ML033180259

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Cycle 15 Core Operating Limits Report, Revision 0
ML033180259
Person / Time
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Issue date: 11/05/2003
From: Gallagher M
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
5928-03-20221
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{{#Wiki_filter:AmerGensb AmerGen Energy Company, LLC www.exeloncorp.com An Exelon/British Energy Company 200 Exelon Way Suite 345 Kennett Square, PA 19348 November 5, 2003 5928-03-20221 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 15 Core Operating Limits Report, Revision 0 Pursuant to TMI Unit 1 Technical Specification Section 6.9.5.4, enclosed is a copy of the Cycle 15 Core Operating Limits Report (COLR), Revision 0. The Cycle 15 COLR, Revision 0, provides the cycle-specific limits established to support operation of Cycle 15 up to 697 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. If you have any questions or require additional information, please do not hesitate to contact us. Very truly yours, Michael P. Gallagher Director, Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Enclosure:

TMI Unit 1, Cycle 15 Core Operating Limits Report, Topical Report 179, Revision 0 cc: H. J. Miller, USNRC, Administrator, Region 1 D. M. Skay, USNRC, Senior Project Manager D. M. Kem, USNRC, Senior Resident Inspector PC File No. 95055

AmerGen TMI-1 Cycle 15 Core Operating Limits Report TOPICAL REPORT 179 Rev. O 2 (10/6/2003 I I,, ZIP,_ R. Jaffa Author i I/ Date M. Mahgerefteh -" I-...-, 0109/2003 Review*er

7 t

Date Design Verification Required? A. /'. Design Verification Engineer H. Crawford A 0 ( 1 Section Maniger PORC Chair [E YES l NO If yes - DV#: -"/4 Date / 1/9 Date Date. AGo353 (6/00)

TR 179 Rev. 0 Pane 2 of 32 TABLE OF CONTENTS 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 11 Figure 1 Error Adjusted Rod Insertion Limits 12 4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 14 3 Pump Operation Figure 3 Error Adjusted Rod Insertion Limits 16 2 Pump Operation Figure 4 Full Incore System Error Adjusted 18 Imbalance Limits Figure 5 Out-of-Core Detector System Error Adjusted 19 Imbalance Limits Figure 6 Minimum Incore System Error Adjusted 20 Imbalance Limits Figure 7 LOCA Limited Maximum Allowable Linear Heat Rate 21 Figure 8 Axial Power Imbalance Protective Limits 25 Figure 9 Rector Protection System Maximum Allowable Setpoints 26 for Axial Power Imbalance References 27 Operating Limits Not Required by Technical 28 Specifications DNBR-related Bases Descriptions 30

TR 179 Rev. ( Page 3 of 32 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 through 5 and were documented in Reference 6. 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 697 EFPD. The--Full Incore -System (FIS)--operability-requirements-contained within describe the number and location of Self-Powered Neutron Detector (SPND) strings that must be operable in order to monitor imbalance and quadrant tilt using the FIS. Quadrant tilt limits for FIS, out-of-core detector (OCD] system and minimum incore system [MIS] are given in Table 1. Technical Specification requirements related to quadrant tilt, including operator actions that must be taken in the event quadrant tilt limits are exceeded, are stated in T.S. 3.5.2.4. Rod insertion limits are provided in Figures 1 to 3 to ensure that the safety criteria for DNBR protection, LOCA kw/ft limits, shutdown margin and ejected rod worth are met. Axial Power Shaping Rod (APSR) position limits and restrictions describe how the APSRs must be operated at the end-of-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 6. 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 6 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 LT.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 tventy-four

TR 179 Rev. 0 Page 4 of 32 (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.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 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 Fg(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 4-6) limits ensure FQ(Z) and FN&H limits are met. However, verification that positive margin to FQ(Z) and FNjH 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 Fg(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 7 indicates the LOCA limited maximum. allowable linear heat rates as a function of fuel rod burnup and fuel elevation for Mark-B8V, Mark-B1O/-BlOP, and Mark-B12 fuel types. Bounding values for monitoring these limits for the current cycle in terms of fuel batch, cycle bumup and axial detector levels 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 7, is preserved by the cycle design. Note: Figures 8 and 9 show the conservative generic limits and setpoints currently installed on the plant hardware. The cycle-specific values have been verified to be conservatively bounded by the generic values. COLR Figure 8 provides the Axial Power Imbalance Protective Limits (APIPL) that preserve the DNBR and Centerline Fuel Melt design criteria.

