ML15323A432: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(4 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[TMI-15-123, Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11]]
| number = ML15323A432
| issue date = 11/16/2015
| title = Three Mile Island, Unit 1 - Cycle 21 Core Operating Limits Report, Colr TMI 1, Revision 11
| author name = Atherholt D W
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000289
| license number = DPR-050
| contact person =
| case reference number = TMI-15-123
| document report number = COLR TMI 1, Rev. 11
| document type = Fuel Cycle Reload Report, Letter
| page count = 45
}}
 
=Text=
{{#Wiki_filter:~Exeton Generationm Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 TS 6.9.5.4 November 16, 2015 TM 1-15-123 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
 
==Subject:==
Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11 Enclosed is a copy of the Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11. The Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11, provides the cycle-specific limits established to support operations of Cycle 21 up to 680 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, please do not hesitate to contact us.David W. Atherholt Regulatory Assurance Manager, Three Mile Island Unit 1 Exelon Generation Co., LLC
 
==Attachment:==
: 1) Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11 cc: USNRC Administrator, Region I USNRC Senior Resident Inspector, TMI-1 USNRC Project Manager, TM I-i Director, Bureau of Radiation Protection
-PA Department of Environmental Resources ATTACHMENT Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 TM I-1 Cycle 21 Core Operating Limits Report Revision 11 ix.eton Ueneration..
ThU- 1 Cycle 21 Core Operating Limits Report COLR TMI 1 Rev. !11///Revie /Date DateDate-7/ .j 2 ISR Director, Si e E ciineering COLR TMI 1 Rev. 11 Page 2 of 43 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for TMI-1 Cycle 21 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 LCO 3.5.2 LCO 3.5.2 LCO 3.5.2 LCO 3.5.2 LCOG 3.5.2 LCO 3.5.2 Axial Power Imbalance Protective Limits Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Full Incore System Operability Requirements Quadrant Power Tilt Limits Power Peaking Factors -FQ(Z)Power Peaking Factors -FNAH Regulating Rod Insertion Limits 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-3420, Rev. 0, "Three Mile Island Unit 1 Cycle 21 Reload Report," August 2015.
COLR TMI 1 Rev: 11 Page 3 of 43 TABLE OF CONTENTS PAGE Abstract 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 Incore 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 Incore System -4 Pump Figure 7 Axial Power Imbalance Operating Limits 25 Full Incore System -3 Pump Figure 8 Axial Power Imbalance Operating Limits 28 Full Incore System -2 Pump Figure 9 Axial Power Imbalance Operating Limits 31 Out-of-Core Detector System Figure 10 Axial Power Imbalance Operating Limits 34 Minimum Incore System Enclosure 1 Core Operating Limit Technical Specification Bases 37 Descriptions Enclosure 2 Operating Limits Not Required by Technical 42 Specifications COLR TMI I Rev. 11 Page 4 of 43 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 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 680 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 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 minimum 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 FQ(Z) limits (i.e., ECCS power peaking limits) for core monitoring.
Table 4 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 2), rod insertion (Figures 3-5), and imbalance (Figures 6-10) 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 1 of the Core Monitoring System provides the minimum margin to FQ(Z)
COLR TMI 1 Rev. 11 Page 5 of 43 and limits on the Summary Core Related Tech Specs page.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 ECOS 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 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 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].
Enclosure 1 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 (FNAH) define the reference design peaking condition in the core. The Maximum Allowable Local Linear Heat Rate COLR TMI 1 Rev. 11 Page 6 of 43 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.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.
Enclosure 2 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.
COLR TMI I Rev. 11l Page 7 of 43 Figure 1 SL 2.1.2 Axial Power Imbalance Protective Limits ThermaJ Power Level %(-48.0, 112.0)(1201](-64.3, 89.5) .ACCEPTABLE 4 PUMP OPERATION-48.0, 89.6)100 -(36.1, 112.0)A (36.1, 89.6)=ACCEPTABLE 3 AND 4 PUMP OPERATION 80 -i-48.0, 62.3)( I (36.1,62 (6.,8.5)2.3)_ (64.3, 67.1)rs (64.3, 39.8)(-64.3, 39.8)ACCEPTABLE 2, 3AND 4 PUMP OPERATION 60-40-20 The 3- or 2-pump examp protective limit curves ar based on setpoint curve, that consider an approximate 25% and 51% flow reduction for 3 and 2-pump operation respectively.
The actual setpoint curves will be calculated by the RPS a n will be directly proportion a to the indicated flow.3- nal-80 60-50 30 10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %EXPECTED MINIMUM REACTOR COOLANT FLOW (.qpm)376.64 x 103 281 .35 x 103 185.31 x 10 3 CURVE 1 2 3 Referred to by Technical Specification 2.1.2 COLR TMI 1 Rev. 11 Page 8 of 43 Figure 2 SL 2.3.1 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level %120o-Axial Power Imbalance, %Referred to by Technical Specification 2.3.1 COLR TMI 1 Rev. 11 Page 9 of 43 Table 1 LCO 3.5.2 Full Incore System (FIS) Operability Requirements The Pull 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 JSPNDs J75%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 Pull 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 COLR TMI 1 Rev. 11 Page 10 of 43 TABLE 2 LCO 3.5.2 Quadrant Power Tilt Limits Steady State Limit~a) Steady State Limitla) Maximum Limit 15 < Power  60% Power > 60% Power > 15%Full Incore System 6.83 4.46 16.8 (FIS) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Minimum Incore System 2.78 1.90 9.5 (Is)l" __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _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 tlit 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.
