TMI-15-027, Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10
| ML15062A009 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/27/2015 |
| From: | Atherholt D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TMI-15-027 | |
| Download: ML15062A009 (44) | |
Text
Three Mile Island Unit 1 A Exelon Generation,,
Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 TS 6.9.5.4 February 27, 2015 TM1-15-027 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10
References:
- 1) Letter from D. A. Atherholt to U.S. Nuclear Regulatory Commission, "Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9," dated November 8, 2013.
- 2) Letter from James Barstow to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 30-Day Report," dated December 22, 2014.
In Reference 1, Exelon Generation Company, LLC (Exelon) submitted "Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9," in accordance with TMI-1 Technical Specification (TS) Section 6.9.5.4.
Reference 2 reported the most recent Large Break Loss-of-Coolant Accident (LBLOCA) analysis that resulted in a non-conservative increase in peak cladding temperature (PCT) during a LBLOCA from the application of an additional fuel temperature uncertainty due to a deficiency related to the modeling of fuel thermal conductivity degradation (TCD).
In order to preserve the existing TMI LOCA analysis of record for PCT, TMI implemented a 2 kw/ft penalty to the linear heat rate (LHR) limits in Cycle 20 on October 20, 2014. The penalty was applied through more restrictive operational imbalance limits.
Provided in the attachment to this letter is a copy of the revised Cycle 20 Core Operating Limits Report, COLR TMI 1, revision 10. This is a mid-cycle 20 revision of the COLR due to the above described error in modeling of fuel TCD and provides the updated cycle-specific axial imbalance alarm limits established to support operations of Cycle 20 from BOC to 450 EFPD and then from 450 EFPD up to 715 Effective Full Power Days. LOCA Linear Heat Rate limits for FQ(Z) monitoring are also updated. The cycle-specific core operating limits contained in the report have been determined in accordance with Technical Specification 6.9.5, using the 2 kw/ft penalty reported to the NRC under 10CFR50.46 in Reference 2.
The COLR is being submitted to the NRC in accordance with the TMI Unit 1 Technical Specification Section 6.9.5.4.
U.S. Nuclear Regulatory Commission Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10 February 27, 2015 Page 2 Should you have any questions concerning this letter, please contact Mike Fitzwater at (717) 948-8228.
Respectfully, David W. Atherholt Regulatory Assurance Manager, Three Mile Island Unit 1 Exelon Generation Co., LLC DWA/mdf
Attachment:
- 1) Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10 cc: USNRC Administrator, Region I USNRC Senior Resident Inspector, TMI-1 USNRC Project Manager, TMI-1 Director, Bureau of Radiation Protection - PA Department of Environmental Resources
U.S. Nuclear Regulatory Commission Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10 February 27, 2015 Page 3 bcc: Sr. Vice President, Mid-Atlantic Operations w/o Attachment Vice President, Mid-Atlantic Operations Site Vice President - TMI-1 Plant Manager-TMI-1 Director, Operations - TM I-1 Director, Site Engineering - TM I-1 Manager, Regulatory Assurance - TMI-1 Manager, Licensing - KS Commitment Coordinator - KS W/Attachment Records Management - KS It PA DEP BRP Inspector-TMI-1 It R. P. Jaffa - KS M. Mahgerefteh - KS T. L. Stevens - Cantera II W. Stanley - TMI-1 H. C. Crawford- TMI-1 J. A. Dullinger-TMI-1 M. D. Fitzwater-TMI-1 P. S. Brady- TMI-1
ATTACHMENT Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 TMI-1 Cycle 20 Core Ooeratine Limits Reoort Revision 10
Exelon Generation, TMI- 1 Cycle 20 Core Operating Limits Report COLR TMI 1 Rev. 10 direphe Date Re~viewISQR ) Date 4~ NF Approver Date 17 FEB 2015 I
Date
- Dat
COLR TMI I Rev. 10 Page 2 of 40 TABLE OF CONTENTS PAGE Abstract 3 Full Incore System (FIS) Operability Requirements 6 Table 1 Error Adjusted Quadrant Tilt Limits 7 Table 2 Core Monitoring System Bounding Values for 8 LOCA Limited Maximum Allowable Linear Heat Rate Table 3 LCO DNB Maximum Allowable Radial Peaking Limits 11 Figure 1 Error Adjusted Rod Insertion Limits 13 4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 15 3 Pump Operation Figure 3 Error Adjusted Rod Insertion Limits 17 2 Pump Operation Figure 4 Full Incore System Error Adjusted 19 4 Pump Imbalance Limits Figure 5 Full Incore System Error Adjusted 21 3 Pump Imbalance Limits Figure 6 Full Incore System Error Adjusted 23 2 Pump Imbalance Limits Figure 7 Out-of-Core Detector System Error Adjusted 25 Imbalance Limits Figure 8 Minimum Incore System Error Adjusted 27 Imbalance Limits Figure 9 LOCA Limited Maximum Allowable Linear Heat Rates 29 Figure 10 Axial Power Imbalance Protective Limits 32 Figure 11 Reactor Protection System Maximum Allowable Setpoints 33 for Axial Power Imbalance References 34 Operating Limits Not Required by Technical 35 Specifications DNBR-Related Bases Descriptions 38
COLR TMI I Rev. 10 Page 3 of 40 ABSTRACT 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 References 1 and 2 and were documented in Reference 3. 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 715 EFPD.
