ML17279A795
| ML17279A795 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/2017 |
| From: | Goldman J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TMl-17-103 COLR TMl-1, Rev. 12 | |
| Download: ML17279A795 (40) | |
Text
Exelon Generation Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 October 6, 2017 TMl-17-103 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001
Subject:
Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 Cycle 22 Core Operating Limits Report, COLR TMl-1, Revision 12 TS 6.9.5.4 Enclosed is a copy of the Cycle 22 Core Operating Limits Report, COLR TMl-1, Revision 12. The Cycle 22 Core Operating Limits Report, COLR TMl-1, Revision 12, provides the cycle-specific limits established to support operations of Cycle 22 up to 720 Effective Full Power Days. The cycle-specific core operating limits contained in the report have been determined in accordance with Technical Specification 6.9.5.
The COLR is being submitted to the NRC in accordance with the TMI Unit 1 Technical Specification Section 6.9.5.4.
If you have any questions or require further information, please contact Michael Fitzwater at (717) 948-8228.
Respectfully, Jeffrey A. Goldman Regulatory Assurance Manager, Three Mile Island Unit 1 Exelon Generation Co., LLC
Attachment:
- 1) Cycle 22 Core Operating Limits Report, COLR TMl-1, Revision 12 cc:
USN RC Administrator, Region I USN RC Senior Resident Inspector, TMl-1 USNRC Project Manager, TMl-1 Director, Bureau of Radiation Protection - PA Department of Environmental Resources
AITACHMENT Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 TMl-1 Cycle 22 Core Operating Limits Report Revision 12
__,,g;;:;f
,~
j~ Exelon Generation TMI-1 Cycle 22 Core Operating Limits Report Preparer COLRTMI 1 Rev. 12 "8/JR/IJ Date a'-1R-r:1olr Date
1.0 Core Operating Limits COLR TM! I Rev. 12 Page 2 of38 This CORE OPERATING LIMITS REPORT for TMI-1 Cycle 22 has been prepared in accordance with the requirements of Technical Specification 6.9.5. The Core Operating Limits have been developed using the methodology provided in the references. The following cycle-specific Core Operating Limits are included in this report:
SL 2.1.2 SL 2.3.1 Axial Power Imbalance Protective Limits Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance LCO 3.5.2 Full Incore System Operability Requirements LCO 3.5.2 Quadrant Power Tilt Limits LCO 3.5.2 Power Peaking Factors - Fo(Z)
LCO 3.5.2 Power Peaking Factors - FN6H LCO 3.5.2 Regulating Rod Insertion Limits LCO 3.5.2 Axial Power Imbalance Operating Limits SL 2.1.1 Bases Nuclear Power Peaking Factors SL 2.1.2 Bases Maximum Allowable Local Linear Heat Rates SL 2.3.1 Bases Power-to-Flow Trip Setpoints LCO 3.5.2 Bases Allowable Moderator Temperature Coefficient (MTC)
Alternate Minimum Boron Requirements for Cold Shutdown
- 2. 0 References 2.1 Methodology References BAW-10179P-A, Rev. 8, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," May 2010.
2.2 Other References ANP-3599, Rev. 0, "Three Mile Island Unit 1 Cycle 22 Reload Report," July 2017.
TABLE OF CONTENTS Abstract COLR TMI I Rev. 12 Page 3 of38 PAGE 4
Figure 1 Axial Power Imbalance Protective Limits 7
Figure 2 Reactor Protection System Maximum Allowable Setpoints 8
for Axial Power Imbalance Table 1 Full lncore System (FIS) Operability Requirements 9
Table 2 Quadrant Power Tilt Limits 10 Table 3 Core Monitoring System Bounding Values for 11 LOCA Limited Maximum Allowable Linear Heat Rate Table 4 LCO DNB Maximum Allowable Radial Peaking Limits 14 Figure 3 Regulating Rod Insertion Limits 16 4 Pump Operation Figure 4 Regulating Rod Insertion Limits 18 3 Pump Operation Figure 5 Regulating Rod Insertion Limits 20 2 Pump Operation Figure 6 Axial Power Imbalance Operating Limits 22 Full lncore System - 4 Pump Figure 7 Axial Power Imbalance Operating Limits 24 Full Incore System - 3 Pump Figure 8 Axial Power Imbalance Operating Limits 26 Full Incore System - 2 Pump Figure 9 Axial Power Imbalance Operating Limits 28 Out-of-Core Detector System Figure 10 Axial Power Imbalance Operating Limits Minimum Incore System 30 Core Operating Limit Technical Specification Bases 32 Descriptions Operating Limits Not Required by Technical 37 Specifications
ABSTRACT COLR TMI I Rev. 12 Page 4 of38 This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of TMI-1 Technical Specification 6.9.5. The core operating limits were generated using the methodologies described in the Section 2.1 reference and were documented in the Section 2.2 reference. The core operating limits and reactor protection system limits and setpoints in this report have been analyzed for a maximum end-of-cycle (EOC) length of 720 EFPD.
COLR Figure 1 provides the Axial Power Imbalance Protective Limits (APIPL) that preserve the steady state DNBR, Centerline Fuel Melt, and Cladding Transient Strain design criteria.