COLR TMI 1 Rev. i11 Page I1 of 43 TABLE 3 LCO 3.5.2 Power Peaking Factors -FQ(Z)Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft (a))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 U0, LOOA Limits Batches 21, 22 and 23 Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12. 000 0 MWd/mtU 15.6 16.5 16.5 17.0 17.0 16.8 15.9 34,000 MWd/mtU 13.6 14.5 14.5 15.0 15.0 14.8 13.9 62,000 MWd/mtU 11.7 11.7 11.7 12.0 12.0 12.0 12.0 Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 Batch 20A 0 MWdfmtU 15.1 16.0 16.0 16.5 16.5 16.2 15.3 34,000 MWd/mtU 13.1 14.0 14.0 14.5 14.5 14.2 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 0.3 kW/ft 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. 11l Page 12 of 43 Table 3 (Continued)
Gadolinia Fuel LOCA Limits Batches 21, 22 and 23 -2 wt.% Gadolinia Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 14.8 15.6 15.6 16.1 16.1 15.9 15.1 34,000 MWdtmtU 12.8 13.6 13.6 14.1 14.1 13.9 13.1 62,000 MWd/mtU 11.3 11.3 11.3 11.6 11.6 11.6 11.6 Batches 21, 22 and 23 -3 wt.% Gadolinia Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 14.1 14.9 14.9 15.4 15.4 15.2 14.4 34,000 MWd/mtU 12.1 12.9 12.9 13.4 13.4 13.2 12.4 62,000 MWd/mtU 11.0 11.0 11.0 11.3.11.3 11.3 11.3 Batch 23 -6 wt.% Gadolinia Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 13.2 13.9 13.9 14.4 14.4 14.2 13.5 34,000 MWd/mtU 11.2 11.9 11.9 12.4 12.4 12.2 11.5 62,000 MWd/mtU 10.3 10.3 10.3 10.6 10.6 10.6 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 0.3 kW/ft 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 1 Rev. 11 Page 13 of 43 Table 3 (Continued)
Gadolinia Fuel LOCA Limits Batches 21, 22 and 23 -8 wt.% Gadolinia Core Elevation0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 13.2 13.9 13.9 14.4 14.4 14.2 13.5 34,000 MWd/mtU 11.2 11.9 11.9 12.4 12.4 12.2 11.5 62,000 MWd/mtU 10.3 10.3 10.3 10.6 10.6 10.6 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 0.3 kW/ft 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 Fo(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.
COLR TMI 1 Rev. 11 Page 14 of 43 TABLE 4 LCO 3.5.2 Power Peaking Factors -FNAH LCO DNB Maximum Allowable Radial Peaking (1VARP) Limits Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2.7T.d, 3.5.2.8 The maximum radial peak for each fuel assembly, as measured with the Core Monitoring System (OMS) 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 FNAH 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, referred to in T.S. 3.5.2 by using the following conversion:limit = (LCO DNB MARP) * [1 + 03.3* (1 -P/Pm)J 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 RO pump operation.
These limits have been increased to reflect the 3.8% peaking uncertainty treated by Statistical Core Design (SCD) methodology.
COLR TMI 1 Rev. I11 Page 15 of 43 TABLE 4 (Continued)
MARP Limits -Mark-B-HTP Assemblies Maximum Maximum Maximum Axal xL Aliowbie Axialx/ Allowable x/Lia Allowable owae Pak x/Lak eRadial Peak PeRadial Peak Pe xL 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 TMvI I Rev. 11 Page 16 of 43 Figure 3 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 4 Pump Operation) 110 100 90 CO'6-0=C.)*0 80 70 60 50 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 byI TS 3.5.2.5.b
& 3.5.2.4.e.3 COLR TMI 1 Rev. 11 Page 17 of 43 Figure 3 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90.4-_=80 70 60 50 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 1 Rev. 11 Page 18 of 43 Figure 4 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 3 Pump Operation)
L.0m Cu 4-0a 110 100 90 80 70 60 50 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 1 Rev. 11 Page 19 of 43 Figure 4 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 0-"0 0".Cu 0o 110 100 90 80 70 60 50 40 30 20 10 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 1 Rev. 11 Page 20 of 43 Figure 5 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 2 Pump Operation) 0..4-'4-0 110 100 90 80 70 60 50 40 30 20 10 0 0 25 50 75 100 125 150 175 200 225 250 275 30C 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 1 Rev. 11l Page 21 of 43 Figure 5 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 1.0 Cu o4-0o a, 110 100 90 80 70 60 50 40 30 20 10 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 TMVI I Rev. lI1 Page 22 of 43 Figure 6 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (0 EFPD to 400+/-+10 EFPD)Res Rc egion (-26.6,92 110-( 16.93,102)
Restricted
[Region (-34.71,60) 100-90-80-7O-60-050-S40-30-20 10 L~~!(27.00,92)
(27.81,80) issible Region I Penni S(42.12,60)
(42.12,0)SThis Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (-34.71,0)