TR 179 Rev. 0 Page S of 32 COLR Figure 9 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 8 are not exceeded. contains operating limits not required by TS. The core minimum DNBR and the Maximum Allowable LOCA Linear Heat Rate limits are monitored by the Process Computer Nuclear Applications 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 (FNXH) that define the reference design peaking condition in the core.

TR 179 Rev. O Page 6 of 32 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 I SPNDs l 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). I Quadrant l 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

TR 179 Rcv. 0 Page 7 of 32 APSR Position Limits Before the end-of-cycle APSR pull maneuver is completed, the APSRs may be positioned as necessary for transient imbalance control. The APSR pull maneuver shall be completed (i.e. APSRs fully withdrawn) at 666 +/-10 EFPD. Once the APSR pull maneuver has been completed, the APSRs shall not be inserted for the remainder of the fuel cycle and 0-99% WD shall be considered a "Restricted Region" as defined in the abstract section of this COLR. Note: APSRs may be inserted during preparation for final cycle shutdown into the refueling outage after reactor power is below 20%FP. Source Doc.: BAW-2447, Rev. 1, TMI-1 Cycle 15 Reload Report

TR 179 Rev. 0 Page 8 of 32 TABLE 1 Quadrant Tilt Limits Steady State Limit Steady State Limit Maximum Limit 15 < Power 5 60% Power > 60% Power > 15% Full Incore System 6.83 4.03 16.8 (FIS) Minimum Incore System 2.78 1.90 9.5 (MIS) 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. Source Doc.: Referred to by: BAW-2447, Rev. 1, TMI-1 Cycle 15 Reload Report Tech. Spec. 3.5.2.4

TR 179 Rcv. 0 Pane 9 of 32 TABLE 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft) Batch 11F CMS 0-150 150-275 275-425 425-550 550-697 Level__ EFPD EFPD J EFPD j EFPD j EFPD 8 14.3 13.8 13.2 12.6 11.9 7 -14.3 13.8 13.2 12.6 11.9 6 14.3 13.8 13.2 12.6 11.9 5 14.3 13.8 13.2 12.6 11.9 4 14.3 13.8 13.2 12.6 11.9 3 14.3 13.8 13.2 12.6 11.9 2 14.3 13.8 13.2 12.6 11.9 1 14.3 13.8 13.2 12.6 11.9 Batches 13M, 15A1, 15C2 CMS ll 0-65 65-225 225-375 l 375-550 1 550-697 Level EFPD EFPD EFPD EFPD EFPD 8 15.9 15.4 14.8 14.0 13.4 7 16.2 15.6 15.0 14.2 13.5 6 16.8 16.1 15.4 14.4 13.6 5 16.8 16.1 15.4 14.4 13.6 4 16.7 16.1 15.3 14.4 13.6 3 16.7 16.1 15.3 14.4 13.6 2 16.2 15.6 15.0 14.2 13.5 1 15.9 15.4 14.8 14.0 13.4 Batch 15A3 [ OMS ll 0-175 175-300 l 300-425 l 425-550 550-697 Level goEFPD EFPD EFPD EFPD I FD 8 14.0 13.8 13.5 13.3 13.0 7 14.1 13.9 13.6 13.3 13.0 6 14.3 14.1 13.8 13.5 13.0 5 14.3 14.1 13.8 13.5 13.0 4 14.3 14.0 13.8 13.4 13.0 3 14.3 14.0 13.8 13.4 13.0 2 14.1 13.9 13.6 13.3 13.0 1 14.0 13.8 13.5 13.3 13.0 II

