ML040960086

to 0000-0016-6502-SRLR, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant, Unit 1, Reload 14, Cycle 15.

ML040960086
Person / Time
Site:	Brunswick
Issue date:	02/29/2004
From:	Collins C, Harding M Global Nuclear Fuel
To:	Office of Nuclear Reactor Regulation
References
0000-0016-6502-SRLR, Rev 0
Download: ML040960086 (41)

Text

GNF Global Nuclear Fuel A Joint Venture of GE. Toshiba. & Hitachi 0000-0016-6502-SRLR Revision 0 Class I February 2004 0000-0016-6502-SRLR, Revision 0 Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 14 Cycle 15 Approved: W,!/" ,; Approved: OPto M. E.HHa C. P. Collins Fuel Engineering Serf Customer Account Leader

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF) solely for Progress Energy Carolinas, Inc. (PGN) for PGN's use in defining operating limits for the Brunswick Steam Electric Plant Unit I (BSEP-1). The information contained in this report is believed by GNF to be an accurate and true representation of the facts known or obtained or provided to GNF at the time this report was prepared.

The only undertakings of GNF respecting information in this document are contained in the contract between PGN and GNF for nuclear fuel and related services for the nuclear system for Brunswick Steam Electric Plant Unit I and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither GNF nor any of the contributors to this document makes any representation or warranty (expressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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BRUNSWICK UNIT I 0000-00 1 6-6502-SRLR Reload 14 Revision 0 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF - Fuel Engineering Services and GENE - Nuclear and Safety Analysis personnel. The Supplemental Reload Licensing Report was prepared by G. M. Baka.

This document has been verified by G. N. Marrotte.

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BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 The basis for this report is GeneralElectric StandardApplicationfor Reactor Fuel, NEDE-2401 I-P-A-14, June 2000; and the U.S. Supplement, NEDE-2401 1-P-A-14-US, June 2000.

1. Plant-unique Items Appendix A: Analysis Conditions Appendix B: Decrease in Core Coolant Temperature Events Appendix C: Operating Flexibility Options Appendix D: Implementation of TRACG AOO Methodology Appendix E: Normal and Reduced Feedwater Temperature Limits Appendix F: MELLLA+ Implementation Appendix G: List of Acronyms

2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:

GE I3-P9DTB405-5G6.0/7G5.0-I OOT-146-T (GE 13) 13 46 GE 13-P9DTB402-1 3G6.0/l G2.0- IOOT-146-T (GE13) 13 21 GE14-PIODNAB416-17GZ-IOOT-150-T-2496 (GE14C) 14 112 GE 14-P I ODNAB425- 16GZ-I OOT-150-T-2497 (GE14C) 14 87 GE14-P I ODNAB438-12G6.0-1 OOT-150-T-2498 (GE14C) 14 48 New:

GE14-PIODNAB437-12G6.0- I OOT-150-T-2662 (GE14C) 15 38 GE14-PIODNAB429-18GZ-IOOT-150-T-2661 (GE14C) 15 64 GE14-PIODNAB4I3-16GZ-IOOT-150-T-2660 (GE14C) 15 144 Total 560 Page 4

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0

3. Reference Corc Loading Pattern I Nominal previous cycle core average exposure at end of cycle: 33519 MWd/MT

( 30408 MWd/ST)

Minimum previous cycle core average exposure at end of cycle 33096 MWd/MT from cold shutdown considerations: ( 30024 MWd/ST)

Assumed reload cycle core average exposure at beginning of 13945 MWd/MT cycle: ( 12651 MWd/ST)

Assumed reload cycle core average exposure at end of cycle 32286 MWd/MT (full power): ( 29289 MWd/ST)

Reference core loading pattern: Figure I

4. Calculated Core Effective Multiplication and Control System Worth - No Voids, 201C Beginning of Cycle, keffective Uncontrolled 1.126 Fully controlled 0.957 Strongest control rod out 0.986 R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.000

5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)

(at 20'C) (at 160'C, Xenon Free) 720 0.015

' The previous cycle core average exposure at beginning of cycle - based on the original core configuration - was 14505 MWd/MT (13159 MWd/ST). The previous cycle core average exposures at end of cycle, however, are based on the reconfigured Cycle 14 core. Attempting to use the provided values to directly calculate incremental core average exposures will yield erroneous results.

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BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 - Revision 0

6. Reload Unique TRACG Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 2 Exposure: BOC15 to EOFPC15-5029 MWd/MlT (4562 AINNd/ST) with ICF, NFWVT Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow 1MCPR (MWt) (1000 lb/hr)

GE14C 1.0 1.43 1.24 1.040 7.454 118.5 1.37 GE13 1.0 0.65 1.26 1.020 3.383 145.3 2.90 Exposure: EOFPC15-5029 AlWd/MT (4562 MIWd/ST) to EEOC15 with ICF, NFWVT Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MICPR l__ (WQt) (1000 lb/hr)_

GE14C 1.0 1.36 1.31 1.040 7.118 121.9 1.38 GE13 1.0 0.84 1.34 1.020 4.369 135.3 2.10 Exposure: BOC15 to EEOC15 with ICF, RFWT Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr)

GE14C 1.0 1.28 1.36 1.040 6.687 124.4 1.63 GE13 1.0 0.75 1.43 1.020 3.923 140.9 2.64 2 End of Full Power Capability (EOFPC) is defined as end-of-cycle all rods out, 100% power/104.5% flow, and normal feedwater temperature (NFWT).

