delay value just before notch 45. This is consistent with the information provided in Reference 3.
Framatome ANP, Inc. Proprietary
Attachment Page A-5) ,DEG:02:009
Table 2 EOOS Transient Analysis Results With Nominal Scram Speed and
Exposure Limited to 14,000 MWd/MTU
Power Slow Valve ATRIUM-9B I ATRIUM-9B
/ Flow Characteristics ACPR LHGRFACp
Slow TCV Closure*
100 / 105" 1 TCV closing in 2.0 seconds 0.31 0.98
100 181* 1 TCV closing in 2.0 seconds 0.31 1.00
80 / 105" 1 T6V closing in 2.0 seconds 0.35 0.97
80/ 57.2* 1 TCV closing in 2.0 seconds 0.40 1.00
8o/105t I TCV closing in 2.0 seconds 0.54 0.85
80 / 57.27 1 TCV closing in 2.0 seconds 0.49 0.92
60/ 105t I TCV closing in 2.0 seconds 0.62 0.83
60135.1t 1 TCV closing in 2.0 seconds 0.59 0.95
401/ 105t I TCV closing in 2.0 seconds 0.75 0.78
25/ `1051' 1 TCV closing In 2.0 seconds 0.98 0.70
LRNB No RPT
100/105 NA 0.27 0.99
80/105 NA 0.27 1.00
FWCF With FHOOS
40/105 NA 0.61 0.88
25/105* NA 1.02 0.69
FWCF NO RPT •Wth FHOOS
25 /105* NA 1.01 0.68
Scram initiated by high neutron flux. Scram Initiated by high dome pressure.
The analysis result Is from an exposure prior to NEOC (14,000 MWd/MTU). The ACPR and LHGRFACP Pai .i..e or* rnneagruntivaiv nte" tn P1tablish the thermal limits.
t
4
Framatome ANP, Inc. Proprietary
DEG:02:009
2-W
2.70
2.60,
1W•
2.40
2.0'
2M0
2,10,
IM , 1W.0
JO.
1210
1.10
Attachment Page A-6
0 10 20 30 40 50 00 70 ao 9o 100 110 POWK CA of Riftm
Power MCPRp (%) Limit
100 1.42 80 1.51 80 1.65 25 2.13 25 2.20
0 2.70
Figure 1 NEOC (14,000 MWd/MTU) Slow TCV Closure/FHOOS andlor No RPT Power-Dependent
MCPR Limits for ATRIUM-9B Fuel With NSS Insertion Times
Framatome ANP; Inc. Proprietary
Attachment Page A-7DEG:02:009
0 10 20 30 40 so 6 70 00 90 100 110
Pewuf t% of Ratem
Power LHGRFACp (%) Multiplier 100 0.98 80 0.97 80 0.85 25 0.68 25 0.68
0 0.68
"Figure 2 NEOC (14,000 MWdlMTU) Slow TCV Closure/FHOOS andlor No RPT Power-Dependent
LHGR Multipliers for ATRIUM-9B Fuel With NSS Insertion Times
Technical Requirements Manual - Appendix J L2C9 Reload Transient Analysis Results
K-)
Attachment 8
LaSalle Unit 2 Cycle 9 Operating Limits for Cycle Extension to 19,300 MWd/MTU
LaSalle Unit 2 Cycle 9 August 2002
August 9, 2002 DEG:02:125
Mr. F. W. Trikur Exelon Nuclear Nuclear Fuel Management 4300 Winfield Road Warrenville, IL 60555
A FRAMATOME ANP
FRAMATOME ANP, Inc. "e
PAP,4D1 "A42C el
c~ Fe5rs( )
Dear Mr. Trikur:
LaSalle Unit 2 Cycle 9 Operating Limits for Cycle Extension to 19,300 MWdIMTU
Reference: 1) Exelon task order NFM-MW-B080, LaSalle 2 Cycle 9 Coastdown Analysis, July 9, 2002
2) Contract for Fuel Fabrication and Reliated Components and Services dated as of October 24, 2000 between Siemens Power Corporation and Commonwealth Edison Company for LaSalle Nuclear Plant.
In response to Reference 1 analyses have been performed to'support extending 6peration at LaSalle Unit 2 Cycle 9 out to 19,300 MWd/MTU. Limits are established for base case operation and three equipment out-of-service scenarios. The analysis results and operating limits are presented in the attachment.
