ML073300455

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Cycle 17 Core Operating Limits Report, COLR, Revision 5
ML073300455
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/16/2007
From: David Helker
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
5928-07-20231
Download: ML073300455 (39)
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Text

AmerGen Energy Company, LLC www.exeloncorp.com AmerGenS An Exelon Company 20o Exelon Way Kennett Square, PA 19348 November 16, 2007 5928-07-20231 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit 1 (TMI Unit 1)

Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Cycle 17 Core Operating Limits Report, COLR TMI 1, Revision 5 Pursuant to TMI Unit 1 Technical Specification (TS) Section 6.9.5.4, enclosed is a copy of the Cycle 17 Core Operating Limits Report, COLR TMI 1, Revision 5. The Cycle 17 Core Operating Limits Report, COLR TMI 1, Revision 5, provides the cycle-specific limits established to support operation of Cycle 17 up to 691 Effective Full Power Days, adds thermal limits for Mark-B-HTP fuel, provides revised reactor protection system limits and setpoints for axial power imbalance, and provides updated references. Revision 5 specifically incorporates additional updated references as a result of a minor core redesign during the Cycle 17 refueling outage.

The cycle-specific core operating limits contained in this report have been determined in accordance with Technical Specification 6.9.5.

If you have any questions or require additional information, please do not hesitate to contact us.

Respectfully, David P. Helker Manager - Licensing

Enclosure:

TMI-1 Cycle 17 Core Operating Limits Report, COLR TMI 1, Revision 5 cc: S. J. Collins, USNRC, Administrator, Region I P. J. Bamford, USNRC, Project Manager, TMI Unit 1 D. M. Kern, USNRC, Senior Resident Inspector, TMI Unit 1 File No. 95055

ENCLOSURE CYCLE 17 CORE OPERATING LIMITS REPORT COLR TMI 1, REVISION 5

AmerGen TMI-1 Cycle 17 Core Operating Limits Report COLR TMI I Rev. 5 R. Jaffa Preparer QAV /. Date Date' ev-iewer ". Date SQR / ISR (1000-ADM-1291.01) Date E. Eilola E. Eilola Date D irecd-'M5,ern

COLR TMI 1 Rev. 5 Page 2 of 37 TABLE OF CONTENTS PAGE Abstract 3 Full Incore System (FIS) Operability Requirements 6 APSR Rod Insertion Limits 7 Table 1 Quadrant Thlt 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 13 Figure 1 Error Adjusted Rod Insertion Limits 15 4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 17 3 Pump Operation Figure 3 Error Adjusted Rod Insertion Limits 19 2 Pump Operation Figure 4 Full Incore System Error Adjusted 21 4 Pump Imbalance Limits Figure 5 Full Incore System Error Adjusted 22 3 Pump Imbalance Limits Figure 6 Full Incore System Error Adjusted 23 2 Pump Imbalance Limits Figure 7 Out-of-Core Detector System Error Adjusted 24 Imbalance Limits Figure 8 Minimum Incore System Error Adjusted 25 Imbalance Limits Figure 9 LOCA Limited Maximum Allowable Linear Heat Rate 26 Figure 10 Axial Power Imbalance Protective Limits 30 Figure 11 Rector Protection System Maximum Allowable Setpoints 31 for Axial Power Imbalance References 32 Operating Limits Not Required by Technical 33 Specifications DNBR-related Bases Descriptions 35

COLR TMI I Rev. 5 Page 3 of 37 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 References 3 and 4. 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 691 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 [OCDI 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

COLR TMI I Rev. 5 Page 4 of 37 (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.dJ. (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.21.

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 Mark-B10, 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 4 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

COLR TMI 1 Rev. 5 Page 5 of 37 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 1 Rev. 5 Page 6 of 37 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 1 Rev. 5 Page 7 of 37 APSR Position Limits The Axial Power Shaping Rods (APSRs) may be positioned as necessary during the Power Imbalance Detector Correlation (PIDC) test. The APSRs shall be withdrawn from the core before exceeding 4 EFPD and prior to thermal power escalation above 80% RTP. Once the APSR pull maneuver has been completed, the APSRs 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 1 Rev. 5 Page 8 of 37 TABLE 1 Quadrant Tilt Limits Steady State Limit Steady State Limit Maximum Limit 15 < Power < 60% Power > 60% Power > 15%

Full Incore System 6.83 4.50 16.8 (FIS)

  • Minimum Incore System 2.78 1.90 9.5 (MIS) _ I 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 I Rev. 5 Page 9 of 37 TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft (a))

