BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15

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Core Operating Limits Report, Revision 2, Cycle 15
ML053260559
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 11/14/2005
From: O'Neil E
Progress Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 05-0137
Download: ML053260559 (33)
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Text

Progress Energy NOV 1 4 2005 SERIAL: BSEP 05-0137 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325/License No. DPR-71 Core Operating Limits Report (COLR), Revision 2 for Unit 1, Cycle 15 Ladies and Gentlemen:

In accordance with the requirements of Technical Specification 5.6.5.d, Carolina Power &

Light Company, now doing business as Progress Energy Carolinas, Inc. is submitting Revision 2 of the Core Operating Limits Report (COLR) for the Brunswick Steam Electric Plant (BSEP), Unit 1. Technical Specifications 5.6.5.d requires that the Core Operating Limits Report, including any mid cycle revisions or supplements, be provided to the NRC upon issuance.

A copy of the Unit 1, Cycle 15 COLR, October 2005, Revision 2, is provided enclosed.

This revision of the Unit 1, Cycle 15 COLR becomes effective on November 15, 2005.

The enclosed report was revised in response to General Electric's 10 CFR Part 21 Communication SC04-15, "Turbine Control System Impact on Transient Analyses."

Revision 1 of the COLR for BSEP Unit 1, Cycle 15, was submitted by letter dated June 29, 2005 (i.e., Accession Number ML051890080).

There are no regulatory commitments contained in this letter. Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor - Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. ONeil Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas. Inc.

Brunswick Nuclear Plant P.O Box 10429 Southport, NC 28461

Document Control Desk BSEP 05-0137 / Page 2 WRM/wrm

Enclosure:

Brunswick Unit 1, Cycle 15 Core Operating Limits Report, October 2005, Revision 2.

cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATIN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWEN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 cc (without enclosure):

Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

BSEP 05-0137 Enclosure Brunswick Unit 1, Cycle 15 Core Operating Limits Report, October 2005, Revision 2

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. IB21-0625 B I C1 5 Core Operating Limits Report Page 1, Revision 2 BRUNSWICK UNIT 1, CYCLE 15 CORE OPERATING LIMITS REPORT October 2005 Prepared By: Date: M - r Mourad Aissa Approved By: Date: / I -3 '-a George E. Smith Supervisor BWR Fuel Engineering

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. I B21-0625 BIC15 Core Operating Limits Report Page 2, Revision 2 LIST OF EFFECTIVE PAGES Page(s) Revision 1-2 2 3-6 0 7 2 8 0 9 2 10 1 1 0 12 1 13-21 0 22 2 23 0 24 2 25-30 0

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 BIC15 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subiect Paie Cover .1.............................

List of Effective Pages .............................. 2 Table of Contents .............................. 3 List of Tables .............................. 4 List of Figures .................... 4 Introduction and Summary .................... 5 Single Loop Operation .................. 6 Inoperable Main Turbine Bypass System .................. 6 Feedwater Temperature Reduction .................. 7 APLHGR Limits .................. 7 MCPR Limits .................. 7 RBM Rod Block Instrumentation Setpoints .................. 7 Stability Option M .................. 8 References .................. 9

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 BIC15 Core Operating Limnits Report Page 4, Revision 0 CAUTION References to COLR Figures or Tables should be made using titles only; figure and table numbers may change from cycle to cycle.

LIST OF TABLES Table Title Page Table 1: MCPR Limits ................................................................... 10 Table 2: RBM System Setpoints .................................................................... I Table 3: PBDA Setpoints ................................................................... 12 LIST OF FIGURES Figure Title or Description Pave Figure 1: APLHGR Limit Versus Average Planar Exposure ................................................................... 13 Figure 2: APLHGR Limit Versus Average Planar Exposure ................................................................... 14 Figure 3: APLHGR Limit Versus Average Planar Exposure ................................................................... 15 Figure 4: APLHGR Limit Versus Average Planar Exposure ................................................................... 16 Figure 5: APLHGR Limit Versus Average Planar Exposure ................................................................... 17 Figure 6: APLHGR Limit Versus Average Planar Exposure ................................................................... 18 Figure 7: APLHGR Limit Versus Average Planar Exposure ................................................................... 19 Figure 8: APLHGR Limit Versus Average Planar Exposure ................................................................... 20 Figure 9: GE13 and GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) .......................................... 21 Figure 10: GE13 and GE14 Power-Dependent MAPLHGR Limit, MAPLHGR(P) ........................................ 22 Figure 11: GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) .......................................................... 23 Figure 12: GE13 and GE14 Power-Dependent MCPR Limit, MCPR(P) ........................................................ 24 Figure 13: Stability Option III Power/Flow Map: OPRM Operable, Two Loop Operation, 2923 MWt ......... 25 Figure 14: Stability Option III Power/Flow Map- OPRM Inoperable, Two Loop Operation, 2923 MWt ....... 26 Figure 15: Stability Option III Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWt ...... 27 Figure 16: Stability Option III Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt ....28 Figure 17: Stability Option III Power/Flow Map: OPRM Operable, FWTR, 2923 MWt ................................ 29 Figure 18: Stability Option III Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt ............................. 30

