TMI-13-155, Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9

Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9

ML13317A073
Person / Time
Site:	Three Mile Island
Issue date:	11/08/2013
From:	Atherholt D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-13-155
Download: ML13317A073 (36)

Text

A"n Exelon Generation,,

Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 TS 6.9.5.4 TMI-13-155 November 08, 2013 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 20 Core Operating Limits Report, COLR TMI 1, Revision 9 Enclosed is a copy of the Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9.

The Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9, provides the cycle-specific limits established to support operations of Cycle 20 up to 715 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.

Respectfully, David W. Atherholt Regulatory Assurance Manager, Three Mile Island, Unit 1 Exelon Generation Company, LLC DWA/mdf

Enclosure:

cc: USNRC Region I, Regional Administrator USNRC Project Manager, TMI, Unit 1 USNRC Senior Resident Inspector, TMI, Unit 1

~I- xeton Generation TMI-1 Cycle 20 Core Operating Limits Report COLR TMI 1 Rev. 9

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COLR TMI I Rev. 9 Page 2 of 35 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 20 3 Pump Imbalance Limits Figure 6 Full Incore System Error Adjusted 21 2 Pump Imbalance Limits Figure 7 Out-of-Core Detector System Error Adjusted 22 Imbalance Limits Figure 8 Minimum Incore System Error Adjusted 23 Imbalance Limits Figure 9 LOCA Limited Maximum Allowable Linear Heat Rates 24 Figure 10 Axial Power Imbalance Protective Limits 27 Figure 11 Rector Protection System Maximum Allowable Setpoints 28 for Axial Power Imbalance References 29 Operating Limits Not Required by Technical 30 Specifications DNBR-Related Bases Descriptions 33

COLR TMI I Rev. 9 Page 3 of 35 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. 9 Page 4 of 35 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 FNAH, 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.

COLR Figure 11 provides the Protection System Maximum Allowable Setpoints

COLR TMI I Rev. 9 Page 5 of 35 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. 9 Page 6 of 35 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. 9 Page 7 of 35 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 _

(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. 9 Page 8 of 35 TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft (a))

UO LOCA Limits Batches 20 (Except Batch 20B), 21 and 22 Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.7 15.7 11.8 2.506 16.6 16.6 11.8 4.264 16.8 16.8 12.0 6.021 17.0 17.0 12.0 7.779 17.0 17.0 12.0 9.536 16.8 16.8 12.0 12.000 15.9 15.9 12.0 Batch 20B Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.6 15.6 11.8 2.506 16.5 16.5 11.8 4.264 16.7 16.7 12.0 6.021 16.9 16.9 12.0 7.779 16.9 16.9 12.0 9.536 16.4 16.4 12.0 12.000 15.5 15.5 12.0 (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 have been reduced by 0.2 kW/ft based on compliance with SER to BAW-10192-A.

NOTE: LHR limits provided are based on nuclear power source.

COLR TMI I Rev. 9 Page 9 of 35 Table 2 (Continued)

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 14.9 14.9 11.4 2.506 15.7 15.7 11.4 4.264 15.9 15.9 11.6 6.021 16.1 16.1 11.6 7.779 16.1 16.1 11.6 9.536 15.9 15.9 11.6 12.000 15.1 15.1 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 14.2 14.2 11.1 2.506 15.0 15.0 11.1 4.264 15.2 15.2 11.3 6.021 15.4 15.4 11.3 7.779 15.4 15.4 11.3 9.536 15.2 15.2 11.3 12.000 14.4 14.4 11.3 Batch 21 - 6 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 13.3 13.3 10.4 2.506 14.0 14.0 10.4 4.264 14.2 14.2 10.6 6.021 14.4 14.4 10.6 7.779 14.4 14.4 10.6 9.536 14.2 14.2 10.6 12.000 13.5 13.5 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 have been reduced by 0.2 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 Rev. 9 Page 10 of 35 Table 2 (Continued)

Gadolinia Fuel LOCA Limits Batches 20, 21 and 22 - 8 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU' 0.000 13.3 13.3 10.4 2.506 14.0 14.0 10.4 4.264 14.2 14.2 10.6 6.021 14.4 14.4 10.6 7.779 14.4 14.4 10.6 9.536 14.2 14.2 10.6 12.000 13.5 13.5 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 have been reduced by 0.2 kW/ft based on compliance with SER to BAW-10192-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. 9 Page II of 35 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:

FN AH 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 Rev. 9 Page 12 of 35 TABLE 3 (Continued)

MARP Limits - Mark-B-HTP Assemblies Axial Maximum Axial Maximum Axialx/ Maximum Aloae Peak x/L Allowable Peak x/L Allowable Peak x/L Allowable Radial Peak 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 Rev. 9 Page 13 of 35 Figure 1 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 4 Pump Operation) 110 100 90 1~

80 a) 0 70 0.

a) 4-(U 60

.4-0 50 C) 4-(U 40 C.)