Li., LOCA Limitq Batch 130 & 15B2 Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.9 15.9 12.8 2.506 16.8 16.8 12.8 4.264 16.8 16.8 12.8 6.021 17.0 17.0 12.8 7.779 16.8 16.8 12.8 9.536 16.8 16.8 12.8 12.000 15.9 15.9 12.8 Batch 17 & 18 Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.9 15.9 12.4 2.506 16.8 16.8 12.4 4.264 16.8 16.8 12.4 6.021 17.0 17.0 12.4 7.779 17.0 17.0 12.4 9.536 16.8 16.8 12.4 12.000 15.9 15.9 12.4 Batch 1 9 (b)

Core Elevation 0 40,000 (feet) MWd/mtU MWd/mtU 0.000 15.7 15.7 2.506 16.6 16.6 4.264 16.6 16.6 6.021 17.0 17.0 7.779 17.0 17.0 9.536 16.8 16.8 12.000 15.9 15.9 (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. 5 Page 10 of 37 Table 2 (Continued)

(Gndnlini Ia1 LMWMCA Limitq Batch 17 & 18 3 w/o Gd Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 14.4 14.4 11.7 2.506 15.2 15.2 11.7 4.264 15.2 15.2 11.7 6.021 15.4 15.4 11.7 7.779 15.4 15.4 11.7 9.536 15.2 15.2 11.7 12.000 14.4 14.4 11.7 Batch 17 & 18 8 w/o Gd Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 13.5 13.5 11.0 2.506 14.2 14.2 11.0 4.264 14.2 14.2 11.0 6.021 14.4 14.4 11.0 7.779 14.4 14.4 11.0 9.536 14.2 14.2 11.0 12.000 13.5 13.5 11.0 Batch 18 2 w/o Gd Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.1 15.1 12.0 2.506 15.9 15.9 12.0 4.264 15.9 15.9 12.0 6.021 16.1 16.1 12.0 7.779 16.1 16.1 12.0 9.536 15.9 15.9 12.0 12.000 15.1 15.1 12.0 (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. 5 Page 1I of 37 Table 2 (Continued) atnlnainin FiaaI LOMA Limits Batch 192 w/o Gd(b)

Core Elevation 0 40,000 (feet) MWd/mtU MWd/mtU 0.000 14.9 14.9 2.506 15.7 15.7 4.264 15.7 15.7 6.021 16.1 16.1 7.779 16.1 16.1 9.536 15.9 15.9 12.000 15.1 15.1 Batch 19 3 w/o Gd(b)

Core Elevation 0 40,000 (feet) MWd/mtU MWd/mtU 0.000 14.2 14.2 2.506 15.0 15.0 4.264 15.0 15.0 6.021 15.4 15.4 7.779 15.4 15.4 9.536 15.2 15.2 12.000 14.4 14.4 Batch 19 8 w/o Gd(b)

Core Elevation 0 40,000 (feet) MWd/mtU MWd/mtU 0.000 13.3 13.3 2.506 14.0 14.0 4.264 14.0 14.0 6.021 14.4 14.4 7.779 14.4 14.4 9.536 14.2 14.2 12.000 13.5 13.5 (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-10192-A.

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

COLR TMI 1 Rev. 5 Page 12 of 37 Table 2 (Continued) rmadninina Fula LOC)A LimitS Batch 15B2 2 w/o Gd Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.1 15.1 12.1 2.506 15.9 15.9 12.1 4.264 15.9 15.9 12.1 6.021 16.1 16.1 12.1 7.779 16.4 16.4 12.1 9.536 15.9 15.9 12.1 12.000 15.1 15.1 12.1 (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.

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 (5.70 kW/ft) and the current fraction of rated power.

COLR TMI 1 Rev. 5 Page 13 of 37 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.

MARP Limits - Mark-BlO and Mark-B12 Assemblies Axial Peak Elevation action of Core Height = x/LI Axial Peak 0.2 0.4 0.6 0.8 1.1 1.9543 1.9464 1.9336 1.9078 1.2 2.0023 1.9855 1.9610 1.8937 1.3 2.0424 2.0170 1.9659 1.8408 1.5 2.0991 1.9723 1.8374 1.7165 1.7 1.9473 1.8266 1.7059 1.6000 1.9 1.7999 1.6953 1.5927 1.4995

COLR TM! 1 Rev. 5 Page 14 of 37 TABLE 3 (Continued)

MARP Limits - Mark-B-HTP Assemblies Axial Maximum Axial Maximum 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

.2 0.40 2.00080 1. 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 1 Rev. 5 Page 15 of 37 Figure 1 (Page 1 of 2)

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

a. 70 60 0A V'

50 SU 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.

SThis figure is referred to by TS 3.5.2.5.b &3.5.2.4.e.3I

COLR TMI 1 Rev. 5 Page 16 of 37 Figure 1 (Page 2 of 2)

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

70 a-w 60

'6~

0 50 40 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% betw een 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.30'

COLR TMI 1 Rev. 5 Page 17 of 37 Figure 2 (Page 1 of 2)

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

0 C. 70 60 0 50 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% betw een sequential groups 5 and 6, and 6 and 7 shall be maintained.