.. ... ........... .. .I ....I ....I ....lllpw{ ... .I I IIW I .... TIIt lTII WlT .... I1[ IT ... ..I T I I ........... ...............: ....: ....: -: ---: ....: L i *-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 Indicated Axial PowerlImbalance, %FP 40 45 50 COLR TMI I Rev. 11 Page 23 of 43 Figure 6 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (400+/-+10 EFPD to 550 +/-10 EFPD)SRestricted Region (-24.90,92)
(-31.65,80)
/t (-31.85,60)
(-31.85,0) 110 (-16.95,102) 4--100 1 90 80 Permissible Region t70.Ci 0Y a-60 Jr (15.61,102) S(22.10,92)
(22.22,80)
Permissible Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 ted)n 50 40 30 20 (35.54,60)
(35.54,0)10-D ....I .. .. I ....T Q
* n I ....I .... @ ....@ .... @ .... I .... g .... I .... I .... .... m-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TM! I Rev. 11 Page 24 of 43 Figure 6 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (550 +10 EFPD to EOC)Restricted Region-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 25 of 43 Figure 7 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (0 EFPD to 400+/-+10 EFPD)Restricted Region (-33.97,A (-34.86,4 90 80 (-19.75,77)
~O).5) 0..*0 a, 0 05.0 al 70O 60O 50 40-30-20-10-(14.76,77)
Restricted Region (22.91,69)
(28.01,60) ermssible Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (42.27,45)
(42.27,0)(-34.86,0)
! .... .... ! .... ! .... ! .... ! .... ! .... .... ! .... .... ! .... ,=,! .... ! .... ! .... ! .... .... t.!-50 40 30 20 10 -5 0 5 10 15 Indicated Axial Power Imbalance, %FP 20 25 30 35 40 45 50 COLR TMI 1 Rev. 11 Page 26 of 43 Figure 7 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (400 +/-+10 EFPD to 550 +/-+10 EFPD)90 Restrdc Regih cted (-72,7 80 SRestricted (14.76,77)
Region 71.1 (-25.13,69)
(-31.85,60) 70-602 (22.33,69)
(22.42,60) beRegion 4 (-32.01,45)
I emss ible Region 0, 0.w C,-50 40 30 20 10 Seri~ssi (35.69,45)
(35.69,0)This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (-32.01,0).I.................................".1...............~.
I D-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11*Page 27 of 43 Figure 7 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (550 +10 EFPD to EOC)90 I Restricted I Restricted Region (-30.8 (-15.19,77) 80 (-23.88,69) 7 39,60) 6[ emssible Region]50 34,45) n 0N 40 (-31.0* (12.13,77)
Region (19.02,69)
(22.42,60)
* Permissible Region i* This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (35.69,45)
I., 30 20 10 (-31.04,0)
(35.69,0).... ....... ...... ... :.... l....,, i-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. ll Page 28 of 43 Figure 8 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (0 EFPD to 400 +/-10 EFPD)SRestricted Region 60 Restricted Region (-20.00,52)
(12.20,52)
(-26.72 (-34.17,40)
(-35.01,30)
,46)50 40 ibeg Reion ]0 0.0s_0 30 20 10 (17.99,46)
(23.98,40)
SPermsbeego This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (33.69,30)
(33.69,0)(-35.01,0), ..,..., ... ...r ....
..!... .!, , ... .!.!, t I-: ....: I-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 29 of 43 Figure 8 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (400+/-+10 EFPD to 550+/-+10 EFPD)60 Restricted Region (-25.36,46)
(-32.06,40)
/SRestricted Region (-17.45,52)
(12.20,52)
/50.(17.99,46) 40 J Permssible Region 3 20 C, 10 (22.63,40)
IThis Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (33.69,30)
(33.69,0)(-32.16,0)
.................
,............
!........
!.... :.... .:.... :....U:....
].... :.... :........I 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. I11 Page 30 of 43 Figure 8 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (550+/-+10 EFPD to EOC)60 Restricted Region (-15 Restricted Region.99,46)(-24.11,46)/
(-.l n n U, .(-31 .20,30)40[ ernssible Region]o a- 30_o* o 20 (22.63,40)
(33.69,30)
(33.69,0)10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4
(-31.20,0).r':.. .. I ................
....... ........!.... .................
,,,....................,. 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 31 of 43 Figure 9 (Page 1 of 3)LCO 3.5.2 Axial power Imbalance Operating Limits Out-of-Core Detector System (0 EFPD to 400+/-+10 EFPD)Restricted Region (-20.0 (-27.48,80)
(-28.85,60)
(-28.85,0) 35 -3i 110/[Permissible 4 Pumnp Region S(See 3 and 2 Pump Limits 70 l inTabe Beow)6050400 10 (10.8,10)
I Restricted SPermissible 4 Pump Region ]/59,o This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4I (35.91, 0)0-25 15 5 0 5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits (0 EFPD to 400 +/-10 EFPD)for 3 and 2 Pump Operation Power Neg. 1mb. Pos. Imb.(%FP) (%FP)3 Pump Operation 77 -14.17 9.38 69 -20.80 17.35 60 -28.15 22.43 45 -29.34 36.40 0 -29.34 36.40 Power Neg. Imb. Pos. 1mb.2 Pump Operation 52 -14.97 7.45 46 -21.54 13.14 40 -28.80 19.00 30 -29.82 28.53 0 -29.82 28.53 COLR TMI 1 Rev. 11 Page 32 of 43 Figure 9 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (400+/-+10 EF~PD to 550+/-+10 EFPD)110 S Restricted Region (29.62,60)
