Text

Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr
	ML20236T196
Person / Time
Site:	Brunswick
Issue date:	07/01/1998
From:	Dresser T, Siphers J; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20135G046	List: BSEP-98-0144, Transmits Colrs,Supplemental Reload Licensing Rept & LOCA Analysis Rept.Ge LOCA Analysis Rept Is Considered Proprietary Info,Per Encl Affidavit.Proprietary Info Withheld Per 10CFR9.17 & 10CFR2.790; ML20236T192; ML20236T196; ML20236T197;
References
	2B21-0088, 2B21-0088-R01, 2B21-88, 2B21-88-R1, NUDOCS 9807280023
	Download: ML20236T196 (36)
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._

l-l ENCLOSURE 2 i

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORTS, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT BRUNSWICK UNIT 2, CYCLE 13 CORE OPERATING LIMITS REPORT JULY 1998 1

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9807290023 980717 PDR ADOCK 05000324 P

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j CP&t. Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 B2C13 Core Operating Limits Report Page 1, Revision 1 l

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BRUNSWICK UNIT 2, CYCLE 13 l

CORE OPERATING LIMITS REPORT l

l July 1998 Prepared B)

Q Date:

6/30/98 Thomas M. Dresser Approved Date:

7/1/98 John fSiph/s Superintendent l

BWR Fuel Engineering J

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 B2C13 Core Operating Limits Report Page 2. Revision 1 i

LIST OF EFFECTIVE PAGES Page(s)

Revision 1-35 1

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- CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 3. Revision 1 i

. TABLE OF CONTENTS Subject Page Number Cover...............................................................................................................1 List of Effective Pages...................................

........................................................2

- Tabl e o f Co n t e n ts.......................................................................................... 3 List o f Tables / List o f Figures............................................................................. 4 Introd uc tio n & S um m ary............................................................................. 6 S in gl e Loop Ope rati o n........................................................................................... 7 i

inoperable Main Turbine Bypass System................................................................. 7 A P L I I G R L i m i t s............................................................................................... 8 l

M C P R L i mi ts......................................................

.8 RBM Rod Block instrumentation Setpoints...

...................................................8 APRM Flow Biased Simulated Thermal Power-Ifigh.............................................. 8 APRM Control Rod Block Upscale (Flow Biased)......................................... 9 Till El A Stability Solution...........................

.....................9 j

R e fere nces.............................................

.................I0

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 4. Revision 1 LIST OF TABLES Table Title Page Number Table 1: MCPR Lirnits....................

......................I1 Table 2: RB M Sy st em S et poi n ts............................................................

.. 12 Table 3: Aligned Drive Flow......

.. 13 LIST OF FIGURES Figure Title or Description Page Number Figure 1: APLHGR Limit Versus Average Planar Exposure..............

.............14 Figure 2: APLiiGR Limit Versus Average Planar Exposure....

...........................15 Figure 3: APLHGR Limit Versus Average Planar Exposure..........

.................16 Figure 4: APLIIGR Limit Versus Average Planar Exposure................................

.17 Figure 5: APLIIGR Limit Versus Average Planar Exposure....

....... 18 Figure 6: APLIIGR Limit Versus Average Planar Exposure...

.......................19 Figure 7: APLIIGR Limit Versus Average Planar Exposure......

.....................20 Figure 8: APLliGR Limit Versus Average Planar Exposure..

.. 21 Figure 8a: APLHGR Limit Versus Average Planar Exposure...

..........22 Figure 8b: APLHGR Limit Versus Average Planar Exposure.................................. 23 Figure 9: M A P L H G R ( F)..........................................

...................24 1

L Figure 10: M A P L 1 I G R( P)................................................................. 2 5

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Figure 11: M C P R( F)....................................

..... 26 C___.___________.____._._____

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 82C13 Core Operating Limits Report Page 5, Revision 1 t

LIST OF FIGURES / LIST OF TABLES - CONTINUED Figure -

Title or Description Page Number i

Figure 12: MCPR(P)..............................................................

.......27 Figure 13:

Power / Flow Map Stability Regions:

Normal T,w, Non-Setup (B2C13)..................

..... 28 i

l Figure 14:

Power / Flow Map Stability Regions:

l Normal T,w, Setup (B2Cl 3 ).................

.........................29 Figure 15:

Power / Flow Map Stability Regions:

Reduced T,w, Non-Setup (B2Cl3 )......

...........30 Figure 16:

Power / Flow Map Stability Regions:

Reduced T rw, Setup (B2C 13 ).................................................. 31 Figure 17:

EI A Setpoint Allowable Values versus Aligned Drive Flow:

Normal T,w, Non-Setup (B2Cl 3)...

................32 Figure 18:

_ El A Setpoint Allowable Values versus Aligned Drive Flow:

Normal T rw, Setup (B2C13)........................

........................33 Figure 19:

EI A Setpoint Allowable Values versus Aligned Drive Flow:

Reduced T rw, Non-Setup (B2C13)........

.................34 Figure 20:

EI A Setpoint Allowable Values versus Aligned Drive Flow:

Reduced T rw, Setup (B2C 13)............................