This figure is&referredt 3.5.2.5.b ITS ob 3.5.2.4.e.3

COLR TM! 1 Rev. 5 Page 18 of 37 Figure 2 (Page 2 of 2)

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

Ca 70

0. 60 1OR 50 S0 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.

[Thi figure is referred to by "TS3.5.2.5.b & 3.5.2.4.e.3 '

COLR TMI 1 Rev. 5 Page 19 of 37 Figure 3 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation) 110 100 90 80 70 0) 0A 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 I

COLR TMI I Rev. 5 Page 20 of 37 Figure 3 (Page 2 of 2)

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

.90 80 0

CI. 70 60 50 SU "o 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. 5 Page 21 of 37 Figure 4 Full Incore System Error Adjusted 4 Pump Imbalance Limits (0 EFPD to EOC) 110 -r

(-22.14,102,)E 16.11 2)

Restricted 100 Restricted Region Region

( 2

(-30.0/2,92 90 (21.93,92) 80- I (28.36,80)

(-35.46,80) 70 1Permisible RegionI 60- Pebleissione

(-35.65,60) (28.56,60)

I- 50 ý 40,

.E 0A 30-20-10.

This Figure is referred to by r3s565.0i I T.S. 3.5.2.7 & 3.5.2.4.e.4 I

.... . ... . . . ..... . .. . . .. .(28,56.f) 45 35 -30 20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FIP

COLR TMI 1 Rev. 5 Page 22 of 37 Figure 5 Full Incore System Error Adjusted 3 Pump Imbalance Limits (0 EFPD to EOC) 90.

Resrited]

Region Restricted I

(-22.39,77) 80.

(14.1 77) Regio

(-30.21 70. (20.84,69) 75,69)

(-35.65,60) 60- (28.38,60)

Pensible Rgion 50. - erisil gion Re~e

(-35.80,45) . 10 (28.71,45)

R Is 0I 0.

30.

0 "o

0 20-10o This Figure is referred to by T.S. 3.5.2.7 &3.5.2.4.e.4

.(-35.80,0) I

...................................... 4...................................El-a. .... I 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. 5 Page 23 of 37 Figure 6 Full Incore System Error Adjusted 2 Pump Imbalance Limits (0 EFPD to EOC) 60 T Resticte (-22.63,52)

I-(12.02,52)

Restricted Region 50-(-30.48,46) (17.06,46)

(-34.88,40) 40.- (22.09,40)

Permissible Region Arrtissible gion

(-35.95.30) w J IL 30-I R

\ (28.86,30) 0 20-0A S) 10i This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4

(-35.95,0) i a . . . .. . . . . . . . . . . i . . . . a- . N.... N.- N.... N., ý ....... (28.86,0) .....

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

COLR TMI 1 Rev. 5 Page 24 of 37 Figure 7 Out-of-Core Detector System Error Adjusted Imbalance Limits (0 EFPD to EOC) 110.

(-15.86,102) (10.08,102) Restrcted Restricted ILReion

(-23.61,92) (15.87,92)

(-29.08,80) Perrrissible 4 Rirrp Region 80 (22.30,80)

(See 3 and 2 Rurrm Linits inTable Below) 70

(-29.74,60) 60 (22.94, 60) 0 50 40 30 20 This [ gure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 J 10 (22.94, 0)

  • I I I I . . . . d. . . . . . . . . . . . . .

-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, %FP Olut-nf-C'nra Detartor ~ygtam Error AdJustAdl ImbalannA Limit.- (0) F-FPQ to FOO for q and 2' Pump O~pAratonn Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.

4%&Z ~4%EE a 3 Pump Operation 2 Pump Operation 77 -16.68 8.76 52 -17.49 7.28 69 -24.37 15.36 46 -25.12 12.23 60 -29.74 22.78 40 -29.46 17.19 45 -30.23 23.42 30 -30.71 23.88 0 -30.23 23.42 0 -30.71 23.88

COLR TMI 1 Rev. 5 Page 25 of 37 Figure 8 Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to EOC) 110 35 25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Power Imbalance, */.JP

..... ... LA-- r,,- .j!

iviirirriiin inc1QrA ~A r-rror aj1Ii~q= imnmianca L imits k E-EE-I- In ~LUC) for 'Aand 9'Pi mp OpAratinn Power Neg. Imb. Pos. Imb. Power Neg. Imb. Pos. Imb.