(29.62, 0)-40 30 20 10 -5 0 5 10 15 20 25 30 35 '40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance ULiits (400 +/-10 EFPD to 550 +/-10 EFPD)for 3 and 2 Pump Operation Power (%Fp).77 69 Neg. Imb.3 Pump Operation-11.74-19.50 Pos. 1mb.(%FP)9.38 16.80 Power Neg. Imb. Pos. 1mb.(%FP) (%FPt 2 Pump Operation 52 -12.54 7.45 46 -20.24 13.14 40 -26.77 17.71 30 -27.09 28.53 0 -27.09 28.53 60 -26.13 17.08 45 -26.61 30.11 0 -26.61 30.11 COLR TMI I Rev. 11 Page 33 of 43 Figure 9 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (550 +/-10 EFPD to EOC)Restricted Region (-1 7.5 (-24.55,80)
(-25.21,60)
S(-25.21,0)
~110] (-9.00,102) 5492)1 90 f, 80 Permissible 4 Pump Region (See 3 and 2 Pump 70 SLimits in Table Below) 6 0..] 50'S 40 S30 20 10..5*.. ....(6.05,102)K (12.88,92)
SPermissible 4 Pump Region Restricted Region (29.62,60)
(29.62, 0)1o-40 30 I I I 6 I I I 25-20-15 5 0 5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits (550 +/-10 EFPD to EOC)for 3 and 2 Pump Operation Power Neg. Imb. Pos. 1mb.3 Pump Operation 77 -9.82 6.86 69 -18.30 13.63 60 -25.21 17.08 45 -25.69 30.11 0 -25.69 30.11 Power Neg. 1mb. Pos. Imb.(%FP) (%FP)2 Pump Operation 52 -10.61 7.45 46 -19.04 13.14 40 -25.85 17.71 30 -26.17 28.53 0 -26.17 28.53 COLR TMI 1 Rev. 11 Page 34 of 43 Figure 10 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (0 EFPD to 400 +/-10 EFPD)110 Restricted Operation (-24.25,80)
(-25.74,60)
(-25.74,0)
(32.00,60)
(32.00,0)-40 30-25 15 5 0 5 10 15 20 25 Indicated Axiai Power Imbalance, %FP Minimum Incore System Imbalance Limits (0 EFPD to 400 +10 EFPD)for 3 and 2 Pump Operation 30 35 40 Power Neg. Imb. Pos. 1mb.3 Pump Operation 77 -12.20 7.89 69 -18.25 15.15 60 -24.95 19.80 45 -26.27 32.53 0 -26.27 32.53 Power Neg. 1mb. Pos. Imb.2 Pump Operation 52 -13.08 6.33 46 -18.85 11.50 40 -25.45 16.83 30 -26.79 25.50 0 -26.79 25.50 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 1 Rev. 11 Page 35 of 43 Figure 10 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (400 +/-10 EFPD to 550 +/-10 EFPD)Restricted Operation (-16.2, (-22.42,80)
(-23.27,60)
(-23.27,0)
(26.31,60)
(26.31,0)l , t , , : ....: ....: ....: ....,-40 30 20 10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Imbalance Limits (400 +/-10 EFPD to 550 +/-10 EFPD)for 3 and 2 Pump Operation Power Neg. 1mb. Pos. 1mb.3 Pump Operation 77 -10.00 7.89 69 -17.07 14.65 60 -23.12 14.97 45 -23.80 26.83 0 -23.80 26.83 Power Neg. Imb. Pos. 1mb.2 Pump Operation 52 -10.68 6.33 46 -17.68 11.50 40 -23.82 15.67 30 -24.32 25.50 0 -24.32 25.50 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 1 Rev. l11 Page 36 of 43 Figure 10 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (550+/-+10 EFPD to EOC)110 Restricted Operation (-15.18 (-21.59,80)
(-22.44,60)
(-22.44,0)
,92)(26,31,60)
(26.31,0)-40 30-25 15 5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Imbalance Limits (550 +/--10 EFPD to EOCI for 3 and 2 Pump Operation Power Neg. 1mb. Pos. Imb.3 Pump Operation 77 -8.26 5.62 69 -15.99 11.79 60 -22.29 14.97 45 -22.97 26.83 0 -22.97 26.83 Power Neg. 1mb. Pos. Imb.2 Pump Operation 52 -8.94 6.33 46 -16.59 11.50 40 -22.79 15.67 30 -23.49 25.50 0 -23.49 25.50 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. 11 Page 37 of 43 Enclosure 1 Core Operating Limit Technical Specification Bases Descriptions COLR TMI 1 Rev. 11 Page 38 of 43 SL 2.1.1 Bases Nuclear Power Peaking Factors 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 COLR TMI 1 Rev. I11 Page 39 of 43 SL 2.1.2 Bases Maximum Allowable Local Linear Heat Rates 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 Burnttp Linear Heat Rate Linear Heat Rate to (MWd/mtU) to Melt (LHRTM) 1% Transient__________ (kW/ft) 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 TMII 1 Rev. 11 Page 40 of 43 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 RO 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 1 Rev. 11 Page 4l of 43 LCO 3.5.2 Bases -Allowable MTC Limit vs. Power Level.4-, 0)0 0 0 U a)L..4-.Cu 1~a, E a)I-2~0'U 0)0 U 10 9 8 7 6 5 4 3 2 1 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 TMI 1 Rev. I11 Page 42 of 43 Enclosure 2 Operating Limits Not Required by Technical Specifications COLR TMI 1 Rev. 11 Page 43 of 43 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)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 ECOS LOCA criteria.
The T.S. 3.3.1.1l.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 730 ft 3 of 12,500 ppm boron with B-10 content no less than 19.5 atom percent, or the equivalent of at least 770 ft 3 of 12,500 ppm boron with B- 10 content no less than 18.5 atom percent, or the equivalent of at least 820 ft 3 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.