Very truly yours,
D. E. Garber Project Manager
FRAMATOME ANP, Inc. 2101 Horn Rapids Road - Richland WA 99352 Tel 509-375-8100 Fax 509-375-8402 wwwusframatome-anpcom
Framatome ANP, Inc. Proprietary
An AREVA and Siemens company
Framatome ANP, Inc. Proprietary
DEG:02:125 Attachment Page A-1
LaSalle Unit 2 Cycle 9 Operating Limits for Cycle Extension to 19,300 MWd/MTU
With Technical Specification Scram Speeds
Exelon has determined that LaSalle Unit 2 Cycle 9 (L2C9) will exceed the current EOC licensing
exposure of 18,458.2 MWd/MTU and requested (Reference 3) Framatome ANP, Inc. (FRA-ANP) to
perform additional analyses to support operation to an exposure of 19,300 MWd/MTU for the
following scenarios:
* Base case operation with TSSS. * FHOOS operation with TSSS. • Operation with no bypass and FHOOS with TSSS. • Operation with any combination of TCV slow closure, no RPT or FHOOS with TSSS.
The current EOC operating limits for LaSalle Unit 2 Cycle 9 were provided in References 1 and 2,
and support operation to a cycle exposure of 18,458.2 MWd/MTU. The limiting analyses from
References 1 and 2 were analyzed to determine the operating limits for the cycle extension to
19,300 MWd/MTU. Additional power/flow state points were analyzed for certain events to ensure
completeness in determining the operating limits. The analyses were performed with the
Reference 4 parameters with the exceptions noted in Reference 3; FFTR/FHOOS temperature
reduction, steam line pressure drop, and recirculation pump torque. This letter report summarizes
the transient analysis results and operating limits to support the L2C9 cycle extension.
Cycle Extension
L2C9 was originally licensed to an EOC cycle exposure of 18,458.2 MWd/MTU. Recent discussions
with Exelon indicate that L2C9 is expected to begin coastdown operation at approximately 17,300
MWd/MTU. Data provided by Exelon indicates that the cycle will extend coastdown operation to an
exposure of approximately 19,020 MWd/MTU. In order to provide some conservatism and flexibility,
additional full power capability was included. L2C9 is conservatively modeled to operate at rated
power to a cycle exposure of 19,300 MWd/MTU.
TSSS Base Case Operation
The base case limits consider transient analysis results from the load rejection with no bypass
(LRNB) and feedwater controller failure (FWCF) events. Reference 1 provided the EOC base case
operating limits for TSSS scram times.
Framatome ANP, Inc.Proprietary
DEG:02:125 Attachment Page A-2
"'-- Table 1 presents the analysis results used to establish the TSSS base case limits for the cycle
extension. Figures 1 and 2 present TSSS MCPRp limits to support base case operation for
ATRIUMTM-9B* and GE9 fuel, respectively. The sum of the L2C9 safety limit MCPR (1.11 per
Reference 5) and the ACPR results from Table 1 are also presented in the figures. Figure 3 presents
the base case LHGRFACP multipliers for ATRIUM-9B fuel and the LHGRFACp results from Table 1.
TSSS FHOOS Operation
Exelon requested that FRA-ANP provide a set of operating limits to protect operation forFHOOS.
This set of limits considers transient analysis results from the FWCF with FHOOS and the LRNB with
FHOOS events.
Table 2 presents the analysis results used to establish limits to protect operation in the FHOOS
scenario for the cycle extension. Figures 4 and 5 present TSSS MCPRp limits to support operation
with FHOOS for ATRIUM-9B and GE9 fuel, respectively. The sum of the L2C9 safety limit MCPR
(1.11 per Reference 5) and the ACPR results from Table 2 are also presented in the figures.
Figure 6 presents the FHOOS LHGRFACp multipliers for ATRIUM-9B fuel and the LHGRFACp results
K> from Table 2.
TSSS FHOOS and TBVOOS Operation
Exelon requested that FRA-ANP provide a set of operating limits to protect operation in the FHOOS
and TBVOOS scenario. -This set of limits considers transient analysis results from the FWCF with
TBVOOS, FWCF FHOOS with TBVOOS, FWCF with FHOOS and LRNB with FHOOS events.
Reference 2 provided the EOC TBVOOS or FHOOS operating limits for TSSS scram times.