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BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0

7. Selected Margin Improvement Options Recirculation pump trip: No Rod withdrawal limiter: No Thermal power monitor: Yes Improved scram time: Yes (Option B)

Measured scram time: No Exposure dependent limits: Yes Exposure points analyzed: 2 (EOFPC15-5029 MWd/MT and EEOC15)

8. Operating Flexibility Options Extended Operating Domain (EOD): Yes EOD type: Maximum Extended Load Line Limit (MELLLA)

Minimum core flow at rated power: 99.0 %

EOD type: Maximum Extended Load Line Limit Plus (MELLLA+) 3 Minimum core flow at rated power: 85.0 %

Increased Core Flow: Yes Flow point analyzed throughout cycle: 104.5 %

Feedwatcr Temperature Reduction: Yes (MELLLA)

No (MELLLA+)

Feedwater temperature reduction during cycle: I1 0.3 0F Final feedwater temperature reduction: I 10.3 0F ARTS Program: Yes Single-loop operation: Yes (MELLLA)

No (MELLLA+)

3 MELLLA+ operation is not allowed until approved by the U.S. Nuclear Regulatory Commission. See Appendix F.

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BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 Equipment Out of Ser ice:

Safety/relief valves Out of Service 4 Yes (MELLLA)

No (MELLLA+)

ADS Out of Service Yes (I valve OOS)

MSIVOOS (w/ zero SRVs OOS) 5 Yes (MELLLA)

No (MELLLA+)

TBPOOS 6 Yes

9. Core-wide AOO Analysis Results Methods used: GEMINI (TRACG); GEXL-PLUS Exposure range: BOC15 to EOFPC15-5029 MWd/JMT (4562 W1Vd/ST) with ICF 7

Uncorrected ACPR/ICPR Event Flux SQ/A All Fuel Types Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 267 0.145 2 Exposure range: EOFPC15-5029 AlWd/NIT (4562 MN d/ST) to EEOC15 with ICF, NFWVT Uncorrected ACPRIICPR Event Flux Q/A All Fuel Types Fig.

(%NBR) (%NBR)

Load Reject %v/oBypass 358 - 0.168 3 Exposure range: BOC15 to EEOC15 with ICF and TBPOOS, NFWT Uncorrected ACPRIICPR Event Flux Q/A All Fuel Types Fig.

(%NBR) (%NBR)

FW Controller Failure 386 0.190 4 4 Credit taken for 10 of II valves.

5 The MSIVOOS option is not referenced or supported within GESTAR I.

6 Credit taken for 3 of 4 valves.

7 Uncorrected ACPR/ICPR is being reported since this is the term used in developing the operating limit for TRACG-based analyses.

8 Not available from the TRACG transient output.

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BRUNSWICK UNIT I 0000-001 6-6502-SRLR IRrlanA Ivla 1Ad Pe vircin n se;lll- v Exposure range: EOFPC15-5029 MIlWd/MlT (4562 MNN'd/ST) to EEOC15 with ICF, RFWT Uncorrected ACPRIICMR Event Flux Q/A All Fuel Types Fig.

(%NBR) (%NBR)

FW Controller Failure 282 - 0.193 5 Exposure range: BOCI5 to EEOC15 with ICF and TBPOOS, RFNVT Uncorrected ACPR/ICPR Event Flux Q/A All Fuel Types Fig.

(%NBR) (%NBR) _

FW Controller Failure 336 - 0.212 6

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AQO Summary The rod withdrawal error (RWE) event in the maximum extended operating domain was originally analyzed in the GE BWR Licensing Report, Marimumn Extended Operating Domain Analysis for Brunswick Steam Electric Plant, NEDC-31654P, February 1989. The MCPRs for Brunswick Unit I Cycle 15 RWE are not generally bounded by the safety limit adjusted operating limit MCPRs in Table 10-5(a) or 10-5(b) of NEDC-31654P. The limiting results are shown in the table below for the RBM System setpoints shown in Table 10-5(c) of NEDC-31654P. The RBM operability requirements specified in Section 10.5 of NEDC-31654P have been evaluated to ensure that the Safety Limit MCPR and cladding 1% plastic strain criteria will not be exceeded in the event of an unblocked RWE event. The minimum OLMCPR with RBM inoperable, after cycle-specific SLMCPR adjustment, is 1.45 (=1.40*1.11/1.07).

RBM Setpoint Cycle 15 All HTSP Results Without RBM Filter ACPR 108.0 0.17 111.0 0.20 114.0 0.24 117.0 0.29 Page 9

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0

11. Cycle MCPR Values 9 Safety limit: 1.11 Single loop operation safety limit: 1.12 ECCS OLMCPR Design Basis: See Section 16 Non-pressurization events:

Exposure range: BOC15 to EOCI5 All Fuel Types Control Rod Withdrawal Error (RBM setpoint at 108%) 1.28 Loss of Feedwater Heating 10 1.26 Fuel Loading Error (mislocated) Not limiting GE14C GE13 Fuel Loading Error (misoriented) 1.23 1.24 Pressurization events:

Exposure range: BOC15 to EOFPC15-5029 MNN'd/1*IT (4562 NIWd/ST) with ICF 12 Exposure point: EOFPC15-5029 NIWd/NIT (4562 NVl'd/ST)

Option A Option B All Fuel Types All Fuel Types Load Reject w/o Bypass 1.51 1.33 9 The Operating Limit MCPRs for two loop operation (TLO) bound the Operating Limit MCPRs for Single Loop Operation (SLO); therefore, the Operating Limit MCPRs need not be changed for SLO.

10See Appendix B.

" The mislocated bundle fuel loading error OLMCPR is bounded by the pressurization event OLMCPR.

