ML20217D048
| ML20217D048 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/30/1999 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20217D047 | List: |
| References | |
| NUDOCS 9910140164 | |
| Download: ML20217D048 (14) | |
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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT Revision 1 )
September 1999 j gR10140164 990930 p ADOCK 05000498 PDR Core Operating Limits Report, Rev 1 September 1999 Page 1 of 13
South Texas Project Unit I Cycle 9 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 1 Cycle 9 has been prepared in accordance with the requirements of Technical Specirication 6.9.1.6. The core operating limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.
The Technical Specifications affected by this report are:
- 1) 2.1 SAFETY LIMITS
- 2) 2.2 LIMITINO SAFETY SYSTEM SETTINGS
- 3) 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT LIMITS
- 4) 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMITS
- 5) 3/4.1.3.6 CONTROL RODINSERTION LIMITS
- 6) 3/4.2.1 - AFD LIMITS
- 7) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR
- 8) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR
- 9) 3/4.2.5 DNB PARAMETERS 2.0 OPERATING LIMITS COLR Section 2.8 provides for an alternate minimum measured Reactor Coolant System flow limit consistent with plugging up to 10% of steam generator tr.* oes and Departure from Nucleate Boiling requirements. When using the alternate minimum flow limit, the Tava limit is reduced for RCS flow no less than 380,500 gpm. Setpoint and constant values for OPAT and OTAT are also revised accordinely when this alternate mode of operation is entered.
The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented below.
2.1 SAFETY LIMITS (Specification 2.1) 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T vg) shall not exceed the limits shown in Figure 1, or in Figure 2 when operating under alternate operating criteria consistent with reduced Reactor Coolant System flow as addressed in COLR Section 2.8.
Core Operating Limits Report, Rev 1 September 1999 Page 2 of 13
F j
~ . i South Texas Project u Unit 1 Cycle 9 2.2 - LIMITING SAFETY SYSTEM SE'ITINGS (Specifiestion 2.2) ,
' 2.2.1 The Loop design flow for Reactor Coolant Flow-Low is 95,400 gpm (or
- j. 92,500 gpm for altemate operation with reduced RCS flow).
2.2.2 The Over Temperature AT and Overpower AT setpoint parameter values are j listed below:
Overtemperature AT Setnoint Parameter Values ti; measured reactor vessel AT lead / lag time constant, ti = 8 see T2; measured reactor vessel AT lead / lag time constant, T2 = 3 see t3; measured reactor vessel AT lag time constant, t3 = 0 sec I
. t4; measured reactor vessel average temperature lead / lag time constant, '
T4 = 28 see T5 ; measured reactor vessel average temperature lead / lag time constant, is = 4 see T6; measured reactor vessel average temperature lag time constant, T6 = 0 sec Ki; Overtemperature AT reactor trip setpoint, Ki = 1.14; or , Ki = 1.13 for alternate operation with reduced RCS flow K2; Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/ F l
K3 ;Overtemperature AT reactor trip setpoint pressure coefficient .
K3 = 0.00143/p:,ig T'; Nominal full power Tavg, T' s 589.0 'F (including altemate operation with reduced RCS flow)
\
P'; Nominal RCS pressure, P' = 2235psig f i(AI) is a function of the indicated difference between top and bottom
. detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that; . j J
(1)- For ge - gb between -70% and +8%, or +6% for altemate operation with reduced RCS flow, f (Al) i = 0, where qt and qs are percent RATED THERMAL POWER in the top and bottom halves of the Core Operating Limits Report, Rev 1 September 1999 Page 3 of 13 l'
i
I . .
South Texas Pioject Unit i Cycle 9 core respectively, and qi + qbi s total THERMAL POWER in percent l ,
, of RATED THERMAL POWER; (2) For each percent that the magnitude of gi - qb exceeds -70%, the AT Trip Setpoint shall be automatically reduced by 0.0% ofits value at RATED THERMAL POWER; and (3) For each percent that the magnitude of qt - qb exceeds +8%, or +6%
for alkrnate operation with reduced RCS flow, the AT Trip Setpoint shall be automatically reduced by 2.65% ofits value at RATED THERMAL POWER.