~Exeton Generationm Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 TS 6.9.5.4 November 16, 2015 TM 1-15-123 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
 
==Subject:==
Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11 Enclosed is a copy of the Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11. The Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11, provides the cycle-specific limits established to support operations of Cycle 21 up to 680 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, please do not hesitate to contact us.David W. Atherholt Regulatory Assurance Manager, Three Mile Island Unit 1 Exelon Generation Co., LLC
 
==Attachment:==
: 1) Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11 cc: USNRC Administrator, Region I USNRC Senior Resident Inspector, TMI-1 USNRC Project Manager, TM I-i Director, Bureau of Radiation Protection
-PA Department of Environmental Resources ATTACHMENT Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 TM I-1 Cycle 21 Core Operating Limits Report Revision 11 ix.eton Ueneration..
ThU- 1 Cycle 21 Core Operating Limits Report COLR TMI 1 Rev. !11///Revie /Date DateDate-7/ .j 2 ISR Director, Si e E ciineering COLR TMI 1 Rev. 11 Page 2 of 43 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for TMI-1 Cycle 21 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 LCO 3.5.2 LCO 3.5.2 LCO 3.5.2 LCO 3.5.2 LCOG 3.5.2 LCO 3.5.2 Axial Power Imbalance Protective Limits Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Full Incore System Operability Requirements Quadrant Power Tilt Limits Power Peaking Factors -FQ(Z)Power Peaking Factors -FNAH Regulating Rod Insertion Limits 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-3420, Rev. 0, "Three Mile Island Unit 1 Cycle 21 Reload Report," August 2015.
COLR TMI 1 Rev: 11 Page 3 of 43 TABLE OF CONTENTS PAGE Abstract 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 Incore 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 Incore System -4 Pump Figure 7 Axial Power Imbalance Operating Limits 25 Full Incore System -3 Pump Figure 8 Axial Power Imbalance Operating Limits 28 Full Incore System -2 Pump Figure 9 Axial Power Imbalance Operating Limits 31 Out-of-Core Detector System Figure 10 Axial Power Imbalance Operating Limits 34 Minimum Incore System Enclosure 1 Core Operating Limit Technical Specification Bases 37 Descriptions Enclosure 2 Operating Limits Not Required by Technical 42 Specifications COLR TMI I Rev. 11 Page 4 of 43 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 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 680 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 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 minimum 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 FQ(Z) limits (i.e., ECCS power peaking limits) for core monitoring.
Table 4 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 2), rod insertion (Figures 3-5), and imbalance (Figures 6-10) 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 1 of the Core Monitoring System provides the minimum margin to FQ(Z)
COLR TMI 1 Rev. 11 Page 5 of 43 and limits on the Summary Core Related Tech Specs page.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 ECOS 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 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 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].
Enclosure 1 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 (FNAH) define the reference design peaking condition in the core. The Maximum Allowable Local Linear Heat Rate COLR TMI 1 Rev. 11 Page 6 of 43 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.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.
Enclosure 2 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.
COLR TMI I Rev. 11l Page 7 of 43 Figure 1 SL 2.1.2 Axial Power Imbalance Protective Limits ThermaJ Power Level %(-48.0, 112.0)(1201](-64.3, 89.5) .ACCEPTABLE 4 PUMP OPERATION-48.0, 89.6)100 -(36.1, 112.0)A (36.1, 89.6)=ACCEPTABLE 3 AND 4 PUMP OPERATION 80 -i-48.0, 62.3)( I (36.1,62 (6.,8.5)2.3)_ (64.3, 67.1)rs (64.3, 39.8)(-64.3, 39.8)ACCEPTABLE 2, 3AND 4 PUMP OPERATION 60-40-20 The 3- or 2-pump examp protective limit curves ar based on setpoint curve, that consider an approximate 25% and 51% flow reduction for 3 and 2-pump operation respectively.
The actual setpoint curves will be calculated by the RPS a n will be directly proportion a to the indicated flow.3- nal-80 60-50 30 10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %EXPECTED MINIMUM REACTOR COOLANT FLOW (.qpm)376.64 x 103 281 .35 x 103 185.31 x 10 3 CURVE 1 2 3 Referred to by Technical Specification 2.1.2 COLR TMI 1 Rev. 11 Page 8 of 43 Figure 2 SL 2.3.1 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level %120o-Axial Power Imbalance, %Referred to by Technical Specification 2.3.1 COLR TMI 1 Rev. 11 Page 9 of 43 Table 1 LCO 3.5.2 Full Incore System (FIS) Operability Requirements The Pull 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 JSPNDs J75%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 Pull 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 COLR TMI 1 Rev. 11 Page 10 of 43 TABLE 2 LCO 3.5.2 Quadrant Power Tilt Limits Steady State Limit~a) Steady State Limitla) Maximum Limit 15 < Power  60% Power > 60% Power > 15%Full Incore System 6.83 4.46 16.8 (FIS) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Minimum Incore System 2.78 1.90 9.5 (Is)l" __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _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 tlit 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.