...................35 l

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 B2C13 Core Operating Limits Report Page 6. Revision 1

. INTRODUCTION AND

SUMMARY

This report specifies for Brunswick Unit 2, Cycle 13 the Thermal Hydraulic Instability (THI)

EI A Stability Solution Monitored Region and Restricted Region as required by Improved Technical Specifications (ITS) 3.2.3 and 3.3.1.3, and the Technical Requirements Manual Specification (TRMS) 3.2. This report also specifies the Exclusion Region. The Monitored Region, Restricted Region and Exclusion Region are indicated on the familiar power / core flow map. This report specifies the " Setup" and "Non-Setup" scram values of the APRM Flow ~ Biased Simulated Thermal Power-High Allowable Value (" Flow Biased Scram") as required by ITS

' 3.2.3 and 3.3.1.1. This report also specifies the " Setup" and "Non-Setup" control rod block

. values of the,APRM Flow Biased - Upscale Allowable Value (" Flow Biased Rod Block") as required by the TRMS 3.3. The scram and rod block values are indicated on the power / drive y

- flow domain in which the Flow Control Trip Reference cards operate.

This report specifies for Brunswick Unit 2, Cycle 13 the limits to support operation with one recirculation loop in operation as required by ITS LCO 3.4.1. This report specifies for Brunswick Unit 2, Cycle 13 the limits to support operation with an inoperable Main Turbine Bypass System as required by ITS 3.7.6.

This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 13 as required by ITS 5.6.5. The values of the Average Planar Linear Heat Generation Rate (APLHGR) limits, along with associated core flow and core power adjustment factors are provided as required by ITS 5.6.5.'a.1. The values of the Minimum Critical Power Ratio (MCPR) limits, along with associated core flow and core i

' power adjustment factors are provided as required by ITS 5.6.5.a.2.

The' Allowable Values'for Function 2.b ofITS 3.3.1.1, APRM Flow Biased Simulated Thermal l

- Power-High are provided as required by ITS 5.6.5.a.3. The rod block monitor upscale trip setpoints and allowable values are provided as required by ITS 5.6.5.a.4.

Per ITS 5.6.5.b and 5.6.5.c, these values have been determined using NRC approved p

methodology and are established such that all applicable limits of the plant safety analysis are i met.

O' Preparation of this report was performed in accordance with Quality Assurance requirements as l

specified in Reference 1.

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. CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088

. B2C13 Core Operating Limits Report '

Page 7, Revision 1 l

l SINGLE LOOP OPERATION.

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' Brunswick Unit 2, Cycle 13 may operate over the entire MEOD range.with Single recirculation Loop Operation (SLO) as permitted by ITS 3.4.1 with applicable limits specified in the COLR

for ITS LCO's 3.2.1,3.2.2, and 3.3.1.1. The applicable limits are:

.- LCO 3.2.1 Average Planar Linear Heat Generation Rate (APLIIGR) Limits: per i

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, the MCPR limits described below and presented in Table 1 and Figures 11 and 12 apply to SLO without modification.

LCO 3.3.1.1 Reactor Protection System Instrumentation Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power - High) Allowable Value: per Reference 1, these limits - described below under THI El A STABILITY SOLUTION -

apply to SLO without modification.

INOPERABLE MAIN TURBINE BYPASS SYSTEM Brunswick Unit 2, Cycle 13 may operate with an inoperable Main Turbine Bypass System in accordance with ITS 3.7.6 with applicable limits specified in the COLR for ITS LCO 3.2.1 and 3.2.2. One bypass valve 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 110 F 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% bypass flow is achieved in 0.30 seconds. The applicable limits are:

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LCO 3.2.1_ Average Planar Linear Heat Generation Rate (APLHGR) Limits: in accordance with Reference 1, TBPOOS requires a reduction in the MAPLGHR(P) limits between 25% and 30% power. This reduction is plotted on Figure 10.

LCO 3.2.2 Minimum Critical Power Ratio (MCPR) Limits: in accordance with Reference 1, TBPOOS requires a increase in the MCPR(P) multiplier between 25% and

'30% power - This increase is plotted on Figure 12. TBPOOS also requires increased

- MCPR limits, included in Table 1.

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 B2013 Core Operating Limits Report Page 8, Revision 1 APLHGR LIMITS i

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 8b. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR-II (Reference 2). Figures I through 8b are to be used only when hand calculations are required as specified in the bases for ITS 3.2.1. Nomial monitoring of the APLHGR limits with POWERPLEX uses the complete set oflattices for each fuel type provided in Reference 3.

The core flow and core power adjustment factors for use in ITS 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.

MCPR LIMITS -

The ODYN OPTION A, ODYN OPTION B, and non-pressurization transient MCPR limits for l

use in ITS 3.2.2 for each fuel type as a function of cycle average exposure are given in Table 1.

i These values were determined with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2) and are consistent with the Safety Limit MCPR of 1.09 specified by ITS 2.1.1.2.

l The core flow and core power adjustment factors for use in ITS 3.2.2 are presented in Figures i 1 and 12. For any given flow / power state, the maximum of MCPR(F) determined from Figure 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit.

