BSEP 06-0034, Supplemental Reload Licensing Report for Brunswick, Unit 1, Reload 15 Cycle 16, December 2005

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Supplemental Reload Licensing Report for Brunswick, Unit 1, Reload 15 Cycle 16, December 2005
ML060950124
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 12/31/2005
From:
Global Nuclear Fuel - Americas
To:
Office of Nuclear Reactor Regulation
References
BSEP 06-0034 0000-0038-9350-SRLR, Rev 0
Download: ML060950124 (44)
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BSEP 06-C'034 Enclosure 2 0000-0038-9350-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 15 Cycle 16, December 2005

GNF Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 0000-0038-9350-SRLR Revision 0 Class I December 2005 Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 15 Cycle 16

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Progress Energy Carolinas, Inc. ("Recipient") in support of the operating license for Brunswick Unit 1 (the "Nuclea.r Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of tae Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Infcrmation or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.

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BRUNSWICK UNIT 1 0000-0038-9350-SI'RLR Reload 15 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 GEEN - Nuclear and Safety Analysis personnel. The Supplemental Reload Licensing Report was prepared by G. M. Baka and C. F. Lemb. This document has been verified by R. D. McCord and M. A. Holmes.

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BRUN';WICK UNIT 1 0000-0038-9350-SRLR Reload 15 Revision 0 The basis for this report is GeneralElectric StandardApplicationfor Reactor Fuel, NEDE-240 11-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: TRACG AOO Methodology Appendix E: MELLLA+ Implementation Appendix F: Normal and Reduced Feedwater Temperature Limits Appendix G: List of Acronyms
2. Rcload Fuel Bundles Fuel Type Cycle Number Loaded Irradiated:

GE'14-P I ODNAB416-17GZ-I OOT- 150-T-2496 (GE 14C) 14 3 GE:14-P I ODNAB425-16GZ-I OOT-150-T-2497 (GE 14C) 14 16 GE:14-P I ODNAB438-12G6.0-l OOT-150-T-2498 (GE14C) 14 45 GE:14-PIODNAB413-16GZ-IOOT-150-T-2660 (GE14C) 15 144 GE'14-P I ODNAB429-18GZ-I OOT-150-T-2661 (GE 14C) 15 64 GE'14-P I ODNAB437-12G6.0-1 OOT-150-T-2662 (GE 14C) 15 38 New::

GE'14-P I ODNAB437-12G6.0-1 OOT-150-T-2662 (GE14C) 16 40 GE :14-P I ODNAB425-1 8GZ- I OOT- I 50-T-2854 (GE 14C) 16 60 GE'14-P IODNAB407-16GZ-IOOT-150-T-2853 (GE 14C) 16 150 Total: 560 Pagre 4

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0

3. Reference Core Loading Pattern Core Average Cycle Average Exposure Exposure i i 33609 MWd/MT 19476 MWd/MT Nominal previous end-of-cycle exposure: (30489 MWd/ST) (17669 MWd/ST)

Minimum previous end-of-cycle exposure 33170 MWd/MT 19037 MWd/MT (for cold shutdown considerations): (30091 MWd/ST) (17270 MWd/ST)

. . 13709 MWd/MT 0 MWd/MT Assumed reload beginnig-of-cycle exposure: (12436 MWd/ST) (0 MWd/ST)

Assumed reload end-of-cycle exposure (rated 31839 MWd/MT 18130 MWd/MT conditions): (28884 MWd/ST) (16447 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 Ful!.y controlled 0.956 Strongest control rod out 0.986 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.000 Cycle average exposure at which R occurs 0 MWd/MT
5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)

(at 201C) (at 1601C, Xenon Free)

Analytical Requirement Achieved 720 >0.01 1 0.015 Page 5

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0

6. Reload Unique TRACG Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters I Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1 )

Peaking Factors Fuel Bundle Bundle Initial Fuel Local Radial Axial R-Factor Power Flow MCPR Desgn (MWt) (1000 lb/hr) C GE14C 1.0 1.47 1.35 1.040 7.674 118.7 1.34 Operating domain: ICF (HBB)

Exposure range : MOC to EOC (Application Condition: 1 )

Peaking Factors

'Fuel Bundle Bundle Initial

.Feln Local Radial Axial R-Factor Power Flow MCPR Design 13(MWt) (1000 lb/hr) MCPR GE14C 1.0 1.33 1.34 1.040 6.955 124.3 1.45 Operating domain: ICF with TBVOOS and NFWT (HBB)

Exposure range : BOC to EOC (Application Condition: 2 )

. ____ Peaking Factors l

'Fuel Bundle Bundle Initial Dein Local Radial Axial R-Factor Power Flow MP DEsign 1.34 1.040 (MWt) (1000 lb/br) MCPR GE14C 1.0 1.33 040124.3 6.955 1.45 Operating domain: ICF with TBVOOS and RFWT (UB)

Exposure range : BOC to EOC (Application Condition: 2 )

Peaking Factors l

'Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power BFlowlI R Desig 1(MWt) (1000 lb/hr) MCPR GE14C r1.0 1.24 1.38T 1.040 6.448 127.8 1.77 XExposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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BRUNE-WICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0

7. Selected Margin Improvement Options 2 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 Table 7-1 Cycle Exposure Range Designation 3

Name Exposure Range BOC to MOC BOC16 to EOR16-4130 MWd/MT (3747 MWd/ST)

MOC to EOC EOR164130 MWd/MT (3747 MWd/ST) to EOC16 BOC to EOC BOC16toEOC16 2 Refer t3 GESTAR for those margin improvement options that are referenced and supported within GESTAR.

