TMI-10-003, Submittal of Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7

Submittal of Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7

ML100131304
Person / Time
Site:	Crane
Issue date:	01/11/2010
From:	Atherholt D Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-10-003
Download: ML100131304 (42)

Text

{{#Wiki_filter:Exelkn Three Mile Island Unit 1 Telephone 717-948-8ooo Nuclear Route 441 South, PO. Box 480 Middletown, PA 17057 TS 6.9.5.4 TMI-10-003 January 11, 2010 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7 Enclosed is a copy of the Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7. The Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7, provides the cycle-specific limits established to support operation of Cycle 18 up to 671 Effective Full Power Days. The cycle-specific core operating limits contained in this report have been determined in accordance with Technical Specification 6.9.5. This COLR is being submitted to the NRC in accordance with the TMI Unit 1 Technical Specifications Section 6.9.5.4. If you have any questions, please do not hesitate to contact us. Respectfully, h/David W. Atherholt Regulatory Assurance Manager Exelon Generation Company, LLC Attachment cc: S. J. Collins, Administrator, Region I, USNRC D. M. Kern, USNRC Senior Resident Inspector, TMI Unit 1 P. J. Bamford, USNRC Project Manager, TMI Unit 1 +c-c1

Exelon." Nuclear TMI-I Cycle 18 Core Operating Limits Report COLR TMI I Rev. 7 / R. Jaffa t( Preparer /- M. Mahgerefteh ¢ R v'iewFýer / SQR "" fl*l¢/ T. Stevens N* Approver "ate Date Date Date Date W. C a rst e Direc* *. e "gnei -4

COLR TMI 1 Rev. 7 Page 2 of 41 TABLE OF CONTENTS PAGE Abstract 3 Full Incore System (FIS) Operability Requirements 6 APSR Rod Insertion Limits 7 Table 1 Error Adjusted Quadrant Tilt Limits 8 Table 2 Core Monitoring System Bounding Values for 9 LOCA Limited Maximum Allowable Linear Heat Rate Table 3 LCO DNB Maximum Allowable Radial Peaking Limits 15 Figure 1 Error Adjusted Rod Insertion Limits 18 4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 20 3 Pump Operation Figure 3 Error Adjusted Rod Insertion Limits 22 2 Pump Operation Figure 4 Full Incore System Error Adjusted 24 4 Pump Imbalance Limits Figure 5 Full Incore System Error Adjusted 25 3 Pump Imbalance Limits Figure 6 Full Incore System Error Adjusted 26 2 Pump Imbalance Limits -Figure 7 Out-of-Core Detector System Error Adjusted 27 Imbalance Limits Figure 8 Minimum Incore System Error Adjusted 28 Imbalance Limits Figure 9 LOCA Limited Maximum Allowable Linear Heat Rate 29 Figure 10 Axial Power Imbalance Protective Limits 34 Figure 11 Rector Protection System Maximum Allowable Setpoints 35 for Axial Power Imbalance References 36 Operating Limits Not Required by Technical 37 Specifications DNBR-related Bases Descriptions 39

COLR TMI I Rev. 7 Page 3 of 41 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 671 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 [OCDJ 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. Axial Power Shaping Rod (APSR) position limits and restrictions describe how the APSRs must be operated during the cycle. 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 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

COLR TMI I Rev. 7 Page 4 of 41 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) o 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 Mark-B 12 and Mark-B-HTP fuel types. 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 5 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 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.

COLR TMI 1 Rev. 7 Page 5 of 41 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 1 Rev. 7 Page 6 of 41 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.: Referred to by: B&W 86-1172640-00 Tech. Spec. 3.5.2.4.a and 3.5.2.7.a

COLR TMI 1 Rev. 7 Page 7 of 41 APSR Position Limits The Axial Power Shaping Rods (APSRs) shall be fully withdrawn from the core prior to Zero Power Physics Testing. The APSRs shall not be used during the Power Imbalance Detector Correlation (PIDC) test. Once the APSRs are fully withdrawn, they shall not be inserted for the remainder of the fuel cycle during normal operation and 0-98% WD shall be considered a "Restricted Region" as defined in the abstract section of this COLR. Note: Periodic movement of the APSRs to verify their operability required by Technical Specification 4.7.1 is allowed provided that the APSRs are returned to the fully withdrawn position each time the verification is completed. Note: The APSRs may be inserted during preparation for final cycle shutdown into the refueling outage after reactor power is below 20%FP.