Table 2 presents the analysis results used to establish limits to protect operation in the FHOOS and
TBVOOS scenario for the cycle extension.' Figu'res 7 'and 8 piresent TSSS MCPRp limits to support
operation in the FHOOS and TBVOOS scenario for AT'RIUM-9B and GE9 fuel, respectively. The
sum of the L2C9 safety limit MCPR (1.11 per Reference 5) and the ACPR results from Table 2 are
also presented in the figures. Figure 9 presents the FHOOS and TBVOOS LHGRFACP multipliers for
ATRIUM-9B fuel and the LHGRFACP results from Table 2.
* ATRIUM is a trademark of Framatome ANP.
* Framatome ANP, Inc. Proprietary
DEG:02:125 Attachment Page A-3
TSSS TCV Slow Closure, No RPT or FHOOS Operation KY
Limits to support operation with any combination of TCV slow closure, no RPT or FHOOS consider
transient analysis results for the following scenarios: TCV slow closure (up to all four valves); EOC
RPT OOS; FHOOS; and a combination of FHOOS and EOC RPT oOS. (Note: TCV slow closure
analyses with FHOOS are bound by TCV slow closure analyses at nominal feedwater temperature.)
Reference 1 provided the EOC TSSS operating limits for the same EOOS scenarios.
Table 3 presents the analysis results used to establish the cycle extension limits for any combination
of TCV slow closure, no RPT or FHOOS. Figures 10 and 11 present TSSS MCPRp limits to support
operation with any combination of TCV slow closure, no RPT or FHOOS for ATRIUM-9B and GE9
fuel, respectively. The sum of the L2C9 safety limit MCPR (1.11 per Reference 5) and the ACPR
results from Table 3 are also presented in the figures. Figure 12 presents the any combination of
TCV slow closure, no RPT or FHOOS LHGRFACp multipliers for ATRIUM-9B fuel and the
LHGRFACp results from Table 3.
Single-Loop Operation
Figures 1-12 provide the two-loop operation (TLO) MCPRp limits and LHGRFACp multipliers for the
L2C9 cycle extension. Reference 7 indicates that the consequences of base case pressurization
transients in single-loop operation (SLO) are bound by the consequences of the same transient
initiated from the same power/flow conditions in TLO and that the TLO base case ACPRs and the
LHGRFACp multipliers remain applicable for SLO. The conclusion that TLO ACPR results generally
bound SLO results has been demonstrated for both base case operation and some equipment out
of-service scenarios for other BWRs. Although specific L2C9 analyses for SLO have not been
performed, FRA-ANP expects the TLO operation ACPR results would remain applicable in SLO for
all scenarios. Reference 5 indicates the L2C9 TLO safety limit MCPR is 1.11 and the SLO safety
limit MCPR is 1.12. Therefore, SLO MCPRp limits for base case, FHOOS, FHOOS and TBVOOS,
and any combination of TCV slow closure, no RPT or FHOOS can be determined by adding 0.01 to
the appropriate MCPRP limits reported in the above figures to account for the increase in safety limit
MCPR. The ATRIUM-9B LHGRFACn multipliers in Figures 3, 6, 9, and 12 remain applicable for
SLO.
GE9 Mechanical Limits
References 8 and 9 provided the initial evaluations of the GE9 mechanical limits for L2C9. These
evaluations were updated in References 1 and 2. An evaluation of the GE9 mechanical limits for the
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DEG:02:125 Attachment Page A-4
"-•-. rated'power analyses reported in Tables 1-3 was performed. The cycle extension analysis results
are bound by the previous limiting L2C9 GE9 1% strain results presented in References 8 and 9.
Therefore, the adjustments (if any) currently applied to the GE9 fuel limits remain applicable for the
cycle extension.
Licensing Applicability
References 5 and 6 provided the original L2C9 licensing analyses and limits for which FRA-ANP was
responsible to a cycle exposure of 18,458.2 MWd/MTU. 'References 1 and 2 updated portions-of the
licensing analyses and limits for proposed ITS scram speeds and corrected fuel thermal conductivity.
FRA-ANP has performed additional evaluations to determine the applicability of the current licensing
analyses and limits to the L2C9 cycle extension. The evalua'tions demonstrated that the current
analysis results and limits remain applicable for the L2C9 cycle extension with the exception of the
MCPRp limits and LHGRFACp multipliers.
The L2C9 operating limits provided in References 1 and 2'remain applicable to a cycle exposure of
18,458.2 MWd/MTU (core exposure of 30,266.2 MWd/MTU). The MCPRp limits and LHGRFACp
"x_- multipliers presented in Figures 1-12 must be used for operation beyond a cycle exposure of
18,458.2 MWd/MTU, and are applicable to a cycle exposure of 19,300 MWd/MTU. The base case
MCPRp limits and LHGRFACp multipliers are valid for any feedwater temperature within the upper
and lower bounds defined by Reference 4, Item 3.12. The other limits support operation with up to a
120OF decrease in feedwater temperature from the nominal value.