COLR Figure 2 provides the Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance which combine the power /flow and error-adjusted axial imbalance trip setpoints that ensure the APIPL of Figure 1 are not exceeded.
The Full Incore System (FIS) operability requirements contained in Table 1 describe the number and location of Self-Powered Neutron Detector (SPND) strings that must be operable in order to monitor imbalance and quadrant tilt using the FIS.
Quadrant power tilt limits for FIS, out-of-core detector [OCD] system and mimmum incore system [MIS] are given in Table 2. Technical Specification requirements related to quadrant tilt, including operator actions that must be taken in the event quadrant tilt limits are exceeded, are stated in T.S. 3.5.2.4.
Table 3 contains the total peaking hot channel factor Fo(Z) limits (i.e., ECCS power peaking limits) for core monitoring.
Table 4 contains the nuclear enthalpy rise hot channel factor FN6H limits (i.e., initial condition DNB peaking) for core monitoring. During normal conditions, operation within quadrant tilt (Table 2), rod insertion (Figures 3-5), and imbalance (Figures 6-10) limits ensure Fo(Z) and FN6H limits are met.
However, verification that positive margin to Fo(Z) and FN6H limits exists may be required during the following abnormal conditions:
T.S. 3.5.2.2.e (operation with an inoperable rod)
T.S. 3.5.2.4.e (operation with quadrant tilt in excess of steady-state limits)
T.S. 3.5.2.5.b (operation with control rods in the Restricted Region)
T.S. 3.5.2.7.d (operation with imbalance in the Restricted Region)
Display 1 of the Core Monitoring System provides the minimum margin to Fo(Z) and FN6H limits on the Summary Core Related Tech Specs page.
COLR TMI I Rev. 12 Page 5 of38 Rod insertion limits are provided in Figures 3 to 5 to ensure that the safety criteria for DNBR protection, LOCA kw /ft limits, shutdown margin and ejected rod worth are met. Technical Specification requirements related to control rod positions, including operator actions that must be taken in the event control rod positions enter Restricted or Not Allowed Regions, are stated in T.S.
3.5.2.5.
Imbalance limits for FIS, OCD and MIS are given in Figures 6 to 10. Technical Specification requirements related to axial power imbalance, including operator actions that must be taken in the event imbalance enters the Restricted Region, are stated in T.S. 3.5.2.7.
COLR Figures 3 through 10 may have three distinctly defined regions:
- 1. Permissible Region
- 2. Restricted Region
- 3. Not Allowed Region (Operation in this region is not allowed)
The limiting criteria within the Restricted Region are ECCS power peaking and initial condition DNB peaking.
Since the probability of accidents related to these criteria is very low, especially in a twenty-four (24) hour time frame, inadvertent operation within the Restricted Region for a period not exceeding twenty-four (24) hours is allowed [T.S. 3.5.2.5.b and 3.5.2.7.e], provided that hot channel factors are within the limits given in Tables 3 and 4. Similarly, continued operation with quadrant tilt greater than the steady-state tilt limit for a period not exceeding twenty-four (24) hours is allowed [T.S. 3.5.2.4.e]
provided that hot channel factors are within the limits given in Tables 3 and 4, with the added requirement that reactor power must be reduced 2% for each 1 % tilt in excess of the tilt limit [T.S. 3.5.2.4.d]. (Note that continued operation with quadrant tilt greater than the steady-state tilt limit is also permitted without hot channel factor verification as long as the alternate guidance in T.S.
3.5.2.4.e is followed).
The limiting criteria within the Not Allowed Region are the shutdown margin limit and potential ejected rod worth. Inadvertent operation in this region is not permitted and requires immediate action to exit the region. Acceptable control rod positions shall be attained within two (2) hours [T.S. 3.5.2.5.b.2]. contains descriptions of limits and factors related to core operating limit TS bases. The Nuclear Power Peaking Factors for axial flux shape (FNz) and hot channel nuclear enthalpy rise (FN6H) define the reference design peaking condition in the core. The Maximum Allowable Local Linear Heat Rate limits for centerline fuel melt and cladding transient strain are the basis for the imbalance portions of the Axial Power Imbalance Protective Limits and Setpoints.
The Power-to-Flow Trip Setpoint, in combination with the axial power imbalance trip, protects against violation of steady-state DNBR criteria.
COLR TMI I Rev. 12 Page 6 of38 The Allowable Moderator Temperature Coefficient (MTC) as a function of power level preserves the LOCA Limited Maximum Allowable Linear Heat Rate limits in COLR Table 3 for partial power and three pump operation. contains operating limits not required by TS. The minimum boron volumes and concentrations for the Boric Acid Mix Tank (BAMT) and Reclaimed Boric Acid Storage Tanks (RBAT) are the boron levels needed to achieve cold shutdown conditions throughout the cycle using these tanks.