COLR TMI I Rev. 7 Page 8 of 41 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 4.34 16.8 FFIS) Minimum Incore System 2.78 1.90 9.5 (MIS) 11 1 1 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 1203-7, Hand Calculations for Quadrant Power Tilt and Core Power Imbalance. Referred to by: Tech. Spec. 3.5.2.4

COLR TMI 1 Rev. 7 Page 9 of 41 TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft (a)) UID LOCA Liot Batch 18 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.9 16.8 16.8 17.0 17.0 16.8 15.9 40,000 MWd/mtU 15.9 16.8 16.8 17.0 17.0 16.8 15.9 62,000 MWd/mtU 12.4 12.4 12.4 12.4 12.4 12.4 12.4 Batch 19 0 MWd/mtU 15.9 16.8 16.8 17.0 17.0 16.8 15.9 40,000 MWd/mtU 15.9 16.8 16.8 17.0 17.0 16.8 15.9 62,000 MWd/mtU 12.5 12.5 12.5 12.5 12.5 12.5 12.5 Batch 20A 0 MWd/mtU 15.4 16.3 16.3 16.5 16.5 16.2 15.3 40,000 MWd/mtU 15.4 16.3 16.3 16.5 16.5 16.2 15.3 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Note: LHR limits provided are based on nuclear source power.

COLR TMI 1 Rev. 7 Page 10 of 41 Table 2 (Continued) IMo LOCA Limitq Ifrnntinuadl Batch 20B Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.8 16.7 16.7 16.9 16.9 16.4 15.5 40,000 MWd/mtU 15.8 16.7 16.7 16.9 16.9 16.4 15.5 62,000 MWd/mtU 12.5 12.5 12.5 12.5 12.5 12.5 12.5 Batch 20 (except Batch 20A and 2 0B)(b) Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.7 16.6 16.6 17.0 17.0 16.8 15.9 40,000 MWd/mtU 15.7 16.6 16.6 17.0 17.0 16.8 15.9 62,000 MWd/mtU 12.3 12.3 12.3 12.5 12.5 12.5 12.5 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. (b) The kW/ft limits were reduced by 0.2 kW/ft from 0 to 4.264 feet based on compliance with SER to BAW-101 92-A. Note: LHR limits provided are based on nuclear source power.

COLR TMI I Rev. 7 Page 11 of 41 Table 2 (Continued) Gadnlinie Fuel LOCA Limits Batch 18 2 w/o Gd Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.1 15.9 15.9 16.1 16.1 15.9 15.1 40,000 MWd/mtU 15.1 15.9 15.9 16.1 16.1 15.9 15.1 62,000 MWd/mtU 12.0 12.0 12.0 12.0 12.0 12.0 12.0 Batch 18 3 w/o Gd 0 MWd/mtU 14.4 15.2 15.2 15.4 15.4 15.2 14.4 40,000 MWd/mtU 14.4 15.2 15.2 15.4 15.4 15.2 14.4 62,000 MWd/mtU 11.7 11.7 11.7 11.7 11.7 11.7 11.7 Batch 18 8 w/o Gd 0 40,000 62,000 MWd/mtU 13.5 14.2 14.2 14.4 14.4 14.2 13.5 MWd/mtU 13.5 14.2 14.2 14.4 14.4 14.2 13.5 MWd/mtU 11.0 11.0 11.0 11.0 11.0 11.0 11.0 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Note: LHR limits provided are based on nuclear source power.

COLR TMI 1 Rev. 7 Page 12 of 41 Table 2 (Continued) Gadnlinie Fuel LOCA Limits Batch 19 2 w/o Gd Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 15.1 15.9 15.9 16.1 16.1 15.9 15.1 40,000 MWd/mtU 15.1 15.9 15.9 16.1 16.1 15.9 15.1 62,000 MWd/mtU 12.1 12.1 12.1 12.1 12.1 12.1 12.1 Batch 19 3 w/o Gd 0 40,000 MWd/mtU MWd/mtU 14.4 14.4 15.2 1i5.2 15.2 15.2 15.4 15.4 15.4 15.4 15.2 15.2 14.4 14.4 62,000 MWd/mtU 11.8 11.8 11.8 11.8 11.8 11.8 11.8 Batch 19 8 w/o Gd 0 MWd/mtU 13.5 14.2 14.2 14.4 14.4 14.2 13.5 40,000 MWd/mtU 13.5 14.2 14.2 14.4 14.4 14.2 13.5 62,000 MWd/mtU 11.1 11.1 11.1 11.1 11.1 11.1 11.1 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. Note: LHR limits provided are based on nuclear source power.

