BSEP-05-0139, Core Operating Limits Report (Colr), Revision 1 for Unit 2, Cycle 17

Core Operating Limits Report (Colr), Revision 1 for Unit 2, Cycle 17

ML053330287
Person / Time
Site:	Brunswick
Issue date:	11/21/2005
From:	O'Neil E Progress Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP-05-0139
Download: ML053330287 (34)

Text

ao Progress Energy NOV 2 P2005 SERIAL: BSEP 05-0139 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 2 Docket No. 50-324/License No. DPR-62 Core Operating Limits Report (COLR), Revision 1 for Unit 2, Cycle 17 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 1 of the Core Operating Limits Report (COLR) for the Brunswick Steam Electric Plant (BSEP), Unit 2. 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 2, Cycle 17 COLR, November 2005, Revision 1, is enclosed. This revision of the Unit 2, Cycle 17 COLR becomes effective on November 22, 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 0 of the COLR for BSEP Unit 2, Cycle 17, was submitted by letter dated March 28, 2005 (i.e., Accession Number ML050910206).

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 05-0139 / Page 2 WRM/wrm

Enclosure:

Brunswick Unit 2, Cycle 17 Core Operating Limits Report, November 2005, Revision 1 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: 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)

ATIN: Ms. Brenda L. Mozafari (Mail Stop OWFN 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 05-0139 Enclosure Brunswick Unit 2, Cycle 17 Core Operating Limits Report, November 2005, Revision 1

I I NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-1064 B2C17 Core Operating Limits Report Page 1, Revision I BRUNSWICK UNIT 2, CYCLE 17 CORE OPERATING LIMITS REPORT November 2005

__ . j .

p.

.- .I Prepared By: Date: i49- 300 S Mourad Aissa Approved By: Date: //1 7-0 .-

(Pt.aj)

George . Smith Supervisor BWR Fuel Engineering

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 2, Revision 1 LIST OF EFFECTIVE PAGES Page(s) Revision 1 -2 1 3-6 0 7 1 8-9 0 10 1 11-22 0 23 1 24 0 25 1 l

26 -31

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subject Page 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 APLH.GR Limits ..........  ;.7 MCPR Limits ........... 7 RBM Rod Block Instrumentation Setpoints .............................. 8 Stability Option I .............................. 8 Power/Flow Maps .............................. 8 References ............................. 10

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1 064 B2C17 Core Operating Limits 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 Pane Table 1: MCPR Limits ..................................... I Table 2: RBM System Setpoints .................................... 12 Table 3: PBDA Setpoints .................................... 13 LIST OF FIGURES Figure Title or Description Page Figure 1: APLHGR Limit Versus Average Planar Exposure .................................... 14 Figure 2: APLHGR Limit Versus Average Planar Exposure .................................... 15 Figure 3: APLHGR Limit Versus Average Planar Exposure .................................... 16 Figure 4: APLHGR Limit Versus Average Planar Exposure .................................... 17 Figure 5: APLHGR Limit Versus Average Planar Exposure .................................... 18 Figure 6: APLHGR Limit Versus Average Planar Exposure .................................... 19 Figure 7: APLHGR Limit Versus Average Planar Exposure ..................................... 20 Figure 8: [not used] .................................... 21 Figure 9: Flow-Dependent MAPLHGR Limit, MAPLHGR(F) .................................... 22 Figure 10: Power-Dependent MAPLHGR Limit, MAPLHGR(P) ............................................. 23 Figure 11: Flow-Dependent MCPR Limit, MCPR(F) .24 Figure 12: Power-Dependent MCPR Limit, MCPR(P) .25 Figure 13: Stability Option III Power/Flow Map: OPRM Operable, Two Loop Operation, 2923 MWt ......... 26 Figure 14: Stability Option m Power/Flow Map: OPRM Inoperable, Two Loop Operation, 2923 MWt ....... 27 Figure 15: Stability Option ImPower/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWt ...... 28 Figure 16: Stability Option m Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt .... 29 Figure 17: Stability Option m Power/Flow Map: OPRM Operable, FWTR, 2923 MWt ............................... 30 Figure 18: Stability Option III Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt ............................. 31

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 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 2, Cycle 17 operation at up to

- - - --- I a

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 2, Cycle 17 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 LIMT 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.