3 End of Rated (EOR) is defined as the cycle average exposure corresponding to all rods out, 100% poiver/100%

flow, and normal feedwater temperature.

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BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revisi:Dn 0

8. Operating Flexibility Options 4 The fol owing information presents the operational domains and flexibility options which are supported by the reload licensing analysis. Inclusion of these results in this report is not meant to imply that these domains and options have been fully licensed and approved for operation.

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+) 5 Minimum core flow at rated power: 85.0 %

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

Feedwater Temperature Reduction: Yes (MELLLA)

No (MELLLA+)

Feedwater temperature reduction during cycle: 1 10.3 0F Final feedwater temperature reduction: 1 10.3 0F ARTS Program: Yes Single Loop Operation: Yes (MELLLA)

No (MELLLA+)

Equipment Out of Service:

One Safety/relief valves Out of Service: Yes (MELLLA)

No (MELLLA+)

ADS Out of Service: Yes (1 Valve OOS)

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

No (MELLLA+)

TBVOOS (w/ one SRV OOS) 6 Yes 4 Refer to GESTAR for those operating flexibility options that arc referenced and supported within GESTAR.

5 MELL:A+ operation is not allowed until approved by the U.S. Nuclear Regulatory Commission. See Appendix E.

6

\When the Turbine Bypass System is credited, 3 of 4 valves are assumed operable in the analysis.

Pag e 8

BRUNSWICK UNIT I 0000-0038-9350-SRLR Relnad 15 Revision 0

9. Core-wide AOO Analysis Results 7 Methods used: GEMINI (TRACG), GEXL-PLUS Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1)

Uncorrected ACPR/ICPR 8 EetFlux Q/A9

=_Event l (%rated) (%rated) GE14C Fig.

Load Rejection w/o Bypass 315 l 0.158 2 FW Controller Failure 265 - 0.143 3 Operating domain: ICF (HBB)

Exposure range : MOC to EOC (Application Condition: 1)

Uncorrected ACPRICPR __

Event l Q/A Fig. GE14C

___ ___

___ __

___ __ ___ ___ __ (% rated) (% rated) G 1 CF g Load ejection w/o Bypass 434 0.185 4 FW Controller Failure 381 - 0.181 5 Operating domain: lCF with TBVOOS and NFWT (HBB)

Exposure range : BOC to EOC (Application Condition: 2)

Uncorrected ACPR/ICIPR Event Flux Q/A G1CFg

(%~~~rated) (%rated) G1CFg FW Controller Failure 458 - 0.204 6 Operating domain: ICF with TBVOOS and RFWT (UB)

Exposure range : BOC to EOC (Application Condition: 2)

Uncorrected ACPR/ICIPR Event Flux Q/A G1CFg

______ (%~~rated) (%rated) G1CFg ntroller Failure 394 - 0.241 7

' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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

9Not available from the TRACG transient output.

Pagte 9

BRUNE-WICK UNIT I 0000-0038-9350-SIILR Reload 15 Revision 0

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The rod withdrawal error (RWE) event in the maximum extended operating domain was originally analyzed in the GE BWR Licensing Report, Maximum Extended Operating Domain Analysis for Brmnsw!ck Steam Electric Plant, NEDC-31654P, February 1989. The MCPRs for Brunswick Unit I Cycle 16 RWE are not generally bounded by the safety limit adjusted operating limit MCIPRs 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 (for RBM inoperable: OLMCPR 2 1.40 for power 2 90% and OLMC1'R 2 1.70 for power < 90%) have been evaluated and shown to be sufficient to ensure that the Safety Limit MCPR will not be exceeded in the event of an unblocked RWE event. In addition, the cladding 1%plastic strain criteria have been met.

RBM Setpoint Cycle 16 All HTSP Results Without RBM Filter ACPR 108.0 0.18 111.0 0.22 114.0 0.27 117.0 0.29 Page 10

BRUNSWICK UNIT 1 0000-0038-9350-SRLR Reload 15 Revision 0

11. Cytcle MCPR Values 10,11 Two loop operation safety limit: 1.11 Single loop operation safety limit: 1.12 Stability MCPR Design Basis: See Section 15 EC'CS MCPR Design Basis: See Section 16 (Initial MCPR)

Non-pressurization events:

Exposure range: BOC to EOC GE14C Control Rod Withdrawal Error (RBM setpoint at 108%) 1.29 Loss of Feedwater Heating 12 1.26 Fuel Loading Error (mislocated) Not limiting 13 Fuel Loading Error (misoriented) 1.17 Limiting Pressurization Events OLMCPR Summary Table: 14 Cond. Exposure Range Option A Option B GE14C GE14C I Normal Operation (w/ Equipment-in-Service)

=_ BOC to MOC l 1.52 l 1.34 MOC to EOC 1.56 1.38 2 TBVOOS (w/ one SRV OOS)

BOC to EOC, NFWT 1.61 1.43 BOC to EOC, RFWT l 1.70 1.52

'0Exposure range designation is defined in Table 7-1.

