ML20202B862
| ML20202B862 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/01/1997 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20202B837 | List: |
| References | |
| NUDOCS 9802120112 | |
| Download: ML20202B862 (33) | |
Text
Core Operating Limits Report Cycle 9 San Onofre Nuclear Generating Station SONGS Unit 3 9902120112 990206 '.
PDR ADOCK 05000361-PM P
I
COLR HTC tu, one.itna ti.it. amet LCS 3.1.100 3.1 REACTIVITY CONTROL SYSTEMS LCS 3.1.100 Mcderator Temperature Coefficient (HTC)
The HTC shall be > [more positive than) -3.7 E 4 Ak/k/*F at RTP.
AND The steady state MTC shall be no more positive than the upper MTC limit shown in Figure 3.1.100-1.
VALIDITY STATEMENT: Effective upon start of Cycle 9.
APPLICABILITY: MODES 1 and 2 with K,,, a 1.0 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Refer to LC0 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to LC0 3.1.4
_ . . . - _ . _ . . _ . . . _ . _ . _ . . . _ . . _ _ . . . _ . . . . . . _ . . _ . . . _ . . _ , _ . - . . . . . . . . _ . - . . _ _ ~ .
i SAN ON0FRE--UNIT 3 3.1-100-1 Rev. 1 May 13, 1997 l
l f
. , . , . . - - , - . - - y
COLR MTC cor, overette,a usiti enort LCS 3.1.100 NOTE: Predicted MTC values shall be adjusted based on Mode 2 measurements to permit direct comparison with cigure 3.1.100 1.
Figure 3.1.1001 MOST POSITIVE MTC VS. POWER 0.6 0.5
\
0.4 N 0.3 N
" 0.2 N
's w
Q-o N N
g-0.1 --
Most Positive MTC Limit
~
a MTC (E-4 dK/K/F) = 0 5. (0.008 X % RTP)
-0.3 -
-0.4 -
0 10 20 30 40 50 60 70 80 90 100 POWER LEVEL (% RTP)
SAN ONOFRE--UNIT 3 3.1-100-2 Rev. 1 May 13, 1997 W
COLR MTC s r. o r.t.ba_U.iti n. net LCS 3.1.100 LCS 3.1.100 ModeratorTemperatureCoefficient(MTC)
BA3ES The limitations on MTC are provided to ensure that the assumptions used in the
-the accident and transient analysis remain valid throughout each fuel cycle.
The limiting events with respect to the MTC limits ares a CEA ejection at the beginning of core life and a main steam line break at the end of core life.
The Surveillance Requirements for measurement of the MTC during each fuel cycle are adequate to confirm the NIC value since this coefficient changes slowly dua princi with fuel burnup. pally to the reduction The confirmation in RCS that the measured boronMTC concentration associated value is within its limit provides assurance that the coefficient will be maintained within acceptable values throughout each fuel cycle.
i
=--
SAN ONOFRE- VNIT 3 - 3.1-100-3 Rev. 1 May 13, 1997
- aer a w *m. _ - - - - - - - - - - - - -
i
COLR Regulating CEA cor, ener. tina u.its enert insertion Limits
' CS 3.1.102 3.1 REACTIVITY CONTROL SYSTEMS LCS 3.1.102 Regulating CEA Insertion Limits The regulating CEA groups shall be limited to the withdrawal ,
sequence, and insertion limits specified in Figure 3.1.102 1- 1 I
VAllDITY STATEMENT: Effective upon TSIP Implementation. '
APPLICABILITY: MODE I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Refer to LC0 3.1.7 SURVEILL*sNCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to LC0 3.1.7 e
SAN ON0FRE--UNIT 3 3.1-102-! Rev. O April 24, 1996
s:
z 8 REGULAllNG CEA WITHDRAWAL VS THERMAL POWER a
E?
C 5
108* GP. 6 5 /
w 1.0 E
0.9 - :3 s c:
0.8 -
! 2 -
E e 2
- 5:
8 0.7 s 7
3 h ]l $0
- Transant
- E
= V 0.6 - "s xs
- E inselhon IJmit - f
- -, m 9 Vs G s
- O m
F oc 0.5 - 0l g, g g i$
ir M o
E 5 0.4 E I - I A s!
