ML050910212

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0000-0028-0680-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17.
ML050910212
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Site: Brunswick Duke Energy icon.png
Issue date: 01/31/2005
From:
Global Nuclear Fuel - Americas
To:
Office of Nuclear Reactor Regulation
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0000-0028-0680-SRLR, Rev 0
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BSEP 05-0024 Enclosure 2 0000-0028-0680-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17, January 2005

GNF Global Nuclear Fuel A Joint Venhm d GE. Toshiba & Hit"&

0000-0028-0680-SRLR Revision 0 Class I January 2005 0000-0028-0680-SRLR, Revision 0 Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17 Approved: by xxLO Approved: v_ _

u. E. inArdingSenaies C. P. Colli unt Fuel Engineering Services Customer Account Leader

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Important Notice Regarding the Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for Progress Energy Carolinas, Inc. (PGN) for PGN's use in defining operating limits for the Brunswick Steam Electric Plant Unit 2 (BSEP-2). The information contained in this report is believed by GNF-A to be an accurate and true representation of the facts known or obtained or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting information in this document are contained in the contract between PGN and GNF-A for nuclear fuel and related services for the nuclear system for Brunswick Steam Electric Plant Unit 2 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-A 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 2 0000-0028-0680-SRLR Reload 16 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 E. W. Gibbs.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 The basis for this report is General Electric 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: Implementation of TRACG AOO Methodology Appendix E: MELLLA+ Implementation Appendix F: List of Acronyms
2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:

GE14-PIODNAB399-16GZ-I OOT-150-T-2418 (GE14C) 15 38 GE14-PIODNAB398-13GZ-IOOT-150-T-2417 (GE14C) 15 37 GE14-PIODNAB420-18GZ-IOOT-150-T-2572 (GE14C) 16 119 GE14-P 1ODNAB419-6G7.0/7G6.0/3G2.0- 1OOT-150-T-2573 (GE14C) 16 40 GE 14-P I ODNAB425-3 G7.0/14G6.0/1 G2.0-I OOT- 150-T-2574 (GE14C) 16 40 GE 14-P I ODNAB439- 12G6.0-l OOT-150-T-2575 (GE 14C) 16 38 New:

GE 14-P I ODNAB439-12G6.0-1 OOT-150-T-2575 (GE 14C) 17 40 GE 14-P I ODNAB425-3 G7.0/14G6.0/1 G2.0-1 OOT- 150-T-2574 (GE14C) 17 64 GE14-P I ODNAB413-16GZ-I OOT-150-T-2660 (GE14C) 17 144 Total:

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR 1PD1n-4 14

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3. Reference Core Loading Pattern I Nominal previous cycle core average exposure at end of cycle: 34102 MWd/MT

( 30936 MWd1ST)

Minimum previous cycle core average exposure at end of cycle 33676 MWd/MT from cold shutdown considerations: ( 30550 MWd/ST)

Assumed reload cycle core average exposure at beginning of cycle: 14561 MWd/MT

( 13209 MWd/ST)

Assumed reload cycle core average exposure at end of cycle 32751 MWd/MT (full power): ( 29711 MNMd/ST)

Reference core loading pattern: Figure 1

4. Calculated Core Effective Multiplication and Control System Worth - No Voids, 20 0 C Beginning of Cycle, keff Uncontrolled 1.128 Fully controlled 0.959 Strongest control rod out 0.990 R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.000
5. Standby Liquid Control System Shutdown Capability Boron (ppm) Margin Shutdown (Ak)

(at 20'Q (at 160'C, Xenon Free) 720 0.013 l The previous cycle core average exposure at beginning of cycle was 14798 MWd/MT (13424 MN~d/ST).