- All MCPR limits presented in Table 1, Figure i1 and Figure 12 were determined without EOC-RPT operable and 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 ITS 3.3.2.1 (Table 3.3.2.1-1) are presented in Table 2. These values were determined consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI methodology and GEXL-PLUS critical power conclation described in

. GESTAR-II (Reference 2).

APRM FLOW BIASED SIMULATED TIIERMAL POWER-HIGli The APRM Flow Biased Simulated Thermal Power-liigh setpoint as referenced by ITS 3.3.1.1 and TRMS 3.2 is described in the TH1 EI A Stability Solution section below, l

' CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 9. Revision 1 l

APRM CONTROL ROD. BLOCK UPSCALE (FLOW BIASED)

The APRM Control Rod Block Upscale (Flow Biased) setpoint as referenced in TRMS 3.3 is described in the THI EI A Stability Solution section below.

THI EIA STABILITY SOLUTION I

implementation of the THI EI A Stability Solution involves exclusion from certain areas of the power / flow map and specific restrictions for operating in other areas. Stability Regions generally protect the high power / low flow regions of the power /fiow map and include: an Exclusion

. Region from which plant operation is excluded by the APRM Flow-biased Scram; a Restricted Region in which operation is restricted to conditions where the Boiling Boundary exists at least four feet above the bottom of the core (Fraction of Core Boiling Boundary or FCBB shall be

- s 1.0, per ITS 3.2.3); and a Monitored Region in which operation is allowed only if the potential for a developing THI event is mor itored by the Period Based Detection System (PBDS operable, per ITS 3.3.1.3). Flow Control Trip Reference (FCTR) cards provide the ITS 3.3.1.1 automatic APRM Flow-biased Scram and the TRMS 3.2 Restricted Region Entry Alarm (RREA) using the

.TRMS 3.3 Flow-biased Rod Block setpoint. Because the flow signal for these automatic functions is based on drive flow and not core flow, the COLR Flow-biased Scram and Rod Block 1

limits Allowable Values are included as functions of drive flow (Figures 17-20). These curves allow quantification of Technical Specification compliance, once the drive flow input is aligned in accordance with Table 3. However, the Stability' Regions defined by these limits as well as the l

Monitored Region (which is not incorporated into the FCTR card) are analyzed by EI A in terms of power versus core flow. Because.the plant Operators are accustomed to monitoring plant condition in terms of core flow, the COLR provides the Stability Regions on the power /(core) flow map for Operations..i recognition of human performance factors. Day-to-day and time-

. pressured responses by the Operator should use the power / flow map stability regions

-(Figures 13-16). These Figures define the Monitored and Restricted Regions for compliance with ITS 3.2.3 and 3.3.1.3 and TRMS 3.2. Core flow nominal trip setpoint values on Figures 13-16 correspond to the nominal trip setpoint values translated into drive flow and installed in the FCTR cards.

As required by TRMS 3.2, should neither channel of the RREA be operable to protect against unintentional entry into the Restricted Region, the plant must be operated below the flow control line associated with the lowest thermal power in the Restricted Region, or continuous monitoring j

of thermal power and core flow maintained by a qualified individual.

The EI A Stability Solution provides for distinct Flow-biased Scram and Rod Block setpoints for

" Setup" as well as normal or "non-Setup" conditions (the Monitored Region boundary is

. unchanged by Setup). "Non-Setup" setpoints (Figures 13,15,17,19) enforce the normal L

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 10. Revision 1 Exclusion and Restricted Regions described above. Setup setpoints (Figures 14,16,18,20) are to be used only when the FCBB s 1.0, and allow operation in the Restricted Region. When operating in Setup, the Flow-biased Rod Block setpoints generally increase in power to the Flow-biased Fcram or power / flow map boundaries. The Flow-biased Scram setpoint generally increases by an equivalent amount (within the power / flow map boundaries) to avoid spurious I

scrams from power spikes. The inherent stability from maintaining FCBB less than onejustifies continued operation in the Restricted Region, but not in that portion of the power /How map which in Setup becomes unprotected by the Flow-biased Scram. The alarm associated with the Rod Block ceases to be a RREA when in Setup, but signals to Operations a similar need to immediately move to a more stable region of the power / flow map.

The EI A Stability Solution generically provides for distinct Flow-biased Scram and Rod Block setpoints for recirculation pump SLO and two loop operation. Ilowever, for BNP the two loop i

operation (TLO) Flow-biased Scram and Rod Block setpoints, and TLO Stability Regions, are applicable for SLO without modification (Reference 1).

The El A Stability Solution provides for distinct Flow-biased Scram and Rod Block setpoints for normal and reduced feedwater :emperature conditions (" normal" and " alternate" setpoints) because the core is more susceptible to instabilities with decreasing feedwater temperature.