" The Operating Limit MCPRs for Two Loop Operation (TLO) bound the Operating Limit MCPRs for Single Loop Operaticn (SLO); therefore, the Operating Limit MCPRs need not be changed for SLO.

12See Appendix B.

3 The Dislocated bundle fuel loading error OLMCPR is bounded by the pressurization event OLMCPR.

14 Each .application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperature unless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loop operation safety limit MCPR.

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BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Pressurization events: 15 Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1 )

Option A Option B

_ ; _::  : _____: ____._= _____^_____: __-; _ GE14C GE14C Load Rejection w/o Bypass 1.52 1.34 FW Controller Failure Not Limiting16 Not Limiting' Operating domain: ICF (HBB)

Exposure range MOC to EOC (Application Condition: 1) 4 - Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.56 1.38 FW (Controller Failure Not Limiting 16 Not Limiting' 6 Operating domain: ICF with TBVOOS and NFWVT (HBB)

Exposure range : BOC to EOC (Application Condition: 2 )

4 Option A Option B GE14C GE14C FW Controller Failure 1.61 1.43 Operating domain: ICF with TBVOOS and RFWT (UB)

Exposure range : BOC to EOC (Application Condition: 2 )

- - Option A Option B FW ___________Failure_ GE14C GE14C FWController Failure 1.70 1.52

12. Overpressurization Analysis Summary Event PsI Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) - ICF (H-IBB) 1270 1279 1316 Figure 8 15 Application condition numbers shown for each of the following pressurization events represent the application conditions for which this event contributed in the determination of the limiting OLMCPR value.

16 The FW Controller Failure OLMCPR is bounded by the Load Rejection wv/o Bypass event OLMCPR.

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BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0

13. Leading ErrorResults Variable water gap misoriented bundle analysis: Yes 17 Misoriented Fuel Bundle ACPR GE.4-1? I0DNAB416-17GZ-IOOT-150-T-2496 (GE14C) 0.06 GE 14-? 1ODNAB413-16GZ-100T-150-T-2660 (GE14C) 0.06 GE 14-'? I ODNAB429-18GZ-1OOT-150-T-2661 (GE14C) 0.06 GE 14-'? 1ODNAB437-12G6.0- I00T- 150-T-2662 (GE 14C) 0.05 GE 14-? 1ODNAB407- 16GZ- 1OOT-150-T-2853 (GE 14C) 0.06 GE 14-? 1ODNAB425- 18GZ-100T-150-T-2854 (GE 14C) 0.06
14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence (BPWS) plant, therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-240 11-P-A-US.
15. Stability Analysis Results 15.1 Introduction The BVWROG Regional Mode DIVOM Guideline recommends that a plant specific DIVOM slope be used for Option III OPRM setpoint determination (Reference 1 in Section 15.4).

However, since Brunswick Unit I will be implementing the Detect and Suppress Solution - Confirmation Density (DSS-CD) solution in the near future, the interim DIVOM approach as a function of Figure of Merit Mill be applied until DSS-CD is implemented (Reference 2 in Section 15.4).

Should the Option III OPRM system be declared inoperable, the BWROG Interim Corrective Action will constitute the stability licensing basis for Brunswick Unit I Cycle 16.

15.2 Stability Option III Brunswick Unit I has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range lvlonitor-OPRM) as described in Reference 3 in Section 15.4. Plant specific analysis incorporating the Opi:ion III hardware is described in Reference 4 in Section 15.4. Reload validation has been 17Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 performed in accordance with the licensing basis methodology described in Reference 5 in Section 15.4.

The stability based MCPR Operating Limit is provided for two conditions as a function of OPRM amplitude setpoint in the following table. The two conditions evaluated are for a postulated oscillation at 45% rated 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 16. The reload validation calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 16 as long as the selected OPRM setpoint produces values for OLMCPR(SS) and OLMCPR(2PT) that are less than the corresponding acceptance criteria.

OPRM Setpoint OLMCPR(SS) OLMCPR(2PT) 1.05 1.2093 1.0914 1.06 1.2302 1.1103 1.07 1.2519 1.1298 1.08 1.2743 1.1501 1.09 1.2975 1.1711 1.10 1.3216 1.1928 1.11 1.3455 1.2144 1.12 1.3702 1.2367 1.13 1.3959 1.2598 1.14 1.4225 1.2839 1.15 1.4502 1.3089 Rated Power Acceptance Off-rated OLMCPR OLMCPR as Criteria @ 45% Flow 18 described in SRLR Section 11 15.3 Interim Corrective Action Stability GE SIL-380 recommendations and the BWROG Interim Corrective Actions in Reference 6 in Section 15.4 have been included in the Brunswick Unit I Cycle 16 operating procedures. Regions of restricted operation defined in Attachment I of Reference 7 in Section 15.4 and expanded in Reference 6 in Section 15.4, ar. applicable to Brunswick Unit 1. The standard ICA stability regions are expanded as appropriate to offer stability protection for Brunswick Unit I Cycle 16 in accordance with Reference 8 in Section 15.4.

18 Thc off-rated OLMCPR is the maximum of the Kp adjusted MCPR or the MCPRr at 45% core flow.

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BRUNSWICK UNIT I 0000-0038-9350-SRlLR Reload 15 Revision 0 15.4 References

1. Plant-Specific RegionalMode DIVOMProcedure Guideline, GE-NE-0000-0028-97 14-RI ,

June 2, 2005.