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 6, Revision 0 Sinele Loop Operation Brunswick Unit 2, Cycle 17 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 1, the Figures 9 and 10 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 1 and Figures 11 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 to illustrate where these setpoints occur. Note that the APRMSTP setpoints are only approximations,shown at the estimatedcoreflow correspondingto the actual driveflow-basedsetpoints. The approximationsserve to indicate where the operatormay encounter theAPRMSTPsetpoints (LCO 3.3.1.1. ReactorProtectionSystem InstrumentationFunction 2.b (Average PowerRangeMonitorsSimulated Thermal Power - High Allowable Value)).

Inoperable Main Turbine Bypass Svstem Brunswick Unit 2, Cycle 17 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.

Three 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 110F 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 1, 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.

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 7, Revision 1 Feedwater Temperature Reduction A variation within 1OT of nominal feedwater temperature or a power level less than 30% rated has been evaluated as in compliance with normal feedwater temperature operating limits. A feedwater temperature reduction of > 1O0 together with reactor power of at least 30% rated requires the use of FWTR MCPR limits (Table 1) and Stability Option III 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 7. These values were determined with the SAF.ER/GESTR LOCA methodology described in GESTAR-Il (Reference 2).

Figures 1 through 7 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 10 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 GEXL14 critical power correlation described in GESTAR-il (Reference 2) without assuming EOC-RPT, 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 11 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 10 for the power range 23% < P < 40%.

All MCPR limits presented in Table 1 and Figure 11 and Figure 12 apply to two recirculation pump operation and SLO without modification.

NGG Nuclear Fuels Mgmt. &Safety Analysis Design Calc. No. 2B21-1064 B2C1 7 Core Operating Limits Report Page 8, Revision 0 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 GEM!INI(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 regarding required operability of the RBM, consistent with Technical Specification Table 3.3.2.1-1.

Stability Option III Brunswick Unit 2 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 m 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 higherstability limitsfor various MCPR operating limits greater than the least limiting AOO OLMCPR values (from Table I or Figures11 or 12), but the suggested stability setpoints ensure no OLMCPR restrictionsfrom Option III. Table 3 shows thatfor an OPRM setpoint (Amplitude Setpoint Sp) of 1.13, OLMCPR(SS) is less restrictive than Figure11 at 45%

maximiumflow or Figure12 at 60.6% maximum power. Table 3 also shows that OLMCPR(2PT) is less restrictive than any limiting Table I OLMCPRfor 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 17. PerTable 3-2 of Reference 6, an Sp value of 1.13 supports selection of a Confirmation Count Setpoint Np of 15 or less.

Stability Option m also affects the power/Flow maps as described below.

Power/Flow Maps 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 mIas 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% drive flow (which is approximately 63-64% core flow) where the system is required to be enabled. Note that the power/flow maps can only approximatethe licensed EnabledRegion, because the maps display coreflow, while the EnabledRegion is based on driveflow.

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

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C1 7 Core Operating Limits Report Page 9, Revision 0 has the Simulated Thermal Power (STP) scram and rod block limits appropriately reduced for SLO.

Note that the ST? 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.

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 10, Revision 1 References

1) BNP Design Calculation 2B21-1064; "Preparation of the B2C17 Core Operating Limits Report," Revision 1, November 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 1 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 1 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 OB21-1015, Revision 3, "BNP Power/Flow Maps," February 2005.

8) Design Calculation 2C51-0001 Revision 3, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (2-C5 1-APRM 1 through 4 Loops and 2-C51-RBM-A and B Loops," 5/26/04

9) NEDE-32906P-A, Revision 1, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," April 2003.

10) GE-NE-0000-0036-9469-RO, Revision 0, "Brunswick 1 and 2 Off-Rated Analyses Below the PLU Power Level," June 2005.