Overpower AT Setpoint Parameter Values ti; measured reactor vessel AT lead / lag time cons. tant, ti = 8 sec T2; measured reactor vessel AT lead / lag time constant, T2 = 3 see t3 ; measured reactor vessel AT lag time constant, T3 = 0 sec T6; measured reactor vessel average temperature lag time constant, T6 = 0 see t7; Time constant utilized in the rate-lag compensator for Tog, T7 = 10 see L; Overpower AT reactor trip setpoint, L = 1.08; (or L = 1.07 for alternate operation with reduced RCS flow)
Ks; Overpower AT reactor trip setpoint Tavg rate / lag coefficient, K5 = 0.02/ F for increasing average temperature, and K5 = 0 for decreasing average temperature K6; Overpower AT reactor trip setpoint Tavg heatup coefficient K6 = 0.002/ F for T > T" and, K6 = 0 for T s T" T"; Indicated full power Tavg, T" s 589.0 F (including alternate operation with reduced RCS flow) f(AI)=
2 0 for all(AI) 2.3 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):
2.3.1 The BOL, ARO, MTC shall be less positive than the limits showt1 in j Figure 3. l l
Core Operating Limits Report, Rev 1 September 1999 i Page 4 of 13 l
l l
South Texas Project Unit I Cycle 9 4
2.3.2 The EOL, ARO, HFP, MTC shall be less negative than -6.12 x 10 Ak/k/ F.
2.3.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -5.22 x 104 Ak/k/'F (300 ppm Surveillance Limit).
l where: BOL stands for Beginning-of-Cycle Life l EOL stands for End-of-Cycle Life ARO stands for All Rods Out HFP stands for Hot Full Power (100% RATED THERMAL POWER) ,
HFP vessel average temperature is 589 *F 2.4 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6):
2.4.1 All banks shall have the same Full Out Position (FOP) of at least 250 steps withdrawn but not exceeding 259 steps withdrawn.
2.4.2 The Control Banks shall be limited in physical insertion as specified in Figure 4.
2.4.3 Individual Shutdown bank rods are fully withdrawn when the Bank Demand i' Indication is at the FOP and the Rod Group Height Limiting Condition for Operation is satisfied (T.S. 3.1.3.1).
2.5 AXIAL FLUX DIFFERENCE (Specification 3.2.1): )
2.5.1 AFD limits as required by Technical Specification 3.2.1 are determined by CAOC Operations with an AFD target band of+3, -12%.
2.5.2 The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 5, as required by Technical Specifications.
2.6 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2): !
2.6.1 F"f = 2.55.
2.6.2 K(Z)is provided in Figure 6.
R 2.6.3 The Fxy limits for RATED THERMAL POWER (F x ) within specific core planes shall be:
2.6.3.1 Less than or equal to 2.102 for all core planes containing Bank "D" control rods, and 2.6.3.2 Less than or equal to the appropriate core height-dependent value from Table I for all unrodded core planes.
2.6.3.3 PFxy = 0.2.
R ese F,y limits were used to confirm that the heat flux hot channel factorFo(Z) will be limited by Technical Specification 3.2.2 assuming the most-limiting axial power Core Operating Limits Report, Rev i September 1999 Page 5 of 13
South Texas Project Unit 1 Cycle 9 1
distributions expected to result for the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in WCAP-8385. "Iherefore, these F,y limits provide assurance that the initial conditions assumed in the LOCA analysis are met,
, along with the ECCS acceptance criteria of 10 CFR 50.46.
! For Unit 1 Cycle 9, the 14Z) penalty is not applied (i.e., L(Z) = 1.0 for all core I '
elevations).
l 2.7 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):
i Standard Fuel VANTAGE SH / VANTAGE + / RFA Fuel
.2.7.1 F"J = 1.49 F"J = 1.557 2.7.2 PFm = 0.3 PFm = 0.3 2.8 DNB PARAMETERS (Specification 3.2.5) 2.8.1 The following DNB-related parameters shall be maintained within the followinglimits:
- a. Reactor Coolant System T,,, s 595*F*
(or s 593 F* with reduced RCS flow of COLR 2.8.1.c)
- b. Pressurizer Pressure, > 2219 psig* *
- c. Minimum Measured Reactor Coolant System Flow 2 392,300 gpm* * *
(or 2 380,500 gpm* *
- _ includes a 1.9'F measurement uncertainty .