2. Determinationof Figureof Meritfor Stability DIVOM Curve Applicability, OG01-0228-001, July 16, 2001.
3. BWVR Owners' Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960-A, November 1995.
4. LicensingBasis Hot Bundle OscillationMagnitudefor Bninswvick I and2, GE-NE-C51-00251-00-01, Revision 0, March 2001.
5. ReactorStability Detect and Suppress Solutions Licensing Basis Methodologyfor Reload Applications, NEDO-32465-A, August 1996.
6. BWR Owners' Group GuidelineforStability Interim CorrectiveAction, BWROG-94079, June 6, 1994.
7. Power Oscillations in Boiling Water Reactors, NRC Bulletin 88-07, Supplement 1, December30, 1988.
8. Review ofBWR Owners' Group Guidelinesfor Stability Interim CorrectiveAction, BWROG-02072, November 20, 2002.
16. Loss-of-Coolant Accident Results 16.1 1DCFR50.46 Licensing Results The ECCS-LOCA analysis is based on the SAFER/GESTR-LOCA methodology. The licensing results applicable to all fuel types in the new cycle are summarized in the following table:

Table 16.1-1 Licensing Results

. . Core-Wide Licensing Local Me-Wate Fuel Type Basis PCT Oxidation Metal-Water (OF) (%) Reaction GE14C 1557 < 1.00 < 0.10 The SAFER/GESTR-LOCA analysis results are documented in Reference I for GE14C in Section 16.4.

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BRUNSWICK UNIT I 0000-0038-9350-ST'LR D.1-~A I1 IXLNUVtU LJ Pni~cin A

-Jvlaitli UJ 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 IOCFR50.46 Error Notifications Number Subject PCT Impact 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 2003-05 Impact of Postulated Hydrogen-Oxygen Recombination 0 Total PCT Adder (IF) +10 The GE14C 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-hydraulic MAPLBGR operating limits to produce a set of fuel type dependant 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. The MAPLHGR operating limits for the remaining fuel bundles are documented in References 2 and 3 for GE14C in Section 16.4.

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BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revi-sin O Table 16.3-1 MAPLHGR Limits Bundle Type: GE 14-P I ODNAB437-1 2G6.0-1 OOT-1 50-T-2662 Average Planar Exposure MAPL11GR (kWft)

(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 16.00 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 17

BRUNSWICK UNIT I 0000-0038-9350-Sl'RLR Reload 15 Revision 0 Table 16.3-2 MAPLHGR Limits Bundle Type: GE 14-PIODNAB407-1 6GZ-1 OOT-1 50-T-2853 Average Planar Exposure MAPLI1GR (kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 9.47 9.91 0.20 0.22 9.57 9.98 1.00 1.10 9.71 10.10 2.00 2.20 9.87 10.25 3.00 3.31 10.02 10.41 4.00 4.41 10.17 10.58 5.00 5.51 10.31 10.74 6.00 6.61 10.45 10.88 7.00 7.72 10.57 11.02 8.00 8.82 10.70 11.17 9.00 9.92 10.82 11.31 10.00 11.02 10.93 11.46 11.00 12.13 11.05 11.60 12.00 13.23 11.06 11.70 13.00 14.33 11.05 11.68 14.00 15.43 11.05 11.66 14.51 16.00 11.05 11.63 15.00 16.53 11.05 11.61 17.00 18.74 11.02 11.48 19.13 21.09 10.91 11.27 20.00 22.05 10.87 11.19 25.00 27.56 10.49 10.65 30.00 33.07 10.08 10.12 35.00 38.58 9.58 9.61 40.00 44.09 9.07 9.10 45.00 49.60 8.54 8.59 50.00 55.12 7.99 8.06 55.00 60.63 6.34 6.49 57.61 63.50 5.03 5.18 57.91 63.84 4.88 5.03 58.17 64.12 -- 4.91 58.19 64.14 4.90 Page 18

BRUNSWICK UNIT I 0000-0038-9350-SRLR Relnod 15 Revisinn 0 Table 16.3-3 MAPLHGR Limits Bundle Type: GE14-PIODNAB425-18GZ-IOOT-150-T-2854 Average Planar Exposure MAPL1IGR (kWI/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 8.85 9.20 0.20 0.22 8.91 9.25 1.00 1.10 9.01 9.34 2.00 2.20 9.14 9.46 3.00 3.31 9.27 9.59 4.00 4.41 9.41 9.73 5.00 5.51 9.54 9.86 6.00 6.61 9.68 9.99 7.00 7.72 9.82 10.12 8.00 8.82 9.95 10.25 9.00 9.92 10.09 10.38 10.00 11.02 10.23 10.51 11.00 12.13 10.27 10.60 12.00 13.23 10.29 10.62 13.00 14.33 10.31 10.65 14.00 15.43 10.34 10.70 14.51 16.00 10.35 10.74 15.00 16.53 10.37 10.77 17.00 18.74 10.44 10.88 19.13 21.09 10.47 10.90 20.00 22.05 10.48 10.90 25.00 27.56 10.28 10.52 30.00 33.07 9.84 10.06 35.00 38.58 9.38 9.60 40.00 44.09 8.91 9.14 45.00 49.60 8.41 8.65 50.00 55.12 7.88 8.12 55.00 60.63 5.70 6.47 56.45 62.23 4.96 5.74 56.61 62.40 -- 5.66 57.61 63.50 5.16 57.77 63.68 5.08 58.04 63.98 4.95 Pagp 19

BRUNSWICK UNIT I 0000-0038-9350-SULR Reload 15 Revision 0 The single-loop operation multiplier on LHGR and MAPLHGR, and the ECCS analytical initial M('PR 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 LHGR and MAPLHGR Multiplier Fuel Type Initial MCPR Single Loop Operation LHGR and MAPLHGR Multiplier GE14C 1.275 0.80 16.4 References The SAFER/GESTR-LOCA analysis base reports applicable to the new cycle core are listed below.