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1064 B2C17 Core Operating Limits Report Page I, Revision 0 Table 1 MCPR Limits (EOC RPT not required)

Non-pressurization Transient MCPR Limits Fuel Type Exposure Range: BOC - EOC GE14 1.26 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-3145 MWd/MT Operable? Option EOFPC-3145 MWd/MT to EOC Operable Normal GE14 A 1.51 1.55 B 1.33 1.37 Operable Reduced GE14 A 1.51 1.55 B 1.33 1.37 Inoperable Normal GE14 A 1.58 1.58 B 1A0 1.40 Inoperable Reduced 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.

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Cabc. No. 2B21-1064 B2C17 Core Operating Limits Report Page 12, Revision 0 Table 2 RBM System Setpoints Setpointa Trip Setpoint Allowable Value Lower Power Setpoint (LPSPb) 27.7

• 29.0 Intermediate Power Setpoint (IPSPb) 62.7

• 64.0 High Power Setpoint (HPSP ) 82.7

• 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 1.40 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).

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 2821-1064 B2C17 Core Operating Limits Report Page 13, Revision 0 Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS) OLMCPR(2PT) 1.05 1.2265 1.1105 1.06 1.2515 1.1331 1.07 1.2775 1.1566 1.08 1.3046 1.1812 1.09 1.3329 1.2068 1.10 1.3624 1.2335 1.11 1.3918 1.2601 1.12 1.4226 1.2880 1.13 1.4547 1.3170 1.14 1.4883 1.3475 1.15 1.5235 1.3793 Acceptance Criteria Off-rated OLMCPR @ Rated Power 45% Flow, 60.6% power OLMCPR PDBA Setpoint Setpoint Value Amplitude Sp 1.13 Confirmation Count Np 15 This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1).

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Caic. 2B21-1064 B2C17 Core Operating Limits Report Page 14, Revision 0 Figure 1 Fuel Type GE14-PlODNAB398-13GZ-1 OT-150-T-2417 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 10.0 9.0 a--

8.0 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWdIMT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 15, Revision 0

., d .

Figure 2 Fuel Type GE14-PIODNAB399-16GZ-IDOT-150-T-2418 (GEl4)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 This Figure is Referred To By 12.0 .Technical Specification 3.2.1 11.0 -- _-II_

7#.11 N

\

Exposure LiUit 10.0I 7/ (GWdfrl) 0.00 0.22 (kW/ft) 9.65 9.73 1.10 9.86 2.20 10.07 9.0 3.31 10.27 4.41 10.45 F

-Prmissible -

5.51 10.58 Region of 6.61 10.69 Operation 7.72 10.78 Y-8.82 10.86 0~ 8.0 1 9.92 10.94 11.02 11.02 12.13 11.11 13.23 11.14 14.33 11.12 15.43 11.11 7.0 16.53 11.10 18.74 11.06 22.05 10.90 I I .

27.56 10.51 33.07 10.09 6.0 _-- 38.58 9.53 44.09 9.02 49.60 8.41 55.12 7.84 60.63 6.44 64.11 4.87 5.0 I 4.0 I I I 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report i .. Page 16, Revision 0 Figure 3 Fuel Type GE14-PIODNAB420-IBGZ-IOOT-150-T-2572 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 10.0 f 9.0

-J rM 0~ 8.0 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWdIMT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design CaIc. 2B21-1064 82C17 Core Operating Limits Report Page 17, Revision 0 Figure 4 Fuel Type GE14-PIODNAB419-6G7.017G6.013G2.0- OOT-150-T-2573 (GE14)

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

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Caic. 2B21-1064 B2C17 Core Operating Limits Report Page 18, Revision 0 Figure 5 Fuel Type GEI 4-PI ODNAB425-3G7.0/1 4G6.0/1 G2.0-1 OOT-1 50-T-2574 (GE14)

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

_i 8.0 0:

-J X:

a.

