ML053190097

Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 2

ML053190097
Person / Time
Site:	Three Mile Island
Issue date:	11/14/2005
From:	Cowan P AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
5928-05-20305
Download: ML053190097 (37)

Text

L LC November 14,2005 5928-05-20305 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 16 Core Operating Limits Report, COLR TMI 1, Revision 2 Pursuant to TMI Unit 1 Technical Specification Section 6.9.5.4, enclosed is a copy of the Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 2. The Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 2, provides the cycle-specific limits established to support operation of Cycle 16 up to 705 Effective Full Power Days, and provides updated references.

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

Since the Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 1 has been replaced by the enclosed Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 2 prior to startup of the new operating cycle, the Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 1 has not been submitted to the NRC.

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

Respectfully, Pamela B.%owan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Enclosure:

TMI-1 Cycle 16 Core Operating Limits Report, COLR TMI 1, Revision 2 cc: S. J. Collins, USNRC, Administrator, Region I F. E. Saba, USNRC, Project Manager, TMI Unit 1 D. M. Kern, USNRC, Senior Resident Inspector, TMI Unit 1 File No. 95055

ENCLOSURE CYCLE 16 CORE OPERATING LIMITS REPORT COLR TMI 1, REVISION 2

AmerGen TMI-1 Cycle 16 Core Operating Limits Report COLRTMI 1 Rev. 2 H. Crawford Reactor Engineering Manager Date

COLR TMI 1 Rev. 2 Page 2 of 35 TABLEOFCONTENTS PAGE Abstract 3 Full Incore System (FIS) Operability Requirements 6 APSR Rod Insertion Limits 7 Table 1 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 13 Figure 1 Error Adjusted Rod Insertion Limits 14 4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 16 3 Pump Operation Figure 3 Error Adjusted Rod Insertion Limits 18 2 Pump Operation Figure 4 Full Incore System Error Adjusted 20 4 Pump Imbalance Limits Figure 5 Full Incore System Error Adjusted 21 3 Pump Imbalance Limits Figure 6 Full Incore System Error Adjusted 22 2 Pump Imbalance Limits Figure 7 Out-of-Core Detector System Error Adjusted 23 Imbalance Limits Figure 8 Minimum Incore System Error Adjusted 24 Imbalance Limits Figure 9 LOCA Limited Maximum Allowable Linear Heat Rate 25 Figure 10 Axial Power Imbalance Protective Limits 28 Figure 11 Rector Protection System Maximum Allowable Setpoints 29 for Axial Power Imbalance References 30 Operating Limits Not Required by Technical 31 Specifications DNBR-related Bases Descriptions 33

COLRTMI 1 Rev. 2 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 1 limits and reactor protection system limits and setpoints in this report have been analyzed for a maximum end-of-cycle (EOC) length of 705 EFPD. I 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. Axial Power Shaping Rod (APSR) position limits and restrictions describe how the APSRs must be operated during the cycle. I 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 I 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: I

1. Permissible Region

2. Restricted Region

3. Not Allowed Region (Operation in this region is not allowed)

The lirniting 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 kame, 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.el provided that hot channel factors are

COLR TMI 1 Rev. 2 Page 4 of 35 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.dI. (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 inunediate 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 F Nlirnits

~ ~(i.e., initial condition DNB peaking) for core monitoring. During normal conditions, operation within quadrant tilt (Table l),rod insertion (Figures 1-3),and imbalance (Figures 4-8) limits ensure I FQ(Z) and F N limits~ ~ are met. However, verifkation that positive margin to FQ(Z) and F N limits~ ~ exists may be required during the following abnormal conditions:

0 T.S.3.5.2.2.e (operationwith an inoperable rod) 0 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) 0 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 F N ~ ~ ,

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 he1 elevation for Mark-B10 and Mark-B12 fuel types. Bounding values for monitoring these limits for the I

current cycle in terms of he1 batch, fuel rod burnup and core elevation are I listed in Table 2. The full power h e a r heat rate lirnits are applicable for partial-power and three-pump operation since the allowable moderator temperature coefficient (nlrrc) as a function of power, shown on page 3 of Figure 9, is preserved by the cycle design. I Note: Figures 10 and 11 show the conservative generic limits and I setpoints currently installed on the plant hardware. The cycle-specific values have been verifled to be conservatively bounded by the generic values.