C 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. 9 Page 14 of 35 Figure 1 (Page 2 of 2)

Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90 80 0

a. 70 0 60 S.-

50 01 t-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. 31

COLR TMI I Rev. 9 Page 15 of 35 Figure 2 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 3 Pump Operation) 110 100 90 80 0.

70 0

60 50 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

COLR TMI I Rev. 9 Page 16 of 35 Figure 2 (Page 2 of 2)

Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 110 100 90 80 0 70 a.

60 0

50 V

2 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.3I

COLR TMI 1 Rev. 9 Page 17 of 35 Figure 3 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation) 110 1~

a) 0 0~

(U 0

a)

.6~

(U U

0 (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 ITS 3.5.2.5.b & 3.5.2.4.e.3

COLR TMI 1 Rev. 9 Page 18 of 35 Figure 3 (Page 2 of 2)

Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 110 100 90 80 0

a. 70 0 60

.6.

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 byl TS 3.5.2.5.b & 3.5.2.4.e.3I

COLR TMI I Rev. 9 Page 19 of 35 Figure 4 Full Incore System Error Adjusted 4 Pump Imbalance Limits (0 EFPD to EOC) 110

(-23.79.102) wI (15.23,102)

Restricted IN .4 Restricted Region 100 ~Region

(-31.59,92) 90

(-37.21,80) 80 (36.51,80) 70

(-37.40,60) I Permissible Region 0) 60 IFPermissible L

Region d

(44.41,60)

C 50 0~

a 4- 40 0

0 a)

(I 30 U

V C

20 10 This Figure is referred to by

(-37.40,0) T.S. 3.5.2.7 & 3.5.2.4.e.4 (44.41,0) 45 35 25 15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

COLR TMI I Rev. 9 Page 20 of 35 Figure 5 Full Incore System Error Adjusted 3 Pump Imbalance Limits (0 EFPD to EOC) 90 Restricted Restricted Region 80 77) Region

(-24.02,77)

(-31.81,69) 70

(-A7 41l 60 (32.02,60) 50 Permissible Regio issible Region II "Xi(44.55,45)

I Permi

(-37.54,45) 0 M

40 0

30 0

20 10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4

(-37.54,0) .(44.55,0)

.... Is

-50 -45 -40 -35 -30 -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. 9 Page 21 of 35 Figure 6 Full Incore System Error Adjusted 2 Pump Imbalance Limits (0 EFPD to EOC) 60 Restricted Restricted Region (-24.25,52) (12.25,52) Region 50

(-32.02,46) (18. 14,46)

(-37.58,40) 40 (24.33,40)

Permiss ible Region I I Prmssibl e\on

(-37.68,30) 0 30 (34.34,30) 0 CL 0

4-20 at 10 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4

(-37.68,0) (34.34,0) 2 aa.a.... 1..-..a-N.M-.Y

-50 -45 -40 30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

COLR TMI 1 Rev. 9 Page 22 of 35 Figure 7 Out-of-Core Detector System Error Adjusted Imbalance Limits (0 EFPD to EOC) t (38.06, 60)

0) 35 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 (0 EFPD to EOC) for 3 and 2 Pump Operation Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.

(%FP) (%FP) (%FP) 3 Pump Operation 2 Pump Operation 77 -18.22 9.41 52 -19.02 7.48 69 -25.84 17.39 46 -26.58 13.26 60 -31.39 26.23 40 -32.03 19.31 45 -31.87 38.55 30 -32.35 29.12 0 -31.87 38.55 0 -32.35 29.12

COLR TMI I Rev. 9 Page 23 of 35 Figure 8 Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to EOC) 110 T Restricted I (-14.95,102) (7.36,102)

Operation 100 *1 ~Restrictled

(-21.96,92) 90

(-27.2 9,80) Permissible 4 Pump Region 80 (26.53,80)

(See 3 and 2 Pump Limits in Table Below) 70 Permissible u iZ

(-27.99,60) o 60 (34.04,60) 40 30 20 -I This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I10

(-27.99,0) (34,04,0)

-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 Adiusted Imbalance Limits (0 EFPD to EOC) for 3 and 2 Pump Operation Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.