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0

6. Reload Unique TRACG Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 2 Operating domain: ICF-HBB Exposure range: BOC17 to EOFPC17-3145 MWd/MT (2853 MWd/ST) l__ _ Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR Desgnj .3 1331. 40(M Wt) (1000 lbfhr) M P GE14C 1.0 1.39 1.33 1.040 7.243 123.0 1.45 Operating domain: ICF-HBB Exposure range: EOFPC17-3145 MWd/MT (2853 MWd/ST) to EEOC17 Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR GE14C 1.0 1.33 1.32 1.040 6.957 125.2 1.48 Operating domain: ICF-FNN'TR-TBVOOS-UB Exposure range: BOC17 to EEOC17 Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR Design (MWt) (1000 lb/hr) MCPR GE14C 1.0 1.27 1.27 1.040 6.634 127.6 1.69 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 2 0000-0028-0680-SRLR RD.,-A 1A A~tcis rvxlua lV:lIUIU jxIUi

7. Selected Margin Improvement Options 3 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 (EOFPC17-3145 MWd/MT and EEOC 17) 3Refer to GESTAR for those margin improvement options that are referenced and supported within GESTAR.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR ID-1 rx~vtll~u A 1if At, RD-icin-rx%,uIlvul A

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8. Operating Flexibility Options 4 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: 110.3 0 F Final feedwater temperature reduction: 11 0.3 0F ARTS Program: Yes Single-loop operation: Yes (MELLLA)

No (MELLLA+)

Equipment Out of Service:

One Safety/relief valve Out of Service Yes (MELLLA)

No (MELLLA+)

ADS Out of Service: Yes (I valve OOS)

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

No (MELLLA+)

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

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

6 When the Turbine Bypass System is credited, 8 of 10 valves are assumed operable in the analysis.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0

9. Core-wide AOO Analysis Results Methods used: GEMINI (TRACG); GEXL-PLUS Operating domain: ICF-IBB Exposure range: BOC17 to EOFPC17-3145 MWd/NIT (2853 MWd/ST) 7 Uncorrected ACPRAICPR Flux QIA 8 Event (%NBR) (%NBR) GE14C Fig.

Load Reject w/o Bypass 314 - 0.147 2 FW Controller Failure 139 - 0.061 3 Operating domain: ICF-HBB Exposure range: EOFPC17-3145 MWdIMT (2853 IMNWd/ST) to EEOC17 Uncorrected ACPRIICPR Event Flux QA/ GE14C Fig.

_ _ _ __ __ __ _ _ _ _ _ _ _ _ _ (% N B R) (% N B R ) _ _ _ _ _ _ _ _ _ _

Load Reject w/o Bypass 408 0.169 4 FW Controller Failure 203 - 0.130 5 Operating domain: ICF-FWTR-TBVOOS-UB Exposure range: BOC17 to EEOC17 Uncorrected ACPR/ICPR Event Flux Q/A GE14C Fig.

(%NBR) (%NBR) Failure_376_0.218_6 FW Controller Failure 376 -0.2 186

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 Brunsivick Steam Electric Plant, NEDC-31654P, February 1989. The MCPRs for Brunswick Unit 2 Cycle 17 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 (for RBM inoperable: OLMCPR 2 1.40 for power 2 90% and 7

Uncorrected ACPRJICPR is being reported since this is the term used in developing the operating limit for TRACG-based analyses.

8Not available from the TRACG transient output.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 OLMCPR 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 17 All HTSP Results Without RBM Filter ACPR 108.0 0.15 111.0 0.20 114.0 0.24 117.0 0.29

11. Cycle MCPR Values 9 Safety limit: 1.11 Single loop operation safety limit: 1.13 ECCS OLMCPR Design Basis: See Section 16 Non-pressurization events:

Exposure range: BOC17 to EOC17 GE14C Control Rod Withdrawal Error (RBM setpoint at 108%) 1.26 Loss of Feedwater Heating 10 1.25 Fuel Loading Error (mislocated) Not limiting 1l Fuel Loading Error (misoriented) 1.25 9The 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.

'° See Appendix B.