TR 179 Rev. 0 Page IO of 32 Table 2 (Continued) Batches 16A, 16B, 16C2 CMS l 0-305 305-400 400-500 500-600 600-697 Level J EFPD EFPD EFPD l EFPD EFPD 8 15.9 15.4 14.8 14.3 13.8 7 16.2 15.6 15.1 14.5 14.0 6 16.8 16.1 15.5 14.8 14.2 -- -5

16.9 16.3

-15.6

14.9

- ---14.3---- 4 16.8 16.1 15.5 14.8 14.2 3 16.8 16.1 15.5 14.8 14.2 2 16.2 15.6 15.0 14.5 14.0 1 15.9 15.4 14.8 14.3 13.8 Batch 17 CMS l 0-697 Level EFPD 8 15.9 7 16.2 6 16.8 5 16.9 4 16.8 3 16.8 2 16.2 1 15.9 A The maximum linear heat rate for each CMS level, as measured with the NAS Thermal Hydraulic Package, should not be greater than the corresponding bounding value from Table 2 above. NAS 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 (5.79 kW/ft) and the current fraction of rated power. LHR limits provided are based on nuclear source power, therefore NAS variable "FNT' must be set equal to 1.0. Source Doc.: BAW-2447, Rev. 1, TMI-1 Cycle 15 Reload Report

TR 179 Rev. ( Pave 11 of 32 TABLE 3 LCO DNB Maximum Allowable Radial Peaking (MARP) Limits Axial Peak Elevation (Fraction of Core Height) Axial Peak 0.2 -0.4 - 0.6 0.8 1.1 1.9672 1.9607 1.9489 1.9206 1.2 2.0312 2.0162 1.9922 1.8995 1.3 2.0857 2.0625 1.9786 1.8412 1.5 2.1091 1.9760 1.8378 1.7103 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 axial 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 FNAH limits for the fuel assemblies with the smallest (or negative) margin. Notes: The LCO DNB Maximum Allowable Radial Peaking (MARP) limits above are equivalent to nuclear enthalpy rise hot channel factor limits, FNiH, referred to in T.S. 3.5.2 by using the following conversion: FNA&H 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. Source Doc.: BAW-2447, Rev. 1, TMI-1 Cycle 15 Reload Report

TR 179 Rcv. 0 Page 12 of 32 Figure 1 (Page 1 of 2) Error Adjusted Rod Insertion Limits (O to 400 +/-10 EFPD; 4 Pump Operation) 110 100 90 L-c0 EL Ca 0 0 0- 'U ci 80 70 60 50 40 30I 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 I ITS 3.5.2.5.b & 3.5.2.4.e.3I

TR 179 Rev. 0 Page 13 of 32 Figure 1 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation) 110 100 90 I-C) 0 IL 0 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 maintahed. This figure Is referred to by ITS 3.5.2.5.b & 3.5.2.4.e.3I

TR 179 Rev. 0 Page 14 of 32 Figure 2 (Page 1 of 2) Error Adjusted Rod Insertion Limits (O to 400 +/-10 EFPD; 3 Pump Operation) 110 100 90 a, C B. cc 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, %Wfthdrawn A Rod group overlap of 25 +5% betw een sequential groups 5 and 6, and 6 and 7 shall be maintained. This figure is ref erred to by I I TS 3.5.2.5.b & 3.5.2A4.e.3 I

TR 179 Rev. 0 Page 15 of 32 Figure 2 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation) 110 100 90 L-0 0 M a, 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, %Wlthdrawn A Pod group overlp of 25 5% between sequential groups 5 and 6, and 6 and 7 shal be rnaartained. Ths figure Is referred to by I TS 3.5.2.5.b 8 3.5 2.4.e.32

TR 179 Rev. 0 Pane 16 of 32 Figure 3 (Page 1 of 2) Error Adjusted Rod Insertion Limits (O to 400 +/-10 EFPD; 2 Pump Operation) 110 100 90 0 0~ D. 10