-80 Figure 1 COLR TMI I Rev. 12 Page 7 of38 SL 2.1.2 Axial Power Imbalance Protective Limits
(-64.5, 67.1)
(-64.5, 39.8)
-70
-60 Thermal Power Level %
(-48.2, 112.0)
ACCEPTABLE 4PUMP 1 120 l OPERATION 100 (36.2, 112.0)
(-48.2, 89.6) 2 (36.2, 89.6)
ACCEPTABLE 3AND 4 PUMP OPERATION 80
(-48.2, 62.3) 3 (36.2, 62.3)
ACCEPTABLE 60 i 2, 3 AND 4 PUMP OPERATION 40 ~
The 3-or 2-pump example protective limit curves are based on setpoint curves that consider an 20 ~
approximate 25% and 51 % flow reduction for 3-and 2-pump operation respectively. The actual setpoint curves will be calculated by the RPS and l
will be directly proportional to the indicated flow.
-50
-40
-30
-20
-10 0
10 20 30 Axial Power Imbalance, %
CURVE 1
2 3
EXPECTED MINIMUM REACTOR COOLANT FLOW (gpm) 376.64 x 103 281.35 x 103 185.31x103 40 Referred to by Technical Specification 2.1.2 (64.5, 89.5)
(64.5, 67.1)
(64.5, 39.8) 50 60 70 80
Figure 2 COLR TMI I Rev. 12 Page 8 of38 SL 2.3.1 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance
(-50.52, 71.50)
(-50.52, 44.18)
(-50.52, 16.64)
N "'
c:i
~
II iii
-80
-70
-60 0
<"i
"'?
II N
CD
-50
-40 Thermal Power Level %
120 '
(-33.50, 108.0)
(13.11, 108.0)
ACCEPTABLE 4PUMP OPERATION
(-33.50, 80.68)
ACCEPTABLE 3AND4 PUMP OPERATION
(-33.50, 53.14)
ACCEPTABLE 100 60 2, 3 AND 4 PUMP OPERATION The 3-or 2-pump example 0
setpoint curves show allowable values for an approximate 25% and 51%
flow reduction for 3-and 2-pump operation respectively.
20 The actual setpoint curve will be calculated by the RPS and will be directly proportional to the indicated flow.
-30
-20
-10 (13.11, 53.14)
<"i II
(")
CD 0
10 20 30 Axial Power Imbalance, %
40 50 Referred to by Technical Specification 2.3.1 (50.00, 71.50)
(50.00, 44.18)
(50.00, 16.64) 8 c:i II v
CD 60 70 80
Table 1 COLR TMI I Rev. 12 Page 9 of38 LCO 3.5.2 Full Incore System (FIS) Operability Requirements The Full Incore System (FIS) is operable for monitoring axial power imbalance provided the number of valid Self Powered Neutron Detector (SPND) signals in any one quadrant is not less than 75% of the total number of SPNDs in the quadrant.
Quadrant SPNDs 75%
wx 85.75 64.5 XY 99.75 75.0 YZ 89.25 67.0 zw 89.25 67.0 Referred to by Technical Specification 3.5.2.4.a
- The Full Incore System (FIS) is operable for monitoring quadrant tilt provided the number of valid symmetric string individual SPND signals in any one quadrant is not less than 75% (21) of the total number of SPNDs in the quadrant (28).
Quadrant Symmetric Strings wx 7,9,32,35 XY 5,23,25,28 YZ 16, 19,47,50 zw 11, 13,39,43 Referred to by Technical Specification 3.5.2. 7.a
Full lncore System (FIS)
Minimum Incore System (MIS)lbl TABLE 2 COLR TMI I Rev. 12 Page IO of38 LCO 3.5.2 Quadrant Power Tilt Limits Steady State Limit<*!
Steady State Limit1*1 Maximum Limit 15 < Power ~ 60%
Power> 60%
Power > 15%
6.83 4.31 16.8 2.78 1.90 9.5 Referred to by Technical Specification 3.5.2.4 (a)
The Steady State Limits apply during power operation above 15%
power, including power and xenon transients.
(b)
No individual long emitter detector affecting the minimum incore tilt calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.
Note:
If the Full Incore System (FIS) is inoperable, FIS tilt limits are applicable to the Out-of-Core (OCD) Detector System following the guidance in OP-TM-300-202, Quadrant Power Tilt and Axial Power Imbalance using the Out-of-Core Detector System.
TABLE 3 LCO 3.5.2 Power Peaking Factors - FQ(Z)
Core Monitoring System Bounding Values for COLR TMI I Rev. 12 Page 11 of38 LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft lal)
Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2.7.d, 3.5.2.8 UO~ LOCA Limits Batches 19, 22, 23 and 24 Core Elevation 0
34,000 62,000 (feet)
MWd/mtU MWd/mtU MWd/mtU 0.000 15.5 13.5 11.6 2.506 16.5 14.5 11.7 4.264 16.6 14.6 11.8 6.021 17.0 15.0 12.0 7.779 17.0 15.0 12.0 9.536 16.8 14.8 12.0 12.000 15.9 13.9 12.0 Batch 20A Core Elevation 0
34,000 (feet)
MWd/mtU MWd/mtU 0.000 15.0 13.0 2.506 16.0 14.0 4.264 16.1 14.1 6.021 16.5 14.5 7.779 16.5 14.5 9.536 16.2 14.2 12.000 15.3 13.3 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Linear heat rate limits at 0.000, 2.506, and 4.264 feet have been reduced by 0.4, 0.3, and 0.2 kW/ft, respectively, based on compliance with SER to the LOCA Evaluation Model for Once-Through Steam Generator Plants topical.