~
~
0 y e 50* GP.4 C 0.3 - Es 3 u. 5
. . . . . . .ji................ / -
k o ....................
h 0.2 -
\
120" GP. 6
\
60* GP. 6
\
70~ GP. 5
- g s
0 5 0.1 's -
x u,
c, 0.0 3,,
I i GP.6 i I I t i GP. 4 I I I 5m em v i
,e
-s 150 120 90 60 30 0 150 120 90 60 30 0 g c c, .
m W.5 W.3 "8 W r; f I i i t i I t I ,
150 120 90 60 30 0 150 120 90 FF*
3 532,
=-2
- CEA Withdrawal-Inches r...-i. ..
. ..i....-.......
COLR Regulating CEA core o retiu u.it. n ort insertion Limits LCS 3.1.102 LCS 3.1.102 Regulating CEA Insertion Limits Bases The Core Operating Limits Report (COLR) Licensee Controlled S)ecification (LCS) for Regulating Control Element Assembly (CEA) Insertion .imits provides ,
CLA withdrawal sequence and insertion limits while operating in Modes 1 and 2. i The long term and short term steady state insertinn limits and transient insertion -limits for each regulating CEA group &re s)ecified graphically as a function of the fraction of rated Thermal Power. T1ese limits ensure that an acceptable power distribution and the minimum shutdown margin is maintained, and the potential effects of CEA misalignment are limited to an acceptable _
level. Limited deviations from the nominal requirements are peimitted with Technical Specification (TS) ACTION statements providing additional compensatory restrictions cnd time limits. TS Surveillance Requirements provide assurance that necessary system components are OPERABLE and CEA group positions that may approach or exceed acceptable limits are detected, with adequate time for an Operator to take any required Action.
SAN ONOFRE--UNIT 3 3.1-102-3 Rev. O April 24, 1996 t ._ - - - - - -
COLR Part Length CEA cor. weretiaa u. tis a.mt insertion Limits
!CS 3.1.103 3.1 REACTIVITY CONTROL SYSTEMS LCS 3.1.103 Part Lengtn CEA Insertion Limits The Part-Length CEA groups shall be limited to the insertion limits specified in Figure 3.1.103-1.
VAllDITY STATEMENT: Effective upon TSIP 1mplementation.
APPLICABILITY: MODE 1 > 20% R1P 4 ACTIONS O
CONDITION REQUIRED ACTION COMPLETION TIME Refer to LCO 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to LC0 3.1.8 2
SAN ON0FRE--UNIT 3 3.1-103-1 Rev. O April 24, 1996 i
z
=
PART LENGTH CEA INSERTION UMIT VS THERMAL POWER l
C 5 -
" 8 1.00 i i i i w 3 i i i i i i 6 1 1 0.90 -
o E8
< 112.5" (75%) g n 8 0 70 -
w C 5 e
- _. 2 y 0.60 En
=o w O o
- - r-
" ~
0 0.50 -
E%
~ 5 g ,l \ Transient :
5 - 0.40 O
I f
1 l
Long Term Stoody State h 0.30 ,
' / Insertion umit
= 0 0.20 --------
E D 22.5" (15%)
o E 0.10 - -
{ o i i i i i i i i i i i i , i kk
~
O 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 5[-
s=
^
Pdtt length CEA Pbsition, Inches Withdrawn "c3 LEn m
$ Om S
COLR Part Length CEA c.r. o .ii y .ite n rt insertion Limits LCS 3.1.103 LCS 3.1.103 Part length CEA Insertion Limits Dases
{
The Core Operating Limits Report (COLR) Licensee Controlled Specification (LCS for Part length Control Element Assembly {
the p) art length CEA insertion limits whileting opera (CEA) Insertion in Mode 1 and reactor Li.aits provid power > 20% of RTP. The transient and steady state aart length CEA insertion -
limits are specified graphically as a function of t1e fraction of rated Thermal Power. The part length CEA limits ensure that safety analysis assumptions for ejected CEA worth and power distribution peaking factors are preserved. Limited deviations from the nominal requirements are permitted with Technical Specification (TS) ACTION statements providing additional compensatory restrictions and time limits. TS Surveillance Requirements
, provide assurance that necessary systeta components are OPERABLE and that CEA positions that may approach or exceed acceptable limits are detected, with adequate time for an Operator to take any required Action.
P i
l
! SAN ONOFRE--UNIT 3 3.1-103-3 Rev. O April 24, 1996
Core Oseratina Lielts temort Power Reduction 1 LCS 3.1.105 ;
i 3.1 REACTIVITY CONTROL SYSTEMS LCS 3.1.105 Control Element Assembly (CEA) Misalignment Power Reduction All full length'CEAs shall be OPERABLE and all full and part '
length CEAs shall be aligned to within 7 inches of all other CEAs in its group.