- Limit not applicable during either a nermal Power ramp in excess of 5% of RTP per minute or a normal Power step in excess of 10% RTP. Includes a 28.4 psi measuitment uncertainty.
- *
- Includes a 2.8% flow measurement uncertamty.
3.0 REFERENCES
3.1 - Letter from R. A. Wiley (Westinghouse) to Dave Hoppes (STPNOC), " Unit 1 Cycle 9 Core Operating Limits Report," 99TG-G-0041 (ST-UB-NOC-1919), April 1999.
3.2 .NUREG-1346, Technical Specifications, South Texas Project Unit Nos. I and 2.
3.3 STPNOC Calculation ZC-7035, Rev.1," Loop Uncertainty Calculation for RCSTavg Instrumentation", 10 19-1998 4 l
- 3.4 STPNOC Calculation ZC-7032, Rev.1," Loop Uncertainty Calculation for Narrow Range
- j. Pressurizer Pressure Monitoring Instrumentation", 6-10-1999.
Core Operating Limits Report, Rev 1 September 1999 Page 6 of 13 ,
r-South Texas Project Unit I Cycle 9 Figure 1 Reactor Core Safety Limit - Four Loops in Operation l
680 1
._ UNACCEPTABLE (0.02,663 $4) 660 N --
-(0.02,660 ) % 2450 PSIA q -
A w %
N -% _w -
- (0.02,650.94)h % %- %
i N g N 640 N g % (1.00.636.50) 2400 PSa w y h ,
N_ N % (
N 2250 PSM N g S (0 02,633 87) N g N I 00'"33"'I " \
c g 620 ' x N s s N g,,,,,o.p __
$ -(0.02.6212$) \
k N* N s s j
g s .
20* eSa y g N m N
'N N
\ \\
8 g
600 1830 PSM DA s
\ \
\ \3 (t30.600.39)
(1a.60s 41) g
% ( (1.30,$97.69)
N w ,
(1.30,589.25)
N <
580 i
'"*" \\
A CC EPTABLE T
! \ \ (1.30,674.64)
\
(1.30,664.71) 560 --
.4 l
-t
._4 .' '
q a
l '1
' 4-540 '
0 0.2 0.4 0.6 0.8 1 1.2 Fraction of RATED THERMAL POWER Core Operating Limits Report, Rev 1 September 1999
I South Texas Project Unit I Cycle 9
{
1 Figure 2 j- Reactor Core Safety Limit - Four Loops in Operation (Alternate) 680
.-- .~.
-~~~ -
ca.or.ss4 a) ~~~ UNACCEPTABLE g - -
660 3 N ' N
- (o o2,66 ) N h g
.x N NON N N (o.o2.652.07) A N g N
2400 PSLA DN N N g 640 N-s N N ase2.sss 4e) s w N. N N N 2250 PSIA N N N (o 02,634 so)gs % (o 99.s32.si) -
N C 2N \
620 N '
\
s N g f (1.00a.621.26) \
o -(o 02.622.37) -A N il N %
'N 2000 PSIA s
N
'N s
'\ \'\
F s s N _N _
A 1830 P N w
's .- % k
@ 600 (i.o7.soo 87) om. sone)
,g 3 (1.30.so5.co)
N s \--<
N \ (1 2 .587.28) 580 ACCEPTABLE o.ur.uo23 \ \,
N \ '
(1m.s73.34)
~
\
S om.ss2.n) 1 560 ;--, j ; !
_j._ ! 4 4
_L a ..1 - 4 .
. .. 2 i
540 '
9 0.2 0.4 0.6 0.8 1 1.2 Fraction of RATED THERMAL POWER Core Operating Limits Report, Rev i September 1999 Page 8 of 13
I
). .
un$t i cyc7eS'
Figure 3
. MTC versus Power Level 7.0
! ((NACCEPTABLE OPERATION 6.0 l 5.0 ----
'4.0 3.0.
C 2.0 ACCEPTABLE OPERATION 1.0 0.0
-1.0
-2.0
-3.0 0.0 20.0 40.0 60.0 80.0 100.0 Relative Power (%)
Core Operating Limits Report , Rev. I September 1999
( ,
South Texas Project Unit 1 Cycle 9
)
Figure 4
~
Control Rod Insertion Limits' versus Power Level !