NOTE: LHR limits provided are based on nuclear power source.
COLR TMI I Rev. 12 Page 12 of38 Table 3 (Continued)
Gadolinia Fuel LOCA Limits Batches 19, 22, 23 and 24 - 2 wt.% Gadolinia Core Elevation 0
34,000 62,000 (feet)
MWd/mtU MWd/mtU MWd/mtU 0.000 14.7 12.7 11.2 2.506 15.6 13.6 11.3 4.264 15.7 13.7 11.4 6.021 16.1 14.1 11.6 7.779 16.1 14.1 11.6 9.536 15.9 13.9 11.6 12.000 15.1 13.1 11.6 Batches 22, 23 and 24 - 3 wt.% Gadolinia Core Elevation 0
34,000 62,000 (feet)
MWd/mtU MWd/mtU MWd/mtU 0.000 14.0 12.0 10.9 2.506 14.9 12.9 11.0 4.264 15.0 13.0 11.1 6.021 15.4 13.4 11.3 7.779 15.4 13.4 11.3 9.536 15.2 13.2 11.3 12.000 14.4 12.4 11.3 Batch 23 - 6 wt.% Gadolinia Core Elevation 0
34,000 62,000 (feet)
MWd/mtU MWd/mtU MWd/mtU 0.000 13.1 11.1 10.2 2.506 13.9 11.9 10.3 4.264 14.0 12.0 10.4 6.021 14.4 12.4 10.6 7.779 14.4 12.4 10.6 9.536 14.2 12.2 10.6 12.000 13.5 11.5 10.6 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Linear heat rate limits at 0.000, 2.506, and 4.264 feet have been reduced by 0.4, 0.3, and 0.2 kW/ft, respectively, based on compliance with SER to the LOCA Evaluation Model for Once-Through Steam Generator Plants topical.
NOTE: LHR limits provided are based on nuclear power source.
Table 3 {Continued)
Gadolinia Fuel LOCA Limits Batches 22, 23 and 24 - 8 wt.% Gadolinia Core Elevation 0
34,000 62,000 (feet)
MWd/mtU MWd/mtU MWd/mtU 0.000 13.1 11.1 10.2 2.506 13.9 11.9 10.3 4.264 14.0 12.0 10.4 6.021 14.4 12.4 10.6 7.779 14.4 12.4 10.6 9.536 14.2 12.2 10.6 12.000 13.5 11.5 10.6 COLR TMI I Rev. 12 Page 13 of38 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Linear heat rate limits at 0.000, 2.506, and 4.264 feet have been reduced by 0.4, 0.3, and 0.2 kW/ft, respectively, based on compliance with SER to the LOCA Evaluation Model for Once-Through Steam Generator Plants topical.
NOTE: LHR limits provided are based on nuclear power source.
The maximum linear heat rate for each CMS level, as measured with the FIDMS Thermal Hydraulic Package, should not be greater than the corresponding bounding value from Table 3 above. CMS Display 1, Summary Core Related Tech Specs, shows the minimum margin to FQ(Z) limits.
Notes:
The LHR limits above are equivalent to the total peaking hot channel factor limits, FQ(Z), referred to in T.S. 3.5.2 by dividing the LHR limits by the product of the core average linear heat rate and the current fraction of rated power. The core average linear heat rate for FQ(Z) calculations is fuel batch specific and is based on nuclear source power to be consistent with the LHR limits above.
TABLE 4 LCO 3.5.2 Power Peaking Factors - FNdH COLR TMI I Rev. 12 Page 14 of38 LCO DNB Maximum Allowable Radial Peaking (MARP) Limits Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2.7.d, 3.5.2.8 The maximum radial peak for each fuel assembly, as measured with the Core Monitoring System (CMS) at the elevation where the assembly axial peak occurs, should not be greater than the corresponding bounding value from the table below.
CMS Display 1, Summary Core Related Tech Specs, shows the minimum margin to FN,..H limits for the fuel assembly with the smallest (or negative) margin.
Notes:
The LCO DNB Maximum Allowable Radial Peaking (MARP) limits below are equivalent to nuclear enthalpy rise hot channel factor limits, FN,..H, referred to in T.S. 3.5.2 by using the following conversion:
FNt.H limit= (LCO DNB MARP) * [1 + 0.3 * (1 - P/Pm)]
where: P = current fraction of power and, Pm = power adjustment factor for RC Pump combination (1.0 for 4 pump, 0.75 for 3 pump)
These limits are applicable to all fuel in the core for 3 and 4 RC pump operation.
These limits have been increased to reflect the 3.8% peaking uncertainty treated by Statistical Core Design (SCD) methodology.