VALIDITY STATEMENT: Rev.1 effective 06/13/97, to be implemented within 30 days APPLICABILITY: MODES I and 2.
ACTIONS r
CONDITION REQUIRED ACTION COMPLETION TIME A. One non group 6 full A.1 Initiate THERMAL POWER In accordance length CEA trippable reduction in accordance with Figure and misaligned from with Figure 3.1.105-1 3.1.105-1.
its group by requirements.
> 7 inches.
B. One group 6 CEA B.1 Initiate THERMAL POWER In accordance trippable and reduction in accordance with Figure misaligned from its with Figure 3.1.105-2 3.1.105-2.
group by > 7 inches, requirements.
C. One part length CEA Cs 1 Initiate THERMAL POWER in accordance initially a 112.5" reduction in accordance with Figure misaligned from its with Figure 3.1.105 3 3.1.105-3.
group by > 7 inches. requirements.
D. One part length CEA D.1 Initiate THERMAL POWER in accordance initially < 112.5" reduction in accordance with Figure misaligned from its with Figure 3.1.105-4 3.1.105-4.
group by > 7 inches. requirements.
(continued)
SAN ONOFRE--UNIT 3 3.1 105 1 Rev. O July 29,1996 -
COLR CEA Hisalignment fore Operattna tietts Peport Power Reduction LCS 3.1.105 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME <
E. Required Action and T.1 Refer to TS 3.1.5. In accordance associated Completion with TS 3.1.5.
Time of Condition A, B, C, or D not met.
0 SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY Refer to LCO 3.1.5 9
(
\
i SAN ON0FRE--UNIT 3 3.1-105-2 Rev. O July 29, 1996
-u
COLR CEA Hisalignment fort 00erof f ar iimits #crort Power Reduction LCS 3.1.105 REQUIRED POWER REDUCTION AFTER SINGLE NON-GROUP 6 FULL LENGTH CEA DEVIATION
- 20" (120 Minutes,18%) ,
% ACCEPTABLE M 15 -
ti OPERATION 5
p I (60 Minutes,10%)
@'0-1 O
E REGION OF 5- UNACCEPTABLE
~
OPERATION (15 Minutes,0%)
On -, , , , ,
0 20 40 , 60 80 100 120 TIME AFTER DEVIATION (MINUTES)
FIGURE 3.1.105-1 When core power is reduced to $8% of rated power per this limit curve, further reduction is not required by this specification.
SAN ONOFRE--bHIT 3 3.1-105-3 Rev. O July 29, 1996
COLR CEA m salignment (cre overottae af fts recart Power Reduction I.CS 3.1.105 REQUIRED POWER Rr ' TION AFTER SINGLE GROUP 6 FULL ' a.H CEA DEVIATION
- 20 REGION OF E. ~
ACCEPTABLE .
'$. OPERATION (120 Minutes,13%)
x n o
P-
@ 10 -
[ll ' (60 Minutes,7%)
x -
REGION OF 8~ -
UNACCEPTABLE OPERATION (15 Minutes,0%)
0.= -. '. . . .
0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)
FIGURE 3.1.105-2 When core power is reduced to 628s of rated power per this limit curve, further reduction is not required by this specification.
SAN ON0FRE--UNIT 3 3.1-105-4 Rev. O July '9, 1996 9
=-s,
COLR cEA Misalignment re , coerettaa n=res accert Power Reduction LCS 3.1.105 REQUIRED POWER REDUC (ION .FTER SINGLE PART LENGTH CL? 0F',IATION (CEA INITIALLY t 112.5 INCHES WITHDRAWN)
=
l 20 - ,
REGION OF g 1s - ACCEPTABLE F_. OPERATION 5.
p.
l Rio -
! O y (120 hiinutes,5%)
a:
5- (60 Minutes,0%) ' '
I 5- (15 hiinutes,0%) ,
RIGION OF UNACCEPTABLE orexAnow 0: : . . - . .
0 20 40 60 80 100 '
120
, TIME AFTER DEVIATION (MINUTES)
FIGURE 3.1.105-3 SAN ONOFRE UNIT 3 3.1 105-5 Rev. I December 2, 1996 oA
. . . . . . . . . . . . . _ _ _ _ . J
COLR CEA Hisalignment cor, one.iina u.n. en, ort Power Reduction LCS 3.1.105 REQUIRED POWER REDUCTION AFTER SINGLE PART LENGTH CEA DEVIATION *
(CEAINITIALLY<112.5INCHESWITHDRAWN) 20 REGION OF E
oc 15 -
ACCEPTABLE
- e. OPERATION O 10 -
8 u
(120 Minutes,5%)
5- l (60 Minutes,2%)
meoxm or 0=
(15 Minutes,0%)
- i
[
0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)
FIGURE 3.1.105-4 When core power is rt Jeed to 50% of rated power per this limit curve, further a
reduction is not required by this specification.