References for GE14C

1. Brunswick Nuclear Plant Unit I and 2 Extended Power Uprate Task 0407 ECCS-LOCA SAFER/GESTR Project Task Report, GE-NE-A22-00113-27-01, Revision 0, June 2001.
2. Supplemental Reload Licensing Reportfor Brunswick Steam ElectricPlant Unit 1 Reload 14 Cycle 15, 0000-0016-6502-SRLR, Revision 1, June 2005.
3. Supplemental Reload Licensing Reportfor Brunswick Steam Electric Plant Unit 1 Reload 13 Cycle 14, J 1l-03936SRLR, Revision 2, March 2002.

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+ E1 E0l ?S[ n Bl 44 il l l lff 40 [DE] E 38 GE] D1 [EGD 0 ISO[1E]E] l[

36 [gC E] [E]J[E 1[E [GE]fE[GE D G DOG G D [gG D] [GE] [EE G [E Gg [D [H F][

34 M1[3E%~ On ME Mgl[ MEN1g EuM  % Js EB N 32 [E [ M ] [ D[ [ G 30 ILI DGI LDGDGDGDD LI 26EC [mEl IEK-9 mIM E1-1 mag Manm~mim 01MDDM [DE[GE] [1E] [H]OF 24 E [ 1[ [FE] EE 1 M' 22 m EIuTIfj ~ [§T mzm~ ~ mmm~ 1 j~jImm 20 18 elm0 LNE [ H U L w Lel N T[ T [T E ME]m11M~ mm- MsRNO WRMm 16 [E1D]EI ] [E 1EH [1ED SEl E]IM E 14 E-] M [D [Dll 12 WE 8,-[Po WEl 'el 0 N NEll WN B-ToM E 7m 0ETlM 10 U~WEz zIW~ ;oRIDm mE Nl l l 1 1 8 IS DEHE] [ LEE EEELE]

LE] ELE E 6 NMl WlE Win SEl WlE [mm Nl Nl ml 4 M FJ[I ElEI ][EF El I 1 lE [OE M 2 MALt EMA ME] MlM Lem 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 Fuel Type A=GE1 4-PI ODNAB416-17GZ- IOOT-1 50-T-2496 (Cycle 14) F=GE14-P IODNAB437-12G6.0-l OOT-150-T-2662 (Cycle 15)

B=GE14-PI ODNAB425-16GZ-I OOT-150-T-2497 (Cycle 14) G=GE14-PI ODNAB407-16GZ-I OOT-150-T-2853 (Cycle 16)

C=GE14-P I ODNAB438- 12G6.0-l OOT-150-T-2498 (Cycle 14) H=GE14-PI ODNAB425-18GZ-I OOT-150-T-2854 (Cycle 16)

D=GE14-PI ODNAB413-16GZ- IOOT- 150-T-2660 (Cycle 15) 1=GE14-P IODNAB437-12G6.0-l OOT-150-T-2662 (Cycle 16)

E=GE14-PIODNAB429-18GZ-IOOT-150-T-2661 (Cycle 15)

Figure 1 Reference Core Loading Pattern Page 21

BRUNSWICK UNIT 1 0000-003 8-9350-SIILR Reload 15 Revision 0 Al:

I 0.0 1.0 2.0 3.0 4.0 5.0 6.0 0.0 1.0 2.0 3.0 40 5.0 6.0 Time (sec) Time (sec) 200.0 B- Level - Inch above Sep Skirt

-Vessel Steam Flow 175.0 -&-Turbine Steam Flow

-+- Feedwater Flow aa 75.0 3.0 4.0 5.0 6.0 0.0 1.0 2.0 3.0 4.0 0.0 6.0 Time (sec) Time (sec)

Figure 2 Plant Response to Load Rejection wlo Bypass (MOC ICF (HBB))

Page: 22

BRUNSWICK UNIT I 0000-003 8-9350-SI'LR Reload 15 Revision 0 375 0,

-- Neutron Flux

-- Core Inlet Flow -.- Vessel Press Rise (psi)

-h Core Inlet Subcooling 325.0 - Total SRV Flow

-*- Bypass Valve Flow 2C0.0 275.0 225.0 5!

125.0 e

S2 tooo( .% l75.0 1010.0 70.

125.0 50.0 n.o -25.0 .

0.0 zo 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 e.0 2.0 4.0 6.0 8°0 10.0 1Z0 140 16.0 181 20.0 Time (sec) TIme (sec) 2000. 1.0-1.0 0.5

. @I I- 750  ; .0.0 S

0 i~-.