COLR TMI 1 Rev. 7 Page 13 of 41 Table 2 (Continued) Gadnlinin FuPI LOCA Limits Batch 20 2 w/o Gd(b) Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 Core Elevation (feet) 0.000 2.506 4.264 6.021 7.779 9.536 12.000 0 MWd/mtU 14.9 15.7 15.7 16.1 16.1 15.9 15.1 40,000 MWd/mtU 14.9 15.7 15.7 16.1 16.1 15.9 15.1 62,000 MWd/mtU 11.9 11.9 11.9 12.1 12.1 12.1 12.1 Batch 20 3 w/o Gd(b) 0 MWd/mtU 14.2 15.0 15.0 15.4 15.4 15.2 14.4 40,000 MWd/mtU 14.2 15.0 15.0 15.4 15.4 15.2 14.4 62,000 MWd/mtU 11.6 11.6 11.6 11.8 11.8 11.8 11.8 Batch 20 8 w/o Gd(b) 0 MWd/mtU 13.3 14.0 14.0 14.4 14.4 14.2 13.5 40,000 MWd/mtU 13.3 14.0 14.0 14.4 14.4 14.2 13.5 62,000 MWd/mtU 10.9 10.9 10.9 11.1 11.1 11.1 11.1 (a) Linear interpolation for allowable linear heat rate limits between specified bumup points and core elevation points is valid for these tables. (b) The kW/ft limits were reduced by 0.2 kW/ft from 0 to 4.264 feet based on compliance with SER to BAW-10192-A. Note: LHR limits provided are based on nuclear source power.

COLR TMI 1 Rev. 7 Page 14 of 41 Table 2 (Continued) 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. 7 Page 15 of 41 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 tables below. CMS Display 4, Thermal Limiting Condition Hot Channel Factor page, shows the minimum margin to FNAH limits for the fuel assemblies with the smallest (or negative) margin. Notes: The LCO DNB Maximum Allowable Radial Peaking (MARP) limits below are equivalent to nuclear enthalpy rise hot channel factor limits, FNAH, referred to in T.S. 3.5.2 by using the following conversion: FNAH limit = (LCO DNB MARP) * [1 + 0.3 * (1 - P/Pm)] where: P = Current fraction of power and, Pm = power adjustment factor for RC Pump combination (1.0 for 4 pump, 0.75 for 3 pump) These limits are applicable to all fuel in the core for 3 and 4 RC pump operation. These limits have been increased to reflect the 3.8% peaking uncertainty treated by Statistical Core Design (SCD) methodology.

COLR TMI I Rev. 7 Page 16 of 41 TABLE 3 (Continued) MARP Limits - Mark-B 12 Assemblies Axial Maximum Axial Maximum Allowable Peak x/L Allowable Radial XIL Radial Peak Peak 0.00 1.96226 0.00 2.17980 0.10 1.95830 0.10 2.16262 0.14 1.95672 0.14 2.13725 0.20 1.95434 0.20 2.09919 0.40 1.94642 0.40 1.97234 1.1 1.5 0.60 1.93362 0.60 1.83747 0.80 1.90788 0.80 1.71650 0.88 1.89758 0.88 1.66811 0.90 1.89501 0.90 1.65602 1.00 1.88214 1.00 1.59553 0.00 2.01923 0.00 2.06808 0.10 2.01080 0.10 2.00772 0.14 2.00743 0.14 1.98357 0.20 2.00237 0.20 1.94735 0.40 1.98551 0.40 1.82662 1.2 1.7 0.60 1.96103 0.60 1.70594 0.80 1.89377 0.80 1.60003 0.88 1.86687 0.88 1.55767 0.90 1.86014 0.90 1.54708 1.00 1.82651 1.00 1.49412 0.00 2.06787 0.00 1.90460 0.10 2.05516 0.10 1.85230 0.14 2.05008 0.14 1.83137 0.20 2.04245 0.20 1.79999 0.40 2.01703 0.40 1.69538 1.3 1.9 0.60 1.96594 0.60 1.59270 0.80 1.84088 0.80 1.49957 0.88 1.79086 0.88 1.46232 0.90 1.77835 0.90 1.45301 1.00 1.71582 1.00 1.40644 Notes: Values for heights (x/L) extrapolation. of 0.0, 0.10, 0.14, 0.88, 0.90, and 1.0 are calculated using linear The MARP for an axial peak of 1.5 and an axial height of x/L = 0.00 is restricted to a radial of 2.1. The 2.1 radial corresponds to a MARP of 2.1798 after a 3.8% peaking uncertainty treated by the SCD is applied.