SAN ON0FRE--UNIT 3 3.1-105-6 Rev. 1 July 29, 1996
- - --- .- . _. . . _ _ _ - = . _ . _
COLR CEA Misalignment (cre Occretiae [fefts acroet Power Reduction LCS 3.1.105 LCS 3.1.105 CEA Misalignment Power Redu-tion Bases LCS 3.1.105 The Core Operating Limits Report (COLR) Licensee Controlled Specification (LCS) for Control Element Assembly (CEA) Misalignment Power Reduction provides the power reduction required following a single CEA becoming misaligned from its group by greater than 7 inches wl.ile operating in Modes 1 and 2. There are 4 separate power reduction figures provided, with application being dependent un the type of CEA, either " full length" or "part-length", and the initial position of the "part length" CEA. For " full-length" CEAs, there are two "sub types" identified: "non-Group 6" and " Group 6". For "part length" CEAs, there are two initial conditions identified: " initially a 112.5 inches withdrawn" or " initially < 112.5 inches withdrawn".
The reason for establishing four separate )ower reduction figures is that full-length group 6 CEAs and/or part-lengt1 CEAs are typically used during normal operation. Therefore, a misalignment would most likely involve a CEA in one of these CCA groups. Furthermore, due to the design of the part-length CEAs and their associated insertion limits, it is possible for an inward misalignment to add positive reactivity to the core. Thus, the initial s
position of a single misaligned part length CEA must be considered.
The required poser reductions are spcified graphically as a function of time following the CEA deviation event. For the first 15 minutes, no power reduction is necessary since there is sufficient thermal margin already reserved in the Core Operating Limits Supervisory System (COLSS) or, if COLSS is out-of service, the amount of thermal margin administrative 1y established by LCS 3.2.101, Departure from Nucleate Boiling Ratio (DNBR). After 15 minutes, a power reduction may be required to increase the thermal margin to offset the build-in of Xenon and its detrimental affect on the radial core power distribution (called " distortion"). ,
Reactor power is required to be reduced to compensate for the increased radial power peaking that occurs following a CEA misalignment. At lower power levels, the potentially adverse consequences of increased radial power peaking can be eliminated.
The magnitudes of the required power reductions differ because of the
~ mechanical design differences between full length and part-length CEAs and the core physics characteristics due to the fuel load pattern. There are two (continued)
SAN ON0FRE--UNIT 3 3.1-105-7 Rev. O July 29, 1996 w .. _. , . - .
7 COLR CEA Misalignment rm emeris a t-irs amrt Power Reduction LCS 3.1.105 l LCS 3.1.105 CEA Alignment power Reduction Bases 1
major mechanical differences between full-length and part length CEAs: the l 1engths and types of neutron absorbers. In a part length CEA, the neutron absorber is inconel and is positioned entirely in the lower half of the CEA.
In a full-length CEA, there ate two types of neutron absorbers: silver-indium-cadmium, located in the bottom 12.5 inches of the CEA, and 136 inches of baron carbide, located above the silver indium cadmium.
Since Inconel is neutronically less reactive than boron carbide and silver-indium cadmium, there will be less of a distortion of the coie power distribution as a results of a misalignment of a single part length CEA initially a 112.5 inc!.es withdrawn. Therefore, the magnitude of the power reduction for a part length CEA initially a 112.5 inches withdrawn is less than that for a full-length CEA. However, the positive reactivity added by the misalignment of a single part-length CEA initially < 112.5 inches with' drawn and the resulting power increase is more significant than the difference in the absorbers and a power reduction is required to return power to s 50% RTP where there is sufficient margin already reserved.
One of the core physics characteristics established by the fuel load pattern is CEA reactivity. CEA reactivity depends on the power being produced in the fuel assembly into which the CEA is, inserted. Analysis of a single group 6 CEA misalignment need only be considered with the power being produced in the fuel assemblies into which a group 6 CEA could be inserted. For all other full-length CEAs, the most adverse conditions must be considered. Due to the physical location of group 6, it is unlikely that misalignment of a single group 6 CEA will be most limiting; and typically it is not. Therefore, the magnitude of the power reduction for a group 6 CEA is less than that for the limiting full length non-group 6 CEA.