  • 0 (D

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, %Wfthdrawn A Rod group overlap of 25 5% betw een sequential groups 5 and 6. and 6 and 7 shal be nreintained. Ths figure is referred to by I ITS 3.5.2.5.b & 3.5.2.4.e.3l

TR 179 Rcv. O Pace 17 of 32 Figure 3 (Page 2 of 2) Error Adjusted Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation) 110 100 90 I-a- co 0 0-R Cu 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, %Wlthdrawn A Rod group overlap of 25 5% between sequential groups 5 and 6, and 6 and 7 shall be ramitained. This figure isreferred to by I TS 3.5.2.5. b & 3.5.2A4.e.3I1

TR 179 Rev. 0 Page 18 of 32 Figure 4 Full Incore System Error Adjusted Imbalance Limits (O EFPD to EOC) Restricted l (-22.43,102) l Region l (-27.18,92) (-33.87.80) (-35.46,60) [TrissibIe 110-100' 90-(20.07,102) \\slb~e Region I Permnissible Region I --Restricted-Region 26.60,92) (29.90,80) 1(30.20,60) e Region 80-70 60 3a 50 c) Lto s 0 E 40 10 16 30 - 20 10I (.35.46,0) (30.20,0) ... ^...... -50 -45 -40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP This Figure is referred to by I I T.S. 3.5.2.7 & 3.5.2.4.e.4 I

TR 179 Rev. 0 Pane 19 of 32 Figure 5 Out-of-Core Detector System Error Adjusted Imbalance Limits (O EFPD to EOC) 110. -50 -45 -40 -35 30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Azdal Power Imbalance, 'OVP ah&sFiresrelerredtoby5I I T.S 3.5 Z7&3.524.e.4 I

TR 179 Rev. 0 Page 20 of 32 Figure 6 Minimum Incore System Error Adjusted Imbalance Limits (O EFPD to EOC) Restricted (-14.64,102) Operabon I-(.18.85,92) (-24.95.80) (-26.93,60) (-26.93,0) (1243,102) Rsrc L2 --I peaioJ 80 I Remissible RegxinI 70 2 EU 0 IEU 60 50 40 -50 -45 -40 -35 .30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, */%FP lThis Fxguwe Is ref erred to byl I T.S. a5 27 & 3.5.2.4.e.4

TR 179 Rev. 0 Page21 of32 Figure 7 (Page 1 of 4) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B8V Fuel Assemblies 18 17 LHR Limits are provided based on Nuclear Source Power (39.5, 16.5) 9 16 -2 ia a: 15 4-(U = a) 0 E13 2 x W 12 I-(45.750, I. I. 11+ (62, 10.6) 10. I .A..d 0 0 20.

0.

I 40 0 6 I 10 20 30 40 50 60 70 IReferred to by Tech Spec 3.5.2.8 1 Burnup, GWd/mtU 0- 0 and 12 ft -- 2 and 10 ft --A--4 and8ft +6 ftl

C'. TR 179 Rev. 0 Page 22 of 32 Figure 7 (Page 2 of 4) LOCA Limited Maximum Allowable Linear Heat Rates Mark-BIO and Mark-BlOP Fuel Assemblies 18 - 17 E 16 4-rr 15 4-cis . 14 M < 13 E cu 12 11 10 0 10 20 30 40 50 60 Burnup, GWd/mtU 70 IReferred to by Tech Spec 3.5.2.8 l G--0 and 12 ft 2.506,4.264, 7.779 and 9.536 ft -A 6.021 ft Note: The MALHR of 16.8 kW/ft at the 7.779 ft. elevation Is administrative. A limit of 17.3 kW/ft is acceptable providing cycle-specific evaluation of PCT.