The Full Incore System (FIS) operability requirements contained within 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 tilt limits for FIS, out-of-core detector [OCD] system and minimum incore system [MIS] are given in Table 1. 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.
Rod insertion limits are provided in Figures 1 to 3 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 4 to 8. 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 1 through 8 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, initial condition DNB peaking, and potential ejected rod worth. 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 2 and 3. Similarly, continued operation with quadrant tilt
COLR TMI I Rev. 10 Page 4 of 40 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 2 and 3, 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 criterion within the Not Allowed Region is the shutdown margin limit. 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].
Table 2 contains the total peaking hot channel factor FQ(Z) limits (i.e., ECCS power peaking limits) for core monitoring. Table 3 contains the nuclear enthalpy rise hot channel factor FNAH limits (i.e., initial condition DNB peaking) for core monitoring. During normal conditions, operation within quadrant tilt (Table 1), rod insertion (Figures 1-3), and imbalance (Figures 4-8) limits ensure FQ(Z) and FNAH limits are met. However, verification that positive margin to FQ(Z) and FNAH 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 4 of the Core Monitoring System provides the minimum margin to FQ(Z) limits on the Thermal Limiting Condition Core Summary page and to FN H, limits on the Thermal Limiting Condition Hot Channel Factor page.
COLR Figure 9 indicates the LOCA limited maximum allowable linear heat rates as a function of fuel rod burnup and fuel elevation for the Mark-B-HTP fuel type. Bounding values for monitoring these limits for the current cycle in terms of fuel batch, fuel rod burnup and core elevation are listed in Table 2.
The full power linear heat rate limits are applicable for partial-power and three-pump operation since the allowable moderator temperature coefficient (MTC) as a function of power, shown on page 3 of Figure 9, is preserved by the cycle design.
COLR Figure 10 provides the Axial Power Imbalance Protective Limits (APIPL) that preserve the DNBR and Centerline Fuel Melt design criteria.
COLRTMI I Rev. 10 Page 5 of 40 COLR Figure 11 provides the 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 10 are not exceeded. contains operating limits not required by TS. The Maximum Allowable Local Linear Heat Rate limits are monitored by the Process Computer core monitoring system software as part of the bases of the required limits and setpoints. 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. contains the bases descriptions of the Power-to-Flow Trip Setpoint to prevent violation of DNBR criteria and the Design Nuclear Power Peaking Factors for axial flux shape (FNz) and hot channel nuclear enthalpy rise (FNAH) that define the reference design peaking condition in the core.
COLR TMI I Rev. 10 Page 6 of 40 I 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 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 Source Doc.: B&W 86-1172640-00 Referred to by: Tech. Spec. 3.5.2.4.a and 3.5.2.7.a
COLR TMI I Rev. 10 Page 7 of 40 I TABLE 1 Error-Adjusted Quadrant Tilt Limits Steady State Limit Steady State Limit Maximum Limit 15 < Power < 60% Power > 60% Power > 15%
Full Incore System 6.83 4.53 16.8 (FIS)
Minimum Incore System 2.78 1.90 9.5 MIS (a) I (a) No individual long emitter detector affecting the minimum in-core 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.