Normal setpoints (Figures 13,14,17,18) are to be used below 30% power or when feedwater temperature is within 50 F rated equivalent of nominal. The alternate setpoints (Figures 15,16 19,20) are to be used above 30% rated thermal power when feedwater is reduced by more than 50"F rated equivalent (50"F * (% power /100)"") in accordance with 2OP-32. For example, a feedwater temperature reduction of 40 F from the design value associated with 50%

power would require the alternate setpoints because this reduction would exceed the allowable reduction of 38.3"F, calculated by 50*0.50""

REFERENCES 1)

BNP Design Calculation 2B21-0088;" Preparation of the B2Cl3 Core Operating 1.imits Report," Revision 1; June 1998.

2)

NEDE-24011-P-A: " General Electric Standard Application for Reactor Fuel,"

(latest approved version).

3)

NEDC-31624P, Supplement 2;" Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13," Revision 5, June 1998.

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l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 -

82C13 Core Operating Limits Report Page 11, Revision 1 Table I MCPR Limits EOC-RPT Not Required

-1 Non-pressurization Transient MCPR Limits Exposure Range

~ Fuel Type BOC-EOC GE8x8NB 3 1.29 gel 3 129 Pressurization Transient MCPR Limits:

Turbine Bypass System Operable i

Normsl and Reduced Feedwater Temperature

, MCPR Option t nel Type Exposure Range:

Exposure Range:

BOC to EOFPC-2205 EOFPC-2205 mwd /MT to mwd /MT EOC i

i A

GE8x8NB-3 1.35 1.44

.j gel 3 1.35 1.44 B

GE8x8NB 3 1.30 1.36 GE13 1.30 1.36 l

1 Pressurization Transient MCPR Limits:

Inoperable Main Turbine Bypass System Normal Feedwater Feedwater Temperature Temperature Reduction MCPR Option Fuel Type I:Al m ure Exposure Exposure Esposure Range:

Range:

l BOC to EOFPC-2205 ROC to EOFPC.

EOFPC-2205 r

EOFPC-2205 mwd /MI to 2205 MWdSIT mwd /MT to MWdSIT EOC I.OC A

GESx8NB-3 1.39 1.48 1.41 1.49 GE13 1.39 1.48 1.41 1.49

.B GE8x8ND-3 1.34 1.40 1.36 1.41 GE13 1.34 1.40 1.36 1.41 This Table is referred to by improved Technical Specifications 3.2.2,3.4.1, and 3.7.6.

I CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 12, Revision 1 Table 2 i

RBM System Setpoints l

Setpoint Trip Setpoint Allowable Value Lower Powcr Setpoint (LPSP*)

27.0 s 29.0 Intermediate Power Setpoint (IPSP')

62.0 s 64.0 Ifigh Power Setpoint (llPSP*)

82.0

- s 84.0 b

Low Trip Setpoint (LTSP )

s 115.1 s 115.5 b

Intermediate Trip Setpoint (ITSP )

s 109.3 s 109.7 I

b liigh Trip Setpoint (IITSP )

s 105.5 s 105.9 to s 2.0 seconds s 2.0 seconds i

Setpoints in percent of Rated %ermal Power.

b.

Setpoints relative to a full scale reading of 125. For example, s 115.1 means s 115.1/125.0 of full scale.

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

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7 l-CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Lalc. No. 2821-0088 B2C13 Core Operating Limits Report Page 13, Revision 1 Table 3 Aligned Drive Flow The Scram and Rod Block trip setpoints are provided by Flow Control Trip Reference (FCTR) cards. The FCTR cards have their drive flows calibrated each cycle by OPT-50.10,"APRM FCTR Card Drive Flow Alignment". The calibration " aligns" the cunent cycle drive flow to the drive flow used when the EI A flow mapping solution was developed for BNP. The COLR presents the B2Cl3 Scram and Rod Block trip setpoints as a function of aligned drive flow. This Table 3 provides an equation foc deriving the aligned drive flow from the FCTR card input drive flow signal:

100.005 A** - 30.294 A'

+ 69.711 W ri 69.711 -( A"* - A**)

where:

W is the aligned drive flow to be used for Figures 17 through 20 o

W is the input drive flow signal 3

a' and A'*" are the current values for the FCTR card alignment This Table supports improved Technical Specifications 3.2.3 and 3.3.1. I and Technical Requirements Manual Specifications 3.2 and 3.3.

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CP&L Nucle:r Fuels Mgmt. & SIfity An: lysis Design Calc. 2B21-0088

' B2C13 Core Operating Limits Report Page 14, Revision 1 Figure 1 Fuel Type GE10-P8HXB320-11GZ-100M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 i

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This Figure is Referred To By 1

-J 1

improved Technical

)

13.0 7 - --- -

Specification 3.2.1 I

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+ - +- -

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Exposure Lmt t

{

(GWd/MT) (kW/ft) j i

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e 0 00 10 81 I

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10.0 0.22 10 87

, Permissible.

t-1.10 10.97 Region of 4

E 2.20 15.50 operation i

'8 3 31 11.24 E

4 41 11.39 e

i 0

9.0 5 51 11.53 I

4 d

6 61 11.68 3

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7.72 11.84 l

8.82 12.00 8.0 p---

9 92 12.16

---'-l'-

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i 11.02 12.33 j

13.78 12.52 i

16 53 12.40 l

7.0 b --

22.05 11 93

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27.56 11.44 j

1 33.07 10 85 38 58 10 26 6.0

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f 5.0 I

0 5

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

{

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CP&L Nuclear Fu;ls Mgmt. & S fety Artylsis Desip C Jc. 2B21-0088 82C13 Core Operating Limits Report Page 15, Revision 1 I

i Figure 2 Fuel Type GE10-P8HXB322-11GZ-70M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 I

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This Figure is Referred To By i

i 13.0,

L--- -i F --. -- -

q.