Core Hydrodynamic Stability Analysis
The L2C9 stability analysis was updated for the extended cycle exposure of 19,300 MWd/MTU. For
each power/flow point, decay ratios were calculated to determine the highest expected decay ratio
throughout the cycle. Table 4 provides the updated results for the stability decay ratio analysis.
Reference 6 provided the current stability analysis decay ratios. The cycle extension analysis was
based on an updated STAIF methodology previously utilized for LaSalle Unit 1 Cycle 10.
For reactor operation under conditions of single-loop operation, final feedwater temperature reduction
(FFTR) and/or operation with feedwater heaters out of service, it is possible that higher decay ratios
could be achieved than are shown for normal operation.
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DEG:02:125 Attachment Page A-5
References
1. Letter, D. E.'Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 2 Cycle 9 Operating Limits for Proposed ITS Scram Times and Corrected Fuel Thermal Conductivity," DEG:01:046, March 22, 2001.
2. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 2 Cycle 9 NSS Base Case and TBVOOS or FHOOS Operating Limits for Proposed ITS Scram Times with Corrected Fuel Thermal Conductivity," DEG:01:076, May 15, 2001.
3. Exelon Task Order, LaSalle 2 Cycle 9 Coastdown Analysis, NFM-MW-B080, July 9, 2002.
4. EMF-2323 Revision 0, LaSalle Unit 2 Cycle 9 Principal Transient Analysis Parameters, Siemens Power Corporation, March 2000.
5. EMF-2440 Revision 0, LaSalle Unit 2 Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 2000.
6. EMF-2437 Revision 0, LaSalle Unit 2 Cycle 9 Reload Analysis, Siemens Power Corporation, October 2000.
7. EMF-95-205(P),Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis for ATRIUM TM-9B Fuel, Siemens Power Corporation, June 1996.
8. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 2 Cycle 9 Transient Power History Data for Confirming Mechanical Limits for GE9 Fuel," DEG:00:185, August 3, 2000.
9. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "Additional Analysis for LaSalle Unit 2 Cycle 9 1% Plastic Strain Compliance for GE9 Fuel," DEG:00:213, September 6, 2000.
Framatome ANP, Inc. Proprietary
Attachment Page A-6
DEG:02:125
Table 1 Base Case Transient Analysis Results
Power ATRIUM-9B ATRIUM-9B GE9
/Flow ACPR LHGRFACP ACPR
LRNB
100/105 0.33 1.000 0.41
80/105 0.32 1.000 0.40*
60 / 105 0.31 1.023 0.37
FWCF
100/105 0.26 1.055 0.32*
80/105 0.30 1.055* 0.36*
60/105 0.37 1.007* 0.42*
40/105 0.53* 0.931 * 0.59*
25 / 105 0.82* 0.776* 0.90*
* The analysis results are from an exposure prior to 19,300 MWd/MTU. The ACPR and LHGRFAC, results
are conservatively used to establish the thermal limits.