I-

.1.OI

-1.s

(.0 2.0 4.0 6.0 8.0 10.0 l02 14.0 16.0 18.0 20.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.2 16.0 1.,) 200 Time (sec) Time (sec)

Figure 3 Plant Response to FW Controller Failure (MOC ICF (HBB))

Page 23

BRUNSWICK UNIT 1 0000-0038-9350-SRLR Relnod 15 Revision 0 a:

s:

0.0 .0 4.0 0.0 6.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 Time (sec) Time (soc) 0X 75.0 S-

.40.0I

(.0 1.0 2.0 3.0 4.0 5.0 6.0 1.0 2.0 3.0 60 Time (sec) Time (sec)

Figure 4 Plant Response to Load Rejection w/o Bypass (EOC ICF (HBB))

Page 24

BRUNSWICK UNIT I 0000-003 8-9350-SRLR Reload 15 RevisiDn 0

-'-Vessel Press Rise (psi) 325.0 4 B Total SRV Flow

- Bypass Valve Flow 275.0 +

225.0 2 1750 cc 125.0 75.0 25.0 l l 250-snv - _

0.0 20 4.0 6.0 6.0 10.0 12.0 140 16.0 1.1) 20.0 Time (sec) rime (sec)

V r: 75.0 S.

110 2.0 4.0 6.0 6.0 10.0 IZ0 14.0 16.0 18.0 20.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.3 20.0 Time (sec) Time (sec)

Figure 5 Plant Response to FW Controller Failure (EOC ICF (HBB))

Page 25

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 RevisiDn 0

-- Neutron Flux

-*-Core Inlet Flow

--- Core Inlet Subcooling 200.0 20 100.0w X~

s0.0 do I i 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 Time (sec) a 70.0 20I 0 10.0 12.0 14.0 16.0 18.0 20.0 0.0 2.0 4.0 6.0 0.0 10.0 12.0 Time (sec) Time (sec)

Figure 6 Plant Response to FW Controller Failure (EOC NFWT ICF (HBB) with TBVOOS)

Page 26

BRUNSWICK UNIT I 0000-0038-9350-SrRLR Reload 15 Revision 0 2zs0.- 1-1

.

Neutron Flux

-*-Core Inlet Flow j Vessel Press Rise (psi)

-6Core Inlet Subcooling 325.0 -6 Total SRV Flow

-*-Bypass Valve Flow 200.0 275.0 22550 150.0 v2 tr 100.0

't125.0 75.0 s0.0 o.o 0.0 2.0 4.0 t.0 t.0

,.

10.0 Time (sec)

V 12.0 14.0 16.0 18.0 20.0 25.0

-25..0 1.5 0.0 Z0 4.0 e.o n.e a.0o Time (sec) 0ZO 14.0 18.0 18.r

_

2 .0 25O.0 1.0 0.5

%

V 75.0 t

0

.1.0

.1.5

.2.0 '.

0.0 2.0 4.0 e.0 n.e is.o 12.0 14.0 16.0 1.11 20.0 Time (sec) Time (sec)

Figure 7 Plant Response to FW Controller Failure (EOC RFWT ICF (UB) with TBVOOS)

Page 27

BRUNSWICK UNIT I 0000-0038-9350-Sl' LR Reload 15 Revision 0 M

0.0 1.0 z0 30 4.0 00 6.0 7.0 00 1.0 20 3.0 4.0 0.0 f60 7.0 Time (see) Time (see) 200.0 e

  • 2 75.0 3.0 4.0 5.0 6.0 7.0 0.0 1.0 2.0 3.0 4.0 50 60 7.0 Time (sec) Time (see)

Figure 8 - Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)

Page 28

BRUNS WICK UNIT I 0000-0038-9350-SE' LR 11lorlI Rvien BRNWC UI 0-08930SL Appendix A Analysis Conditions The reactor operating conditions and the pressure relief and safety valve configuration used in the reload licensing analysis for this plant and cycle are presented in Tables A-I and A-2 below.

Table A-1 Reactor Operating Conditions Analysis Value Parameter NFWT RFWT Thermal power, MWt 2923.0 2923.0 Core flow, Mlb/hr 80.5 80.5 Reactor pressure (core mid-plane), psia 1059.3 1035.3 Inlet enthalpy, Btu/lb 529.1 512.2 Non-fuel power fraction 19 _ _

Steam flow, Mlb/hr 12.78 11.06 Dome pressure, psig 1030.1 1007.2 Turbine pressure, psig 963.9 956.9 Table A-2 Pressure Relief and Safety Valve Configuration Valve Type Number of Lowest Setpoiint Valves (psig)

Safety/R.-lief Valve 10 1163.9 9 Not axailable in the TRACG output files.

Page 29

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload IS Revision 0 Appendix B Decrease in Core Coolant Temperature Events The Loss of Feedwater Heating (LFWH) event was analyzed for Brunswick Unit I Cycle 16 using the BWR Simulator Code. The use of this code is permitted in GESTAR II. The transient plots, neutron flux and he.t 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 16 in accordance with Reference B-i.

Reference B-1. Determinationof Limiting Cold WaterEvent, NEDC-32538P-A, February 1996.

Page 30

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 RevisiDn 0 Appendix C Operating Flexibility Options Reference C-I provides a basis for operation of the Brunswick Steam Electric Plant (BSEP) with one Main Sleamline Isolation Valve Out of Service (MSIVOOS) (three steamline operation) and all S/RVs 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 E).