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. I1B21-0625 BICl5 Core Operating Limits Report Page 5, Revision 0 Introduction and Summary CAUTION References to COLR Figures or Tables should be made using titles only; figure and table numbers may change from cycle to cycle.

This COLR revision was performed to support Brunswick Unit 1, Cycle 15 operation at up to 2923 MWt. The main changes are those associated with the thermal limits and Power-Flow maps.

This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 1, Cycle 15 as required by TS 5.6.5.

OPERATING LIMIT REQUIREMENT Average Planar Linear Heat Generation Rate (APLHGR) limits TS 5.6.5.a. 1 (with associated core flow and core power adjustment factors)

Minimum Critical Power Ratio (MCPR) limits TS 5.6.5.a.2 (with associated core flow and core power adjustment factors)

Period Based Detection Algorithm (PBDA) Setpoint for Function 2.f of TS 3.3.1.1, TS 5.6.5.a.3 Oscillation Power Range Monitor (OPRM)

Allowable Values and power range setpoints for Rod Block Monitor Upscale TS 5.6.5.a.4 Functions of TS 3.3.2.1 Per TS 5.6.5.b and 5.6.5.c, these values have been determined using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The limits specified in this report support single loop operation (SLO) as required by TS LCO 3.4.1 and inoperable Main Turbine Bypass System as required by TS 3.7.6.

In order to support the Stability Option m with an inoperable OPRM scram function, the following is also included in this report:

OPERATING LIMIT l REQUIREMENT BWROG Interim Corrective Action Stability Regions TS 3.3.1.1 LCO Condition I This report conforms to Quality Assurance requirements as specified in Reference 1.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 B I C15 Core Operating Limits Report Page 6, Revision 0 Single Loop Operation Brunswick Unit 1, Cycle 15 may operate over the entire MEOD range with Single Recirculation Loop Operation (SLO) as permitted by TS 3.4.1 with applicable limits specified in the COLR for TS LCO's 3.2.1, and 3.2.2. The applicable limits are:

LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: per Reference I, the Figures 9 andlO described in the APLHGR Limits section below include a SLO limitation of 0.8 on the MAPLHGR(F) and MAPLHGR(P) multipliers.

LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: per Reference 1, Table I and Figures II and 12, the MCPR limits presented apply to SLO without modification.

Various indicators on the Power/Flow maps are provided not as operating limits but rather as a convenience for the operators: a single loop operation (SLO) Entry Rod Line is shown on the two loop operation maps to avoid regions of instability in the event of a pump trip; a maximum core flow line is shown on the single loop operation maps to avoid vibration problems; and APRM STP Scram and Rod Block nominal trip setpoint limits are shown at the estimated core flow corresponding to the actual drive flow-based setpoints to indicate where the operator may encounter these setpoints (LCO 3.3.1.1, Reactor Protection System Instrumentation Function 2.b (Average Power Range Monitors Simulated Thermal Power - High Allowable Value).

Inoperable Main Turbine Bvpass Svstem Brunswick Unit I, Cycle 15 may operate with an inoperable Main Turbine Bypass System in accordance with TS 3.7.6 with applicable limits specified in the COLR for TS LCO 3.2.1 and 3.2.2.

Two or more bypass valves inoperable renders the System inoperable, although the Turbine Bypass Out-of-Service (TBPOOS) analysis supports operation with all bypass valves inoperable for the entire MEOD range and up to 11 0IF rated equivalent feedwater temperature reduction. The system response time assumed by the safety analyses from event initiation to start of bypass valve opening is 0.10 seconds, with 80% of the bypass flow capacity achieved in 0.30 seconds. The applicable limits are as follows:

LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: in accordance with Reference I as shown in Figure 10, TBPOOS does not require an additional reduction in the MAPLGHR(P) limits, as the Turbine Bypass Operable and Inoperable limits are identical.

LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: in accordance with Reference I, TBPOOS does not require an additional increase in the MCPR(P) multiplier as shown in Figure 12, as the Turbine Bypass Operable and Inoperable limits are identical. TBPOOS requires increased MCPR limits, included in Table 1.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 B IC1 5 Core Operating Limits Report Page 7, Revision 2 Feedwater Temperature Reduction A variation within 10 F of nominal feedwater temperature has been evaluated as in compliance with normal operating limits. A feedwater temperature reduction of > I OF requires the use of FWTR MCPR limits (Table 1) and Stability Option m limits (Figures 17 and 18).

APLHGR Limits The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures 1 through 8. These values were determined with the SAFER/GESTR LOCA methodology described in GESTAR-il (Reference 2).

Figures 1 through 8 are to be used only when hand calculations are required as specified in the bases for TS 3.2.1. Hand calculated results may not match a POWERPLEX calculation since normal monitoring of the APLHGR limits with POWERPLEX uses the complete set of lattices for each fuel type provided in Reference 3. The core flow and core power adjustment factors for use in TS 3.2.1 are presented in Figures 9 and 10. For any given flow/power state, the minimum of MAPLHGR(F) determined from Figure 9 and MAPLHGR(P) determined from Figure 10 is used to determine the governing limit. Figure 10 was revised to include limits derived from Reference 11 for the power range 23% < P < 40%.

MCPR Limits The Scram Speed MCPR OPTION A, OPTION B, and non-pressurization transient MCPR limits for use in TS 3.2.2 for each fuel type as a function of cycle average exposure are given in Table 1.

These values were determined with the GEMINI(TRACG) methodology and GEXL-PLUS critical power correlation described in GESTAR-il (Reference 2), and are consistent with a Safety Limit MCPR of 1.11 specified by TS 2.1.1.2. The core flow and core power adjustment factors for use in TS 3.2.2 are presented in Figures I1 and 12. For any given power/flow state, the maximum of MCPR(F) determined from Figure 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit. Figure 12 was revised to include limits derived from Reference 11 for the power range 23% < P < 40%. All MCPR limits presented in Table 1, Figure 11 and Figure 12 apply to two recirculation pump operation and SLO without modification.

RBM Rod Block Instrumentation Setpoints The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in TS 3.3.2.1 (Table 3.3.2.1-1) are presented in Table 2. These values were determined to be consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI(TRACG) methodology and the GEXL-PLUS critical power correlation described in GESTAR-il (Reference 2). Reference 8 revised certain of these setpoints to reflect changes associated with the installation of the NUMAC PRNM system. The table also includes information

b. +;

,I PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. I B21-0625 B ICl 5 Core Operating Limits Report Page 8, Revision 0 regarding required operability of the RBM, consistent with Technical Specification Table 3.3.2.1-1.

Stabilitv Option 1II Brunswick Unit 1 has implemented BWROG Long Term Stability Solution Option m (Oscillation Power Range Monitor-OPRM) with the methodology described in Reference 4. Plant specific analysis incorporating the Option mII hardware is described in Reference 5. Reload validation has been performed in accordance with Reference 6. The resulting stability based MCPR Operating Limit is provided for two conditions as a function of OPRM amplitude setpoint in Table 3. If desirable, Table 3 would support higher stability limits for various MCPR operating limits greater than the least limiting Table I AOO OLMCPR values, but the suggested stability setpoints are bounded by Table 1. Table 3 shows that OLMCPR(SS) is never as limiting as Figure 11 for any listed OPRM setpoint (Amplitude Setpoint Sp). Table 3 also shows that OLMCPR(2PT) is never as limiting as Table 1 for an OPRM setpoint of 1.13. Therefore the OPRM PBDA setpoint limit referenced by function 2.f of Table 3.3.1.1-1 of Technical Specification 3.3.1.1 is 1.13 for Cycle 15.

Per Table 3-2 of Reference 6, an Sp value of 1.13 supports selection of a Confirmation Count Setpoint Np of 15 or less.

Six Power/Flow maps for use at up to 2923 MWt (Figures 13-18) were developed based on References 1 and 7 to facilitate operation under Stability Option III as implemented by function 2.f of Table 3.3.1.1-1 and LCO Condition I of Technical Specification 3.3.1.1. All six maps illustrate the region of the power/flow map above 25% power and below 60% flow where the system is required to be enabled.

The maps supporting an operable OPRM function 2.f (Figures 13, 15 and 17) show a Scram Avoidance Region, which is not a licensing requirement but is an operator aid to illustrate where the OPRM system may generate a scram to avoid an instability event. Figures 13 and 15 differ only in that the Figure 15 that supports SLO, indicates the maximum allowable core flow at 45 Mlbs/hr, and has the Simulated Thermal Power (STP) scram and rod block limits appropriately reduced for SLO.