COLR TMI 1 Rev. i11 Page I1 of 43 TABLE 3 LCO 3.5.2 Power Peaking Factors -FQ(Z)Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft (a))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 U0, LOOA Limits Batches 21, 22 and 23 Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12. 000 0 MWd/mtU 15.6 16.5 16.5 17.0 17.0 16.8 15.9 34,000 MWd/mtU 13.6 14.5 14.5 15.0 15.0 14.8 13.9 62,000 MWd/mtU 11.7 11.7 11.7 12.0 12.0 12.0 12.0 Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 Batch 20A 0 MWdfmtU 15.1 16.0 16.0 16.5 16.5 16.2 15.3 34,000 MWd/mtU 13.1 14.0 14.0 14.5 14.5 14.2 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 0.3 kW/ft 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. 11l Page 12 of 43 Table 3 (Continued)
Gadolinia Fuel LOCA Limits Batches 21, 22 and 23 -2 wt.% Gadolinia Core Elevation 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 14.8 15.6 15.6 16.1 16.1 15.9 15.1 34,000 MWdtmtU 12.8 13.6 13.6 14.1 14.1 13.9 13.1 62,000 MWd/mtU 11.3 11.3 11.3 11.6 11.6 11.6 11.6 Batches 21, 22 and 23 -3 wt.% Gadolinia Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 14.1 14.9 14.9 15.4 15.4 15.2 14.4 34,000 MWd/mtU 12.1 12.9 12.9 13.4 13.4 13.2 12.4 62,000 MWd/mtU 11.0 11.0 11.0 11.3.11.3 11.3 11.3 Batch 23 -6 wt.% Gadolinia Core Elevation (feet)0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 13.2 13.9 13.9 14.4 14.4 14.2 13.5 34,000 MWd/mtU 11.2 11.9 11.9 12.4 12.4 12.2 11.5 62,000 MWd/mtU 10.3 10.3 10.3 10.6 10.6 10.6 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 0.3 kW/ft 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 1 Rev. 11 Page 13 of 43 Table 3 (Continued)
Gadolinia Fuel LOCA Limits Batches 21, 22 and 23 -8 wt.% Gadolinia Core Elevation0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 13.2 13.9 13.9 14.4 14.4 14.2 13.5 34,000 MWd/mtU 11.2 11.9 11.9 12.4 12.4 12.2 11.5 62,000 MWd/mtU 10.3 10.3 10.3 10.6 10.6 10.6 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 0.3 kW/ft 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 Fo(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.
COLR TMI 1 Rev. 11 Page 14 of 43 TABLE 4 LCO 3.5.2 Power Peaking Factors -FNAH LCO DNB Maximum Allowable Radial Peaking (1VARP) Limits Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2.7T.d, 3.5.2.8 The maximum radial peak for each fuel assembly, as measured with the Core Monitoring System (OMS) 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 FNAH 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, referred to in T.S. 3.5.2 by using the following conversion:limit = (LCO DNB MARP) * [1 + 03.3* (1 -P/Pm)J 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 RO pump operation.
These limits have been increased to reflect the 3.8% peaking uncertainty treated by Statistical Core Design (SCD) methodology.
COLR TMI 1 Rev. I11 Page 15 of 43 TABLE 4 (Continued)
MARP Limits -Mark-B-HTP Assemblies Maximum Maximum Maximum Axal xL Aliowbie Axialx/ Allowable x/Lia Allowable owae Pak x/Lak eRadial Peak PeRadial Peak Pe xL 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 TMvI I Rev. 11 Page 16 of 43 Figure 3 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 4 Pump Operation) 110 100 90 CO'6-0=C.)*0 80 70 60 50 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 byI TS 3.5.2.5.b
& 3.5.2.4.e.3 COLR TMI 1 Rev. 11 Page 17 of 43 Figure 3 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90.4-_=80 70 60 50 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 1 Rev. 11 Page 18 of 43 Figure 4 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 3 Pump Operation)
L.0m Cu 4-0a 110 100 90 80 70 60 50 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 1 Rev. 11 Page 19 of 43 Figure 4 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 0-"0 0".Cu 0o 110 100 90 80 70 60 50 40 30 20 10 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 1 Rev. 11 Page 20 of 43 Figure 5 (Page 1 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400+/-+10 EFPD; 2 Pump Operation) 0..4-'4-0 110 100 90 80 70 60 50 40 30 20 10 0 0 25 50 75 100 125 150 175 200 225 250 275 30C 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 1 Rev. 11l Page 21 of 43 Figure 5 (Page 2 of 2)LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 1.0 Cu o4-0o a, 110 100 90 80 70 60 50 40 30 20 10 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 TMVI I Rev. lI1 Page 22 of 43 Figure 6 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (0 EFPD to 400+/-+10 EFPD)Res Rc egion (-26.6,92 110-( 16.93,102)
Restricted
[Region (-34.71,60) 100-90-80-7O-60-050-S40-30-20 10 L~~!(27.00,92)
(27.81,80) issible Region I Penni S(42.12,60)
(42.12,0)SThis Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (-34.71,0)
.. ... ........... .. .I ....I ....I ....lllpw{ ... .I I IIW I .... TIIt lTII WlT .... I1[ IT ... ..I T I I ........... ...............: ....: ....: -: ---: ....: L i *-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 Indicated Axial PowerlImbalance, %FP 40 45 50 COLR TMI I Rev. 11 Page 23 of 43 Figure 6 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (400+/-+10 EFPD to 550 +/-10 EFPD)SRestricted Region (-24.90,92)
(-31.65,80)
/t (-31.85,60)
(-31.85,0) 110 (-16.95,102) 4--100 1 90 80 Permissible Region t70.Ci 0Y a-60 Jr (15.61,102) S(22.10,92)
(22.22,80)
Permissible Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 ted)n 50 40 30 20 (35.54,60)
(35.54,0)10-D ....I .. .. I ....T Q
* n I ....I .... @ ....@ .... @ .... I .... g .... I .... I .... .... m-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TM! I Rev. 11 Page 24 of 43 Figure 6 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (550 +10 EFPD to EOC)Restricted Region-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 25 of 43 Figure 7 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (0 EFPD to 400+/-+10 EFPD)Restricted Region (-33.97,A (-34.86,4 90 80 (-19.75,77)
~O).5) 0..*0 a, 0 05.0 al 70O 60O 50 40-30-20-10-(14.76,77)
Restricted Region (22.91,69)
(28.01,60) ermssible Region This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (42.27,45)
(42.27,0)(-34.86,0)
! .... .... ! .... ! .... ! .... ! .... ! .... .... ! .... .... ! .... ,=,! .... ! .... ! .... ! .... .... t.!-50 40 30 20 10 -5 0 5 10 15 Indicated Axial Power Imbalance, %FP 20 25 30 35 40 45 50 COLR TMI 1 Rev. 11 Page 26 of 43 Figure 7 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (400 +/-+10 EFPD to 550 +/-+10 EFPD)90 Restrdc Regih cted (-72,7 80 SRestricted (14.76,77)
Region 71.1 (-25.13,69)
(-31.85,60) 70-602 (22.33,69)
(22.42,60) beRegion 4 (-32.01,45)
I emss ible Region 0, 0.w C,-50 40 30 20 10 Seri~ssi (35.69,45)
(35.69,0)This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (-32.01,0).I.................................".1...............~.