Referred to by: Tech. Spec. 3.5.2.4
COLR TMI I Rev. 10 Page 8 of 40 I TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Aflowable Linear Heat Rate (kW/ft (-))
UO, LOCA Limits Batches 20 (Except Batch 206). 21 and 22 Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.58 13.58 12.0 2.506 16.48 14.48 12.0 4.264 16.8 14.8 12.0 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 20B Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.48 13.48 12.0 2.506 16.38 14.38 12.0 4.264 16.7 14.7 12.0 6.021 16.9 14.9 12.0 7.779 16.9 14.9 12.0 9.536 16.4 14.4 12.0 12.000 15.5 13.5 12.0 (a) Linear interpolation for allowable linear heat rate limits between specified bumup points and core elevation points is valid for these tables. All values at 0.000 and 2.506 feet except those at 62,000 MWd/mtU have been reduced by 0.32 kW/ft based on compliance with SER to BAW-1 0192-A.
NOTE: LHR limits provided are based on nuclear power source.
COLR TMI I Table 2 (Continued)
Rev. 10 Page 9 of 40 I Gadolinia Fuel LOCA Limits Batches 20, 21 and 22 - 2 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 14.78 12.78 11.6 2.506 15.58 13.58 11.6 4.264 15.9 13.9 11.6 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 20, 21 and 22 - 3 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 14.08 12.08 11.3 2.506 14.88 12.88 11.3 4.264 15.2 13.2 11.3 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 21 - 6 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 13.18 11.18 10.6 2.506 13.88 11.88 10.6 4.264 14.2 12.2 10.6 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. All values at 0.000 and 2.506 feet except those at 62,000 MWd/mtU have been reduced by 0.32 kW/ft based on compliance with SER to BAW-10192-A.
NOTE: LHR limits provided are based on nuclear power source.
COLRTM! I Rev. 10 Page 10 of 40 Table 2 (Continued)
Gadolinia Fuel LOCA Umits Batches 20, 21 and 22 - 8 wt.% Gadolinia Core Elevation 0 34.000 62,000 (feet) MWdImtU MWd/mtU MWd/mtU 0.000 13.18 11.18 10.6 2.506 13.88 11.88 10.6 4.264 14.2 12.2 10.6 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 bumup points and core elevation points is valid for these tables. All values at 0.000 and 2.506 feet except those at 62,000 MWd/mtU have been reduced by 0.32 kW/ft based on compliance with SER to BAW-1 0192-A.
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 2 above. FIDMS Display 4, Thermal Limiting Condition Core Summary, shows the minimum margin to FQ(Z) limits for each axial level.
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.
COLR TMI I Rev. 10 Page I I of 40 TABLE 3 LCO DNB Maximum Allowable Radial Peaking (MARP) Limits 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 4, Thermal Limiting Condition Hot Channel Factor page, shows the minimum margin to FNAH limits for the fuel assemblies 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, FNAH, referred to in T.S. 3.5.2 by using the following conversion:
FNAH 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.
COLR TMI I TABLE 3 (Continued)