Note that the STP scram and rod block limits are defined in Technical Specifications, the Technical Requirements Manual, and Plant procedures, and are included in the COLR as an operator aid rather than a licensing requirement. Figure 17 differs from Figure 13 by extending the existing regions to provide additional stability protection during FWTR. Intentional operation with SLO and FWTR is prohibited.

The maps (Figures 14 and 16) supporting an inoperable OPRM function 2.f show the BWROG-94078 Interim Corrective Actions stability regions required to support LCO Condition I.

Both figures also include a 5% Buffer Region around the Immediate Exit Region as an operator aid.

Figures 14 and 16 differ only in that the Figure 16 that supports SLO, indicates the maximum allowable core flow at 45 Mlbs/hr, and has the STP scram and rod block limits appropriately reduced for SLO. Figure 18 differs from Figure 14 by extending the existing regions to provide additional stability protection during FWTR. Intentional operation with SLO and FWTR is prohibited.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 BI Cl5 Core Operating Limits Report Page 9, Revision 2 References

1) BNP Design Calculation IB21-0625; "Preparation of the BIC15 Core Operating Limits Report,"

Revision 2, October 2005.

2) NEDE-2401 1-P-A; "General Electric Standard Application for Reactor Fuel," (latest approved version).
3) NEDC-31624P, "Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit I Reload 14 Cycle 15," Supplement 1, Revision 8, February 2004.
4) NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology,"

November 1995.

5) GE-NE-C51-00251-00-01, Revision 0, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick I and 2," March 2001.
6) NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application," August 1996.
7) Design Calculation 0B21-1015, Revision 2, "BNP Power/Flow Maps for Stability Option III,"

July 2003.

8) Design Calculation IC51-0001 Revision 2, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (I-C51-APRM I through 4 Loops and I -C5 I-RBM-A and B Loops," October 2003.
9) NEDE-32906P-A, Revision 1, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," April 2003.
10) GE-NE-0000-0022-8180-RO, "Brunswick Nuclear Station TRACG Implementation for Reload Licensing Transient Analysis," February 2004.
11) GE-NE-0000-0036-9469-RO, Revision 0, "Brunswick 1 and 2 Off-Rated Analyses Below the PLU Power Level," June 2005.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 BICI5 Core Operating Limits Report Page 10, Revision I Table I MCPR Limits Non-pressurization Transient MCPR Limits FuelType Exposure Range: DOC -EOC GE13 & GE14 r1.28 Pressurization Transient MCPR Limits 100% Power OLMCPR Turbine Feedwater Scram Exposure Range: Exposure Range:

Bypass Temperature Fuel Type Speed System Normal? MCPR BOC to EOFPC-5029 MWd/MT Operable? Option EOFPC-5029 MWd/MT to EOC Operable Normal GE13 & GE14 A 1.51 1.56 B 1.33 1.38 Operable Reduced GE13 & GE14 A 1.51 1.56 B 1.33 1.38 Inoperable Normal GE13 & GE14 A 1.60 1.60 B 1.42 1.42 Inoperable Reduced GE13 & GE14 A 1.66 1.66 B 1.48 1.48 This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 BICIS Core Operating Limits Report Page 11, Revision 0 Table 2 RBM System Setpoints Setpointl Trip Setpoint J Allowable Value Lower Power Setpoint (LPSPb) 27.7

  • 29.0 Intermediate Power Setpoint (IPSP ) 62.7 l 64.0 High Power Setpoint (HPSPb) 82.7 l 84.0 Low Trip Setpoint (LTSPC)
  • 114.1
  • 114.6 Intermediate Trip Setpoint (ITSPC)
  • 108.3 < 108.8 High Trip Setpoint (HTSPC)
  • 104.5
  • 105.0 RBM Time Delay (td2) 2.0 seconds
  • 2.0 seconds a RBM Operability requirements are not applicable:

(1) if MCPR 2 1.70; or (2) if MCPR 2 1.45 and thermal power 2 90% Rated Thermal Power.

b Setpoints in percent of Rated Thermal Power.

C Setpoints relative to a full scale reading of 125.

For example,

  • 114.1 means
  • 114.1/125.0 of full scale.

This Table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1).