Framatome ANP, Inc. Proprietary
Attachment Page A-7
Table 2 TBVOOS and FHOOS Transient Analysis Results
Power ATRIUM-9B ATRIUM-9B GE9 /Flow ACPR LHGRFACp ACPR
FWCF With TBVOOS
100/105 0.35 0.971 0.42
80/105 0.38 1.000 0.46*
60/105 0.45 0.964* 0.52*
40/105 0.55 0.957 0.61
25/105 0.74 0.865 0.79
FWCF FHOOS With TBVOOS
100/105 0.33 1.015 0.38
80/105 0.39 1.031 0.44
60/105 0.49 1.007 0.53
40/105 0.65 0.925 0.70
25/105 0.94 0.789 1.00
FWCF With FHOOS
100/105 0.26 1.089 0.29
80/105 0.33 1.098 0.35
60/105 0.43* 0.964* 0.46*
40/105 0.59 0.957 0.62
25/105 1.06* 0.685* 1.13*
LRNB With FHOOS
* The analysis results presented are from an exposure prior to 19,300 MWd/MTU. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
DEG:02:125
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DEG:02:1125 Attachment Page A-8
Table 3 EOOS Transient Analysis Results
Power ATRIUM-9B ATRIUM-9B GE9
/Flow ACPR LHGRFACp ACPR
TCV Slow Closure
100/ 105* 0.49 0.828 0.62
80/ 105" 0.45 0.894 0.54
80 /57.2* 0.51 0.9711 0.751
80/105t 0.57 0.8541 0.66
80/ 57.21 0.591 0.944* 0.85*
60 / 105t 0.50 0.944 0.58
40 / 105t 0.80 0.818 0.87
25/ 105t 1.001 0.754 1.00
LRNB No RPT
100/105 0.46 0.799 0.61
80/105 0.39 0.871 0.49
FWCF No RPT
40/105 0.50 0.964 0.57
25 / 105 0.68 0.871 0.75
FWCF No RPT With FHOOS
40/105 0.61 0.925 0.67
25 /105 1.04* 0.675* 1.111
Scram initiated by high neutron flux. Scram initiated by high dome pressure. The analysis results presented are from an exposure prior to 19,300 MWd/MTU. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
t
t
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DEG:02:125 Attachment Page A-9
Table 4 Stability Analysis Decay Ratio Results
Power Maximum Maximum / Flow (%) Global Regional
30.1 / 26.6 0.59 0.53
31.6/29.2 0.42 0.50
61.9/45.0 0.67 0.88
73.6 / 50.0 0.73 0.95
78.2 / 60.0 0.52 0.63
82.4 / 60.0 0.57 0.72
Framatome ANP, Inc. Proprietary
DEG:02:125
2.75
2.65
2.55
245
2.35
2.25
2.15
2.05
0. 1.95 U
Attachment Page A-10
0 10 20 30 40 50 60 70 80 90 100 110
Power (% rated)
Power MCPRp (%) Limit
100 1.44 60 1.48 25 1.93 25 2.20
0 2.70
Figure 1 Coastdown (19,300 MWd/MTU) Base Case Power-Dependent MCPR Limits
for ATRIUM-9B Fuel with TSSS insertion Times
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DEG:02:125 Attachment Page A-11
0 10 20 30 40 50 60 70 80 90 100 110
Power (% rated)
Power MCPRp (%) ULmit
100 1.52 60 1.53 25 2.01 25 2.20
0 2.70
Figure 2 Coastdown (19,300 MWdIMTU) Base Case Power-Dependent MCPR Limits
for GE9 Fuel with TSSS Insertion Times
C.
Framatome ANP, Inc. Proprietary ,
DEG:02:125
1.400
1.350
1.300.
1.250
1.200
1.150
EL 1.100
1 050
- 1.000Z
Attachment Page A-12
0 10 20 30 40 50 60 70 80 90 100 110
Power (% rated)
Power LHGRFACP (%) Multiplier
100 1.00 60 1.00 25 0.77 25 0.77
0 0.77
--'Figure 3. Coastdown (19,300-MWd/MTU) Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel with TSSS Insertion Times
Framatome ANP, Inc. Proprietary
DEG:02:125 Attachment Page A-13
0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp (%) Limit
100 1.44 60 1.54 25 2.17 25 2.20
0 2.70
Figure 4. Coastdown (19,300 MWd/MTU) FHOOS Power-Dependent MCPR Limits for
ATRIUM-9B Fuel with TSSS Insertion Times
C.
Framatome ANP, Inc. Proprietary
DEG:02:125
305
2.95
2.85
275
2.65
2.55
2.45
235
225
2.15 a.
S2.05 1.95
1.85
1.75
1.65.
1.55
1.45
1.35
125
1.15
Attachment Page A-14
110
Power (% rated)
Power,. MCPRp (%) Limit
100 . 1.52 60 1.57 25 2.24 25 2.24
0 -2.74
Figure,5 Coastdown,(19,300 MWd/MTU) FHOOS Power-Dependent MCPR Limits for
GE9 Fuel with TSSS Insertion Times-
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Attachment Page A-15
10 20 30 40 50 60 70 80 90 100 110
Power r/. rated)
Power LHGRFACp
(%) Multiplier
100 1.00 60 0.96 25 0.68 25 0.68
0 0.68
Figure 6 Coastdown (19,300 MWd/MTU) FHOOS Power-Dependent LHGR Multipliers
for ATRIUM-9B Fuel with TSSS Insertion Times
1.300
1.250
1.200
1.150.