12 The ICF Operating Limits for the exposure range of BOCI5 to EOFPCI5-5029 MWdIMT (4562 MWd/ST) bound the Operating Limits for the following domains: MELLLA, MELLLA+, MSIVOOS and ICF. See Appendix F regarding the MELLLA+ domain.

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BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Exposurc rangc: EOFPC15-5029 MWdMIT (4562 MWd/ST) to EEOC15 wvith ICF, NFWT 13 Exposure point: EEOC15 O Option A Option B All Fuel Types All Fuel Types Load Reject w/o Bypass T 1.56 T 1.38 Exposure range: BOC15 to EEOC15 with ICF and TBPOOS, NFWVT 14 Exposure point: EEOC15 Option A Option B All Fuel Types All Fuel Types FW Controller Failure 1.60 1.42 Exposure range: EOFPC15-5029 N1Wd/MIT (4562 MlWd/ST) to EEOC15 with ICF, RFNVT i5 Exposure point: EEOC15 Option A Option B All Fuel Types All Fuel Types FW Controller Failure 1.61 1.43 Exposure range: BOC15 to EEOC15 with ICF and TBPOOS, RFWN'T 16 Exposure point: EEOC15 Option A Option B All Fuel Types All Fuel Types FW Controller Failure 1.66 1.48

12. Overpressurization Analysis Summary PsI Pv Plant Event (psig) (psig) Response MSIV Closure (Flux Scram) 1272 1317 Figure 7 13 The NFWT ICF Operating Limits for the exposure range of EOFPC15-5029 MWdlMT (4562 MWd/ST) to EEOC15 bound the Operating Limits for the following NFWT domains: MELLLA, MELLLA+, MSIVOOS and ICF. See Appendix F regarding the MELLLA+ domain.

" The NFWT TBPOOS 1CF Operating Limits for the exposure range of BOC15 to EEOC15 bound the Operating Limits for all NFWT domains with TBPOOS.

15 The RFWT ICF Operating Limits for the exposure range of EOFPC15-5029 MWd/MT (4562 MWd/ST) to EEOC15 bound the Operating Limits for the following RFWT domains: MELLLA, MSIVOOS and ICF.

16 The RFWT TBPOOS ICF Operating Limits for the exposure range of BOC15 to EEOC15 bound the Operating Limits for all RFWT domains with TBPOOS, except MELLLA+, for which RFWT is not allowed. See Appendix F regarding the MELLLA+ domain.

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BRUNSWICK UNIT 1 . 0000-0016-6502-SRLR Reload 14 Revision 0

13. Loading Error Results Variable water gap misoriented bundle analysis: Yes 17 Misoriented Fuel Bundle ACPR GE13-P9DTB405-5G6.o/7G5.0-1OOT-146-T (GE 13) 0.08 GE13-P9DTB402-13G6.0/1 G2.0- IOOT-146-T (GE13) 0.13 GE 14-P I ODNAB416-17GZ- I 00T- I 50-T-2496 (GE I 4C) 0.06 GE 14-P I ODNAB425-16GZ- IOOT-I 50-T-2497 (GE I 4C) 0.12 GE14-PI ODNAB438-12G6.0- OOT-150-T-2498 (GE14C) 0.04 GE 14-P I ODNAB413-16GZ- l00T- 1 50-T-2660 (GE I 4C) 0.06 GE 14-P I ODNAB429-18GZ-IOOT-150-T-2661 (GE14C) 0.06 GE14-PI ODNAB437- 12G6.0- OOT-150-T-2662 (GE 14C) 0.04

14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.

15. Stability Analysis Results Due to the Potential Reportable Condition (PRC 0 1-07) reported by GE on the DIVOM (Delta CPR Over Initial CPR Versus Oscillation Magnitude) slope issue, it is essential to confirm that the generic DIVOM slope used in this Option III stability analysis be applicable to Brunswick Unit I Cycle 15 or an interim OPRM setpoint be used based on a revised DIVOM slope. Should the Option 111 OPRM system be declared inoperable, the BWROG Interim Corrective Action will constitute the stability licensing basis for Brunswick Unit I Cycle 15.

Stability Option III Brunswick Unit I has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM) as described in NEDO-31960-A, BTVR Owners Group Long-Term Stability Solutions Licensing Methodology, November 1995. Plant specific analysis incorporating the Option III hardware is described in GE-NE-C51-00251-00-01, Revision 0, Licensing Basis Hot Bundle Oscillation MagnitudeforBrunswickI and2, March 2001.

Reload validation has been performed in accordance with NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application, August 1996. The stability based MCPR Operating Limit is provided for two conditions as a function of OPRM amplitude setpoint 17Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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BRUNSWICK UNIT I *0000-0016-6502-SRLR PD^I~nf]

lxzuuu 1A I- Revision 0 in the following table. The two conditions evaluated are for a postulated oscillation at 45% core flow steady state operation (SS) and following a two recirculation pump trip (2PT) from the limiting full power operation state point. Current power and flow dependent limits provide adequate protection against violation of the Safety Limit MCPR for postulated reactor instability as long as the operating limit is greater than or equal to the specified value for the selected OPRM setpoint.

The stability-based OLMCPR was calculated for Cycle 15. The reload validation calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 15 as long as the selected OPRM setpoint produces values for OLMCPR(SS) and OLMCPR(2PT) which are less than the corresponding acceptance criteria.