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)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design CaIc. 2B21-1064 B2CI7 Core Operating Limits Report Page 19, Revision 0 Figure 6  ;

Fuel Type GE14-PIODNAB439-12G6.0-100T-150-T-2575 (GE14)

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

_ 8.0 0

Hi M

-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 (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 20, Revision 0 Figure 7 I pI I Fuel Type GE14-PIODNAB413-16GZ-10OT-150-T-2660 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 10.0 9.0 CA 8.0

-J IL 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)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 21, Revision 0 Figure 8

[Not Used]

NGG Nuclear Fuels Mgmt. & Safety Analysis DDesign Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 22, Rev. 0 Figure 9 I Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1 in I I I I This Figure is Referred To By I I I I I Two Loop Operation Limit I 1.05 - Technical Specifications 3.2.1 and 3.4.1 J

1.00 laxF ow 102 5% -

107 %

0.95 117 % 7 0.90 Ua.

Fingfe Loop OperationLit EL 0.85

__ __@ Z r_ __/ _

0 Z:co 0.80

= 0.75 0-

/7 / /

a.

'C 0.65 aL Ic1111

.0 0.65- MAPLHGR(F) = MAPFACF

• MAPLHGRsm MAPLHGRsTD = Standard MAPLHGR Limits MAPFACF(F) = Minimum (1.0, AFWcdlOO+BF) 0.60 Wc = % Rated Core Flow 9.

AF And BF Are Fuel Type Dependent Constants Given Below:

0.55 Max Core Flow

(% Rated) AF BF 102.5 0.6784 0.4861 0.50 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.45 0.40 - .. - i- I I I I I I I I I I I 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. 2B21 -1064 B2C17 Core Operating Limits Report Page 23, Rev. 1 Figure 10 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.05 1.00

--] I1 This

~I II Figure is Referred To BY

/

Technical Specifications 3.2.1, 3.4.1 and 3.7.6 _

0.95 0.90 0.85 Two Loop Operation Lim

< 0.80 0.

0 0.75 4-a IL G 0.70 -_- - __ - _ _~ _ I- nr 1 11 __

a

-j 0.6 a.

c 0.65 0.

0 5 0.60 0.

0 .

0.55 - fJCoreFlow >65% MAPLHGRSD = Standard MAPLHGR Umits 0

a. , 7For P<23%:

0.50 _ l _ No Thermal U~mits Monitoring Required

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

_ l _ MAPFACp= 0.433 + 0.0063 (P-26%)

0.45 4 k l MAPFACp = 1.0 +0.005224 (P-i100%)

0.40

\ l MAPFACp = 0.634 + 0.0035 (P-40%)

rNo Flow Re striction ~FoI 4%

0.35

- TurabieorInpeable-OpeTrablne oBpass MAPFACp = 1.0 + 0.005224 (P-i100%)

0.30 20 2f 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pbypass (26%) Power (% Rated)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 24, Rev. 0 Figure 11 Flow-Dependent MCPR Limit, MCPR(F) 1.80 I<X I Im II 1.75 - . . . .I.-.4 .

MCPR(F) - Max (1.24, AFWc/I00+BF) 1.70 Max Core Flow

(% Rated) AF BF 1.65 KI ...... 102.5 107.0 112.0

- 0.592

- 0.608

-0.625 1.717 1.760 1.812 117.0 - 0.656 1.877 9

-9  !-!-~ - Y 1.60 1.55 1.50 IL 1.45 1.40 1.35 Max FIoI= 1 7%

1.30 107%

102.5%

1.25

_1~ 1 - - -

1.20 This Figure is Referred To By 1.15 4- Technical Specification 3.2.2, 3.4.1 and 3.7.6 . . ._

1-in L 1 I 1 I1 .4 - 4 4 - - -

• h.

20 25 30 35 40 45 50 55 60 65 70 75 .80 85 90 95 100 105 110 115 120 Core Flow (% Rated)

, I, I NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Page 25, Rev. 1 Figure 12 Power - Dependent MCPR Limit, MCPR (P) 3.800 3.700 OLMCPR - Rated MCPR Multiplier (Kp) 3.600 3.500 I-No Flow Restriction - ._ ,1 Turbine Bypass 3.400 V Operable Inoperable or I- _ -

3.300 0 3.200 _ - - - - - 3Operating Umit MCPR:

V _ OLMCPR(P) - Kp*OLMCPR(100) 3.100 vl V ForP <23%:

0. 3.000 No Thermal Umits Monitoring Required a-CI2.900 For 23% s P < PBPASS: Where PwpAss = 26%

cr

a. 2.800 _ -Turbine Bypass Operable or Inoperable 2.700 _OLMCPR(P)= [3.13 + 0.0900(26% - P)]

-j 0 2.600 For 26% s P < 40% Core Flow s 65%:

2.500 - OLMCPR(P) = 1.88 + 0.0129 (40% - P)

Core Flow>65% For 26% SP< 40% Core Flow > 65%:

2.400 OLMCPR(P) = 2.10 + 0.0157 (40% - P) 2.300 For 40 5 P <45%:

2 .n2 - Kp= 1.28 + 0.0135 (45% - P) o 0

T 2.100 - - For 45% S P < 60%:

Al __

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

L- 2.000

'ai 1.900 ._ - _ -- - ForP260%:

Kp = 1.00 + 0.00450 (100% - P) 1.800 Core Flow < 65% - .

C., 1.700 ax

a. 1.30 1.500 - - - - - __ - - - ~This Figure is Referred TOB n 1.300 Technical Specification

- 1.400 - - - - _ - - -3.2.2, 3.4.1, 3.7.6 EL1.200 1.100 1.000 1---- L --

20 2 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pbypass (26Ye) Power (% Rated)

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 13 Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 26, Rev. 0 OPRM Operable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120 -

M inim um Maxim um (M ELLL) (IC F) 110 P ow er Core Flowa, Core Flow,

% M Ibslhr M Ibethr 100 76.19 80.47 100 99 75.04 80.47 98 73.89 80.47 97 72.76 80.47 96 71.61 80.47 90 95 94 70.49 69.36 80.47 80.47 93 68.25 80.47 92 67.13 80.47 80 91 90 86.03 64.93 80.47 80.47 89 63.83 80.47 88 62.74 80.47 70 87 88 61.96 60.58 80.51 80.60 85 59.50 80.70 I 84 58.43 80.79 83 57.37 80.90 no 60 82 56.31 81.05 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50- 78 52.12 81 .7 77 51.08 81.83 78 50.05 81.98 75 49.02 82.13 40 74 73 48.00 46.98 82.29 82.44 72 45.96 82.60 71 44.95 82.75 30 70 69 43.94 42.94 82.91 83.06 68 41.94 83.21 67 40.95 83.37 20 66 65 39.96 38.97 83.52 83.68 64 37.99 83.83 63 37.01 83.99 10 - 62 61 36.04 35.06 84.14 84.29 60 34.10 84.45 59 33.13 84.60 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 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow co/

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 14 Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Stability Option III Power/Flow Map Page 27, Rev. 0 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-

- ,d~ ~ i

-AAPRM T j'-i PMT~rm(MELILL)

STP SB~Ck ~sh (IC ish F)

I100 C97.0 04

- ..... tL 97 er Fl,-

72.79 80.4F 7 9 96 77049 80.47 90 v-9 8

94 704993 69.5 8 0.4 77 80.

85j 59.250 90.470 831 5.037 6 8 0.90 82 54.931 810.057

8 88 .3 80.47

-x'i t .'-" 2[' '

t1, M f'- E1ltX1t 81-t- 55.25- 781.521 40 Reio A - F-~ua SCRAM$+f EnlS ll 76 5.5 19 49.98 37 82.0 71 82.47 1o0 I92

'n  ; 61 44.95 38.04 6350 84.14 84.29 870 434 66 82 .1 319

.13.136 8.60 65 3. 97 83.68 1

- - .t - .4 4 37 99 83 83 1 1 83 37 0 83 99 0 34.10 84.456 738 32.17 82470 0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77 84.7 924 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %Core Flow

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 15 Design CaIc. 2B21-1064 B2C17 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 28, Rev. 0 OPRM Operable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 Min im um M aximumn 110 fl I - - - - I - amF)

PRM STPFSa P 00 . 7 7 t. 847 04 100 99 7 5.04 80.47 TPo 98 73.8 9 8 0.4 7 98 1.9.61 8047 905 70.49 80.47 93 88'.253 80.4 7