Improved Technical l

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i Specification 3.2.1 l

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+... _ L

_ _. -. )

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j Exposure Lmt l

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(GWd/MT) (kW/ft)

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0 00 10 84 Permissible 4

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Region of --J L

I E 10.0 0.22 10.88 t-t 1.10 10 95 l

Operation j

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2.20 11.08 3.31 11.21

{

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4.41 11.35 i

g 9.0 i-5 51 11.50 i

- t T-g 6 61 11.67 aC j

7,72 11.92 I

i 8 82 12.26 i

l - -- -

8.0

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9.92 12.61 11.02 12.95 l

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l 13.78 13.12 i

16.53 12.89 i

l 7.0 22 05 12 29

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27.56 11.67 33.07 10.96 I

I 38 58 10.26 i

6.0 55.12 6 29 5.0

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AVERAGE PLANAR EXPOSURE (GWd/MT) l l

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CP&L Nuchar Fu;ls Mgmt. & S f;ty Analysis Design Cdc. 2821-0088 B2C13 Core Operating Limits Report Page 16, Revision 1 i

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Figure 3 l

l Fuel Type GE10-P8HXB324-12GZ-70M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 l

l i

i I

l i

l This Figure is Referred To By i

13.0 3

l -

r-..,..._

Improved Technical

~

t Specification 3.2.1 f

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? ---.

12.0

- - l l

7-- - p I

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Exposure Lmt I

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,i 2

O 00 10 75 Permissible 3

6 10.0 -- Y-

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b -- -Y t

3 0,22 10.78 b

i 1.10 10 87 2.20 11.07 Operation l

i 3

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3.31 11.32 I

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4 41 11.62 l

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" ~ ~ ~ ~

- - * ~

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5.51 11.83 i

g 6 61 12.02

(

7.72 12.22 8 82 12.44 9.92 12.70 l

8.0

+-

- - - ~ ' - - - - -

13.78 13.17 i

11.02 12.96 3

i 1653 12.93 i

7.0 22.05 12.27

_f._.

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33 07 10 94 38.58 10 27 4

6.0 49l

~.-

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+

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l 5.0 O

5 10 15 20 25 30

'35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT) i

l CP&L Nuct r Fuels Mgmt. & S ftty Anryisis D: sign Calc. 2821-0088 82C13 Cors Oper" ting Limits Report Page 17, Revision 1 i

Figure 4 Fuel Type GE10-P8HXB329-12GZ1-100M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 I

I

{

j i

l i

l This Figure is Referred To By 13.0

-H j

7I- - - - -

Improved Technical l

Specification 3.2.1 j

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i 12.0 4-r------

' - - ---- j -- -j --j- _ --

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i i

I 11.0 4

2--

~

I I

}

i l

[

l 1

~

i h

[

Exposure Permissible I

uma 6 10.0 L. (GWd/MT) (kW/ft)

Region of.._ ;. __ _. _ _ __ L i

b 0 00 10 52 Operation I

E O 22 10.57 I

l 3

i 1.10 1C 70 tr' i

l t

t 2.20 10 92

)

i i

Z 3.31 11.17 e

e

_L _ _ _ j _ _

O 9.0

---g I

d i

4 41 11.35 i

5 51 11.53 1

6 61 11.71 8.0 l

7.72 11.90 B.82 12.12

{

l 9.92 12.37 i

l l

11.02 12.63 7.0 13.78 12.82 F ----- - - t -

---..-_j - l _.-

16 53 12.65 22.05 12.13 l

27.56 11.47 l

6.0

[g 8

10 20 55 67 5.90 i

5.0 O

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

i i

l

l.

CP&L Nucleir Fuel Mgmt. & Sif;ty Analyzis Design Calc. 2821-008 B2C13 Core Operating Limits Report Page 18, Revision 1 Figure 5 Fuel Type GE13-P9DTB363-11GZ-100T-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure i

14.0 I

j I

i I

i l

l l

I l

This Figure is Referred To By l

3 t

L - -~ -

-u improved Technical 13.0 f

l l

j Specification 3.2.1

]

j j

l l

l j

q_ J_._.