TABLE 4 (Continued)
MARP Limits - Mark-B-HTP Assemblies Axial Maximum Axial Maximum Axial Peak x/L Allowable Peak x/L Allowable Peak Radial Peak Radial Peak 0.01 1.92149 0.01 2.17980 0.14 1.92080 0.14 2.17980 0.20 1.92040 0.20 2.17980 0.30 1.91958 0.30 2.11538 0.40 1.91885 0.40 2.04869 1.1 0.50 1.91833 1.4 0.50 1.97877 1.7 0.60 1.91766 0.60 1.89956 0.70 1.91739 0.70 1.82744 0.80 1.91696 0.80 1.74222 0.89 1.88255 0.89 1.68344 0.99 1.80206 0.99 1.62376 0.01 2.00638 0.01 2.17980 0.14 2.00471 0.14 2.14346 0.20 2.00393 0.20 2.10932 0.30 2.00232 0.30 2.03998 0.40 2.00097 0.40 1.96913 1.2 0.50 1.99966 1.5 0.50 1.90702 1.8 0.60 1.99860 0.60 1.82932 0.70 1.95423 0.70 1.76040 0.80 1.87113 0.80 1.67984 0.89 1.81351 0.89 1.62369 0.99 1.73614 0.99 1.57357 0.01 2.09686 0.01 2.13561 0.14 2.09445 0.14 2.05463 0.20 2.09300 0.20 2.02055 0.30 2.09129 0.30 1.96229 0.40 2.08973 0.40 1.89306 1.3 0.50 2.04596 1.6 0.50 1.83577 1.9 0.60 1.96946 0.60 1.76136 0.70 1.89528 0.70 1.69541 0.80 1.80831 0.80 1.62108 0.89 1.74678 0.89 1.56920 0.99 1.67928 0.99 1.52433 x/L 0.01 0.14 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.89 0.99 0.01 0.14 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.89 0.99 0.01 0.14 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.89 0.99 COLR TMI I Rev. 12 Page 15 of38 Maximum Allowable Radial Peak 2.04944 1.97141 1.93753 1.88636 1.82062 1.76522 1.69761 1.63401 1.56668 1.51767 1.47619 1.95940 1.89208 1.86073 1.81433 1.75302 1.69943 1.63696 1.57725 1.51627 1.46966 1.43130 1.87531 1.81763 1.78748 1.74390 1.68924 1.63873 1.58064 1.52546 1.46766 1.42427 1.38821
110 100 90 80 Cll 3::
0 70 Q.
"C Cll..
60 111 a::::....
0 50
- .e 0
"C s 40 111 u :s
.5 30 20 10 0
0 Figure 3 (Page 1 of 2)
LCO 3.5.2 Regulating Rod Insertion Limits Re ion 25 (0 to 400 +/-10 EFPD; 4 Pump Operation) 50 75 (79.5, 102) 100 125 Restricted Region Permissible Re ion 150 175 200 Indicated Rod Index, % Withdrawn (270, 102) 225 250 COLR TMI I Rev. 12 Page 16 of38 (300, 102)
(252, 78) 275 300 A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3
GI :t 0 a.
"C GI..
nl er::
0
~
0 "C
GI..
nl (J
- c
.5 110 100 90 80 70 60 50 40 30 20 10 0
0 25 Figure 3 (Page 2 of 2)
LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 50 75 Not Allowed Re ion 100 125 150 175 (173.2, 102)
Restricted Region 200 Permissible Re ion 225 Indicated Rod Index, % Withdrawn 250 COLR TMI I Rev. 12 Page 17 of38 (252, 78) 275 300 A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3
Cll
~
0 D..,, s ft!
0::
0
- e 0,, s ft!
() :s
.5 Figure 4 (Page 1 of 2)
LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400 +/-10 EFPD; 3 Pump Operation) 110 100 90 COLR TMI I Rev. 12 Page 18 of38 (300, 77) 80 (80.0, 77)
(270.8, 77) 70 60 50 40 30 20 10 0
0 Not Allowed Region 25 50 75 100 125 150 Restricted Region 175 200 Indicated Rod Index, % Withdrawn Permissible Re ion 225 250 (252, 58) 275 A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3 300
Cl)
~
D..
"C s ftl a::
0
~
"C Cl)..
ftl CJ :c
.5 Figure 4 (Page 2 of 2)
COLR TMI I Rev. 12 Page 19 of38 LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 110 100 90 80 (300, 77) 70 60 50 40 30 20 10 0
0 25 Not Allowed Re ion 50 75 100 125 150 175 (174.3, 77)
Restricted Region 200 Indicated Rod Index, % Withdrawn (270.8, 77)
(252, 58)
Permissible R
ion 225 250 275 A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3 300
Cl)
~
D..
"O Cl) -
Ill a:: -
0
~
0 "O s Ill CJ :c
.5 110 100 90 80 70 Figure 5 (Page 1 of 2)
LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation)
COLR TMI I Rev. 12 Page 20 of38 60 (272, 52)
(300, 52) 50 40 30 20 10 0
0 Not Allowed Re ion 25 50 75 (81.0, 52) 100 125 Restricted Region 150 175 200 Indicated Rod Index, % Withdrawn Permissible Re ion 225 250 (252, 38) 275 A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3 300
110 100 90 80 0
ll.