I D-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11*Page 27 of 43 Figure 7 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (550 +10 EFPD to EOC)90 I Restricted I Restricted Region (-30.8 (-15.19,77) 80 (-23.88,69) 7 39,60) 6[ emssible Region]50 34,45) n 0N 40 (-31.0* (12.13,77)
Region (19.02,69)
(22.42,60)
* Permissible Region i* This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (35.69,45)
I., 30 20 10 (-31.04,0)
(35.69,0).... ....... ...... ... :.... l....,, i-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. ll Page 28 of 43 Figure 8 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (0 EFPD to 400 +/-10 EFPD)SRestricted Region 60 Restricted Region (-20.00,52)
(12.20,52)
(-26.72 (-34.17,40)
(-35.01,30)
,46)50 40 ibeg Reion ]0 0.0s_0 30 20 10 (17.99,46)
(23.98,40)
SPermsbeego This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (33.69,30)
(33.69,0)(-35.01,0), ..,..., ... ...r ....
..!... .!, , ... .!.!, t I-: ....: I-50 40 30 20 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 29 of 43 Figure 8 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (400+/-+10 EFPD to 550+/-+10 EFPD)60 Restricted Region (-25.36,46)
(-32.06,40)
/SRestricted Region (-17.45,52)
(12.20,52)
/50.(17.99,46) 40 J Permssible Region 3 20 C, 10 (22.63,40)
IThis Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (33.69,30)
(33.69,0)(-32.16,0)
.................
,............
!........
!.... :.... .:.... :....U:....
].... :.... :........I 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. I11 Page 30 of 43 Figure 8 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (550+/-+10 EFPD to EOC)60 Restricted Region (-15 Restricted Region.99,46)(-24.11,46)/
(-.l n n U, .(-31 .20,30)40[ ernssible Region]o a- 30_o* o 20 (22.63,40)
(33.69,30)
(33.69,0)10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4
(-31.20,0).r':.. .. I ................
....... ........!.... .................
,,,....................,. 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP COLR TMI 1 Rev. 11 Page 31 of 43 Figure 9 (Page 1 of 3)LCO 3.5.2 Axial power Imbalance Operating Limits Out-of-Core Detector System (0 EFPD to 400+/-+10 EFPD)Restricted Region (-20.0 (-27.48,80)
(-28.85,60)
(-28.85,0) 35 -3i 110/[Permissible 4 Pumnp Region S(See 3 and 2 Pump Limits 70 l inTabe Beow)6050400 10 (10.8,10)
I Restricted SPermissible 4 Pump Region ]/59,o This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4I (35.91, 0)0-25 15 5 0 5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits (0 EFPD to 400 +/-10 EFPD)for 3 and 2 Pump Operation Power Neg. 1mb. Pos. Imb.(%FP) (%FP)3 Pump Operation 77 -14.17 9.38 69 -20.80 17.35 60 -28.15 22.43 45 -29.34 36.40 0 -29.34 36.40 Power Neg. Imb. Pos. 1mb.2 Pump Operation 52 -14.97 7.45 46 -21.54 13.14 40 -28.80 19.00 30 -29.82 28.53 0 -29.82 28.53 COLR TMI 1 Rev. 11 Page 32 of 43 Figure 9 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (400+/-+10 EF~PD to 550+/-+10 EFPD)110 S Restricted Region (29.62,60)
(29.62, 0)-40 30 20 10 -5 0 5 10 15 20 25 30 35 '40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance ULiits (400 +/-10 EFPD to 550 +/-10 EFPD)for 3 and 2 Pump Operation Power (%Fp).77 69 Neg. Imb.3 Pump Operation-11.74-19.50 Pos. 1mb.(%FP)9.38 16.80 Power Neg. Imb. Pos. 1mb.(%FP) (%FPt 2 Pump Operation 52 -12.54 7.45 46 -20.24 13.14 40 -26.77 17.71 30 -27.09 28.53 0 -27.09 28.53 60 -26.13 17.08 45 -26.61 30.11 0 -26.61 30.11 COLR TMI I Rev. 11 Page 33 of 43 Figure 9 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (550 +/-10 EFPD to EOC)Restricted Region (-1 7.5 (-24.55,80)
(-25.21,60)
S(-25.21,0)
~110] (-9.00,102) 5492)1 90 f, 80 Permissible 4 Pump Region (See 3 and 2 Pump 70 SLimits in Table Below) 6 0..] 50'S 40 S30 20 10..5*.. ....(6.05,102)K (12.88,92)
SPermissible 4 Pump Region Restricted Region (29.62,60)