12.0 p ----

t l

l Exposure Umst 1

~

.f i

i l

(GWd/MT) (kW/ft) g

+

11.0 o no 33,39 ---+r-

- -- A 0.22 11.51 i

j g

I j

l i

i i

i E

1.10 11.62 I

I Permissible

_i 10.0 8

- Region of i

4 41 11.89 Operation 5 51 11.99 i

l j

i g

l 6 61 12.10 r

I t_,_ J 0

9.0 7.72 12.21 i

I 8 82 12.33 d

9 92 12.46 j

4 11.02 12.59 13.78 12 60

^

i l

8.0 is 53 12 35 i

19.29 12 08 4

22.05 11.82 i

i 27.56 11.14 t

I 7.0 33 07 to43

. a...._

j i

38.58 9 74 j

+

44 09 9 07 49 60 8 41 6.0 55.12 7.73 I

60 63 7.04 i

I 65.26 6 44 5.0 0

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

i

CP&L Nucle:r Fuels Mgmt. & S fety Anitysis D sign Calc. 2B21-0088 82C13 Core Operating Limits Report Page 19, Revision 1 i

l l

l Figure 6 Fuel Type GE13-P9DTB363-11GZ1-100T-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 l

I I

l l

t l

l j

j This Figure is Referred To By i

i_.

Improved Technical

~'

j f_ --l J__

13.0 j

{

l l

Specification 3.2.1 I

i l

I 12.0 L- - - ;-

'i l

l i

I j

_ _ _ _. p.

I l

i l

i I

Exposure Limit (GWd/MT) (kW/ft)

{

! -Lr 11.0 0 00 11.34

-* ~

r-4 0 22 11.46 l

j I

8 f

l 1.10 11.62 i

i I

l l

2 20 11.70 Permissible I

i 3

E 10.0

,[

t - Region of -"-

--7 l

l Operation l

5.51 11.99 J

6 61 12.09 I

E 7.72 12.20 l

i l

i g

9.0 8.82 12.32 4--

p-

-+-

l g

9 92 12.44 j

11.02 12.55 1

I 13.78 12.57 i

8.0 16 53 12.34 l

u-

- 4 _. _.

19.29 12.07 i

22 05 11.81 l

27.56 11.14 l

I t

j 7.0 33 07 10 43 l

38.58 9 73 l

i i

44.09 9 06 49.60 8.41-l I

55.12 7.73 6.0 60.63 7.04

~~

~ - - ~ '

-~~

65.29 6.44 I

1 1

s 3

5.0 0

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

E__.__

1 CP&L Nucle r Fuels Mgmt. & Safety An:lytis D: sign Ccic. 2821-0088 B2C13 Corr, Operating Limits RIport Page 20, Revision 1 j

Figure 7 Fuel Type GE13-P9DTB393-4G6.0/9G5.0-100T-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 l

l I

I j

i t

i i

l This Figure is Referred To By 13.0

--t Improved Technical

+

l l

Specification 3.2.1 I

I l

l l

i I

l l

1 l

-t -

j 12.0 3

7

t i

l j

I i

Exposure Limd j

j (GWa/MT) (kW/ft) l 1

11.0 j

o co 11 o3 y

5[

0 22 11 09 i

I l

j j

I 1.10 11.19 l

l j

2.20 11.28 h 10.0

,37 b-Permissible b^

' ~~j 3.3 Region of

~,~

^-

,4 l

l 5 51 11.57 Operation l

8 l

6.61 11.67 L. _ __, __ '

j__.

f 9.0 9.92 12.00 7 12 8

___g_

d I

I 4

l 11.02 12 11 j'

i 13.78 12.12 8.0 ---f 16.53 12.00 y -

~4-

-- t - - - --

- + - -

19.29 11.76 2

i 22.05 11.50 1

I 27.56 10.96 I

i 7.0

-l-33 07 10 28 38.58 9 54 j

i 44 09 8.85 1

49.60 8.19 l-6.0 55 75

~

~ ~~

7 ~ ~ i- -

2 l

64.14 6 48 i

i I

I 1

l i

i l

5.0 Y

O 5

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

l

[

\\

l-CP&L Nuctrr Fu;is Mgrnt. & S:fety An: lysis Dr. sign Cric. 2B21-008 B2C13 Core Operating Umits Report Page 21, Revision 1 l

l t

l Figure 8 Fuel Type GE13-P9DTB395-12G5.0100T-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure i

14.0 l'

l l

l

{

i I

l This Figure is Referred To By E

L.-M

.. _1 Improved Technical 13.0 1-

-t --

f l

l i

Specification 3.2.1 i

i l

i i

I i

d i_I L. --. u-

_d

. -.__ } _...