- 122 m g % I Ann a,W (79.259): 122 sep % '
(79Jsg: 121 a , %
"*** (7e.assi: 1ie m., %
260 '
N"if "'P W
- (rr.as4):117 sep %
' ** / '
- 240
, )
220 ,
e' Bank 8 , l
' f 200 '
/
~
180 ; ,
U M 174) -.
b s '
E.160 f ,e 7 Bank C ,
140 , ,
/ ,
' e 120 , ,
' r 100 , '
r h , j 80 ,' '
r , BankD
' /
& n
- Resp j 2
40 , ,
20 s- 0t9,0) 0 O 10 20 30 40 50 60 70 80 90 100 RELATNE POWER (%)
Control Bank A is already withdrawn to Full Out Position. Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of 2: 250 and 5; 259 steps withdrawn, inclusive.
Core Operating Limits Report Rev.1 September 1999 Page 10 of 13
South Texas Project Unit ! Cycle 9 Figure 5 AFD Limits versus Rated Thermal Power 120 100 l-11,901 111,901
~~
UNACCEPTABLE [ k UNACCEPTABLE -
~
OPERATION
/- ) '
OPERATION 80 u / \
$ / T
& -. A L
- -- / \
g '
r 3 60
{c / \
8
[ ACCEPTABLE t OPERATION g I-31,50! !31,50!
40
-1 .
20 l
l 0 l
-50 -40 -30 -20 -10 0 10 20 30 40 50 i Flux Difference (AI) %
)
i Core Operating Limits Report Rev. I September 1999 Page 11 of 13
South Texas Project Unit i Cycle 9 f Figure 6 l ,
l K(Z)- Normalized Fo(Z) versus Core IIcight l
l 1.2 -
l Q 1 ,
E _
r E
o 0E '
, if i E x o.s Core Elevation FQ' K(Z)
O 0.0ft 2.55 1.0 ed -
7.0 ft 2.55 1.0 -
14.0' 2.359 0.925 c.2 0
0.0 7.0 14.0 l CORE HGGHT(FT)
.~
l-Core Operating Limits Report , Rev. I September 1999 Page 12 of 13 .
l
I South Texas Project Unit I Cycle 9 l
> Table 1
, Unrodded Fxy for Each Core Height Core Height Unrodded Core Height Unrodded (Ft.) Fxy (Ft.) Fxy '
14.000 3.496 6.800 1.887 13.800 3.158 6.600 1.894 l 13.600 2.812 6.400 1.907 13.400 2.461 6.200 1.915 l .13.200 2.191 6.000 1.920 l 13.000 2.021 5.800 1.926 l 12.800 1.983 5.600 1.935 .
l 12.600 1.967 5.400 1.946 i 12.400 1.968 5.200 1.956 l 12.200 1.965 5.000 1.963 12.000 1.969 4.800 1.965 11.800 1.977 4.600 1.964 11.600 1.992 4.400 1.962 11.400 2.011 4.200 1.967 11.200 2.033 4.000 1.978 11.000 2.044 3.800 1.961 10.800 2.051 3.600 1.947 10.600 2.055 3.400 1.924 10.400 2.054 3.200 1.907 10.200 2.046 3.000 1.895 10.000 2.033 2.800 1.884 l 9.800 2.017 2.600 1.875 l 9.600 2.001 2.400 1.862
.9.400 1.987 2.200 1.848 9.200 'l.976 2.000 1.832 9.000 1.969 1.800 1.817
- 8.800 1.964 1.600 1.803
- 8.600 1.960 1.400 1.810 l 8.400 1.934 1.200 1.813
- 8.200 1.922 1.000 1.827 l 8.000 1.909 0.800 1.958 l 7.800 1.901 0.600 2.195
! 7.600 1.893 0.400 2.487 7.400 1.887 0.200 2.777 7.200' l.884 0.000 3.066 7.000 1.884 For Unit I Cycle 9. the L(Z) penalty is not applied (i.e.,14Z) = 1.0 for all core elevations). i Core Operating Limits Report , Rev. I September 1999 Page 13 of 13 t.
A ttachment 2 NOC-AE-000664 ATTACHMENT 2 Unit 2 Cycle 7 Core Operating Limits Report Revision 1 l