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-0625 B I C15 Core Operating Limits Report Page 12, Revision I Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS) OLMCPR(2PT) 1.05 1.2375 1.0925 1.06 1.2651 1.1169 1.07 1.2940 1.1424 1.08 1.3243 1.1691 1.09 1.3559 1.1971 1.10 1.3892 1.2264 1.11 1.4224 1.2558 1.12 1.4573 1.2866 1.13 1.4940 1.3190 1.14 1.5325 1.3530 1.15 1.5731 1.3888 Acceptance Criteria Off-rated OLMCPR @ Rated Power OLMCPR 45% Flow PDBA Setpoint Setpoint Value Amplitude Sp 1.13 1.14 1.15 Confirmation Count Np 15 16 16 This Table is referred to byTechnical Specification 3.3.1.1 (Table 3.3.1.1-1).

I ,

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 13, Revision 0 Figure 1 Fuel Type GE13-P9DTB405-5G6.017G5.0-1OOT-146-T-2378 (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 13.0 _ _ l4 1 1I 12.0 I This Figure is Referred To By Technical Specification 3.2.1 I

IExposure Limit 11.0 (GWdIMt) (kW/ft) 0.00 10.71 0.22 10.78 1.10 10.91 I--

10.0I 2.20 11.08 3.31 11.22 4.41 11.35 5.51 11.47 PemsilI__

E Region o

6.61 11.61 Oprto 11.75

-s 9.0 1 7.72 8.82 11.89 EL 9.92 12.04 11.02 12.18

\ _ ME,,

13.78 12.17 8.0 16.53 12.02 19.29 11.82 22.05 11.58 27.56 11.17 33.07 10.60 7.0 38.58 10.18 44.09 9.82 49.60 9.49 55.12 9.19 6.0 60.63 8.81 64.74 8.51 5.0 l I ,I I I I I I-0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 14, Revision 0 Figure 2 Fuel Type GE13-P9DTB402-13G6.01 G2.0-0OT-146-T-2379 (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 3 10.0 CD

-j 9.0 8.0 7.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 15, Revision 0 Figure 3 Fuel Type GE14-PIODNAB4416-17GZ-1OOT-150-T-2496 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 - U p * - p- p- U I u . I U I I 7*I .

This Figure is Referred To By 11.0 , w

,{ B I Technical Specification 3.2.

Exposure

/

Limit (GWd/Mt) (kW/Rt)

IN 0.00 9.27 10.0 7

0.22 9.33 1.10 9.44 2.20 9.59 3.31 9.76 4.41 9.93 9.0 5.51 t0.tt 6.61 t0.30 *iI 7.72 to.50 I-- 8.82 10.71 9.92 10.91 8.0-I 11.02 11.12 12.13 11.31

-j 13.23 11.36 14.33 11.35 15.43 11.34 7.0 .- 16.53 11.31 18.74 11.23 Region of\ i 22.05 11.03 Operation t 27.56 10.60 33.07 10.12 6.0 - 38.58 44.09 49.60 55.12 9.49 8.91 8.37 7.87 I

60.63 6.53 5.01 64.27 4.88 4.0 - I I i I 1 I - U I - I - p- S a a-0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 16, Revision 0 Figure 4 Fuel Type GE14-PIODNAB425-16GZ-1OOT-150-T-2497 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 8.0 s:

I)

(L 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0625 B1C15Core Operating Limits Report Page 17, Revision 0 Figure 5 Fuel Type GE14-PlODNAB438-12G6.0-10OT-150-T-2498 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 I.-

-j 8.0 w

-j 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 BiC15 Core Operating Limits Report Page 18, Revision 0 Figure 6 Fuel Type GE14-PIODNAB413-16GZ-10OT-150-T-2660 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 . - i I - . m i

11.0

,*14 This Figure is Referred To ByI 1Technical Specification 3.2.1 -

jf N Exposure Limit (GWd/Mt) (kW/ft) X 10.0 / 0.00 1.10 9.57 9.66 K 2.20 9.77 I I I 3.31 9.92 CI 4.41 10.08 5.51 10.26 9.0 -

l 6.61 10.44 7.72 10.59 8.82 10.74 9.92 10.87

% 11.02 11.00 8.0- 12.13 11.12 13.23 11.15

-j C, 14.33 11.16 0~ 15.43 11.16 15.99 11.16 16.53 11.16 _ I 7.0 -1 18.74 11.13 21.09 11.02 22.05 10.98 27.56 10.57 33.07 10.15 6.0 38.58 9.65 44.09 9.12 49.60 8.59 55.12 8.04 60.63 6.48 5.0 63.50 5.18 I 64.16 4.88

_ . I, I I I 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

I '. . I PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 19, Revision 0 Figure 7 Fuel Type GE14-PlODNAB429-18GZ-10OT-150-T-2661 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 I.-