3 Pump Operation 2 Pump Operation 77 -14.46 7.32 52 -15.14 6.17 69 -21.47 13.34 46 -22.08 10.68 60 -26.38 20.10 40 -26.25 15.19 45 -27.06 20.92 30 -27.58 21.30 0 -27.06 20.92 0 -27.58 21.30

COLR TMI 1 Rev. 5 Page 26 of 37 Figure 9 (Page 1 of 4)

LOCA Limited Maximum Allowable Linear Heat Rates Mark-B 10 Fuel Assemblies (UO Fuel Rods) 18 17 S16 or n 15 0

14-S13 E

E 12 11 10 0 10 20 30 40 50 60 70 Burnup, GWd/mtU IReferred to by Tech Spec 3.5.2.8 1

-- e--0 and 12 ft -E-2.506, 4.264, 7.779 and 9.536 ft -&--6.021 ft I Note: The MALHR of 16.8 kW/ft at the 7.779 f. elevation is administrative. A limit of 17.3 kWMft is acceptable providing cycle-specific evaluation of PCT.

COLR TMI I Rev. 5 Page 27 of 37 Figure 9 (Page 2 of 4)

LOCA Limited Maximum Allowable Linear Heat Rates Mark-B12 Fuel Assemblies (U02 Fuel Rods) 18-LHR Limits are provided based on Nuclear Source Power (40,17.0) 17 (40,16.8)

~16-6 (40,15.9) 4a-M 15 14-

.0 0

1*-1 E 13(62,12.4)

E x

12 11 10 10I I , 40 I I 0 10 20 30 40 50 60 70 Burnup, GWd/mtU IReferred to by Tech Spec 3.5.2.8 1 R-4--0 and 12 ft --B-2.506, 4.264 and 9.536 ft -- 6.021 and 7.779 fti

COLR TMI 1 Rev. 5 Page 28 of 37 Figure 9 (Page 3 of 4)

LOCA Limited Maximum Allowable Linear Heat Rates Mark-B-HTP Fuel Assemblies (UO2 Fuel Rods) 18.0 LHR Limits are provided based on Nuclear Source Power (40,17.0) 17.0

[]

(40,16.8) 16.0 o (40,15.9)

C 15.0 +

. 14.0 -I-10 E 13.0 -F E

E ca12.0

+

11.0 -I 10.0 0 10 20 30 40 50 60 70 IReferred to by Tech Spec 3.5.2.8 Bumup, GWd/mtU 2.506,4.264 and 9.536 ft --- 6.021 and 7.779 ft --- Oand 12ft

COLR TMI 1 Rev. 5 Page 29 of 37 Figure 9 (Page 4 of 4)

MTC Limit vs. Power Level 10 9-8-

I -I 7-6 - -

5 - -

E - . . . .. -

4 ------ -------------- L---------- L-------------

3 - -

2 1

0-0 20 40 60 80 100 Percent Full Power

COLR TMI 1 Rev. 5 Page 30 of 37 Figure 10 Axial Power Imbalance Protective Limits Thermal PowerLevel % 70 -60 -50 30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %

EXPECTED MINIMUM CURVE REACTOR COOLANT FLOW (Ib/hr) 1 137.77 x 106 2 103.22 x 106 3 67.90 x 108

COLR TMI 1 Rev. 5 Page 31 of 37 Figure II Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level %

120

(-33.50, 108.0) (13.11, 108.0) 4 PUMP OPERATION 100 m = -0.989 m = +2:145 80

(-50.52, 71.50) (50.00, 71.50) 60 ACCEPTABLE

(-50.52,45.47) 2, 3 AND 4 PUMP OPERATION (50.00, 45.47) 40

(-50.52, 19.34) 20- (50.00, 19.34)

C6-II

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

COLR TMI 1 Rev. 5 Page 32 of 37

REFERENCES:

1. BAW-10179P-A, Rev. 6, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," December 2004.
2. FRA-ANP Doc. No 86-1172640-00, "Detector Lifetime Extension Final Report for TMI- 1," September 1988.
3. ANP-2665, Rev. 1, "Three Mile Island Unit 1 Cycle 17 Reload Report," November 2007.
4. 51-9066032-000, "TMI-1 Cycle 17 Redesign Verification Report," November 2007.

COLR TMI 1 Rev. 5 Page 33 of 37 Enclosure I Operating Limits Not Required by Technical Specifications

COLR TMI 1 Rev. 5 Page 34 of 37 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 8 and 9 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:

FRA-ANP Mark-B10 / Mark-B12 / Mark-B-HTP LHR to melt = 21.9 kW/ft

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 (BWS'D 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 807 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 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 TM! 1 Rev. 5 Page 35 of 37 Enclosure 2 DNBR-Related Bases Descriptions

COLR TMI I Rev. 5 Page 36 of 37 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 9 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 8). 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 I Rev. 5 Page 37 of 37

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
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