A maximum of 120 minutes is allotted to concurrently reduce power and/or eliminate the misalignment. The 120 minute limit is based solely on the duration evaluated in the applicable analyses. Since there is no safety analysis basis provided beyond the 120 minute limit Technical Specification 3.1.5 requires that the plant be placed in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after reaching the 120 minute liniit. However, during the power reduction to achieve Mode 3 conditions, continued efforts to re-align the affected CEA are acceptable and recommended.
At all times throughout a required power reduction, THERMAL POWER shall be reduced by greater then or equal to the amount specified by the appropriate
< figure for the given time following the CEA deviation.
(continued)
SAN ONOFRE--UNIT 3 3.1-105-8 Rev. O July 29, 1996
r~
COLR CEA Misalignment c .. e r tin u.it a rt Power Reduction
, LCS 3.1.105 i- LCS 3.1.105 CEA Misalignment Power Reduction Bases-The analysis performed to determine the figures contains the following basic assumptions:
- 1. Only one CEA is misaligned;
- 2. The magnitude of the required power reduction is determined from the increase in the integrated radial peaking factor (F,), represented by static and dynamic distortion factors, the Power Operating Limit (POL)-to-F, ratio and the thermal margin reserved in COLSS as a function of power level;
- 3. The increase in F, is evaluated for only 120 minutes;
- 4. The thermal margin increase accompanying the decrease in core inlet temperature is used to compensate for the thermal margin decrease accompanying the decrease in RCS pressure;
- 5. The change in the axial power distribution due to the misalignment of a
-single CEA has been considered, when applicable,.in the power reduction curves;
- 6. Core power is ett.umed to remain at its initial value for the full-length CEA and the part-length CEA initially a 112.5 inches withdrawn analyses.
No credit is taken for the decrease in the power level due to the negative reactivity added as a result of an inward deviation, and
- 7. The increase,in core power for the part-length CEA initially < 112.5 inches withdrawn analysis is explicitly considered.
..=
SAN ONOFRE- UNIT 3 3.1-105-9 Rev. I December 2, 1996
COLR LNR cor, o . retina u.its an. ort LCS 3.2.100 3.2 POWER DISTRIBUTION LIMITS LCS 3.2.100 linear Heat Rate (LHR)
LHR shall not exceed 13.0 kW/ft.
VAllDITY STATEMENT: Effective upon TSIP implementation.
APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP.
h ACTIONS CONDITION REQUIRED ACTION COMPLETION TlHE I
Refer to LC0 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to LC0 3.2.1 SAN ON0FRE- UNIT 3 3.2-100-1 Rev. O June 18, 1997
COLR LHR core om.tt u.it, n It LCS 3.2.100 LCS 3.2.100 linear Heat Rate (LHR)
BASES The COLR limitation on LHR ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200*F. Actions and Surveillance Requirements are provided by the Technical Specifications (TS).
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory system (COLSS) or the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the LHR does not exceed its limits. The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate. With the reactor operating at or below this calculated power level the LHR limit is not exceeded.
The COLSS calculated core power and the COLSS calculated core power operating limits based on LHR are continuously monitored and displayed to the operator.
A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit. This provides adequate margin to the LHR operating limit for normal steady state operation. Normal reactor power transients- or equipment failures which do not require a reactor tri) may result in this core power operating limit being exceeded, in the event 111s occurs, COLSS alarms will be annunciated. If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation. The COLSS calculation of the LHR includes appropriate penalty factors which provide, with a 95/95 probability / confidence level, that the maximum LHR calculated by COLSS is conservative with respect to the actual maximum LHR existing in the core. These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering design factors, axial densification, software algorithm modelling, computer processing, rod bow and core power measurement.
The core power distribution and a corresponding power o)erating limit based on LHR are more accurately determined by the COLSS using tie incore detector system, fhe CPCs determine LHR less accurately with the excore detectors.
Therefore, when COLSS is not available the TS LCOs are more restrictive due to the uncertainty of the CPCs. However, when COLSS initially becomes inoperable, the added margin associated with CPC uncertainty is not immediately required and a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action is provided for appropriate corrective action.