TR 179 Rev. 0 Page 23 of 32 Figure 7 (Page 3 of 4) LOCA Limited Maximum Allowable Linear Heat Rates Mark-B12 Fuel Assemblies 18, 4-(U 5a: to 0 CU 0 10 20 30 40 50 60 70 I Refered to by Tech Spec 3.5.2.8 1 Burnup, GWd/mtU {- O- 0 and 12 ft -- 2.506, 4.264 and 9.536 ft -- 6.021 and 7.779 ft

TR 179 Rcv. 0 Page 24 of 32 Figure 7 (Page 4 of 4) MTC Limit vs. Power Level 0) a-C) 0i -I... a) 0) E 0) 0 Cu C, 0 IL 10 9. 8 - 71~ 6 5 4 3 2 1 0* I-- - - - - - - - - - - - - ~I 0 20 40 60 80 100 Percent Full Power

TR 179 Rcv. 0 Page 25 of 32 Figure 8 Axial Power Imbalance Protective Limits Thermal Power Level, % 1208-tl-, -58.5, 80.4 -58.5, 57.8 -58.5,30.4 - 43.8,112.0 37.8,112.0 / ACCEPTABLE 4 PUMP. OPERATION 1 00 -43. 89.7 37.8,89.7 ACCEPTABLE 80 3 AND 4 PUMP OPERATION -43.8 62.4 37.8, 62.4 60 ACCEPTABLE 2,3 AND 4 PUMP OPERATION N \\ 53.0,80,4 53.0,57.8 53.0, 30.4 40 - 20 - I t I I -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 COOL ANT FLOW (Ih/hr) 137.77 x 1 O6 103.22x 106 67.90 x 1 O6

TR 179 Rev. 0 Page 26 of 32 Figure 9 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance Thermal Power Level, % 120 T -30.0,108.0 24.5,108.0 ml = 1.900 -50.0,70.0 -50.0.4Z6 -50.0,15.1 ACCEPTABLE 4 PUMP 100 OPERATION a -30.0,80.6 24.5,80.6 ACCEPTABLE

3AND4 PUMP OPERATION a

60 -30.0,53a1 24.5,53.1 4 ACCEPTABLE 2, 3 AND 4 PUMP OPERATION 40. m2 = -1.854 45.0.70.0 45.0,42.6 45.0,15.1 0 'rv Alf II 20.1-01 TL 1l 0. I'. N. Al Z& m Ii Ma -80 -70 -60' -50 -40 -30 -20 -10 0 10 20 Axial Power Imbalance, % 30 40 50 60 70 80

TR 179 Rev. 0 Paae 27 of 32

REFERENCES:

1.

BAW-10179P-A. Rev. 4, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," August 2001.

2.

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

3.

BAW-10103A, Rev. 3, 'ECCS Analysis of B&W's 177-FA Lowered Loop NSS," July 1977.

4.

BAW-1915P-A, "Bounding Analytical Assessment of NUREG-0630 Models on LOCA kw/ft Limits with Use of FLECSET," November 1988.

5.

BAW-10104P-A. Rev. 5, "B&W ECCS Evaluation Model," November 1988.

6.

BAW-2447, Rev. 1, "Three Mile Island Unit 1 Cycle 15 Reload Report," September 2003.

TR 179 Rev. O Page 28 of 32 Operating Limits Not Required by Technical Specifications

TR 179 Rev. () Page 29 of 32 Core Minimum DNBR Operating Limit (

Reference:

BAW-2250) The core minimum DNBR value as measured with the NAS Thermal Hydraulic Package (Display 1 or 4) should not be less than 2.02 (102% ICDNBR).

2.

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-B8V LHR to melt = 20.5 kW/ft

3.

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 BWST is required by Technical Specifications 3.3.1.1.a to be available as a source of borated water to meet ECCS LOCA criteria. The T.S. 3.3.1.1.a requirements also ensure that there is a sufficient source of borated water available to bring the reactor to cold shutdown under normal operating conditions. Although not required by T.S., other sources of borated water can be used in lieu of the BWST for the purpose of achieving cold shutdown under normal operating conditions. The minimum boron level needed in the BAMT or RBATs 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.

TR 179 Rev. 0 Page 30 of 32 DNBR-Related Bases Descriptions

TR 179 Rev. 0 Pane31 of 32 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).-7-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.

TR 179 Rcv. O Pane 32 of 32

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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