12.0 t

I j

Exposure Limit l

(GWd/MT) (kW/ft) l i

4 L-4. _ -

11.0 o oO 11.15 j

6 0.22 11.24

)

l f

l

{

1.10 11.38 i

i i

g l-2 20 11.50 i

Permissible i

I l

10.0 3.31 i'.57

---+

t-l 4 41 11 66 --. Reg. ion of -

4 j

E 5 51 11.74 Operation I

j 3

6 61 11.83 l

I i

i E

I 7.72 11 92 i

l l

l g

9.0 8 82 12.02 ]~

7 i ~~'

- ~~'~~~ "

T---

---~~

g i

9.92 12.11 i

i 4:

11.02 12.21 1

i i

r 13 78 12.21 i

8.0 1

to 53 12.04 p

--t b

i 19.29 11.78 e

22.05 11.51 i

i 27.56 10 98 1

I

~

7.0 33 07 10 44 r- - -

i 38.58 9 73 J

I l-l 44.09 9.03 I

g 49 60 8 33 l

55 12 7.64 6.0 go g3 g 93 64 28 6 49 l

i I

4 5.0 O

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

CP&L NucMr Fu:Is Mgmt. & S:fity Ane/ tis Design Ca!c. 2821-0088 B2C13 Core Operating Limits Report Page 22, Revision 1 l.

l F

i Figure 8a 1

Fuel Type GE10-P8HXB320-11GZ-100T-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure j

l j

i j

l l

l i

i i

This Figure is Referred To By

}

9 L

Improved Technical 13.0

- + -

l l

l Specification 3.2.1 l

i l

h.. - l; i

i 12.0 I

l i

I t

j I

11.0

- 4 l

Exposure Limit l

I I

E l (GWd/MT) (kW/ft) l l

l i

R 0 00 10.44 Permissible l

E 10.0 0 22 10.49. _L -

7 Region of ---- 1 l

b 1.10 10 59 I

Operat. ion E

2.20 10.72 1

i d

3.31 10.85 i

i f

9.0 d 4j

~ ~~

L

~~

'~

g5 T~ ~ ~ f L-' ' -

--- - t d

6.61 11.28 4

I 7.72 11.43 i

i 8 82 11.47

)

8.0

-- -t 9.92 11.49 t---- -- *I--

11.02 11.52 i

i j

13.78 11.59 i

l 16 53 11.49 i

r 7.0

.}

22.05 11.11 J

t.-

___4

..-_p_

27.56 11.02 38 58 10.53 4947 9.97 48 60 8

6.0

' ' ~

-~~ ~

~~ ~ ~ ~ ~ '

5 6 2

55.83 6.29 i

i 1

5.0 0

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

CP&L Nucle:r Fuels Mgmt. & Sity Anitysis D: sign Cric. 28214088 l

82C13 Cora Oper:: ting Limits Report Page 23, Revision 1 i

Figure 8b Fuel Type GE10-P8HXB324-12GZ-100T-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 i

}

I I

i i

l This Figure is Referred To By 13.0

-t -

l-.

u Improved Technical l

I f

Specification 3.2.1 l

I i

i i

I l

d-rl - -i---

12.0

-t- ---

t--- - J i

j l

i r

+

4 1

i i

j i1 i-11.0 -- 7 Exposure t-

~ -- + - - l

+-

f l

Limit l

t j.

I g

(GWd/MT) (kW/ft)

I i

y 0 00 10 40 l

Permissible j

!!. 10.0 1

0 22 10 43

..)

Region of L- --

--.-.L.__..