COLR TMI 1 Rev. 7 Page 17 of 41 TABLE 3 (Continued) MARP Limits - Mark-B-HTP Assemblies Maximum Maximum x/a AiL AlwbeRda Peak x/L Allowable Peak x/L Allowable Radial Radial Peak Peak 0.00 1.92810 0.00 1.97903 0.10 1.92645 0.10 1.90417 0.14 1.92627 0.14 1.88470 0.20 1.92549 0.20 1.90340 0.40 1.92402 0.40 1.96949 0.60 1.92297 0.60 1.82753 0.80 1.92242 0.80 1.67863 0.88 1.90002 0.88 1.63285 0.90 1.87983 0.90 1.63588 1.00 1.79999 1.00 1.57121 0.00 2.00856 0.00 1.77373 0.10 2.00502 0.10 1.68669 0.14 2.00464 0.14 1.66357 0.20 2.00349 0.20 1.67955 0.40 2.00080 0.40 1.76225 0.60 1.99931 0.60 1.69477 0.80 1.87838 0.80 1.56172 0.88 1.83049 0.88 1.52182 0.90 1.81850 0.90 1.53086 1.00 1.73949 1.00 1.46872 0.00 2.09361 0.00 1.60832 0.10 2.08786 0.10 1.51495 0.14 2.08745 0.14 1.48917 0.20 2.08581 0.20 1.50272 0.40 2.08276 0.40 1.58120 0.60 1.97214 0.60 1.57910 0.80 1.80957 0.80 1.46203 0.88 1.75989 0.88 1.42598 0.90 1.75469 0.90 1.43644 1.00 1.68247 1.00 1.38119

COLR TMI I Rev. 7 Page 18 of 41 Figure 1 (Page 1 of 2) Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 4 Pump Operation) 110 100 90 C) 0 0. '0 '0 r-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% betw een sequential groups 5 and 6, and 6 and 7 shall be maintained. This figure is referred to by TS 3.5.25.b & 3.5.2.4.e.3

COLR TMI I Rev. 7 Page 19 of 41 Figure 1 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90 0 0L 0 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 by TS 3.5.2.5.b & 3.5.2.4.e.3

COLR TMI 1 Rev. 7 Page 20 of 41 Figure 2 (Page I of 2) Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 3 Pump Operation) CL 0 0- "a(D 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% betw een sequential groups 5 and 6, and 6 and 7 shall be maintained. This figure is referred to by[ STS 3.5.2.5.b & 3.5.2.4.e.3 II

COLR TMI 1 Rev. 7 Page 21 of 41 Figure 2 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +10 EFPD to EOC; 3 Pump Operation) 110 100 90 C) 0 0~ C) 4-Cu '4-0 a C) .0~ Cu I.) C 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% betw een 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. 7 Page 22 of 41 I Figure 3 (Page 1 of 2) Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation) CL .0. cc 0 V S 110 100 90 80 70 60 50 40 30 20 10 0 0 25 50 75 100 125 150 175 200 225 250 275 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 I 300

COLR TMI 1 Rev. 7 Page 23 of 41 Figure 3 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 110 100 90 0 -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% betw een 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. 7 Page 24 of 41 Figure 4 Full Incore System Error Adjusted 4 Pump Imbalance Limits (0 EFPD to EOC) 110-(-21.38,102) Restricted Region 1 (-31.98,92) (-37.86,80) 100 -1 90 - (15.51,102)~Restricted Region I (37.5. IPermissible Region 80 70 T 5,80) (47.05,60) (-38.78,60) J IPrmssible RegionI 0) 0~ 0 60 50 I I 40+ I 30 20. 10-I This Figure is referred to by J 3.5.2.7 & 3.5.2.4 (47.05,0) (-38.78,0) I.... L.... I = = i J.................................... .1...... I...... .... 45 -40 I I 30

• I 2 I

I 3 4 0 25 30 35 40 45 50 20 -15 -10 -5 0 5 10 15 21 Indicated Axial Power Imbalance, %FP