(29.62, 0)1o-40 30 I I I 6 I I I 25-20-15 5 0 5 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits (550 +/-10 EFPD to EOC)for 3 and 2 Pump Operation Power Neg. Imb. Pos. 1mb.3 Pump Operation 77 -9.82 6.86 69 -18.30 13.63 60 -25.21 17.08 45 -25.69 30.11 0 -25.69 30.11 Power Neg. 1mb. Pos. Imb.(%FP) (%FP)2 Pump Operation 52 -10.61 7.45 46 -19.04 13.14 40 -25.85 17.71 30 -26.17 28.53 0 -26.17 28.53 COLR TMI 1 Rev. 11 Page 34 of 43 Figure 10 (Page 1 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (0 EFPD to 400 +/-10 EFPD)110 Restricted Operation (-24.25,80)
(-25.74,60)
(-25.74,0)
(32.00,60)
(32.00,0)-40 30-25 15 5 0 5 10 15 20 25 Indicated Axiai Power Imbalance, %FP Minimum Incore System Imbalance Limits (0 EFPD to 400 +10 EFPD)for 3 and 2 Pump Operation 30 35 40 Power Neg. Imb. Pos. 1mb.3 Pump Operation 77 -12.20 7.89 69 -18.25 15.15 60 -24.95 19.80 45 -26.27 32.53 0 -26.27 32.53 Power Neg. 1mb. Pos. Imb.2 Pump Operation 52 -13.08 6.33 46 -18.85 11.50 40 -25.45 16.83 30 -26.79 25.50 0 -26.79 25.50 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 1 Rev. 11 Page 35 of 43 Figure 10 (Page 2 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (400 +/-10 EFPD to 550 +/-10 EFPD)Restricted Operation (-16.2, (-22.42,80)
(-23.27,60)
(-23.27,0)
(26.31,60)
(26.31,0)l , t , , : ....: ....: ....: ....,-40 30 20 10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Imbalance Limits (400 +/-10 EFPD to 550 +/-10 EFPD)for 3 and 2 Pump Operation Power Neg. 1mb. Pos. 1mb.3 Pump Operation 77 -10.00 7.89 69 -17.07 14.65 60 -23.12 14.97 45 -23.80 26.83 0 -23.80 26.83 Power Neg. Imb. Pos. 1mb.2 Pump Operation 52 -10.68 6.33 46 -17.68 11.50 40 -23.82 15.67 30 -24.32 25.50 0 -24.32 25.50 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 1 Rev. l11 Page 36 of 43 Figure 10 (Page 3 of 3)LCO 3.5.2 Axial Power Imbalance Operating Limits Minimum Incore System (550+/-+10 EFPD to EOC)110 Restricted Operation (-15.18 (-21.59,80)
(-22.44,60)
(-22.44,0)
,92)(26,31,60)
(26.31,0)-40 30-25 15 5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incore System Imbalance Limits (550 +/--10 EFPD to EOCI for 3 and 2 Pump Operation Power Neg. 1mb. Pos. Imb.3 Pump Operation 77 -8.26 5.62 69 -15.99 11.79 60 -22.29 14.97 45 -22.97 26.83 0 -22.97 26.83 Power Neg. 1mb. Pos. Imb.2 Pump Operation 52 -8.94 6.33 46 -16.59 11.50 40 -22.79 15.67 30 -23.49 25.50 0 -23.49 25.50 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. 11 Page 37 of 43 Enclosure 1 Core Operating Limit Technical Specification Bases Descriptions COLR TMI 1 Rev. 11 Page 38 of 43 SL 2.1.1 Bases Nuclear Power Peaking Factors 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 COLR TMI 1 Rev. I11 Page 39 of 43 SL 2.1.2 Bases Maximum Allowable Local Linear Heat Rates 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 Burnttp Linear Heat Rate Linear Heat Rate to (MWd/mtU) to Melt (LHRTM) 1% Transient__________ (kW/ft) 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 TMII 1 Rev. 11 Page 40 of 43 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 RO 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 1 Rev. 11 Page 4l of 43 LCO 3.5.2 Bases -Allowable MTC Limit vs. Power Level.4-, 0)0 0 0 U a)L..4-.Cu 1~a, E a)I-2~0'U 0)0 U 10 9 8 7 6 5 4 3 2 1 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 TMI 1 Rev. I11 Page 42 of 43 Enclosure 2 Operating Limits Not Required by Technical Specifications COLR TMI 1 Rev. 11 Page 43 of 43 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)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 ECOS LOCA criteria.
The T.S. 3.3.1.1l.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 730 ft 3 of 12,500 ppm boron with B-10 content no less than 19.5 atom percent, or the equivalent of at least 770 ft 3 of 12,500 ppm boron with B- 10 content no less than 18.5 atom percent, or the equivalent of at least 820 ft 3 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.}}

Latest revision as of 19:56, 20 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML15323A432&oldid=1488945"