OPRM Setpoint OLMCPR(SS) OLNICPR(2PT)'

1.05 1.2136 1.1343 1.06 1.2355 1.1548 1.07 1.2582 1.1760 1.08 1.2817 1.1980 1.09 1.3062 1.2209 1.10 1.3316 1.2447 1.11 1.3568 1.2682 1.12 1.3830 1.2927 1.13 1.4101 1.3181 1.14 1.4384 1.3445 1.15 1.4679 1.3720 Acceptance Off-rated 0LMCPR Rated Power Criteria @ 45% Flow OLMICPR as described in SRLR Section 11 Interim Corrective Action Stability GE SIL-380 recommendations and BWROG Interim Corrective Actions (BWROG-94079) have been included in the Brunswick Unit I Cycle 15 operating procedures. Regions of restricted operation defined in Attachment I to NRC Bulletin No 88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BIVRs), and expanded in BWROG-94079, are applicable to Brunswick Unit 1. The standard ICA stability regions are expanded as appropriate to offer stability protection per BWROG-02072 for Brunswick Unit I Cycle 15.

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BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0

16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The LOCA method used is SAFER/GESTR-LOCA. The licensing results applicable to each fuel type in the new cycle are summarized in the following table:

Table 16.1-1 Licensing Results Licensing Local Corc-Wide Fuel Type Basis PCT Oxidation Metal-Water (OF) (%) Reaction GE14C 1557 < 1.00 <0.10 GE13 1707 < 1.00 < 0.10 The SAFER/GESTR-LOCA analysis results for these fuel types are documented in Reference 16-1.

16.2 10CFR50.46 Error Evaluation The IOCFR50.46 errors applicable to the Licensing Basis PCT are shown in the table below.

Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GE14C I OCFR50.46 Error Notifications Number Subject PCT Impact (OF) 2002-01 Error in core spray injection elevation +5 2002-02 Error in SAFER initial bulk water level +10 2002-05 Error in WEVOL calculation of downcomer free 0 volume 2003-01 Impact of SAFER level/volume table error on PCT -5 Total PCT Adder (IF) +10 The GE14C Licensing Basis PCT remains below the IOCFR50.46 limit of 2200'F.

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BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Table 16.2-2 Impact on Licensing Basis Peak Cladding Temperature for GE13 IOCFR5O.46 ErrorNotifications Number Subject PCT Impact

('F) 2001-02 An inconsistency in the pressure rate equation +10 2002-01 Error in core spray injection elevation +5 2002-02 Error in SAFER initial bulk water level +10 2002-04 SAFER computer platform change 0 2002-05 Error in WEVOL calculation of downcomer free 0 volume 2003-01 Impact of SAFER level/volume table error on PCT 0 2003-03 Impact of SAFER initial pressure drop on the PCT 0 Total PCT Adder (IF) +25 The GE13 Licensing Basis PCT remains below the IOCFR50.46 limit of 2200'F.

16.3 ECCS-LOCA Operating Limits The ECCS MAPLHGR operating limits have been merged with the thermal-mechanical MAPLHGR operating limits to produce a set of fuel type dependent composite MAPLHGR limits representing the most restrictive values of both. The most and least limiting values of these composite MAPLHGRs for each of the new fuel bundles in this cycle are shown in the tables below:

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BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Table 16.3-1 NIAPLHIGR Limits Bundle Type: GE14-PIODNAB413-16GZ-IOOT-150-T-2660 Average Planar Exposure lIAPLIIGR (kl/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 9.57 9.68 0.20 0.22 9.60 9.70 1.00 1.10 9.66 9.78 2.00 2.20 9.77 9.91 3.00 3.31 9.92 10.06 4.00 4.41 10.08 10.22 5.00 5.51 10.26 10.38 6.00 6.61 10.44 10.55 7.00 7.72 10.59 10.73 8.00 8.82 10.74 10.91 9.00 9.92 10.87 11.11 10.00 11.02 11.00 11.31 11.00 12.13 11.12 11.52 12.00 13.23 11.15 11.66 13.00 14.33 11.16 11.75 14.00 15.43 11.16 11.74 14.51 15.99 11.16 11.73 15.00 16.53 11.16 11.71 17.00 18.74 11.13 11.58 19.13 21.09 11.02 11.38 20.00 22.05 10.98 11.30 25.00 27.56 10.57 10.75 30.00 33.07 10.15 10.21 35.00 38.58 9.65 9.69 40.00 44.09 9.12 9.17 45.00 49.60 8.59 8.65 50.00 55.12 8.04 8.11 55.00 60.63 6.48 6.64 57.61 63.50 5.18 5.34 58.20 64.16 4.88 5.05 58.23 64.19 - 5.03 58.48 64.46 _ 4.91 58.50 64.48 _ 4.90 Page 16

BRUNSWICK UNIT I 0000-001 6-6502-SRLR rMInnrl 14 RPvUc,;nn n Table 16.3-2 MIAPLHGR Limits Bundle Type: GE 14-P I ODNAB429-1 8GZ- I OOT-1 50-T-2661 Average Planar Exposure MAPLIIGR (kWV/ft)

(GWd/ST) (GWd!MT) Most Limiting Least Limiting 0.00 0.00 8.89 9.12 0.20 0.22 8.98 9.20 1.00 1.10 9.05 9.30 2.00 2.20 9.16 9.42 3.00 3.31 9.29 9.53 4.00 4.41 9.43 9.65 5.00 5.51 9.55 9.81 6.00 6.61 9.68 9.97 7.00 7.72 9.81 10.10 8.00 8.82 9.94 10.23 9.00 9.92 10.08 10.37 10.00 11.02 10.23 10.52 11.00 12.13 10.28 10.62 12.00 13.23 10.31 10.66 13.00 14.33 10.34 10.70 14.00 15.43 10.37 10.76 14.51 15.99 10.39 10.80 15.00 16.53 10.41 10.84 17.00 18.74 10.49 10.96 19.13 21.09 10.53 10.97 20.00 22.05 10.55 10.98 25.00 27.56 10.35 10.59 30.00 33.07 9.89 10.12 35.00 38.58 9.43 9.65 40.00 44.09 8.95 9.18 45.00 49.60 8.45 8.69 50.00 55.12 7.92 8.16 55.00 60.63 5.83 6.60 56.71 62.51 4.97 5.74 56.87 62.69 - 5.66 57.61 63.50 - 5.29 58.03 63.97 - 5.08 58.30 64.27 - 4.95 Page 17