8.0

-i 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Cabc. No. 1B21-0625 BIC15 Core Operating Limits Report Page 20, Revision 0 Figure 8 Fuel Type GEI4-PIODNAB437-12G6.0-1OOT-150-T-2662 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 U - I - I - I - p- I

  • p- p- p- . p p- p This Figure is Referred To By 11.0 [Technical Specification 3.2.1 _

I I 10.0 .1- I IA 1 JOUI m ;..,,;

I1E. "L I

.1 (GWdIMt) (kWlft) 9.06

/

0.00 1.10 9.20 2.20 9.31 9.0 3.31 9.43 4.41 9.55 5.51 9.68 I- 6.61 9.81 7.72 9.95 8.0 1 8.82 10.09

-j 9.92 10.23 11.02 10.38 12.13 10.45 Cl!

IL 13.23 10.48 Permissible 7.0 1 1 14.33 10.51 15.43 10.54 Region of - \ I 15.99 10.55 Operation 16.53 10.56 ILX 18.74 10.56

-- 1 21.09 10.49 6.0 22.05 10.47 27.56 10.20 33.07 9.87 38.58 9.42 44.09 8.95 5.0 49.60 8.45 55.12 7.91 60.63 5.56 62.02 4.91 t - i l 4.0 - I I - P- I - I - I m I -

0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Ahalysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 21, Revision 0 Figure 9 GE13 and GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 1.05 ]

I I I I This Figure is Referred To By - n Technical Specifications TWO Loop Operation Limit I 1.00 - I-__I 3.2.1, 3.4.1 and 3.7.6 I I I I I I .

7 V I 0.95 -

I I I I Max Flow = 102.5%

107% N K7'4, 7

7

-U 0.90 1 112% 7 117%

C)

IL

< 0.85 9-

/*0 / L.i.1.-L.L.

44j4 - 4. 4. ! 4. 4. 4

.Single Loop Operation Limit -

7 70o 777-r TT L.n m 0.80 / / ) .

IL W_

0~ 0.75 C 0.70 a) 3 MAPLHGR(F) = MAPFACF

MAPLHGRsTD = Standard MAPLHGR Limits D(C0.65 MAPFACF(F) = Minimum (1.0, AFVCSIOO+BF) 0 NVc = % Rated Core Flow 0

U: 0.60 AF And BF Are Fuel Type Dcpendent Constants Given Below:

Max Core Flow 0.55 (% Rated) AF BF 102.5 0.6784 0.4861 107.0 0.6758 0.4574 0.50 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.45 nAn 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design CaIc. No. 1B21-0625 B1C15 Core Operating Limits Report I r ., Page 22, Revision 2 Figure 10 GE13 and GE14 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.05 I--

1.00 - J I I I 1 This Figure is Referred To By Technical Specifications I 0.95 3.2.1, 3.4.1r and 3.7.6 _i

- - - - - - I I i I i i :i _ i 0.90 3 0.85 Two Loop Operation U-

0.80 IL Core IlwSingle Loop Operation LimitJ 0~

2 0.70 A PLHGR(P) MAPFACp

(

LL 0.65 c MAPLHGRSTD = Standard MAPLHGR Limits

-J aa.

<0. 0.60 _ For P < 23%:

la 0.55 lCore Flow> 65% No Thermal Limits Monitoring Required I_

0 For 23% s P < 26%, Turbine Bypass Operable or Inoperable:

1gL 0.50 MAPFACp= 0.433 + 0.0063 (P-26%)

0.45 For 26% s P < 40%, Core Flow 565%:

, MAPFACp = 1.0 + 0.005224 (P-100%)

For 26% 5 P < 40%, Core Flow > 65%:

0.40 MAPFACp =0.634 + 0.0035 (P-40%)

No Flow Restriction Fo P> 40 0.35 Turbine Bypass For P2 40%

Operable or Inoperable MAPFACp = 1.0 + 0.005224 (P-100%)

0.30 I 20 2 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Pbypass (26%)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 23, Revision 0 Figure 11 GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1.70 1.60 IL 1.50 1.40 1.30 1.20 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

  • 1' . . - 1 PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Figure 12 Page 24, Revision 2 GE13 and GE14 Power - Dependent MCPR Limit, MCPR (P) 3.8000 3.7000 I I I I II I iI OLMCPR__ Rated MCPR Multiplier (Kp) _-

3.6000 3.5000 I1 11 1 '-= 1 1 1 1 I- -

3.4000 No Flow Restrction I I I I I v Turbine Bypass 3.3000 7` Operable or Operating Limit MCPR:

Inoperable OLMCPR(P) = Kp*OLMCPR(1 00) 3.2000

% -- 7--T I 0 3.1000 For P < 23%:

V No Thermal Limits Monitoring Required

.. 3.0000 _ _

VI For 23% P < PBypAss: Where PBYPASS = 26%

gZ 2.9000 Turbine Bypass Operable or Inoperable N 2.8000 2 2.7000 OLMCPR(P)= [3.13+ 0.0900(26% - P)]

I 2.6000 r Core Flow>65% _

o 2.5000 For 26% 5 P < 40% Core Flow s 65%:

OLMCPR(P) = 1.88 + 0.0129 (40% - P) 2.4000 For 26% s P < 40% Core Flow > 65%:

2.3000 - r- - - - -

OLMCPR(P) = 2.10 + 0.0157 (40% - P) 2.2000 2.1000 - z zl zZ-z -

For 40 s P < 45%:

Kp= 1.28 + 0.0135 (45% - P)

, 2.0000 For 45% < P < 60%:

Al 1.9000 Kp = 1.18+ 0.00667 (60% - P)

A-1.8000 ore Flow >65% For P 2 60%:

, 1.7000 Kp = 1.00 + 0.00450 (100% - P) cL 1.6000 1.5000

= 1.4000 I =This Figure is Referred To By g 1.3000 Technical Specification o 1.2000 I _ 3.2.2, 3.4.1, 3.7.6 n 1.1000 cy 1.0000 20 21 30 35 40

I

~.

45 50 55 I I I1II1 60 65 70 75 80 85 90 95 100 Pbypass (26%) Power (% Rated)

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 13 Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 25, Revision 0 OPRM Operable, Two Loop Operation, 2923 MWt 120.0 This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I M Inim um Maximum (MELLL) (IC F)

Core Core 110.0 Power Flow, Flow.

% Mlb/.hr M Ibslhr 100 76.19 80.47 100.0 99 75.04 8047 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90.0 95 70.49 90.47 94 6936 90.47 93 68.25 80.47 92 67.13 80.47 80.0 91 90 69.03 64.93 80.47 90.47 89 63.83 80.47 88 62.74 80.47 87 81.66 80.51 70.0 86 60.59 80.60 85 59.50 80.70 I 84 58.43 80.79 83 57.37 80.90 60.0 82 58.31 81.05

a. 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 61.67 77 51.08 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 73 48.98 82.44 72 45.96 82.60 71 44.95 82.79 30.0 70 69 43.94 42.94 82.91 83.06 66 41.94 83.21 67 40.95 83.37 20.0 66 65 39.96 38.97 83.52 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 10.0 61 35.06 84.29 60 34.10 84.45 59 33.13 84.60 58 32.17 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow COI

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 14 Design Calc. No. 1B21-0625 B1 C1 5 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 26, Revision 0 I

OPRM Inoperable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minim um Maximum (M ELLL) (IC F)

Core Core 110.0 Power Flow. Flow,

% M lbslhr M lb s/hr 100 76.19 80.47 100.0 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90.0 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 80.0 91 90 66.03 64.93 80.47 80.47 89 63.83 80.47 88 92.74 80.47 70.0 87 86 61.66 60.58 80.51 80.60 85 69.50 80.70 84 58.43 80.79 83 57.37 80.90 i 60.0 82 56.31 81.05 0.o 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.67 77 51.08 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 30.0 70 43.94 82.91 69 42.94 83.06 68 41.94 83.21 67 40.95 83.37 20.0 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 10.0 62 36.04 84.14 61 35.06 84.29 60 34.10 84.45 59 33.13 84.60 0.0 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow C (7Z

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 15 Design Caic. No. 1B21-0625 B1 C1 5 Core Operating Limits Report Stability Option III Power/Flow Map Page 27, Revision 0 OPRM Operable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 120.0 and the Technical Requirements Manual Specification 3.3 1 M In Im um M axim un (M ELLL) (ICF)

Core Core 110.0 Power Flow, Flow,

% U lb/lhr M lbs/hr 100 76.19 80.47 100.0 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90.0 95 70.49 80.47 94 689.36 80.47 93 68.25 80.47 92 67.13 80.47 80.0 91 90 66.03 64.93 80.47 80.47 89 63.83 80.47 88 62.74 80.47 70.0 87 86 61.86 60.58 80.51 80.60 85 59.50 80.70 84 58.43 80.79 6

0 60.0 83 82 57.37 56.31 80.90 81.05 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.87 77 51.08 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 82.44 72 45.986 82.60 71 44.95 82.75 30.0 70 43.94 82.91 689 42.94 83.06 68 41.94 83.21 67 40.95 83.37 20.0 66 39.96 83.52 65 38.97 83.68 84 37.99 83.83 63 37.01 83.99 10.0 62 36.04 84.14 61 35.06 84.29 60 34.10 84.45 59 33.13 84.60 0.0 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow C03