COLR Figure 10 provides the Axial Power Imbalance Protective Limits (APIPL) I that preserve the DNBR and Centerhe Fuel Melt design criteria.

COLR TMI 1 Rev. 2 Page 5 of 35 COLR Figure 11 provides the Protection System Maximum Allowable Setpoints I 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 I 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 s o h a r e as part of the bases of the required limits and setpoints. The rninimum boron volumes and concentrations for the Boric Acid Mix Tank (BAMT) and Reclaimed Boric Acid Storage Tanks (RBA'I') 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 ( F N ~ ~ )

that d e k e the reference design peaking condition in the core.

COLRTMI 1 Rev. 2 Page 6 of 35 Full Incore System (FIS)

Operability Requirements 0 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 J

I XY 99.75 75.0 1

1 YZ 89.25 67.0 m 89.25 67.0 The Full Incore System (FIS) is operable for monitoring quadrant tilt provided the number of valid syrnmetric 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 Spmunetric Strings wx 7, 9, 32, 35 XY 5, 23, 25, 28 yz 16, 19, 47, 50 II m 1 11. 13. 39. 43 1 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. 2 Page 7 of 35 APSR Position Limits The Axial Power Shaping Rods (APSRs) shall be inserted at the initial startup following fuel reload and 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% FCP. 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 0-99% WD shall be considered a "Restricted Region" as defined in the abstract section of this COLR.

Note: Periodic movement of the APSRs to venfy 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 veriflcation is completed.

Note: m e APSRs may be inserted during preparation for findl cycle shutdown into the refueling outage after reactor power is below 20%FP.

COLR TMI 1 Rev. 2 Page 8 of 35 TABLE 1 Quadrant Tilt Limits Mote: If the Full Incore System (FIS) is inoperable, FIS tilt lirnits 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. 2 Page 9 of 35 TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (Ir"/ft ("1)

Batch 1 3 N Core Elevation 0 40,000 62,000 (feet) MWdlmtU MWd/mtU MWdlmtU 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 16 & 17 Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWdlmtU 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 18(b)

Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.7 15.7 12.2 2.506 16.6 16.6 12.2 4.264 16.6 16.6 12.2 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 (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

COLRTMI 1 Rev. 2 Page 10 of 35 Table 2 (Continued)

Batch 16 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 Batch 17 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 8 w/o Gd Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWdlmt U MWdlmtU 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.o (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevatic points is valid for these tables.

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

COLRTMI 1 Rev. 2 Page 11 of 35 Table 2 (Continued)

Batch 18 2 w/o Gd(b)

Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 14.9 14.9 11.8 2.506 15.7 15.7 11.8 4.264 15.7 15.7 11.8 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 Batch 18 3 w/o Gd(b)

Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mt U MWd/mtU 0.000 14.2 14.2 11.5 2.506 15.0 15.0 11.5 4.264 15.0 15.0 11.5 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 18 8 w/o Gd")

Core Elevation 0 40,000 62,000 (feet) MWd/mtU MWd/mtU MWdlmtU 0.000 13.3 13.3 10.8 2.506 14.0 14.0 10.8 4.264 14.0 14.0 10.8 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 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables.

(b)ThekW/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.

COLRTMI 1 Rev. 2 Page 12 of 35 Table 2 (Continued)

The maximum linear heat rate for each CMS level, as measured with the FIDMS Thermal I 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 I minimum margin to FQ(2) limits for each axial level.