70 "C
Q)..
cu It:
60 0
~
0 50 "C
.2l cu 40 CJ :c.:
30 20 10 0
Figure 5 (Page 2 of 2)
COLR TMI I Rev. 12 Page21 of38 LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation)
(272, 52) (300, 52)
(0, 4.0) 0 25 Not Allowed Re ion 50 75 100 125 150 175 (176.4, 52)
Restricted Region 200 Indicated Rod Index, % Withdrawn (252, 38)
Permissible Re ion 225 250 275 A Rod group overlap of 25 _+/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.
This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3 300
Figure 6 (Page 1of2)
COLR TMI I Rev. 12 Page 22 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region
(-34.25, 80)
(-35.28, 60)
(-35.28, 0)
Full Incore System - 4 Pump (0 EFPD to 400 +/-10 EFPD)
(-19.58, 102)
Permissible Region CD ;:
0 a..
'C CD -
Ill a::
0
'C.e Ill u
- a
.E 110 100 90 80 70 60 50 40 30 20 10 (17.11, 102)
Permissible Region Restricted Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (45.87, 60)
(45.87, 0) 45 35 25 15 -10
-5 0
5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Rev. 12 Page 23 of38 Figure 6 (Page 2 of 2)
LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region Full Incore System - 4 Pump (400 +/-10 EFPD to EOC) 110
(-13.45, 102)
(16.93, 102) 100 90
(-28.56, 80) 80 Permissible Region I 70
(-29.55, 60) 60 0
a..,,
.e 50 cu IX 0
"01!-,,
40
.e cu u :c 30
.E 20 10
(-29.55, 0)
Permissible Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 Restricted Region (40.54, 60)
(40.54, 0) 45 35 25 15 -10
-5 0
5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
Figure 7 (Page 1 of 2)
COLR TMI I Rev. 12 Page 24 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region
(-34.49, 60)
(-35.46, 45)
(-35.46, 0)
Full Incore System - 3 Pump (0 EFPD to 400 +/-10 EFPD) 90
(-19.88, 77) 80 70 60 Permissible Region 20 10 (14.79, 77)
Permissible Region Restricted Region This Figure is referred to by T.S. 3.5.2. 7 & 3.5.2.4.e.4 (46.04, 45)
(46.04, 0)
-50
-45
-40 30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
Restricted Region Figure 7 (Page 2 of 2)
COLR TMI I Rev. 12 Page 25 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits
(-28.79, 60)
(-29.72, 45)
(-29.72, 0)
Full Incore System - 3 Pump (400 +/-10 EFPD to EOC)
(-13.74, 77)
Permissible Region GI
- I:
0 a..
"C G>
- I:
.2 cc...
0
- .e 0
"C s Ill u :c.:
90 80 70 60 50 40 30 20 10 (14.79, 77)
Permissible Region Restricted Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (40.72, 45)
(40.72, 0) 45 35 25 15
-10
-5 0
5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
Figure 8 (Page 1 of 2)
COLR TMI I Rev. 12 Page 26 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region
(-34.72, 40)
(-35.63, 30)
(-35.63, 0)
-50 40 -35 Full Incore System - 2 Pump (0 EFPD to 400 +/-10 EFPD) 60
(-20.17, 52)
(12.18, 52) 50 40 Permissible Region Permissible Region CD
- i:
0 a..
30 "C
CD
- i:
..2 Ci:...
0
~
0 20 "C.!
Ill u
- c
.5 10 Restricted Region (34.42, 30)
This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (34.42, 0) 25 15
-10
-5 0
5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP 50
-50 Figure 8 (Page 2 of 2)
COLR TMI I Rev. 12 Page 27 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region
(-29.03, 40)
(-29.90, 30)
(-29.90, 0)
-45 35 -30 Full Incore System - 2 Pump (400 +/-10 EFPD to EOC) 60
(-14.04, 52)
(12.18, 52) 50 40 Permissible Region Permissible Region G) ll 0
30 D.
"O ;
0
~
0
~
D "O
20 s
u
- c;
.E 10 Restricted Region (34.42, 30)
This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (34.42, 0)
-25 15
-10
-5 0
5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP 50
Restricted Region
(-28.01, 80)
(-29.46, 60)
(-29.46, 0)
Figure 9 (Page 1 of 2)
LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (0 EFPD to 400 +/-10 EFPD) 110
(-13.51, 102) 100 90 r--~~~~~~~~,80 Permissible 4 Pump Region (See 3 and 2 Pump Limits 70 in Table Below) 60 0
50 ll.
'ti s nl a:
40 0
~
0 al 30 nl u
.5 20 10 (11.14, 102)
Permissible 4 Pump Region Restricted Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 COLR TMI I Rev. 12 Page 28 of38 (39.55, 60)
(39.55, 0)
-40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector S)lstem Imbalance Limits (0 EFPD to 400 +/-10 EFPD) for 3 and 2 Pump Operation Power Neg. lmb.
Pos. lmb.
Power Neg. lmb.