.f1 92 92 8.3 80.47 80 1L f iT H L4 91 90 6 6.0 3 64.83 80.47 8 0 .47 8 63.8 3 64 7 I i-;.t- tI I---y l t2Httl1t1.t-ittlllf~tllit 11;I 88 92.74 80.47 70 86 60.58 80.90 85 5.50 90.70 84 58.43 57.3 7 8079 8 0.90 83 50 -*1!:1slf-MMt]i LIll!IIlLIIILi1L llbl tl8 7 74I 7027 522 48.05 51.08 816 621.291 81.83 72 45.186 8260 73 46.98 82.46

-lt 7 82 g l1[11 1.070 3604 8t lit-;+l6 641 8 39 26 39.96 883.7

- MlbhrMaxCweFlow 60645 3.0 3 84.45 0 58 3217 84. 70 0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %Core Flow

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 16 Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 29, Rev. 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 l 120 -

M inim um Maximum (MELLL) (IC F)

Cor. Core 110 Power Flow, Flow.

% i lbolhr t lbelhr 100 76.19 80.47 100 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90 - 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 80 91 90 66.03 64.93 80.47 80.47

i. . 89 63.83 80.47 88 62.74 80.47 70 87 8i1.66 80.51 86 60.58 80.60 85 59.50 80.70 84 58.43 80.79 83 57.37 80.90 so 82 56.31 81.05 81 55.25 81.21 80 54.20 81.36 40- 79 53.16 81.52 78 52.12 81.67 77 51.08 81.83 76 50..0 81.98 75 49.02 82.13 74 48.00 82.29 40 Rego 73 72 46.98 45.96 82.44 82.60 71 44.95 82.75 30 - ei 70 43.94 82.91 69 42.94 83.06 e8 41.94 83.21 5% E 67 40.95 83.37 20 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 10 62 36.04 84.14 61 35.06 84.29 60 34.10 84.45 59 33.13 84.60 0 . . . . . . . . . . .

58 32.17 84.70 0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow Ccot

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 17 Design Caic. 2B21-1064 B2C17 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 30, Rev. 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 10M - In Im um M axim um a rPRMSTPSeCmo core P owe9r F low. Flo.w,

. = _ J. 4_ . ff~-t=i  % M lbs/hr iT lb*/hr 100 7 6.1 9 8 0 .47 tt9 7161 _ 8 0 .47 r92 193 7v16 6

67.13

. 5 80.47 47

. !3 914 90 8 80.47 sol - t-1i ,,..L-.,.893 9; 8t6 .0 II8467 81 52825 81. 2°1 f8 90 4.03 819.

40 i72 394 49.00 4698 45.46 7

822.9 82 .44

.62 1 20 7 T 1 Iiiiiiiiiii~iilLIIIIILllrI 1 85 38.97 83.68 4 1 5 37.28 8383 2 0

0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow

NGG Nuclear Fuel Mgmt. & Safety Analysis Figure 18 Design Calc. 2B21-1064 B2C17 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 31, Rev. 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 M inim um M aximumrn (MELLL) (IC F) 110 Core Core Pow.r Flow, Flow, M Ibslhr M ibs/hr 100 76.19 80.47 100 99 75.04 80.47 9a 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90 95 70.469 60.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 80 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 98 62.74 80.47 70 87 61.66 80.51 86 60.58 80.60 85 59.50 80.70 84 58.43 80.79 I 60 83 82 57.37 56.31 90.90 81.05 81 55.25 81.21 80 54.20 81.36 79 53.16 50 78 52.12 81.52 81.67 77 51.09 81.83 76 50.05 81.98 75 49.02 82.13 40 74 49.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 30 70 43.94 82.91 69 42.94 83.06 68 41.94 83.21 67 40.95 83.37 20 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 10 62 36.04 64.14 61 35.06 84.29 60 34.10 84.45 33.13 84.60 0 _____e I ~ k I~V-I ~'11 17V77L U;-~- ov "

59

_~ 58 32.17 64.70 0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77 84.7 92.4 Mlbslhr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow CON'