Rev. 10 Page 12 of 40 I MARP Limits - Mark-B-HTP Assemblies Axial Maximum Maximum Maximum Peak x/L Allowable Radial Peak Peak x/L Allowable Peak x/L Allowable Radial Peak Radial Peak 0.01 1.92149 0.01 2.17980 0.01 2.04944 0.14 1.92080 0.14 2.17980 0.14 1.97141 0.20 1.92040 0.20 2.17980 0.20 1.93753 0.30 1.91958 0.30 2.11538 0.30 1.88636 0.40 1.91885 0.40 2.04869 0.40 1.82062 1.1 0.50 1.91833 1.4 0.50 1.97877 1.7 0.50 1.76522 0.60 1.91766 0.60 1.89956 0.60 1.69761 0.70 1.91739 0.70 1.82744 0.70 1.63401 0.80 1.91696 0.80 1.74222 0.80 1.56668 0.89 1.88255 0.89 1.68344 0.89 1.51767 0.99 1.80206 0.99 1.62376 0.99 1.47619 0.01 2.00638 0.01 2.17980 0.01 1.95940 0.14 2.00471 0.14 2.14346 0.14 1.89208 0.20 2.00393 0.20 2.10932 0.20 1.86073 0.30 2.00232 0.30 2.03998 0.30 1.81433 0.40 2.00097 0.40 1.96913 0.40 1.75302 1.2 0.50 1.99966 1.5 0.50 1.90702 1.8 0.50 1.69943 0.60 1.99860 0.60 1.82932 0.60 1.63696 0.70 1.95423 0.70 1.76040 0.70 1.57725 0.80 1.87113 0.80 1.67984 0.80 1.51627 0.89 1.81351 0.89 1.62369 0.89 1.46966 0.99 1.73614 0.99 1.57357 0.99 1.43130 0.01 2.09686 0.01 2.13561 0.01 1.87531 0.14 2.09445 0.14 2.05463 0.14 1.81763 0.20 2.09300 0.20 2.02055 0.20 1.78748 0.30 2.09129 0.30 1.96229 0.30 1.74390 0.40 2.08973 0.40 1.89306 0.40 1.68924 1.3 0.50 2.04596 1.6 0.50 1.83577 1.9 0.50 1.63873 0.60 1.96946 0.60 1.76136 0.60 1.58064 0.70 1.89528 0.70 1.69541 0.70 1.52546 0.80 1.80831 0.80 1.62108 0.80 1.46766 0.89 1.74678 0.89 1.56920 0.89 1.42427 0.99 1.67928 0.99 1.52433 0.99 1.38821
COLR TMI I Figure 1 (Page 1 of 2)
Rev. 10 Page 13 of 40 I Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 4 Pump Operation) 110 100 90 80 CL 70 0 60 a-.
50 V)
S-40 30 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn 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
COLRTMI I Figure 1 (Page 2 of 2)
Rev. 10 Page 14 of 40 I Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90 80 0
.. 70 60 S50 S40
-- 30 2-10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn 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
COLR TMI I Rev. 10 Page 15 of 40 Figure 2 (Page 1 of 2)
Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 3 Pump Operation) 110 100 90 80 70 0~ 60 V
50
.0 40 30 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn 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
COLR TMI I Figure 2 (Page 2 of 2)
Rev. 10 Page 16 of 40 I Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 110 100 90 80 70 0< 60 50 I-40 30 20 10 0
0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn 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
COLR TMI I Rev. 10 Page 17 of 40 Figure 3 (Page 1 of 2)
Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation) 110 100 90 I- 80 U) 0 70 0~
C) 4-(U 60 S.-
0 50 a) 4.* 40
'U U
C 30 20 10 (0,5.9) 0 0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn 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 by1 TS 3.5.2.5.b &3.5.2.4.e.3 I
COLR TMI I Figure 3 (Page 2 of 2)
Rev. 10 Page 18 of 40 I Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 110 100 90 80 go70 0
60 S
50 0
40 30 20 10 0
225 250 275 300 Indicated Rod Index, % Withdrawn 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 b ITS 3.5.2.5.b &3.5.2.4.e.3
COLR TMI I Rev. 10 Page 19 of 40 Figure 4 (Page 1 of 2)
Full Incore System Error Adjusted 4 Pump Imbalance Limits (0 EFPD to 450 +/-10 EFPD) 110
('-19.22.102) (15.23,102)
[]
Restricted 100 ~Region estricted Region
(-26.90,92) (26.73.92) 9o
(-34.92,80) 80 (366.51,80) 70 l[Permissible R e on l 60 (44.17,60)
(-35.11,60)
I Pe Issible 0
I, 50 V
40
- 0 30 20 FThis Figure is referred to by
(-35.11,0) LT.S. 3.5.2.7 & 3.5.2.4.e.4 (44.17,0)
Z....