COLR TMI 1 Rev. 7 Page 25 of 41 Figure 5 Full Incore System Error Adjusted 3 Pump Imbalance Limits (0 EFPD to EOC) 90 -r RestrictE RegioneeI Restricted (-18.38,77) 80 (-32.24,69) y70- ,60) 60 Permissible Region 50 (7.8,77)Region ~~1(47.22,45) (-38.09 I I (-38.95,45) 4 0 0 0~ 0 '8 40-30 20 10. (-38.95,0) This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (47.22,0) I I I 45 -40 5 -35 25 -2.0 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

COLR TMI 1 Rev. 7 Page 26 of 41 Figure 6 Full Incore System Error Adjusted 2 Pump Imbalance Limits (0 EFPD to EOC) 60 Restricted I Rest L

• Region

(-18.66,52) (-32.50,46) (-38.32,40) 40 PermissibleRegion (-39.12,30) 30 0 (8.13,52) Re (20.44,46) (26.3 SPermissible Region ricted gion + 7,40) P (33.82,30) 4-0 0 .2 _-0 20 -I 10 10. This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 I (-39.12,0) (33.82,0) I*..; -50 -45 -40 30 20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

COLR TMI 1 Rev. 7 Page 27 of 41 Figure 7 Out-of-Core Detector System Error Adjusted Imbalance Limits (0 EFPD to EOC) 110-Restricted (-15.20,102) Region 100 - (-25.54,92) 90O (-31.43,80) Pernissible 4 Pump Region 80 (See 3 and 2 Purp Linits in Table Below) 70 (-32.78,60) S60 - (9.58,102) Restricted I ~Region ] (31.13,80) SPermnissible 4 Pump Region 0 a. 0 z4 40: .S 30-(40.66, 60) (40.66, 0) 20 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 0-(-32.78,0) I m -40 -35 5 5 0 -30 -25 -20 -15 -10 -5 0 10 15 20 25 30 35 40 45 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Frror AdJusted Imbalano.r Limits (0 FFPD to FOC) for q and 2 Pump Operation Power Neg. Imb. Pos. Imb. 3 Pump Operation 77 -12.91 2.82 69 -26.33 17.58 60 -32.12 26.26 45 -33.28 41.18 0 -33.28 41.18 Power Neg. Imb. Pos. Imb. 2 Pump Operation 52 -13.73 3.60 46 -27.10 15.54 40 -32.79 21.35 30 -33.78 28.70 0 -33.78 28.70

COLR TMI 1 Rev. 7 Page 28 of 41 Figure 8 Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to EOC) 110T Restricted (-13.11,102) (8.02,102) I I Operation I (-22.55,92) 9 (-28.10,80) Perrissible 4 Pump Region (See 3 and 2 Pump Limits in Table Below) 70 0 (-29.40,60)

a.

60 I M 5trie g te.U Operation (17.14,92) (27.68,80) Permissible 4 Pump Region 0 50 40 30 20 0 (36.57,60) (36.57,0) This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (-29.40,0) I -40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Minimum Incor. System Error Adjusted Imhalance Limits (0 FFPD to FOC) for 'I and 2 Pump Operation Power Neg. Imb. Pos. Imb. Mm*- (%P 4%.IEP 3 Pump Operation 77 -10.93 1.74 69 -23.14 15.15 60 -28.65 23.34 45 -29.92 36.94 0 -29.92 36.94 Power Neg. Imb. Pos. Imb. 4%EEý ~(OFP) %P 2 Pump Operation 52 -11.60 2.57 46 -23.75 13.39 40 -29.35 19.00 30 -30.45 25.71 0 -30.45 25.71

COLR TMI 1 Rev. 7 Page 29 of 41 Figure 9 (Page 1 of 5) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B 12 Fuel Assemblies (U02 Fuel Rods) 18 17

• 16 X' 15

.*4 0 13 E E S12 11 10 0 10 20 30 40 50 60 70 Burnup, GWd/mtU I Referred to by Tech Spec 3.5.2.8 1 1-0 and 12 ft --S 2.506, 4.264 and 9.536 ft - 6.021 and 7.779 ft I

COLR TMI 1 Rev. 7 Page 30 of 41 Figure 9 (Page 2 of 5) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B-HTP Fuel Assemblies, Except Batches 20A and 20B (U02 Fuel Rods) 18.0 17.0 16.0 M 15.0 .4) 14.0 cc 13.0 E E x 12.0 11.0 10.0 0 10 20 30 40 50 60 70 I Referred to by Tech Spec 3.5.2.8 1 Burnup, GWd/mtU j-9--2.506, 4.264 and 9.536 ft -A--6.021 and7.779ft --O-Oand 12fti