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Table 16.3-3 NIAPLI]GR Limits Bundle Type: GE I 4-P I ODNAB437-1 2G6.0-1 OOT-I 50-T-2662 Average Planar Exposure MIAPLIIGR (kNNlft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 9.06 9.21 0.20 0.22 9.11 9.27 1.00 1.10 9.20 9.36 2.00 2.20 9.31 9.48 3.00 3.31 9.43 9.62 4.00 4.41 9.55 9.76 5.00 5.51 9.68 9.90 6.00 6.61 9.81 10.05 7.00 7.72 9.95 10.21 8.00 8.82 10.09 10.37 9.00 9.92 10.23 10.53 10.00 11.02 10.38 10.71 11.00 12.13 10.45 10.84 12.00 13.23 10.48 10.91 13.00 14.33 10.51 10.98 14.00 15.43 10.54 11.03 14.51 15.99 10.55 11.05 15.00 16.53 10.56 11.06 17.00 18.74 10.56 11.03 19.13 21.09 10.49 10.94 20.00 22.05 10.47 10.89 25.00 27.56 10.20 10.62 30.00 33.07 9.87 10.28 35.00 38.58 9.42 9.80 40.00 44.09 8.95 9.32 45.00 49.60 8.45 8.82 50.00 55.12 7.91 8.29 55.00 60.63 5.56 6.58 56.27 62.02 4.91 5.93 57.61 63.50 - 5.23 58.05 63.99 5.00 58.14 64.09 4.96 Page 18

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 The single loop operation multiplier on LHGR and MAPLHGR and the ECCS Initial MCPR values applicable to each fuel type in the new cycle core are shown in the table below.

Table 16.34 Initial MCPR and Single Loop Operation PLHIGR and MAPLHGR Multiplier Initial MCPR Single Loop Operation Fuel Type PLIIGR and MiAPLHIGR Multiplier GE14C 1.275 0.80 GE13 1.200 0.80 16.4 References The SAFER/GESTR-LOCA analysis base reports applicable to the new cycle core are listed below.

Reference No. Reference 16-1 Brunsvick NuclearPlant Unit I and2 Extended Power UprateTask 0407 ECCS-LOCA SAFER/GESTR Project Task Report, GE-NE-A22-00113-27-01, Revision 0, June 2001.

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e'0- P19 lIDl~ [ WM 3ms MDl§IDlwoE Ml~ eM M 28 124 AE]ID[EE [E] C I][E] [E] m[DE] D 3f [E))[F] [CD [E] D ID [CDGED [I [

10ElES lSEl ES l[E lE [lEl [El 1 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 FuelType A=GE13-P9DTB405-5G6.0MG5.0-lOOT-146-T (Cycle 13) F=GE14-PIODNAB413-16GZ-IOOT-150-T-2660 (Cycle 15)

B=GE13-P9DTB402-13G6.0/IG2.0-]OOT-146-T (Cycle 13) G=GE14-PIODNAB429-18GZ-IOOT-150-T-2661 (Cycle 15)

C=GE14-PIODNAB416-17GZ-IOOT-150-T-2496 (Cycle 14) 11=GE14-PIODNAB429-18GZ-lOOT-150-T-2661 (Cycle 15)

D=GE14-PIODNAB425-16GZ-lOOT-150-T-2497 (Cycle 14) 1=GE14-PIODNAB437-12G6.0-lOOT-150-T-2662 (Cycle 15 E=GE14-PIODNAB438-12G6.0-lOOT-150-T-2498 (Cycle 14) _

Figure 1 Reference Core Loading Pattern Page 20

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 0

12 00 1.0 20 so 4.0 50 50 00 1.0 ZO 3.0 Time (sec) Time (sec)

Figure 2 Plant Response to Load Reject w/o Bypass BOC15 to EOFPC15-5029 MWd/NIMT (4562 NINN'd/ST) with ICF Page 21

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 es st 30 40 *0 60 0.0 1.0 zo l0 40 6.0 t0 Time (sec) Time (see)

X soo es

-- ,5.

00 1.0 2.0 10 40 50 s0 *0 2.0 3.0 4.0 50 60 Time (Sec) Time (sec)

Figure 3 Plant Response to Load Reject w/o Bypass EOFPC15-5029 MWdIMT (4562 MWd/ST) to EEOC15 with ICF, NFWT Page 22

BRUNSWICK UNIT I 0000-00 1 6-6502-SRLR Reload 14 Revision 0 U2

,U 13 25

-23 0.0 20 40 *0 *0 10 0 12.0 14 0 1l 0 100 Time (sec) 3.0

-Total Reactivity 10 05 0,00 a

• 0

'U 750 E

00 45 AII

.15

-2.0 4 00 2.0 40 60 r0 100 lZ1 0.0 20 40 60 80 100 12.0 140 16.0 WeO 200 Time (0se) Time (sec)

Figure 4 Plant Response to FW Controller Failure BOC15 to EEOCI5 with ICF and TBPOOS, NFWT Page 23

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 s

e0 20 40 6*0 0 100 120 14.0 160 toI 20.0 00 2.0 4.0 0 ao0 10.0 12.0 14o 160 18.0 200 Tkne (sec) Tbne (sec) 1.I

-Total Reacbvity 10 0e C 00 00 0 a.