Operation 6

1.10 10.51 E

2.20 10.71 l

8 i

3.31 10 96

-b

g d-I-

r- -f- -

9.0 d

6.61 11.59 i

(

7,72 11.78 f

I 8 82 11.92 B.0 r

9 92 12.04 11.02 12.15 13.78 12.21 i

1 16 53 11.98 i

^

7.0

-l 22.05 11.38 a,

27.56 10 97

~,

4 38.58 10 40 49.47 10 06 6.0 d

~~~~

'~

~ ~ ' ~ ~ ~ ~

5 56.29 6.33 i

e i

3 5.0 0

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

l

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 24, Revision 1 Figure 9 I

l Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 l

i i

This Figure is Referred To By l

l i

Improved Technical Specifications i

lTwo Loop Operation Limit l 3.2.1 and 3.4.1 l

1

/

1.00 j

p-

[--

i l

Max Flow = 102.'5%

i i

f f

17%

I l

i 112 %

1 0.90 117% ' ~ ~ ~ ~ ~ ~ ~ "

~

~'E I

l l

l

{

l i

i i

Single Loop Operation' Limit l

i 1

I t

l I

{

oj 0.80 f- -

l i

j

)

l M

j I

i I

I l

0 1

I I

5 l

l

\\

a i

i l

l 1

l E 0.70

- F-- - e -

- E-j l

l MAPLHGR(F) = MAPFAC, ' MAPLilGRs7o 9

MAPLilGRsto - Standard MA PLilGR Limits j

w = % Rated Core Flow j

MAPFACr(F) = Minimum (1.0, A,Wc/100+Br) w 0.60 c

l l

l Ar And By Are Fuel Type Dependent Constants Given Below:

Max Core Flow

(% Rated)

Ar Br 0.50 102.5 0.6784 0.4861 107.0 0.6758 0.4574 i12.0 0.6807 0.4214

?

I17.0 0.6886 0.3828 t

0.40 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2013 Core Operating Limits Report Page 25, Revision 1 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.00 l

This Figure is Referred To By improved Technical Specifications i

I i

3.2.1, 3.4.1 and 3.7.6

_... u. _[__ _ l._ _ J. _ _

7..

i.

j I

i l

l l

Two Loop Operation Limit j

j l

0.90 Fh p

}

7'.

7-p - -

-- _} __.

l l

I l

l i

i I

I i

l i

7-4

.. _u 2.

q l

j' j

l

}

l

~

l O

j I

l

' _I It 0.80 t

i

.. _}

I_

I i

i i

j l

l I

i l

1 l

S j

j l

j j

l

~

[^

Single Loop Operation Limit

~~{-

I e

I i

'i i

l 0

l i

3 0.70 w I - !- -

+-i

-. L-I t--

4--

q-I

{

1 g

1 i

I i

j I

i i

li I

g f

[

Core Flow 5 50%

I MAPLHGR(P) = MAPFACp

MAPLHGRsm I

MAPLHGRsm = Standard MAPLHGR Limits 9 o so

_r Turbine Bypass i

l Operable For P < 25% :

s Titrbine EIyp~ ass ",

No Thermal Limits Monitoring Required

~

For 25% 5 P < 30%:

...-. s. _. - _ a inoperable For Core Flow $ 50% & Turbine Bypass Operable, a

's s

MAPFACp = 0.585 + 0.005224 (P-30%)

A...

For Core Flow s 50% & Turbine Bypass inoperable, 0.50 r-MAPFAC, = 0.567 + 0.0128 (P-30%)

For Core Flow > 50%,

Core Flow > 50%

MAPFACp = 0.433 + 0.005224 (P-30%)

-r Turbine Bypass For P > 30%:

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

inoperable I

0.40

(

20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 f

Power (% Rated) l

(_.

l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-0088 B2C13 Core Operating Limits Report Page 26, Revision 1 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1

I For We (% Rated Core Flow) < 40%,

j i

i MCPR(F) = (ArWc/100+Br)'[l +0.0032 (40-Wc)]

i I

I i

i I

i l,

l 1.70 -+

i

- 1 4

L- --,- - --r- --

l For We (% Rated Core Flow) > 40%,

I l

MCPR(F) = Max (l.20, ArWe/100+Br) l I

i Max Core Flow

-- --- t --

b - ---

(% Rated)

Ar Br 1.60 102.5 0.571 1.655 107.0

- 0.586 I f 97 112.0

- 0.602 1,747 i

i17.0

- 0.632 1.809 l

l I

l l

--j-- -

1.50

-- - [- -

4 C

i I

j I

E I

A i

i N

i 1.40 3 -

1 I

This Figure is Referred To By j

Improved Technical Specification 3.2.2, 3.4.1 and 3.7.6 Max Flow = 117%

112% f l

~

1.30 r -

- - l - - --

j

107 %

102.5 %

I 1.20 l

I

(

i j.

l i

1.10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

L___

l l

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-0088 B2C13 Core Operating Limits Report Page 27, Revision 1 Power - Dependent MCPR Limit, MCPR (P) i OLMCPR I

3.20

)

Rated MCPR Multiplier (Kp) y 3.10

+--

A4-3.00

- ~

~ T or U lo

~l g

\\

l50%

Operating Limit MCPR(P) = Kp* Operating Limit MCPR(100) n 2.90

\\; l Turbine Bypass l-v For P < 25% :

ha 2.80 1-Jnop_erabd _ l-No Thermal Limits Monitoring Required e

m No Limits Specified 0 2.70

-t 7-o 2.60 Core Flow >

For 25% $ P 5 Peypass :

Where Peyrass = 30%

8 50 %

K, = Maximum of 1.481 or Keep g 2.50 Turbine Bypass For Core Flow s 50% & Turbine Bypass Operable, h

Operable For Core Flow > 50% & Turbine Bypass Operable Kpop = [1.90 + 0.02 (30% - P)] / OLMCPR(100)

E 2.40 pp d

^~

~

~ '-

Ket, = [2.20 + 0 02 (30% - P)] / OLMCPR(100) h

~

l j

For Core Flow s 50% & Turbine 6/ pass inoperable, M

2.20

._ i Kpop = [1.96 + 0.072 (30% - P)j / OLMCPR(100) s t Tore Flow < 50%l F r Core Flow > 50% & Turbir e Bypass inoperable 2.10

--7 g 4 Kyt, = [2.81 + 0.05 (30% - P)] / OLMCPR(100) 1Ll Turbine Bypass -

For 30% 5 P < 45% :

inoperable 2.00 t

Kp = 1.28 + 0.0134 (45% - P)

$s.

1.90 m

i n, i

i

(' 1.80 Core Flow < 50%

[1.15 + 0 0 67 (60% - P)

I p

o

_i Turbine Bypass 1.70

-g I

Operable For P > 60% :

~

f 1.60 Kp = 1.00 + 0 00375 (100% - P)

.9

% 1.50 7.

5m 1.40 E

--4 1

This Figure is Referred To By 1.30 m

Improved Technical

]

1.20 4

Specification 322,34.1,3.7.6 15m 1,10 a.

_m

.t. _

1.00 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 PsypAss Power (% Rated) l

8 R

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