I y ............................ Z ]2
.... m.... 0.... I .... B
]
.... IZ .... I: .... I: .... I[---e me *Z.... IZ 45 -40 -35 -30 20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Rev. 10 Page 20 of 40 Figure 4 (Page 2 of 2)
Pull Incore System Error Adjusted 4 Pump Imbalance Limits (450 +/-10 EFPD to EOC) 110
(-15.71.102) (15.23,102)
(-24.91.92) 90 .52,92) 3.13,80) 80 (32.08.80) 70 1.44,60) Permissible RegiOn .60 P R (40.51,60) 50.E50 40 "30 20 This Figure is referred to by I 344,0) T.S. 3.5.2.7 &3.5.2.4.e.440.510)
................... D .... B .... - 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. 10 Page 21 of 40 Figure 5 (Page 1 of 2)
Full Incore System Error Adjusted 3 Pump Imbalance Limits (0 EFPD to 450 +/-10 EFPD) 90 Restricted Restricted Region 80 Region 70 (22.99,69)
(-27.12,69)
(-35.11,60) 60 (32.02,60) 50 1 1Perissbe RegionI (44.31,45)
(-35.25,45) 0 0.,
40
.2= 30 0O 20 10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4
(-35.25,0)
-50 -45 -40 -35 25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Rev. 10 Page 22 of 40 Figure 5 (Page 2 of 2)
Full Incore System Error Adjusted 3 Pump Imbalance Limits (450 +/-10 EFPD to EOC) 90 PR cted 5.95,N)
I esrite 80 (14.84.77)
(-25.13.69) 70 (22.99,69)
(-33.32 ,60) 60 (32.27,60)
- I 50' IPeffissible Region Do.65,45)
(-33.58,45) I 40 0
E. 30 20 10 This Figure Is referred to by
(-33.58,0)
T.S. 3.5.2.7 & 3.5.2.4.e.4 I (40.65.0)
---- ------ 4.. 5 0
-50 40 30 20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Rev. 10 Page 23 of 40 Figure 6 (Page 1 of 2)
Full Incore System Error Adjusted 2 Pump Imbalance Limits (0 EFPD to 450 +/-10 EFPD) 60 -
Restricted Region (-19.68,52) (12.25,52) Region Restricted 50 +
(-27.33,46) (18.14,46)
(-35.30,40) 40 (24.33,40)
Permissible Region I ri~ssibI ~IeR
(-35.39,30) 0 30 r34.34.30n I0 0~
20 03 E
10 This Figure Is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (34.34,0)
(-35.39,0) a............................,'.............a
-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Rev. 10 Page 24 of 40 Figure 6 (Page 2 of 2)
Full Incore System Error Adjusted 2 Pump Imbalance Limits (450 +/-10 EFPD to EOC) 60v L~etdte (-16.18,52) (12.25,52) i Restrticted Region o
50
(-25.34,46) (181.14,46)
(-33.511.40) 40 (24.33.40)
~fIPrisble Rj IPermissible Ron
(-33.72,30) 30- b (34.34,30)
C.
0 20 0
10 Ths Figure Is referred Ito by T.S. 3.[.2.7 &3.5.2.4 .e.4
(-33.72.0) (34.34.0) 45 35 -30 20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP
COLR TMI I Figure 7 (Page 1 of 2)
Rev. 10 Page 25 of 40 II Out-of-Core Detector System Error Adjusted Imbalance Limits (0 EFPD to 450 +/-10 EFPD) 110
(-13.05,102) (9.21,102)
[ Rl=*trirt*,d I Restricted Region
(-20.62,92) 100 90 Resticte (20.43.92) f
(-28.55,80) Permissible 4 Pump Region 80 (30.04,80)
(See 3 and 2 Pump Limits Permissible 4 Pump Region in Table Below) 70
(-29.21,60) 0.60 7.83,60) 0
.U50 040 030 0
20 10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I 4 . .;. . . .... ... . . .: .
. (37.83,0)
-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 System Error Adiusted Imbalance Limits (0 EFPD to 450 +10 EFPD) for 3 and 2 Pumo Operation Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.
__F__ (%FPL (%FPL MMFP (%FPt LFP1 3 Pump Operation 2 Pump Operation 77 -13.86 9.41 52 -14.64 7.48 69 -21.37 17.39 46 -22.10 13.26 60 -29.21 26.23 40 -29.85 19.31 45 -29.69 38.32 30 -30.16 29.12 0 -29.69 38.32 0 -30.16 29.12
COLRTMI I Rev. 10 Page 26 of 40 Figure 7 (Page 2 of 2)
Out-of-Core Detector System Error Adjusted Imbalance Limits (450 +10 EFPD to EOC) 110
(-9.71,102) (9.21,102)
Re(st1.72ed Region Regio
(-18.72,921 (18.32,92)
(-26.84.80) (25.82,80)
(-27.61,60)
-60 (34.34,60) 10 e.