Notes: The LHR limits above are equivalent to the total peaking hot channel factor limits, FQlZ), referred to in T.S. 3.5.2by dividing the LHR limits by the product of the core average linear heat rate (5.71 kW/ft) and the current fraction of rated I power.

COLR TMI 1 Rev. 2 Page 13 of 35 TABLE 3 LCO DIYB Maximum Allowable Radial Peaking (1wIARp) Limits 1.7 1.9522 1.8285 1.7060 1.5963 1.9 1.8011 1.6959 1.5905 1.4944 The maximum radial peak for each fuel assembly, as measured with the Core Monitoring System (CMS)at the elevation where the assembly axbl peak occurs, should not be greater than the corresponding bounding value from Table 3 above. CMS Display 4, Thermal Limiting Condition Hot Channel Factor page, shows the minimum margin to F N ~ Hlimits for the fuel assemblies with the smallest (or negative) margin.

Notes: The K O DNB Maximum Allowable Radial Peaking (MARP) limits above 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.O 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?40peaking uncertainty treated by Statistical Core Design (SCD) methodology.

COLRTMI 1 Rev. 2 Page 14 of 35 Figure 1 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 rtl0 EFPD; 4 Pump operation) 110 100 (107.7,102)* (300,102 n

80 0

Restricted 70 Region U

3 0

40 zE

- 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 25% between sequential groups 5 and 6,and 6 and 7 shall be maintained.

COLRTMI 1 Rev. 2 Page 15 of 35 Figure 1 (Page 2 of 2)

Error Adjusted Rod Insertion Limits (400 &loEFPD to EOC;4 Pump Operation) 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.

COLRTMI 1 Rev. 2 Page 16 of 35 Figure 2 (Page 1 of 2)

Error Adjusted Rod Insertion Limits (0 to 400 f10 EFPD; 3 Pump Operation) 110 100 90 (1 08.37) (300,771 80 a!

8

n. 70 60 rr" w-0 8 50 38 40 5

5 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 55% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

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

Error Adjusted Rod Insertion Limits (400 f10EFPD to EOC; 3 Pump Operation) 100 - -

90 -:

L Not Allowed 60

/

Al (207,43)

J ' ' " i 8 1 ~ l ~ # a # t ~ ~ , , ~ , ,~ , , , , , ~

I 8 0 25 50 75 100 125 150 175 200 225 250 275 31 Indicated Rod Index, %Withdrawn A Rod group overlap of 25 +5% between sequential groups 5 and 6,and 8 and 7 shall be maintained.

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

Error Adjusted Rod Insertion Limits (0 to 400 f10 EFPD; 2 Pump Operation) 110 L

100 -1 90 - -

80 -I f

0 70 -1 P

2 60 -I

/

r (300,52) 1-1 0 (1 09.4,52)

(272,52) 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 25% between sequential groups 5 and 6,and 6 and 7 shall be maintained.

COLR TMI 1 Rev. 2 Page 19 of 35 Figure 3 (Page 2 of 2)

Error Adjusted Rod Insertion Limits (400 f10 EFPD to EOC; 2 Pump Operation) 110 (207,28) 10 f (95,9) / /

0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, %Withdrawn A Rod group overlap of 25 45% betw Ben sequential groups 5 and 6, and 6 and 7 shall be maintained.

COLR TMI 1 Rev. 2 Page 20 of 35 Figure 4 IWl Incore System Error Adjusted 4 Pump Imbalance Limits (0 EFPD to EOC)

(-21.27,102) (20.85,102)

Region 100 -- Region

(-30.07,92) // (26.88,92)

(-35.50,80) (30.16,80)

(-35.69,60) Wrmksible Region (30.36,60) 50 -

• 40 30 --

20 -

• T lot

(-35.69,O) 1 .;.