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. FWITR and FWHOOS will not be allowed while operating in the MELLLA+ domain (See Appendix E).

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 1]..

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

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-9, C-3, and C-6. The ARTS power and flow dependent MCPR limits apply to two recirculation pump system operation and SLO without modification for Brunswick Unit I Cycle 16.

The ARTS power dependent limits in Reference C-9 include an adjustment to the limits provided in References C-3 and C-5 to address the 10 CFR Part 21 Communication in Reference C-8. The pcwer dependent MCPR limits in Reference C-9 also include an adjustment to the K(p) above P-bypass due to the implementation of TRACG (Reference C-7). The MCPR(p) limits provided in Reference C-9 are based on a Safety Limit of 1.11. The Reference C-9 power dependent limits are not altered for Brunswick Unit I Cycle 16.

The ARTS flow dependent limits provided in Reference C-3 are based on a Safety Limit of 1.07. Du.e to the safety limit change for Brunswick Unit I Cycle 16, there will be a required adjustment to the MCPR(f) limits and a validation of the required minimum GE14 OLMCPR for the recirculation pump seizure event. The Reference C-3 MCPR(f) limits are increased for a Safety Limit of 1.11 by the ratio of (1.11/1.07). The following coefficients apply:

Maximum Core Flow A(f) B(1) Flow Intercept MCPR l'oof Rated) (% 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 Page 31

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 The flow dependent MAPLHGR limit multiplier, MAPFAC(f), is not altered for Brunswick Unit I Cycle 16.

From Reference C-5, the SLO OLMCPR was determined to be 1.40 with a SLO SLMCPR of 1.12. The initial rower for the licensing basis pump seizure event is 2143 MWth, which was about 83.8% of the plant licensed thermal power at the time of the analysis. Consequently, the K(P) for this power level from Reference C-5 was approximately 1.06, resulting in a minimum TLO OLMCPR of 1.32 to cover the pump srizure event for GE14 fuel for a SLO SLMCPR of 1.12. After EPU, the licensing basis GE14 pump seizure initial power in MW~h is unchanged, but represents about 73.3% of licensed thermal power, resulting in a K(P) of about 1.12. Since the SLO SLMCPR is 1.12 for Brunswick Unit 1 Cycle 16, the SLO OLMCPR must be greater than or equal to 1.40 for the pump seizure event. Therefore, the minimum GE14 OLMCPR of 1.34 (See Section 11) is conservative for the SLO pump seizure event (1.34*K(73.3) = ].34* 1.12= 1.50> 1.40).

References C-1. AMain Steamline Isolation Valve Out ofService for the Brnswick Steam Electric Plant, EAS-11'7-0987, GE Nuclear Energy (Proprietary), April 1988.

C-2. FeedwaterTemperature Reduction with Maximnum ExtendedLoadLine Limit andIncreasedCore Flowfor Bnrnswick Steam ElectricPlants Units I and 2, NEDC-32457P, Revision 1, GE Nuclear Energy (Proprietary), December 1995.

C-3. Maximum Extended OperatingDomain Analysisfor Brunswick Steam ElectricPlant,NEDC-31654P, GE Nuclear Energy (Proprietary), February 1989.

C-4. TurbineBypass Out of Service Analysisfor CarolinaPower & Light Company'sBrunswick NuclearPlants Units I and 2, NEDC-32813, Revision 3, GE Nuclear Energy (Proprietary), June 1998.

C-5. GEJ4 Fuel Design Cycle-IndependentAnalyses ForBnnswick Steam ElectricPlant Units I and 2, GE-NE-L12-00876-00-O1P, Revision 1, GE Nuclear Energy (Proprietary), February 2001.

C-6. Safety Analysis Reportfor Brunswick Steam Electric Plant Units 1 and 2 Extended Power UpraFe, NEDC-33039P, GE Nuclear Energy (Proprietary), August 2001.

C-7. Brtnswick NuclearStation TRACG Implementationfor Reload Licensing TransientAnalysis, GE-NE-0000-0022-8180-RO, GE Nuclear Energy (Proprietary), February 2004.

C-8. SC04-15, "Turbine Control System Impact in Transient Analyses," 10 CFR Part 21 Communication, October 31, 2004.

C-9. Brunswick I and 2 Off-RatedAnalyses Below the PLUPower Level, GE-NE-0000-0036-9469-F.0, Revision 0, GE Nuclear Energy (Proprietary), June 2005.

Page 32

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Appendix D TRACG AOO Methodology Reference D-l provides the results of the analyses and evaluations supporting the application 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 GE14 fuel. Section 11 of this report presents the MCPR limits based on the methodology of References D-2 and D-3.

References D-1. Bnmswick NuclearStation TRACG ImplementationforReload Licensing TransientAnalysis, GE-NE-0000-0022-8180-RO, GE Nuclear Energy (Proprietary), February 2004.

D-2. TRA CGApplicationfor Anticipated OperationalOccurrences TransientAnalysis, NEDE-32906P-A, Revision 1,April 2003.

D-3. FinalSafety Evaluation Report by the Office of NuclearReactor Regulationfor NEDE-32966P, Supplement2, "TRACGApplicationforAnticipatedOperationalOccurrences Transient Analyses ", March 2005.