Parameters required to maintain the operating limit power level based on LHR, margin to DNB and total core power are also monitored by the CPCs as:uming minimum core power of 20% RATED THERMAL POWER. The 20% Rated Thermal Power (continued)--
SAN ONOFRE--UNIT 3 3.2-100 2 Rev. O June 18, 1997
COLR LHR sm # mtino u.it nort LCS 3.2.100 BASES (continued) i threshold is due to the neutron flux detector system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector reading:. Therefore, in the event that the COLSS is not being used, operation within the DNER limits with COLSS out of service can be maintained by utilizing a predetermined io al power density nargin and a total core power limit in the CPC trip channels. The above listed uncertainty penalty factors plus those associated with startup test acceptance criteria are also included in the CPCs.
While operating with the COLSS out of service, the 'PC calculated LHR is monitored every 15 minutes to identify any adverse trend in thermal margin.
. The increased monitoring of LHR during the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> action period ensures that adequate safety margin is maintained for anticipated operational occurrences and no postulated accident results in consequences more severe than those described in Chapter 15 of the UFSAR.
SAN ON0FRE--UNIT 3 3.2-100-3 Rev. O Jt..e 18, 1997
COLR DN3R cor. o r. tina u.it a.=rt LCS 3.2.101 l
3.2 POWER DISTRIBUTION LIMITS LCS 3.2.101 The Departure from Nucleate Boiling Ratio (DNBR) shall be maintained by one of the following methods:
- a. Maintaining Core Operating Limit Supervisory System (COLSS) calculated core power less than or equal to COLSS calculated core power operating-limit based on DNBR (when COLSS is in service, and either one or both control element assembly calculators (CEACs) are OPERABLE);
- b. (faintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 13.0% RTP (when COLSS is in service and neither CEAC is OPERABLE);
- c. Operating within limits as specified in Figure 3.2.101-1A for initial power :t 904 RTP or Figure 3.2.101-1B for initial power < 90% RTP using any OPERABLE core protection calculator (CPC) channel (when COLSS is out of service and either one or both CEACs are OPERABLE); or
- d. Operating within limits as specified in Figure 3.2.101-2 using any OPERABLE CPC channel (when COLSS is out of service and neither CEAC is OPERABLE).
VALIDITY STATEMENT: Effective upon TSIP implementation.
APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP, ACTIONS w
CONDITION REQUIRED ACTION COMPLETION TIME Refer to LCO 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to LCO 3.2.4 t
SAN ONOFRE--UNIT 3 3.2-101-1 Rev. 1 06/12/97
COLR ONBR core op r. tina u.it. :i.=rt LCS 3.2,101 L
COLSS OUT OF SERVICE (>=90% RTP)
ONE OR BOTH CEACS OPERABLE 2.4 - REGION OF g ACCEPTABLE 8023 - OPERATION E
O 2.2 -
2.1 -
s( 2-3 -0.23 <= ASI <= 0.1 j1.9- DNBR >= 0.3
- ASI + 2.0 g 0.1 < ASI <= 0.23 DNBR >= 2,03 51.8-0
$1.7- REGION OF UNACCEPTABLE 1.6 - OPERATION 1.5 .
-0.3 -0.2 -0.1 0 0.1 0.2 0.3 CPC AXIAL SHAPE INGEX (ASI)
Figure 3.2.101-1A DNBR OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS
- COLSS OUT OF SERVICE
- ONE OR BOTH CEACS OPERABLE SAN ON0FRE--UNIT 3 3.2-101-2 Rev. 1 06/12/97 1
COLR DNBR cor. on.r tina u.its nort LCS 3.2.101 COLSS OUT OF SERVICE (<90% RTP)
ONE OR BOTH CEACS OPERABLE 2.8 2.7- REGION OF ACCEPTABLE g2.6- OPERATION z
O g 2.5 -
2.4- ~
a f 2.3 -
-0.2 <= ASI <= 0.05 h-E 22 DNBR >= 0.b' ASI + 2.43 0.05 < ASI <= 0.2 DNBR >= 2.47 I2.1-k 2- REGION OF UNACCEPTABLE g,g . OPERATION 1.8 - - . .