• ,. ,.., , , . ., ., * , , , .. .J , . . * . .. * , * ,

(30.36,O)

COLR TMI 1 Rev. 2 Page 21 of 35 Figure 5 Full Incore System Error Adjusted 3 Pump Imbalance Limits (0 EFPD to EOC)

J.

80 -- (21.08,77) 70 -- (27.10,69)

/ \

(-35.69,60) I (30.36,60)

(-%.84,45) I (30.50,45)

This Rgure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4

(-35.84,O)

J I 1 I I . . , ., , . . . . . .. ,. . , , . , . , , , , .

1 *

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

COLR TMI 1 Rev. 2 Page 22 of 35 Figure 6 Full Incore System Error Adjusted 2 Pump Imbalance Limits (0 EFPD to EOC)

"T Restricted Region t (21.32,52)

Region 50 --

(-30.51 (27.32,46)

(-%.88,40) 40 -- (30.55,40)

Permissible Region

(-%.98,30) 30 -- I (30.64,30) 20 --

lo --

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

COLR TMI 1 Rev. 2 Page 23 of 35 Figure 7 Out-of-Core Detector System Error Adjusted Imbalance Limits (0 EFPD to EOC)

Restricted (-15.02,102) 5.02.102) (14.58,102)

Region

(-23.84,92) (20.58.92)

/ + \

[24.00.80)

I f (24.65,tio)

.40 -35 -30 T.S. 3.5.2.783.5.2.4.e.4

-25 -20 -15 -10 -5 0 5 10 lndlcated Axial Power Imbalance, %FP 15 20 25

-(24.65,O) 30 35 40 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.

f%FPI (%FpI f%FPI J%FP) J%FP) {%FPI 3 Pump Operation 2 Pump Operation 77 -15.83 15.39 52 -16.63 16.18 69 -24.40 21.33 46 -25.14 22.06 60 -29.77 24.65 40 -30.41 25.28 45 -30.25 25.12 30 -30.73 25.58 0 -30.25 25.12 0 -30.73 25.58

COLR TMI 1 Rev. 2 Page 24 of 35 Figure 8 Minimum Incore System Error Adjusted Imbalance Limits (0 EFPD to EOC)

Restricted (-1 2.80,102) (12.43,102)

Operation f

(-20.87,92) (17.9132)

\

(-25.83,80) rm'ssible4 Rnp Region (See3 and 2 Rnp tinits 80 B Wrmissble 4 Rnp Region (21.22,80)

(-28.53,60) (21.92.60)

(-26.53,O) (21.92,O)

- I P 35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 indicated Axial Power Imbalance, 9/6p M~nimumlncore 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.

PhFP) {%FP) P!FP) P!FP) I%FP) {%FP) 3 Pump Operation 2 Pump Operation 77 -13.67 13.30 52 -14.35 14.18 69 -21.47 18.72 46 -22.08 19.52 60 -26.38 21.92 40 -27.08 22.62 45 -27.06 22.45 30 -27.58 22.97 0 -27.06 22.45 0 -27.58 22.97

COLRTMI 1 Rev. 2 Page 25 of 35 Figure 9 (Page 1 of 3)

L O U Limited IMaximum Allowable Linear Heat Rates Mark-B10 Fuel Assemblies ( U 0 2 Fuel Rods)

LHR Limits are provided based on Nuclear Source Power 17 16 15 14 13 12 --

i 11 - -

lo 0 10 20 30 40 50 60 70 Burnup, GWdmtU IReferred to by Tech Spec 3.5.2.8 I 0 and 12 ft -R-2.506,4.264, 7.779and 9.536ft -;b6.021 ft I Note: The MALHR of 16.8 k W m at the 7.779 ft. elevation is administrative. A limit of 17.3 k W m is acceptable providing cycle-specific evaluation of PCT.