E 0

00.0 2W4 0 40

.1.0

.1.5 o0 2.0 o0 0 80 la0 12.0 140 1.0 180 20.0 00 20 40 60 8.0 10.0 12.0 u.0 160 180 20.0 Time (sec) Time (sec)

Figure 5 Plant Response to FW Controller Failure EOFPC15-5029 MWd/JIT (4562 MAWd/ST) to EEOC15 with ICF, RFWT Page 24

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 250.0 N utron Flux

-- a- Core Inlet Flow z )00 Core Inlet Subcooling V!10.0 I'

100 50 20 40 6.0 a0 10O 120 140 160 10 200 Time (sec) 5000 0.0 20 40 60 80 100 120 14O0 160 0 20.0 00 20 40 60 80 10.0 IZO 140 160 18.0 20.0 Time (Sec) Time (sec)

Figure 6 Plant Response to FW Controller Failure BOC15 to EEOC15 with ICF and TBPOOS, RFWT Page 25

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 275 0

-s--Vessel Press Rise (psi)

-- Total SRV Flow

-.- Bypass Valve Flow 2250 575.0

.S 11:

121250 750 250 0.0 10 20 30 40 50 60 7.0 00 10 20 20 40 5.0 *0 70 T km (sec)

Time (sec)

I 0.0 1.0 2.0 10 40 00 60 7.0 00 I0 2.0 t0 40 o0 60 7.0 Time (sec) Time (sec)

Figurc 7 Plant Response to AISIV Closure Flux Scram Page 26

BRUNSWICK UNIT I

• 0000-0016-6502-SRLR Reload 14 Revision 0 Appendix A Analysis Conditions To reflect actual plant parameters accurately, the values shown in Table A-I were used this cycle.

Table A-1 Parameter Analysis Value Analysis Value NFNVT RFMT Thermal power, MWt 2923.0 2923.0 Core flow, Mlb/hr 80.5 80.5 Reactor pressure, psia 1060.3 1039.8 Inlet enthalpy, BTU/lb 529.4 513.3 Non-fuel power fraction' 8 Steam flow, Mlb/hr 12.79 11.12 Dome pressure, psig 1031.5 1012.2 Turbine pressure, psig 971.4 966.2 Number of Safety/Relief Valves 10 10 Relief mode lowest setpoint, psig 1163.9 1163.9 Recirculation pump power source on-site 19 on-site 19 Turbine control valve mode of operation Partial arc Partial arc I8 Not available in the TRACG output files.

19Bounds operation with off-site power source for reload licensing events for Cycle 15.

Page 27

BRUNSWICK UNIT I 0000-0016-6502-SRLR*

Reload 14 Revision 0 Appendix B Decrease in Core Coolant Temperature Events The Loss of Feedwater Heating (LFWH) event and the Inadvertent HPCI start-up event are the only cold water injection AQOs checked on a cycle-by-cycle basis.

The LFWH event was analyzed for Brunswick Unit I Cycle 15 using the BWR Simulator Code. The use of this code is permitted in GESTAR 11. The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.

In addition, the Inadvertent HPCI start-up event was shown to be bounded by the LFWH event in Brunswick Unit I Cycle 15 in accordance with Reference B-I.

Reference B-I. DeterminationofLimiting Cold Water Event, NEDC-32538P-A, February 1996.

Page 28

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 Appendix C Operating Flexibility Options Reference C-I provides a basis for operation of the Brunswick Steam Electric Plant (BSEP) with one Main Steamline Isolation Valve Out of Service (MSIVOOS) (three steamline operation) and all SRVs in service. For MSIVOOS, the OLMCPRs presented in Section 11 and peak overpressure results in Section 12 are bounding. MSIVOOS will not be allowed while operating in the MELLLA+ domain (see Appendix F).

Reference C-2 provides a basis for operation of the Brunswick Steam Electric Plant (BSEP) with Feedwater Temperature Reduction (FWTR). The required OLMCPRs are provided in Section 11. FWTR and FWHOOS will not be allowed while operating in the MELLLA+ domain (see Appendix F).

Reference C-3 provides a basis for operation of the Brunswick Steam Electric Plant (BSEP) with Maximum Extended Operating Domain (MEOD). The required OLMCPRs are provided in Section I1.

Reference C4 provides a basis for operation of the Brunswick Steam Electric Plant (BSEP) with all Turbine Bypass Valves Out of Service (TBPOOS). The required OLMCPRs are provided in Section 11.

The impact of GE14 fuel on the operating flexibility options is addressed in Reference C-5.

The ARTS power and flow dependent operating limits for all operating flexibility options are provided in References C-3 and C-6. The safety limit change for Brunswick Unit I Cycle 15 from the reference safety limits used in References C-6 and C-3 requires an adjustment to the MCPR(p) below P-bypass limits and MCPR(f) limits. Further, the implementation of TRACG (Reference C-7) requires an adjustment to the K(P) above P-bypass.

The Reference C-6 MCPR(p) below P-bypass is increased for a Safety Limit of 1.1I by the ratio of (I41 J. The power-dependent limits in Figure C-I and Figure C-2 apply to all fuel types in the core.