COLR TMI 1 Rev. 7 Page 31 of 41 Figure 9 (Page 3 of 5) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B-HTP Fuel Assemblies, Batch 20A (U02 Fuel Rods) 18.0 17.0 LHR Limits are provided based on Nuclear Source Power (40, 16.5) 16.0 4-' M 15.0 CD a) 14.0 13.0 E E 12.0 (40,15.4) (40, 15.3) (40, 16.3) (40,16.2) 11.0 10.0 0 10 20 Referred to by Tech Spec 3.5.2.8 30 40 Burnup, GWd/mtU 50 60 70 I---0-ft -e-2.506-ft, 4.264 --- 6.021, 7.779-ft 9.536-ft a 12-ftl

COLR TMI 1 Rev. 7 Page 32 of 41 Figure 9 (Page 4 of 5) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B-HTP Fuel Assemblies, Batch 20B (U02 Fuel Rods) 18.0 LHR Limits are provided based on Nuclear Source Power 17.0 16.0 4T W 15.0 4) 4) '5 14.0 0 13.0 E E X M 12.0 11.0 10.0 0 (40, 16.9) (40, 16.7) u (40, 16.4)¥* (62, 12.5) 10 20 30 40 50 60 70 I Referred to by Tech Spec 3.5.2.81 Burnup, GWd/mtU I I i I-8--o-ft -- e-2.506-ft, 4.264 --- 6.021, 7.779-ft --- 9.536-ft 12-ft I

COLR TMI I Rev. 7 Page 33 of 41 Figure 9 (Page 5 of 5) MTC Limit vs. Power Level C9 0 0 0. 10 9 8 7 6 5 4 3 2 1 0 0 20 40 60 80 Percent Full Power 100

COLR TMI 1 Rev. 7 Page 34 of 41 Figure 10 Axial Power Imbalance Protective Limits Thermal Power Level % -80 -70 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, % CURVE 1 2 3 EXPECTED MINIMUM REACTOR COOLANT FLOW (Ib/hr) 137.77 x 106 103.22 x 106 67.90 x 106

COLR TMI 1 Rev. 7 Page 35 of 41 Figure II Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level % 120 -80 -70 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %

COLR TMI 1 Rev. 7 Page 36 of 41

REFERENCES:

1.

BAW-10179P-A, Rev. 7, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," January 2008.

2.

FRA-ANP Doc. No 86-1172640-00, "Detector Lifetime Extension Final Report for TMI-1," September 1988.

3.

ANP-2848, Rev. 1, "Three Mile Island Unit 1 Cycle 18 Reload Report," December 2009.

COLR TMI I Rev. 7 Page 37 of 41 Operating Limits Not Required by Technical Specifications

COLR TMI I Rev. 7 Page 38 of 41 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. This limit is 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 limit is fuel design-specific; the value for the most limiting fuel design in the current core is used for monitoring as given below: e AREVA Mark-B 12 / Mark-B-HTP / Mark-B-HTP-1 ý: Linear Heat Rate Burnup To Melt (LHRTM) (MWd/mtU) (kW/ft) 0 21.90 40,000 21.90 48,000 21.50 56,000 20.50 60,000 20.50 62,000 20.50

2.

Alternate Minimum Boron Requirements for Cold Shutdown (

References:

T.S. 3.3.1.l.a, T.S. 3.3. Bases, FSAR 9.2.1.2) The Borated Water Storage Tank (BWST) is required by Technical Specifications 3.3.1.1.a to be available as a source of borated water to meet ECCS LOCA criteria. The T.S. 3.3.1. l.a requirements also ensure that there is a sufficient source of borated water available to bring the reactor to cold shutdown under normal operating conditions. Although not required by T.S., other sources of borated water can be used in lieu of the BWST for the purpose of achieving cold shutdown under normal operating conditions. The alternate source of borated water shall contain the equivalent of at least 845 ft 3 of 12,500 ppm boron. 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.

COLR TMI I Rev. 7 Page 39 of 41 DNBR-Related Bases Descriptions

COLR TMI 1 Rev. 7 Page 40 of 41 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 81.97 percent and flow rate is 75.9 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 55.84 percent and flow rate is 51.7 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. 7 Page 41 of 41

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}}