-0.3 -0.2 0.1 0 0.1 02 0.3 CPC AXIAL SHAPE INDEX (ASI)
Figure 3.2.101-1B DNBR OPERATING LIMIT BASED ON CORE PROTECTION CALCULATOR
- COLSS OUT OF SERVICE
- BOTH CEACS INOPERABLE SAN ON0FRE--UNIT 3 3.2-101 3 Rev. 1 06/12/97 5 a
COLR ONBR core oper. tina u.it, n. rt LCS 3.2.101 COLSS OUT OF SERVICE DOTH CEACS INOPERABLE 3.5 3.4 -
REGION OF g 3.3 ACCEPTABLE E OPERATION o 3.2 -
3.1 -
-j -0.2 <= ASI <= 0.0 l
< 3-DNBR >= 1.0
- ASI + 3.1 5 0.0 < ASI <= 0.2 g .9 2 -
DNBR >= 3.1 E
" 2.8 -
REGION OF
{2.7- UNACCEPTABLE 2.s . OPERATION 2.5 - . . .
i i -
-0.3 -0.2 -0.1 0 0.1 0.2 0.3 CPC AXlAL SHAPE INDEX (ASI)
Figure 3.2.101-2 DNBR OPERATING LIMIT BASED ON CORE PROTECTION CALCULATOR
- COLSS OUT OF SERVICE
- BOTH CEACS IN0PERABLE SAN ON0FRE--UNIT 3 3.2-101-4 Rev. 1 06/12/97 m ___-
COLR DNBR cor, oper. tina unit a.cori LCS 3.2.101 LCS 3.2.101 DNBR BASES The COLR limitation on DNBR as a function of Axial Shape Index (ASI) represents a conservative envelope of operating conditions consistent with the safety analysis assumptions and which have been analytically demonstrated adequate to maintan an acceptable minimum DNBR throughout all anticipated operational occurrences, of which the loss of flow transient is the most limiting. Operation of the core with a DNBR at or above this limit provides assurance that an acceptable minimum DNBR will be maintained in the event of a loss of flow transient. The TS provides the required Actions and Surveillance F Requirements to ensure that the minimum DNBR is maintained.
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) or the DNBR channels in the Core Protection Calculators rov lde adequate monitoring of the core power distribution and are cap able (CPCs),
of verifying that the DNBR does not violate COLR s)ecified limits. The COLSS performs this function by continuously monitoring tie core power distribution and calculating a core o)erating power limit corresponding to the allowable minimum DNBR. The CO.SS calculation of core power operating limit based on the minimum DNBR limit includes appropriate penalty factors which provide, with a 95/95 probability / confidence level, that the core power limit calculated by COLSS {
conservative with respect to the actual co(based on thelimit.
re power minimum TheseDNBR limit) is penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering design factors, state parameter measurement, software algorithm modeling, computer processing, rod bow and core power
[ measurement.
Paremeters required to maintain the margin to ONB and total core power are also monitored by the CPCs. In the event that the COLSS is not being used, the DNBR margin can be maintained by monitoring with any OPERABLE CPC channel so that the DNBR remains above the predetermined limit as a function of Axial Shape Index. The above listed uncertainty penalty factors are also included in the CPCs, which assume a minimum of 20% of RATED THERMAL POWER. For the condition in which one or both CEACs are operable, the thermal margin requirements are given as a function of power level. One reqtirement a) plies to 2 90 % RTP and the other applies to < 90% RTP. The 20% RATED THERMA POWER threshold is due to the excore neutron flux detector system being less accurate below 20% core power. Ccre noise level at low power is too large to obtain usable detector readings. The additional CPC uncertainty terms for transient protection are removed from the COLR figures since the curves are intended to lonitor the LC0 only during steady state operation.
The core power distribution and a corresponding POL based on DNBR are more accurately determined by the COLSS using the incore detector system. The CPCs (continued)
SAN ON0FRE--UNIT 3 3.2-101-5 Rev. 1 06/12/97 l
l
COLR DNBR cor we. tina u.it, a n LCS 3.2.101 BASES (continued) determine DNBR less accurately using the excore detectors. When COLSS is not available the TS LCOs are more restrictive due to the uncertainty of the CPCs.
However, when COLSS initially becomes inoperable the added margin associated with CPC uncertainty is not immediately required and a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ACTION is provided for appropriate corrective action.
A DNBR penalty factor has been included in the COLSS and CPC DNBR calculation to accommodate the effects of rod bow. The amount of rod bow in each assembly is dependent upon the average burnup experienced by that assembly. Fuel assemblies that incur higher average burnup will experience a greater magnicude of rod bow. Conversely, lower burnup assemblies will experience less rod bow. In design calculations, the penalty for each batch required to compensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum integrated planar-radial power peak. A single net penalty for COLSS and CPC i: then determined from the penalties associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher burnup batches.
I While operating with the COLSS out of service, the CPC calculated DNBR is monitored every 15 minutes to identify any adverse trend in thermal margin.