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 16 Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 28, Revision 0 OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 M Inim urn Maxim urn (M ELLL) (IC F )

Core C are 110.0 Pow or Flow, Flow, U lbs/hr M lbs/hr 100 76.19 80.47 99 75.04 8 0.4 7 100.0 98 73.89 80.47 97 72.75 8 0.4 7 96 7 1.6 1 80.47 95 70.49 80.47 90.0 94 69.36 80.4 7 93 68.25 80.47 92 67.13 8 0 .4 7 91 66.03 80.47 80.0 90 64.93 80.47 89 63.8 3 80.47 88 62.74 80.47 87 61.66 80.5 1 70.0 86 60.568 80.60 85 59.50 80.70 a 84 568.4 3 80.79 83 57.37 80.90 0

a. 60.0 82 56.31 81 .05 81 55.25 81.2 1 80 54.20 8 1.36 79 53.16 8 1.52 50.0 78 52.12 81.67 77 5 1 .08 81.83 76 50.05 81 .98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 62.44 72 45.96 82 .60 71 44.95 62.75 30.0 70 69 43.94 42.94 82.9 1 83.06 68 41 .94 63.2 1 67 40.95 63.37 20.0 66 65 39.96 36.97 83.52 83.68 64 37.99 83.83 63 37.01 83.99 10.0 62 61 36.04 35.06 84.14 84.29 60 34.10 84.45 59 33.13 84.60 0.0 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % CoreFlow

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 17 Design CaIc. No. 1B21-0625 B1C15 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 29, Revision 0 OPRM Operable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 M inim um M axim um (M ELLL) (IC F)

Cure Cure 110.0 Power Flow, Flow,

% M lb*br M Ibslhr 100 76.19 80.47 100.0 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90.0 95 94 70.49 69.38 80.47 80.47 93 89.25 80.47 92 67.13 80.47 80.0 91 90 66.03 64.93 80.47 80.47 89 63.83 80.47 89 62.74 80.47 87 61.66 80.51 70.0 86 60.58 80.60 85 59.50 80.70 S 84 58.43 80.79 83 57.37 80.90 0 60.0 82 56.31 81.05

a. 61 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.67 77 51.08 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 30.0 70 69 43.94 42.94 82.91 83.08 68 41.94 83.21 67 40.95 83.37 20.0 66 65 39.96 38.97 83.52 83.68 64 37.99 83.93 63 37.01 83.99 62 36.04 10.0 61 35.06 84.14 84.29 59 33.13 84.60 58 32.17 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow c05

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 18 Design Calc. No. 11B21-0625 B1C15 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 30, Revision 0 OPRM Inoperable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0- Min imum Max imum (MEL LL) (IC F) 110.0ale MST C ore Coare Power Flow, Flow,

.5i eARodSTP cl  % M lbslhr MIbsthr 1n nf Region100 76.19 80.47 i 11 I - 99 75.0 80.47 798 7 3.8 9 80.4 7 97 7 2.7 5 80.4 7 88 71.61 80.4 7 90 - 0 .4 9 8 0.4 a 0 7

Regin A - Mana 1 .94 69.36 80.47 93 9825 80.4 7 9,.2 67 .13 80.47 o0. - 91 66.03 80.47 6493 4 .90 90.47 6274 .88 80.47 70.0 87 91.8 6 8a0.51I

. .f l-il~llliilli e.lii!-',9 6 60.58 80.90 95 5.50 80.7 0 84 58.43 80.79 83 5 7.3 7 809 81 55.25 81.21 60 5 4.2 0 8139 50079 5 3.1 6 81.52 5 H i77 7 78 52.1 2 51I.0 8 8i.

8.3 7

76 5 0.0 5 81.98 75 49.2 82.13 40.0 MELLL Line 111111 11  : 74 4 95 822 49 73 4.9 82.44 30.0 .. MII .IH 0 4

.9 4294 832.0

-- 11MT41.94 68l 83.2

-T67 4 0.9 5 8 3.3 7 20.0 4# 66 39.96 83.52 Natural 65 39.97 83.6 8 Circulation 64 6iclto 3 337.99 7.0 1 83.83 8 3.9 9 6002 3 6.0 4 84.14 35%Mi imumPump Speed Minimum Power ine 61 3 5.06 84.29 59 3 3.1 3 84,6 0 nl56 3 2.1 7 8 4.7 0 I 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow

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