(%FP) (%FP) (%FP) (%FP) (%FP) (%FP) 3 Pump Operation 2 Pump Operation 77 -15.82 7.89 52 -16.50 6.33 69 -22.77 15.15 46 -23.37 11.58 60 -27.84 23.19 40 -28.54 17.09 45 -28.51 34.42 30 -29.04 26.00 0 -28.51 34.42 0 -29.04 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.

COLR TMI I Rev. 9 Page 24 of 35 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 18.0 LHR Limits are provided based on Nuclear Source Power (34,17.0) 17.0 (34 16.8) 16.0

~(34,.15.9)

'_ 15.0 0 14.0 cc 13.0 X 12.0 (62,12.0) 11.0 10 10 20 30 40 50 60 7 0 10 20 so 40 50 60" 70 Ir*^ Burnup, GWd/mtU IrtRefrruU LU by I eIH OFpeCU3.D.L.O

--E}--2.506, 4.264 and 9.536 ft A-6.021 and 7.779 ft -e--0 and 12 ft I

COLR TMI I Rev. 9 Page 25 of 35 Figure 9 (Page 2 of 3)

LOCA Limited Maximum Allowable Linear Heat Rates for U02 Fuel Rods Mark-B-HTP Fuel Assemblies, Batch 20B 18.0 17.0 16.0 15.0 4-2 14.0

.0 E413.0 E

,X M 12.0 110 10.0 0 10 20 30 40 50 60 70 0Dcf Arr-fn ht, Tcrh Q'Z 1 Burnup, GWd/mtU

--e- 0 ft 6 2.506 and 4.264 ft 0 6.021 and 7.779 ft 6 9.536 ft X 12 ft

-E-Ot -r256n424f O-.01ad779f 6-.3f xlf

COLR TMI I Rev. 9 Page 26 of 35 Figure 9 (Page 3 of 3)

MTC Limit vs. Power Level 10 S 9 I0 8

"a)

E CL I--

CL

• . 1 0 20 40 60 80 100 Percent Full Power

COLR TMI I Rev. 9 Page 27 of 35 Figure 10 Axial Power Imbalance Protective Limits Thermal Power Level %

120

(-47.9, 112.0) (36.0,112.0)

ACCEPTABLE 4 PUMP OPERATION 100 47.9, 89.6) n2) (36.0, 8 9.6)

(-64.2, 5) ACCEPTABLE (64.2, 89.5) 3 AND 4 PUMP OPERATION 80

(--47.9, 62.3) (36.0, 6:2.3), (64.2, 67.1)

(-64.2, 67 60 -

ACCEPTABLE 2,3AND4 PUMP OPERATION The 3- or 2-pump example 40 setpoint curves show

(-64.2, 39.8) allowable values for an (64.2, 39.8) approximate 25% and 51% flow reduction for 3-and 2-pump operation respectively. The actual 20 setpoint curve will be calculated by the RPS and will be directly proportional to the indicated flow.

-80 -70 50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %

EXPECTED MINIMUM CURVE REACTOR COOLANT FLOW (lb/hr) 1 140.87 x 106 2 105.60 x 106 3 69.74 x 106

COLR TMI 1 Rev. 9 Page 28 of 35 Figure I I Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level %

120 Axial Power Imbalance, %

COLR TMI I Rev. 9 Page 29 of 35

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-I," October 1989.

3. ANP-3246, Rev. 0, "Three Mile Island Unit 1 Cycle 20 Reload Report," August 2013.

COLR TMI I Rev. 9 Page 30 of 35 Enclosure 1 Operating Limits Not Required by Technical Specifications

COLR TMI I Rev. 9 Page 31 of 35 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:

• 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. 3.3.1.1.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 ECCS LOCA criteria. The T.S. 3.3.1.1.a requirements also ensure that there is a sufficient source of borated water available to bring the reactor to cold shutdown under normal operating conditions. Although not required by T.S., other sources of borated water can be used in lieu of the BWST for the purpose of achieving cold shutdown under normal operating conditions.

The alternate source of borated water shall contain the equivalent of at least 755 ft3 of 12,500 ppm boron. There is no T.S. requirement to maintain an alternate source tank at this level, however out-of-service

COLR TMI I Rev. 9 Page 32 of 35 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. 9 Page 33 of 35 Enclosure 2 DNBR-Related Bases Descriptions

COLR TMI I Rev. 9 Page 34 of 35 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 1 Rev. 9 Page 35 of 35

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