The increased monitoring of DNBR during the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> action period ensures that adequate safety margin is maintained'for anticipated operational occurrences and no postulated accident results in consequences more severe than those described in chapter 15 of the UFSAR.
i SAN ON0FRE--UNIl 3 3.2-101-6 Rev. 0 06/12/97
P COLR ASI c r. o r tine u .it. n rt .LCS 3.2.102
---3.2 POWER. DISTRIBUTION LIMITS LCS 3.2.102- Core average Axial Shape Index (ASI) shall be within the following-limits:
- b. COLSS OUT OF SERVICE-(1) -One or Both ",EACs Operable and a 90% RTP -0.23 s ASI s +0.23 (2)- One or Both CEACs Operable and < 90% RTP OR Both CEACs Inoperable -0.20 s ASI s +0.20 VALIDITY STATEMENT: Effective upon TSIP implementation.
APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Refer to LC0 3.2.5 SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY-Refer to LC0-3.2.5 SAN ON0FRE--UNIT 3 3.2-102-1 Rev. 1 06/12/97 k .__ . . . . . . . . .. -.. -.
__.__j
COLR ASI Sm o.*rattaa u.it. n rt LCS 3.2.102 lCS 3.2.102 ASI BASES The Axial Shape Index (ASI) is a measure of the power generated in the lower half of the core less the power generated in the upper half of the core divided by the sum of these powers. This specification is provided to ensure that the core average ASI is maintained within the range of values assumed-as an initial condition in the safety analyses.
The ASI can be determined by utilizing either the Core Operating Limit Supervisory System (COL 5S) or any OPERABLE Core Protection Calculator (CPC) channel. The real time monitoring capability and accuracy of COLSS allows COLSS to monitor power limit margins closely. Consequently, the ASI limit is broader than it would be with the same core without COLSS. Although the
. uncertainty associated with the ASI calculated by the CPCs is not dependent on the operability status of the CEACs, a larger unc9rtainty is applied to the
< 90% RTP case with one or both CEACs operable and to the case of both CEACs inoperable to provide additional conservatism. The COLSS continuously calculates the ASI and compares the calculated value to the parameter established for the COLSS ASI alarm limit. In addition, there is an uncertainty associated with the COLSS calculated ASI; therefore the COLSS ASI alarm limit includes this uncertainty. If the LC0 is exceeded, COLSS alarms are initiated. The ASI limit is selected so that no safety limit will be L
exceeded as a result of an anticipated operational occurrence, and so that the consequence of a design basis accident will be acceptable.
SAN ONOFRE--UNIT 3 3.2-102-2 Rev. 1 06/12/97
. __ . _ , .. _ _. ~ __ _. .
COLR Boron Concentration Limit l core operating uutts poport LCS 3.9.100 j
3.9 REFUELING OPERATIONS - l i
LCS'3.9.100 Boron Concentration Limit With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity conditions is met.
- a. K,,, s 0.95, or
- b. Boron concentration a 2600 ppm.
VALIDITY STATEMENT: Rev. 1 effective-12/1/97, to be implemented within 30 days.
APPLICABILITY: MODE 6.
ACTIONS REQUIRED ACTION COMPLETION TIME CONDITION A.1 Suspend all Immediately A. The-more restrictive of the following not operations involving, met: CORE ALTERATIONS or positive reactivity-
- a. K,,f 5 0.95, or changes.
- b. Boron AND concentration Immediately t 2600 ppm. A.2 Initiate and continue boration at t 40 gpm of a solution containing adequate boron concentration until K ,,is reduced tos0.65.
4 3.9-100-1 Rev. 1 12/1/97 SAN ON0FRE--UNIT 3
l COLR Baron Concentration timit core op rettna u.it nemt LCS 3.9.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.100.1 The boron concentration of the Reactor 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Coolant System and the refueling canal shall be determined by chemical analysis.
/L SAN ON0FRE--ljNIT 3 3.9-100-2
, Rev. 0 June 18, 1997 1
y .
COLR Baron Concentration timit core operating ttatt< aaport LCS 3,9.100 LCS 3.9.100 Boron Concentration Limit BASES
] The limitations on reactivity conditions during REFUELING ensure that: 1) $
the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the ' on dilution incident in the accident analyses. The value of 0.95 or les:. for K,,,
includes a conservative allowance for uncertainties.
U i
o s.
i SAN ON0FRE--UNIT 3 3.9-100-3 Rev. I 12/1/97
_ _ _ . _ . 9