Pos. lmb.
!%FP)
(%FP)
(%FP)
(%FP)
(%FP)
(%FP) 3 Pump Operation 2 Pump Operation 77
-14.36 9.48 52
-15.19 7.50 69
-21.36 17.34 46
-22.13 13.45 60
-28.70 26.26 40
-29.37 19.40 45
-29.96 40.07 30
-30.46 29.28 0
-29.96 40.07 0
-30.46 29.28
Figure 9 (Page 2 of 2)
COLR TMI I Rev. 12 Page 29 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Region Out-of-Core Detector System (400 +/-10 EFPD to EOC) 110
(-7.66, 102) 100 (10.96, 102)
Restricted Region
(-14.25, 92)
(-22.58, 80)
(-23.98, 60)
(-23.98, 0)
Permissible 4 Pump Region (See 3 and 2 Pump Limits in Table Below)
I 0 a.
~ -"'
a:
0
~
"C QI -"'
u iS
.E 90 70 60 50 40 30 20 10 Permissible 4 Pump Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (34.47, 60)
(34.47, 0)
-40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 45 Power
!%FPl 77 69 60 45 0
Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits !400 +/-10 EFPD to EOCl for 3 and 2 Pump Operation Neg. lmb.
Pos. lmb.
Power Neg. lmb.
(%FPl
!%FPl
!%FPl
!%FPl 3 Pump Operation 2 Pump Operation
-8.50 9.48 52
-9.32
-15.03 17.34 46
-15.79
-23.26 26.26 40
-23.93
-24.48 34.98 30
-24.98
-24.48 34.98 0
-24.98 Pos. lmb.
(%FPl 7.50 13.45 19.40 29.28 29.28
Figure 10 (Page 1 of 2)
COLR TMI I Rev. 12 Page 30 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Operation
(-24.87, 80)
(-26.41, 60)
(-26.41, 0)
Minimum Incore System (0 EFPD to 400 +/-10 EFPD) 110
(-11.60, 102) 100 90 80 (See 3 and 2 Pump Limits in Table Below) 70 60 GI ;:
0 CL "C
50 J!!
ca a::
0 40 0
"C ca u
30 iS =
20 (9.46, 102)
Restricted Operation I
Permissible 4 Pump Region I This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (35.59, 60)
(35.59, 0)
-40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 Power
(%FPl 77 69 60 45 0
Indicated Axial Power Imbalance, %FP Minimum lncore System Imbalance Limits (Q EFPD to 400 +/-10 EFPDl for 3 and 2 Pump Operation Neg. lmb.
Pos. lmb.
Power Neg. lmb.
(%FPl
(%FPl
(%FPl
(%FPl 3 Pump Operation 2 Pump Operation
-12.47 8.06 52
-13.15
-18.86 15.23 46
-19.46
-25.57 23.36 40
-26.07
-26.93 35.96 30
-27.46
-26.93 35.96 0
-27.46 Pos. lmb.
(%FPl 6.42 11.84 17.25 26.26 26.26 NOTE: No individual long emitter detector affecting the minimum incore system imbalance calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.
Figure 10 (Page 2 of 2)
COLR TMI I Rev. 12 Page 31 of38 LCO 3.5.2 Axial Power Imbalance Operating Limits Restricted Operation Minimum Incore System (400 +/-10 EFPD to EOC) 110
(-6.28, 102) 100 (9.30, 102)
Restricted Operation
(-12.31, 92)
(-19.93, 80)
(-21.43, 60)
(-21.43, 0) 90 80 Permissible 4 Pump 70 Region)
~-----~60 cu 3:
0 50 II.
"C Cl) -
ca a:
40
~
0
~
0 "C
30 ca u
- c
.E 20 Permissible 4 Pump Region (See 3 and 2 Pump Limits in Table Below This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (30.97, 60)
(30.97, 0)
-40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 Power
(%FP) 77 69 60 45 0
Indicated Axial Power Imbalance, %FP Minimum lncore System Imbalance Limits (400 +/-10 EFPD to EOC) for 3 and 2 Pump Operation Neg. lmb.
Pos. lmb.
Power Neg. lmb.
(%FP)
(%FP)
(%FPl
(%FP) 3 Pump Operation 2 Pump Operation
-7.16 8.06 52
-8.03
-13.11 15.23 46
-1 3.72
-20.63 23.36 40
-21.13
-21.96 31.34 30
-22.48
-21.96 31.34 0
-22.48 Pos. lmb.
(%FPl 6.42 11.84 17.25 26.26 26.26 NOTE: No individual long emitter detector affecting the minimum incore system imbalance calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.
COLR TMI I Rev. 12 Page 32 of38 Core Operating Limit Technical Specification Bases Descriptions
SL 2.1.1 Bases Nuclear Power Peaking Factors COLR TMI I Rev. 12 Page 33 of38 The design nuclear power peaking factors given below define the reference design peaking condition in the core for operation at the maximum overpower. These peaking factors serve as the basis for the pressure/temperature core protection safety limits and the power-to-flow limit that prevent cladding failure due to DNB overheating.