150 040
.I 20 10 T~ iureirefre dto by1
(-27.61.0) (34.34,0) l I .... i.. *
-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 System Error Adjusted Imbalance Limits (450 *10 EFPD to EOC) for 3 and 2 Pumo Ooeration Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.
(F) (%FP) MMEE (%FP) LEFP 3 Pump Operation 2 Pump Operation 77 -10.51 9.41 52 -11.29 7.48 69 -19.46 17.39 46 -20.19 13.26 60 -27.50 26.47 40 -28.14 19.31 45 -28.09 34.82 30 -28.56 29.12 0 -28.09 34.82 0 -28.56 29.12
COLR TMI I Rev. 10 Page 27 of 40 Figure 8 (Page 1 of 2)
Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to 450 +/-10 EFPD) 11l0 Rsrcte (-11.00,102) (7.36,102)
Restricted Operation
(-17.91,92)
- ) (26.53,80)
(-25.16,80) 80 70f I Permissible4 Pump
(-26.01,60) 60 (33.84,60) 0 0
- 0. 50 a
S Lu 0 40
- 0 aU 30 U
'U E
20 10 This Figure is referred to by T.S. 3.5.2.7 & 3 .5.2.4.e.4 I
(-26.01,0) 1I (33.84,0)
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to 450 1:0 EFPD) for 3 and 2 Pump Operation Power Neg. Imb. Pos. Imb. Power Neg. lmb. Pos. lmb.
(%FP) (%Fp) (%FP) 3 Pump Operation 2 Pump Operation 77 -11.88 7.89 52 -12.55 6.33 I 69 -18.72 15.15 46 -19.32 11.58 I 60 -25.86 23.19 40 -26.36 17.09 I 45 -26.54 34.22 30 -27.06 26.00 I 0 -26.54 34.22 0 -27.06 26.00 NOTE: No individual long emitter detector affecting the minimum in-core system imbalance calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.
COLRTMl I Rev. 10 Page 28 of 40 Figure 8 (Page 2 of 2)
Minimum Incore System Error Adjusted Imbalance Limits (450 +/-10 EFPD to EOC) 110 -
Rstricted I (-7.98,102) j (7.56,102) ,_
r _ __ _
(-16.19,92)
(-23.62,80) (22.71,80)
(-24.57,60) (30.67,60)
(-24.57,0) (30.67,0)
&4--
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Error Adjusted Imbalance Limits (450 +/-10 EFPV to EOC) for 3 and 2 Pump Operation Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.
(%PI ( %FP (%FPI im
(%FP1 (YEE1 3 Pump Operation 2 Pump Operation 77 -8.65 7.89 52 -9.53 6.33 69 -16.80 15.15 46 -17.60 11.58 60 -24.32 23.41 40 -24.82 17.09 45 -25.09 31.05 30 -25.62 26.00 0 -25.09 31.05 0 -25.62 26.00 NOTE: No individual long emitter detector affecting the minimum in-core system imbalance calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.
Figure 9 (Page 1 of 3)
LOCA Limited Maximum Allowable Linear Heat Rates for U02 Fuel Rods Mark-B-HTP Fuel Assemblies, Except Batch 20B 18 17 16 15 14 0
E 13 E
2 12 11 10 0 10 20 30 40 50 60 70 X ()
0 Referred by Tech Spec 3.5.2.8 Burnup (GWdImtU)
X C,,
--- 0.0 It and 12 ft -iR-2.506, 4.264, and 9.563 ft --r-6.021 and 7.779 ft i t.
Figure 9 (Page 2 of 3)
LOCA Limited Maximum Allowable Linear Heat Rates for U02 Fuel Rods Mark-B-HTP Fuel Assemblies, Batch 20B (0,
(0, (0,
(II a,I E
.u 0 10 20 30 40 50 60 70 Referred by Tech Spec 3.5.2.8 Bumup (GWdImtU) X~
I 0.0 ft -- 2.506 and 4.264 ft 6.021 and 7.779 ft --- 9.536 ft ---- 12 ft
COLR TMI I Rev. 10 Page 31 of 40 Figure 9 (Page 3 of 3)
MTC Limit vs. Power Level 10 81 _
Ea I 4-0 3 m 2-0 0
0 20 40 60 80 100 Percent Full Power
COLR TMI I Figure 10 Rev. 10 Page 32 of 40 I Axial Power Imbalance Protective Limits Thermal Power Level %
120
(-47.9. 112.0) (36.0. 112.0) 4 ACCEPTABLE 4 PUMP OPERATION 100
-47.9,89.6) (36.0. 851.6) 4#
(-64.2,89.) ACCEPTABLE (64.2.89.5) 3 AND 4 PUMP OPERATION 80
(-64.2,67/
-47.9, 62.3) 0 60-(36.0,6 2.3) (64.2.67.1)
ACCEPTABLE 2.3AND4 PUMP OPERATION The 3- or 2-pump exam pie 40 setpoint curves show
(-64.2. 39.8) allowable values for an (64.2, 39.8) approxdmate 25% and 51% flow reduction for 33-and 2-pump operation respectively. The actual 20 selpoint curve will be calculated by the RPS aend will be directly proportio nal to the indicated flow.