Page 29

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 3.50 I I

-< >50% Flow 3.25 3.00

-Y ~ - F_ \ _ _ _

2.75

'S50% Flow -

2.50 Operating Limit MCPR (P) = K(P)

• Operating Limit MCPR (100) ix C-CL For P < 23%: No Thermal Limits Required O 2.25 . For 23% S P < 26%, > 50% Flow:

OLMCPR(P) = 3.13+ 0.0900.(26% - P) c For 23% S P < 26%,

• 50% Flow:

2.00 . OLMCPR(P) = 2.34 + 0.0700.(26% - P)

For 26%

• P < 45%: K(P) = 1.28 + 0.0135-(45% - P) 1.75 For 45%

• P < 60%: K(P) = 1.18 + 0.00667.(60% - P)

For 60%

• P: K(P) = 1.00 + 0.00450.(100% - P) 1.50 1.25 1.00 I 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

Figure C-1 Power Dependent MCPR for Brunswick Unit 1 Cycle 15 Page 30

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 1.10 1.00 -

0.90 - I --- I___ -

0.80 0.70 -

a.

E 0.60 MAPLHGR(P) = MAPFAC(P).MAPLHGRstd MAPLHGRstd = Rated MAPLHGR limits P s 50%

0.50 I r2-I I Flow For P< 23%: No Thermal Limits Required For 23% S P < 26%, > 50% Flow:

0.40 iI

\T MAPFAC(P) = 0.433+ 0.0063.(P - 26%)

For 23% S P < 26%, S 50% Flow:

MAPFAC(P) = 0.567 + 0.0157-(P - 26%)

> 50% For 26% S P:

Flow MAPFAC(P) =1.0 + 0.005224.(P - 100%)

0.30 -

,U.ZU._II I. I - I . . .I I > .. I. I I

I I1, .1...1. -I 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

Figure C-2 Power Dcpendent MAPL11GR Factor for Brunswick Unit I Cycle 15 Page 31

BRUlNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 The Reference C-3 MCPR(f) limits are increased for a Safety Limit of 1.11 by the ratio of ( )

The following coefficients apply for all fuel types in the core:

Maximum Core Flow

(% of Rated) A(f) B(i) Flow Intercept MCPR

(% of Rated) 102.5 -0.592 1.717 80.51 1.24 107.0 -0.608 1.760 85.61 1.24 112.0 -0.625 1.812 91.64 1.24 117.0 -0.656 1.877 97.10 1.24 The flow-dependent MAPLHGR limit multiplier, MAPFAC(f), is not altered for Brunswick Unit I Cycle 15.

Since the cycle-specific SLO SLMCPR is equal to 1.12, per Reference C-5, the TLO OLMCPR must be greater than or equal to 1.32 (to ensure that the SLO OLMCPR is greater than or equal to 1.40). From Reference C-5, the initial power for the licensing basis pump seizure event is 2143 MW4h, or 73.3% of licensed thermal power for Brunswick Unit I Cycle 15. The K(P) for this power, from Figure C-I, is 1.12. Therefore, the required minimum TLO OLMCPR of 1.32 is conservative for Brunswick Unit I Cycle 15.

References C-I. Main Steamline Isolation Valve Out of Service for the Brunswvick Steam Electric Plant, EAS-1 17-0987, GE Nuclear Energy (Proprietary), April 1988.

C-2. Feedwater Temperature Reduction with Maximum Extended Load Line Limit and Increased Core Flowvfor Brunswvick Steam Electric Plants Units I and 2, NEDC-32457P, Revision I, GE Nuclear Energy (Proprietary), December 1995.

C-3. Maximum Extended Operating Domain Analysis for Bmnswvick Steam Electric Plant, NEDC-31654P, GE Nuclear Energy (Proprietary), February 1989.

C-4. Turbine Bypass Out of Service Analysisfor CarolinaPower & Light Company's Brunswvick Nuclear Plants Units I and2, NEDC-32813, Revision 3, GE Nuclear Energy (Proprietary), June 1998.

C-5. GE)4 Fuel Design Cycle-Independent Analyses for Brunswick Steam Electric Plants Units I and 2, GE-NE-L12-00876-00-OIP, GE Nuclear Energy (Proprietary), February 2001.

C-6. Safety Analysis Report for Brunsivick Steam Electric Plant Units I and 2 Extended Power Uprate, NEDC-33039P, GE Nuclear Energy (Proprietary), August 2001.

Page 32

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 C-7. Brunsvick Nuclear Station TRACG Implementationfor Reload Licensing Transient Analysis, GE-NE-0000-0022-8 180-RO, GE Nuclear Energy (Proprietary), February 2004.

Page 33

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 Appendix D Implementation of TRACG AOO Methodology Reference D-l provides the results of the analyses and evaluations supporting the implementation of TRACG for AOO analyses for the Brunswick Steam Electric Plant Units I and 2. The report requires the increase of K(P) from 1.15 to 1.18 at 60% power (See Appendix C). Additionally, the report specifies a scram speed adjustment factor (SSAF) of 0.18 for GEI4 fuel.Section II of this report presents the MCPR limits based on the methodology of Reference D-2.

References D-l. Brunswick Nuclear Station TRACG Implementation for Reload Licensing Transient Analysis, GE-NE-0000-0022-8180-RO, GE Nuclear Energy (Proprietary), February 2004.

D-2. TRACG Applicationfor Anticipated OperationalOccurrences Transient Analysis, NEDE-32906P-A, Revision 1, April 2003.

Page 34

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 Appendix E Normal and Reduced Feedwater Temperature Limits In some cases, a distinction is made between the OLMCPR values for the normal feedwater temperature (NFWT) and reduced feedwater temperature (RFWT) domains. Specifically, for EOFPC15-5029 MWd/MT to EEOC15, the NFWT and RFWT limits are specified separately. Further, the NFWT and RFWT limits are separated at any cycle exposure for which the TBPOOS operating flexibility option is employed. The RFWT limits, when specified separately from the NFWT limits, apply to both feedwater temperature reduction and feedwater heater out of service. The results of the analyses are insensitive to feedwater temperature deviations of less than 100 F.