Nuclear Enthalpy Rise Hot Channel Factor (Radial-Local Peaking Factor), FN ~H Axial Flux Shape Peaking Factor, FNz FNz = 1.65 (cosine with tails)
- Total Nuclear Power Peaking Factor, FNQ
SL 2.1.2 Bases Maximum Allowable Local Linear Heat Rates COLR TMI I Rev. 12 Page 34 of38 The maximum allowable local linear heat rate limit is the minimum LHR that will cause centerline fuel melt in the rod or cause the fuel rod cladding to exceed the 1.0% transient strain limit. These limits are the basis for the imbalance portions of the Axial Power Imbalance Protective Limits and Setpoints in Figures 1 and 2 of the COLR, respectively. The limits are fuel design-specific; the value for the most limiting fuel design in the current core is used for monitoring as given below:
AREVA Mark-B-HTP Burn up Linear Heat Rate Linear Heat Rate to (MWd/mtU) to Melt (LHRTM) 1 % Transient (kW/ftl Strain (kW /ft) 0 25.16 23.86 50 25.16 1000 25.36 10000 25.24 15000 24.54 20000 24.09 23.86 25000 23.61 30000 23.13 22.63 40000 22.17 21.51 50000 20.99 20.47 60000 17.33 62000 19.57 17.11
COLR TMI I Rev. 12 Page 35 of38 SL 2.3.1 Bases Power-to-Flow Trip Setpoints The nuclear overpower trip setpoint based on RCS flow (power /flow or flux/flow trip) for the current cycle is 1.08. This setpoint applies to four-,
three-and two-pump operation as described in T.S. Table 2.3-1 and Figure 2 of the COLR.
The power /flow trip, in combination with the axial power imbalance trip, provides steady-state DNB protection for the Axial Power Imbalance Protective Limit (Figure 1).
A reactor trip is initiated when the core power, axial power peaking and reactor coolant flow conditions indicate an approach to the DNBR limit.
The power /flow trip also provides transient protection for loss of reactor coolant flow events, such as loss of one RC pump from a four RC pump operating condition and a locked rotor accident.
Power level and reactor flow rate combinations for four-, three-and two-pump operating conditions are as follows:
- 1.
Trip would occur when four reactor coolant pumps are operating if power level is 108 percent and flow rate is 100 percent, or power level is 100 percent and flow rate is 92.5 percent.
- 2.
Trip would occur when three reactor coolant pumps are operating if power level is 80.68 percent and flow rate is 74.7 percent or power level is 75 percent and flow rate is 69.4 percent.
- 3.
Trip would occur when one reactor coolant pump is operating in each loop (total of two pumps operating) if power level is 53.14 percent and flow rate is 49.2 percent or power level is 49 percent and flow rate is 45.4 percent.
The power level trip and associated reactor power/ axial power imbalance boundaries are reduced by the power-to-flow ratio as a percent (1.08 percent) for each one percent flow reduction.
10 9
c Q) 8
~
0 7
0 Q)...
6
- s -
..., LL CIS -
._ E 5 Q) u Q. Q.
E-4 Q) 3 0....
CIS...
2 Q)
"Cl 0
0 COLR TM! I Rev. 12 Page 36 of38 LCO 3.5.2 Bases - Allowable MTC Limit vs. Power Level 0
20 40 60 80 100 Percent Full Power The LOCA Limited Maximum Allowable Linear Heat Rate limits in COLR Table 3 can be maintained for partial power and three pump operation as long as the maximum allowable positive moderator temperature coefficient (MTC) as a function of power level shown above is preserved.
Note that additional MTC limits are defined in TMI-1 Technical Specification 3.1.7.
COLR TM! I Rev. 12 Page 37 of38 Operating Limits Not Required by Technical Specifications
Alternate Minimum Boron Requirements for Cold Shutdown
(
References:
T.S. 3.3.1.1.a, T.S. 3.3. Bases, FSAR 9.2.1.2)
COLR TMI I Rev. 12 Page 38 of38 The Borated Water Storage Tank (BWST) is required by Technical Specifications 3.3.1.1.a to be available as a source of borated water to meet ECCS LOCA criteria. The T.S. 3.3.1.1.a requirements also ensure that there is a sufficient source of borated water available to bring the reactor to cold shutdown under normal operating conditions. Although not required by T.S., other sources of borated water can be used in lieu of the BWST for the purpose of achieving cold shutdown under normal operating conditions.
The alternate source of borated water shall contain the equivalent of at least 740 ft3 of 12,500 ppm boron with B-10 content no less than 19.5 atom percent, or the equivalent of at least 780 ft3 of 12,500 ppm boron with B-10 content no less than 18.5 atom percent, or the equivalent of at least 820 ft3 of 12,500 ppm boron with B-10 content no less than 17.5 atom percent. There is no T.S. requirement to maintain an alternate source tank at this level, however out-of-service time for this tank should be minimized. The design bases for this tank are described in FSAR Section 9.2.1.2.
The Boric Acid Mix Tank (BAMT) or one of the Reclaimed Boric Acid Tanks (RBAT) can be used as the alternate source of borated water.