1.100
1.050
= 1.000 U
cc 0.950
-J 0.900
0 850
0800
0.750
0.700-
* FWCF FHOOS
* LRNB FHOOS -LHGRFACp
+ +
C÷
0.650
0600
0
DEG:02:125
Framatome ANP, Inc. Proprietary
DEG:02:125
2 85
2.75
2.65
2.55
2.45
2.35
2.25
2.15
CL2.05 0.
S1.95
1.85
1 75
1.65
1.55
1.45
1.35
1.25
1.15
Attachment Page A-16
0 10 20 30 40 50 60 70 80 90 100 110
Power (%rated)
Power MCPRp (%) Limit 100 1.46
60 1.60 25 2.17 25 2.20
0 . .. .-2.70
Figure 7 Coastdown (19,300 MWdIMTU) FHoOS and No Bypass Power-Dependent MCPR Limits for ATRIUM-9B Fuel with TSSS Insertion Times
Framatome ANP, Inc. Proprietary
Attachment Page A-17
3.05
2.95
2.85
275
2665
2.55
2 45
2.35
2.25
0- 2.15
2.05
1.95
1.85
1.75
165
1.55
1.45
135
1.25
1.15
0 10 20 30 40 50 60
Power (%rated)
Power MCPRp (%) Limit
100 1.53 60 1.64 25 2.24 25 2.24
0 2.74
70 80 90 100 11C
Figure 8 Coastdown (19,300 MWd/MTU) FHOOS and No Bypass Power-Dependent MCPR Limits
for GE9 Fuel with TSSS Insertion Times
* -FWCF No Bypass
x FWCF FHOOS No Bypass
* FWCF FHOOSa LRNB FHOOS
- OLMCPR
xx 0÷
-I.
DEG:02:125
Framatome ANP, Inc. Proprietary
DEG:02:125
1.3001
1.250
1.200.
1.150
1.1004
0. U
Ii. C, -J
1.050
1000
0950
0900
0 850
0 800
0.750
0700
0 650
0.6000 10 20 30 40 50 60 70 80 90 100 110
Power (%rated)
Power LHGRFACp (%) Multiplier
100 0.97 60 0.96 25, 0.68 25 0.68
0 0.68
Figure 9 Coastdown (19,300 MWd/MTU) FHOOS and No Bypass Power-Dependent LHGR Multipliers
for ATRIUM-9B Fuel with TSSS Insertion Times
Attachment Page A-18
* FWCF No Bypass * FWCF FHOOS No Bypass + FWCF FHOOS a LRNB FHOOS
-LHGRFACp
.4
x xx
Framatome ANP, Inc. Proprietary
DEG:02:125 Attachment Page A-19
0 10 20 30 40 50 60 70 80 90 100 110
Power (% rated)
Power MCPRp (%) Limit 100 1.60 80 1.62 80 1.70 25 2.17 25 2.20
0 2.70
Figure 10 Coastdown (19,300 MWd/MTU) TCV Slow Closure/FHOOS or No RPT Power-Dependent MCPR Limits
for ATRIUM-9B Fuel with TSSS Insertion Times
0.
0. U
Framatome ANP, Inc. Proprietary
DEG:02:125
3.05|
295
265
2.75
265
2 55
245
2.35
2.25 a. E 2.15
205
Attachment Page A-20
0 10 20 30 40 50 60 70 80 90 100 110
Power (% fated)
Power MCPRp (%) Limit
100 1.73 80 1.86 80 1.96 25 2.24 25 2.24
0 2.74
Figure 11 Coastdown (19,300 MWd/MTU) TCV Slow Closure/FHOOS or No RPT Power-Dependent MCPR Limits_
for GE9 Fuel with TSSS Insertion Times
Framatome ANP, Inc. Proprietary
DEG:02:125
x
A
A
u.O.J -l
0 10 20 30 40 50 60
Power (% rated)
Power LHGRFACp (%) Multiplier
100 0.79 80 0.79 80 0.79 40 0.79 25 0.67 25 0.67
0 0.67
70 80 . 90 100 110
Figure 12 Coastdown (19,300 MWd/MTU) TCV Slow Closure/FHOOS or No RPT Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel with TSSS Insertion Times
A Slow TCV + FWCF FHOOS A LRNB FHOOS * LRNB No RPT X FWCFNoRPT 13 FWCF FHOOS No RPT
-LHGRFACp
Attachment Page A-21
K)
+
1.300
1 250
1.200
1.150
1.100
1 050
a. 1000U
: 0950
-a 0900.
0 850.
0800
0750
0700*
0650
A
aA
A
A
A
A
A