Page 35

BRUNSWICK UNIT I 0000-00 1 6-6502-SRLR Reload 14 Revision 0 Appendix F MELLLA4 Implementation Brunswick is seeking approval to operate in the MELLLA+ domain, which would provide greater core flow flexibility, particularly as power approaches 120% of the original licensed thermal power (OLTP).

Approval is not expected prior to startup of Brunswick Unit I Cycle 15. However, the cycle-specific reload licensing analyses were performed to support operation with or without the MELLLA+ domain.

Special consideration of MELLLA+ was given during performance of the transient analyses, stability analyses, and LOCA analyses.

The pressurization transients are generally limiting at high flow conditions. However, the transients were performed at both the minimum MELLLA+ flow (85%) and the maximum ICF flow (104.5%). This ensures that the pressurization transient results bound both MELLLA and MELLLA+. Additionally, the loss of feedwater heating (LFWH) transient, which is more limiting at low flow, was performed at the minimum MELLLA+ flow. Therefore, the limiting subcooling transient bounds both MELLLA and MELLLA+. Reduced feedwater temperature (FFWTR and FWHOOS) and single loop operation (SLO) will not be allowed in conjunction with operation in the MELLLA+ domain. Further, no SRVs will be allowed to be out of service in the MELLLA+ domain. However, the pressurization transients were performed at MELLLA+ with I SRV out of service to ensure that both MELLLA and MELLLA+ are bounded. Finally, TBPOOS will be allowed in the MELLLA+ domain, but MSIVOOS will not.

For EPU/MELLLA+ operation, the Detect and Suppress Solution - Confirmation Density (DSS-CD) is the licensing basis for Brunswick Unit I Cycle 15. The reload checklist as outlined in Reference F-2 is used to confirm that the DSS-CD is applicable to Brunswick Unit I Cycle 15 EPU/MELLLA+ operation.

DSS-CD Plant Specific Applicability Checklist t . Parameter.,J .2A'; Criter XX cpt ance-BWVR Product Line BWR/3-6 design as of July 2002 Yes (BWR/4)

Fuel Product Line GE14 and earlier GE designs Yes (GE 14 and GE 13)

Operating Domain < EPU/MELLLA+ including BWR/3-6 Yes licensed operational flexibility features as of July 2002 Rated TFW 0

• 120 F (EPU/MELLLA) Yes Reduction No TFW Reduction (MELLLA+

extension)

MCPR Margin OLMCPRRated -SLMCPR 2 0.067 Yes (0.196)

OLMCPR Rated Page 36

BRUNSWICK UNIT I 0000-0016-6502-SRLR Reload 14 Revision 0 The application of the ECCS-LOCA analysis to operation in the MELLLA+ power/flow region was addressed in Reference F-3. Elimination of the 1600'F Upper Bound peak cladding temperature limit has been incorporated as defined in Reference F-4.

References F- I. Safety Analysis Reportfor Brunswvick Steam ElectricPlant Units I and 2 Maximum Extended Load Line Limit Analysis Plus, NEDC-33063P, GE Nuclear Energy (Proprietary), November 2002.

F-2. General Electric Boiling Water Reactor Detect and Suppress Solution - Confirmation Density Licensing Topical Report, NEDC-33075P, Revision 3, GE Nuclear Energy (Proprietary), January 2004.

F-3. Brunswick Nuclear Plant Unit 1 and 2 MELLLA + Task 0407 ECCS-LOCA SAFER/GESTR Project Task Report, GE-NE-A22-00113-83-01, Revision 0, September 2002.

F-4. GESTR-LOCA and SAFER Models for Evaluation of Loss-of-Coolant Accident Volume III, Supplement 1, Additional Informationfor Upper Botnd PCT Calculation, NEDE-23785P-A, Volume 111, Supplement 1, Revision 1, March 2002.

Page 37

BRUNSWICK UNIT I 0000-00 1 6-6502-SRLR Reload 14 Revision 0 Appendix G List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective

%NBR Percent Nuclear Boiler Rated 2PT Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio ECCS Emergency Core Cooling System EEOC Extended End of Cycle ELLLA Extended Load Line Limit Analysis EOC End of Cycle EOR End of Rated (All Rods Out 100%Power /1 00%Flow)

ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWTR Feedwater Temperature Reduction GDC General Design Criterion GETAB General Electric Thermal Analysis Basis GSF General Shape Function HAL Haling Bum 11B Ilard Bottom Burn IIBOM Hot Bundle Oscillation Magnitude IICOM Hot Channel Oscillation Magnitude l1FCL High Flow Control Line ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Page 38

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 L}IGR Linear I leat Generation Rate LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LR1IBP Load Rejection with 1lalf Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPLIIGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal NBP No Bypass NCL Natural Circulation Line NFWT Nonnal Feedwater Temperature NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR QOS Out of Service OPRM Oscillation Power Range Monitor Pdome Peak Dome Pressure Psi Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PIlE Peak Hot Excess PLIIGR Peak Linear Heat Generation Rate PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report SS Steady State Page 39

BRUNSWICK UNIT I 0000-001 6-6502-SRLR Reload 14 Revision 0 STU Short Tons (or Standard Tons) of Uranium TBPOOS Turbine Bypass Valves Out of Service TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TTIIBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Burn Page 40

BSEP 04-0037 Enclosure 3 NEDC-31624P, Supplement 1, Revision 8, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 1 Reload 14 Cycle 15, February 2004