COLRTMI 1 Rev. 2 Page 26 of 35 Figure 9 (Page 2 of 3)

LOCA Limited Maximum Allowable Linear Heat Rates MarEr-Bl2 Fuel Assemblies (U02Fuel Rods) 18 LHR Limits are provided based on Nuclear Source Power 17 16

-Y nr 3 15 CI I

I Q)

P-l4 0

13 E

i I_

x g 12 11 10 0 10 20 30 40 50 60 70 Burnup, GWd/mtU

/Referred to by Tech Spec 3.5.2.81 I+ 0 and 12 ft 2.506,4.264and 9.536 ft +6.021 and 7.779ft 1

COLR TMI 1 Rev. 2 Page 27 of 35 Figure 9 (Page 3 of 3)

MTC Limit vs. Power Level 10 CI 9

.-0Ea?

5 8 0

0 0 20 40 60 80 100 Percent Full Power

COLR TMI 1 Rev. 2 Page 28 of 35 Figure 10 N a l Power Imbalance Protective Limits Thermal Power Level, %

12(

943.8,1 1 2.0

/

/143.8,89.7 ACCEPTABLE 4 PUMP OPERATION 1oG 8o

-58.5,80.4 ACCEPTABLE 3 AND 4 PUMP

/ OPERATION

-43.8, 62.4

-58.5,57.8 /t ACCEPTABLE 60 2,3 AND 4 PUMP OPERATION

-58.5.30.4 1 40 20 I I t I I , n

" 1 I I I I I I I

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

EXPECTED MINIMUM CURVE 2 1 137.77x 10' 2 103.22x 10' 3 67.90x 10'

COLR TMI 1 Rev. 2 Page 29 of 35 Figure 11 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level, %

-30.0,108.0 24.5, 108.0 loo --

mi = 1.900 n9=-1.854

-50.0,70.0 45.0,70.0

-50.0,42.6 45.0,42.6

-50.0,15.1 45.0,15.1 70 -60 40 -30 -20 -10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, %

COLRTMI 1 Rev. 2 Page 30 of 35 BFERENCES:

1. BAW-10179P-A,Rev. 5, 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. BAW-2491, Rev. 2, Three Mile Island Unit 1 Cycle 16 Reload Report, November 2005. I

COLRTMI 1 Rev. 2 Page 31 of 35 Enclosure 1 Operating Limits Not Required by Technical Specifications

COLR TMI 1 Rev. 2 Page 32 of 35

1. Maximum Allowable Local Linear Heat Rate Limits

(

Reference:

T.S. 2.1 Bases)

The maximum allowable local linear heat rate limit is the minirnum 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-B 10 / MXk-B12 LHR to melt = 21.9 kW/ft

2. Alternate Minimum Boron Requirements for Colc Shutwwn I

(

References:

T.S. 3.3.1.l.a, T.S. 3.3. Bases, FSAR 9.2.1.2)

The 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 to bring the reactor to cold shutdown under normal operat ns. Although not required by T.S., other sources of borated water can be used in lieu of the BWS" for the purpose of achieving cold shutdown under normal operating conditions.

The minimum boron level needed in the BAMTT or RE3ATs to achieve cold shutdown conditions throughout the cycle is the equivalent of at least 798 ft3 of 12,500 ppm boron. There is no T.S. requirement to maintain these tanks at this level, however out-of-service time for the tanks should be minimized. The design bases for these tanks are described in FSAR Section 9.2.1.2.

COLR TMI 1 Rev. 2 Page 33 of 35 Enclosure 2 DNBR-Related Bases Descriptions

COLR TMI 1 Rev. 2 Page 34 of 35

1. 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 80.6 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 53.1 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. 2 Page 35 of 35

2. Design Nuclear Power Peaking Factors

(

Reference:

T S . 2.1 Bases)

The design nuclear power peaking factors given below defme 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), F N * ~

F N *=~ 1.80 Axial Flux Shape Peaking Factor, FNz FNz = 1.65 (cosine with tails)

Total Nuclear Power Peaking Factor, FNq FNq = F N

• xFNz

~

FNq = 2.97