r- T7-
-80 -70 50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axdal Power Imbalance, %
EXPECTED MINIMUM CURVE REACTOR COOLANT FLOW (lb/hr) 1 140.87 x 10O 2 105.60 x 10a 3 69.74 x 10"
COLR TMI I Figure 11 Rev. 10 Page 33 of 40 I Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level %
120 1
(-33.50, 108.0) (13.11, 108.0)
ACCEPTABLE 4 PUMP OPERATION 100 m=-0.989 m = +2.145
(-33.50, 80.68) (13.11, \80..68)ý98 ACCEPTABLE eu 3 AND 4 PUMP OPERATION (50.00, 71.50)
(-50.52. 71 .50) 60
(-33.50, 53.14) (13.11, 53.14)
ACCEPTABLE 6
2, 3 AND 4 PUMP
(-50.52. 44.18) OPERATION (50.00. 44.18)
I The 3- or 2-pump example 0
0*
setpoint curves show allowable values for an approximate 25% and 51%
flow reduction for 3- and 2-pump operation respectively.
The actual 0
(-50.52, 16.64) setpoint curve (50.00, 16.64)
I will be CM calculated by to the RPS and will be directly 8j U? 04 proportional to II 03, Il the indicated C",
flow. 0,
-80 -70 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %
COLR TMI I Rev. 10 Page 34 of 40
REFERENCES:
- 1. BAW-10179P-A, Rev. 8, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," May 2010.
- 2. FRA-ANP Doc. No 86-1172640-00, "Detector Lifetime Extension Final Report for TMI- 1,' October 1989.
- 3. ANP-3246, Rev. 2, "Three Mile Island Unit 1 Cycle 20 Reload Report," February 2015.
COLR TMI I Rev. 10 Page 35 of 40 I Enclosure 1 Operating Limits Not Required by Technical Specifications
COLR TMI I Rev. 10 Page 36 of 40 Maximum Allowable Local Linear Heat Rate Limits
(
Reference:
T.S. 2.1 Bases)
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 10 and 11 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:
e AREVA Mark-B-HTP Burnup Linear Heat Rate Linear Heat Rate to (MWd/mtU) to Melt (LHRTM) 1% Transient (kW/ft) Strain (kW/ft) 0 25.16 23.99 50 25.16 1000 25.36 10000 25.24 15000 24.54 20000 24.09 23.99 25000 23.61 30000 23.13 22.80 40000 22.17 21.92 50000 20.99 20.57 60000 18.65 62000 19.57 18.40
- 2. Alternate Minimum Boron Requirements for Cold Shutdown
(
References:
T.S. 3.3.1.l.a, T.S. 3.3. Bases, FSAR 9.2.1.2)
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. l.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 755 ft3 of 12,500 ppm boron. There is no T.S. requirement to
COLR TMI I Rev. 10 Page 37 of 40 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.
COLR TMI I Rev. 10 Page 38 of 40 I Enclosure 2 DNBR-Related Bases Descriptions
COLR TMI I Rev. 10 Page 39 of 40 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 11 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 10). 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.
COLR TMI I Rev. 10 Page 40 of 40 I
- 2. Design Nuclear Power Peaking Factors
(
Reference:
T.S. 2.1 Bases)
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), FNAH FNAH = 1.80
" Axial Flux Shape Peaking Factor, FNz FNZ = 1.65 (cosine with tails)
" Total Nuclear Power Peaking Factor, FNQ FNQ =FNAH x FNz FNQ = 2.97