Page 33

BRUNSWICK UNIT I 0000-0038-9350-SRILR Reload 15 Reviqion 0 Appendix E MELLLA+ Implementation Brunswick is seeking approval to operate in the MELLLA+ domain (Reference E-1), 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 16.

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 performancL- of the trans;ient analyses, stability analyses, and LOCA analyses.

The pressurization transients are generally limiting at high flow conditions. However, the transients vwere 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, TBVOOS will be allowed in the MELLLA+ domain, but MSIVOOS will not.

For EPUJ/MELLLA+ operation, the Detect and Suppress Solution - Confirmation Density (DSS-CD) is the licensing basis for Brunswick Unit I Cycle 16. The reload checklist as outlined in Reference E-2 and shown .n Table E-l is used to confirm that the DSS-CD is applicable to Brunswick Unit I Cycle 16 EPU/M ELLLA+ operation.

Table E-1 DSS-CD Plant Specific Applicability Checklist L Parameter Criterion Acceptance EBWR Product Line BWR/3-6 design as of July 2002 Yes (BWR/4)

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

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 (I IOF)

Reduction No TFW Reduction (MELLLA+

extension)

MCPR Margin OLMCPRR td -6SLMCPR 7 Yes (0.165)

OLMCPR Rated Page 34

BRUNSWICK UNIT I 0000-0038-9350-SRlLR Reload 15 Revision 0 Should the DSS-CD OPRM system be declared inoperable, either the BSP Option I or the BSP Option 2 is the backup stability solution for Brunswick Unit I Cycle 16 operation. The appropriate BSP Option may be implemented based on the information provided in Reference E-3.

The application of the ECCS-LOCA analysis to operation in the MELLLA+ power/flow region was addressed in Reference E-4. Elimination of the 16000 F Upper Bound peak cladding temperature limit has been incorporated as defined in Reference E-5.

References E- 1. Safety Analysis Reportfor Bnmswick Steam ElectricPlant Units 1 and2 Maximum Extended LoadLine Limit Analysis Plus, NEDC-33063P, GE Nuclear Energy (Proprietary),

November 2002.

E-2. GeneralElectric Boiling Water ReactorDetect andSuppress Solution - ConfirmationDensi'ty Licensing TopicalReport, NEDC-33075P, Revision 4, July 2004.

E-3. DSS-CD Backup Stability ProtectionEvaluationfor Brunswick Unit 1 Cycle 16, GE-NE-0000-0044-3728-RO, November 2005.

E-4. Brunswick NuclearPlant Unit I and 2 MELLLA + Task 0407 ECCS-LOCA SAFER/GESTR Project Task Report, GE-NE-A22-00113-83-01, Revision 0, September 2002.

E-5. GESTR-LOCA and SAFER Modelsfor Evaluation ofLoss-of-CoolantAccident Volume III, Supplement 1, Additional Informationfor Upper Bound PCT Calculation,NEDE-23785P-A, Volume III, Supplement 1, Revision 1, March 2002.

Page 35

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Appendix F 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, the NFWT and RFWT limits are separated at any cycle exposure for which the TBPOOS operating flexibility option is employed. The RFWT 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 10"F.

Page 36

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Appendix G List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 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 Techmical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection Btu British thermal unit 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 DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)

EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)

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 GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF General Shape Function HAL Haling Burn HBB Hard Bottom Bum HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action Page 37

BRUNSWICK UNIT I 0000-0038-9350-SRLR Reload 15 Revision 0 Acronym Description ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix L8 Turbine Trip on high water level (Level 8)

LCF Low Core Flow LHGR Linear Heat Generation Rate LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MEOD Maximum Extended Operating Domain 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 Normal Feedwater Temperature NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS 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 PHE Peak Hot Excess PLHGR 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 Page 38

BRUNSWICK UNIT 1 0000-0038-9350-SRLR Reload 15 Revisi:n 0 Acronym Description RCF Rated Core Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RV Relief Valve 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 S/RV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service Ss Steady State SSV Spring afety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TSIP Technical Specifications Improvement Program TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Bum Page 39

BSEP 06-0034 Enclosure 4 Global Nuclear Fuels Affidavit Regarding Withholding NEDC-31624P, Supplement 1, Revision 9, From Public Disclosure

Affidavit Affidavit I, Andrew A. Lingenfelter, state as follows:

(1) I am Manager, Fuel Engineering Services, Global Nuclear Fuel - Americas, L.L.C. ("GNF-A") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in the attachment, "NEDC-31624P, Supplement 1, Revision 9, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit I Reload 15 Cycle 16," December 2005.

GNF proprietary information is indicated by enclosing it in double brackets. In each case, the superscript notation 13) refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4) and 2.390(a)(4) for "trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all "confidential commercial information," and some portions also qualify under the narrower definition of "trade secret," within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatorv Commission. 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).

(4) Some examples of categories of information which fit into the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of GNF-A, its customers, or its suppliers;
d. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, of potential commercial value to GNF-A;
e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

Affidavit The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b., above.

(5) To address the 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in (6) and (7) following. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.

The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost, on the order of several million dollars, to GNF-A or its licensor.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The fuel design and licensing methodology is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A or its licensor.

A ffiavit The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.

GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.

Executed at Wilmington, North Carolina, this /1 day of December, 2005.

AcejIiiAndrew A. Lingenfelter Global Nuclear Fuel - Americas, LLC

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