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

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Pressurization events:

Operating domain: ICF-HBB 12 Exposure range: BOC17 to EOFPC17-3145 MWd/MT (2853 MWd/ST)

Option A Option B GE14C GE14C Load Reject w/o Bypass 1.51 1.33 FW Controller Failure Not limiting 13 Not limiting 14 Operating domain: ICF-HBB 14 Exposure range: EOFPC17-3145 MVWd/AIT (2853 MI'"d/ST) to EEOC17 Option A Option B GE14C GE14C Load Reject wv/o Bypass 1.55 1.37 FW Controller Failure Not limiting 14 Not limiting 14 Operating domain: ICF-FWN'TR-TBVOOS-UB 15 Exposure range: BOC17 to EEOC17 Option A Option B GE14C GE14C FW Controller Failure 1.66 1.48

12. Overpressurization Analysis Summary Event PsI Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) 1268 1277 1320 Figure 7 12 The ICF Operating Limits for the exposure range of BOC17 to EOFPC17-3145 MWd/MT (2853 MWd/ST) bound the Operating Limits for the following domains: MELLLA+, MELLLA, ICF and FWTR, MSIVOOS and ICF.

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

14 The ICF Operating Limits for the exposure range of EOFPC17-3145 MWd/MT (2853 MWd/ST) to EEOC17 bound the Operating Limits for the following domains: MELLLA+, MELLLA, ICF and FWTR, MSIVOOS and ICF.

" The TBVOOS ICF-FWTR Operating Limits for the exposure range of BOC17 to EEOC 17 bound the Operating Limits for all domains with TBVOOS. The corresponding Option A and B limits for NFWT are 1.58 and 1.40, respectively.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0

13. Loading ErrorResults Variable water gap misoriented bundle analysis: Yes 16 Misoriented Fuel Bundle ACPR GE14-PIODNAB420-18GZ-100T-150-T-2572 (GE14C) 0.12 GE 14-P 1ODNAB419-6G7.0/7G6.0/3G2.0- OOT-150-T-2573 (GE 14C) 0.12 GE 14-P 1ODNAB425-3G7.0/14G6.0/1 G2.0-1OOT-150-T-2574 (GE 14C) 0.13 GE14-PI ODNAB439-12G6.0-1OOT-150-T-2575 (GE14C) 0.14 GE14-PIODNAB413-16GZ-1OOT-150-T-2660 (GE14C) 0.06
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 15.1 Introduction The BWROG 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 2 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 (FOM) will 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 2 Cycle 17.

15.2 Stability Option III Brunswick Unit 2 has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM) as described in Reference 3 in Section 15.4. Plant specific analysis incorporating the Option III hardware is described in Reference 4 in Section 15.4. Reload validation has been 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 16 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR 1D.icn- A BRNWC UNITmi2 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 17. The reload validation calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 17 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) OLMCPR(2PT) 1.05 1.2265 1.1105 1.06 1.2515 1.1331 1.07 1.2775 1.1566 1.08 1.3046 1.1812 1.09 1.3329 1.2068 1.10 1.3624 1.2335 1.11 1.3918 1.2601 1.12 1.4226 1.2880 1.13 1.4547 1.3170 1.14 1.4883 1.3475 1.15 1.5235 1.3793 Rated Power Acceptance Off-rated OLMCPR OLMCPR as Criteria @ 45% Flow 17 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 2 Cycle 17 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, are applicable to Brunswick Unit 2. The standard ICA stability regions are expanded as appropriate to offer stability protection for Brunswick Unit 2 Cycle 17 in accordance with Reference 8 in Section 15.4.

17 The off-rated OLMCPR is the maximum of the K(P) adjusted MCPR or the MCPR(f) at 45% core flow.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 15.4 References

1. BWVROG Regional Mode DIVOM Guideline, GE-NE-0000-0028-9714-RO, June 2004.
2. Determination of Figureof Meritfor Stability DI VOM Curve Applicability, OGOI-0228-001, July 16,2001.
3. BWIR Owners Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960-A, November 1995.
4. Licensing Basis Hot Bundle OscillationMagnitudefor Brunswick 1 and 2, GE-NE-C51-00251-00-01, Revision 0, March 2001.
5. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodologyfor Reload Application, NEDO-32465-A, August 1996.
6. BWR Owvners' Group Guidelinefor StabilityInterim CorrectiveAction, BWROG-94079, June 6, 1994.
7. Power Oscillations in Boiling Water Reactors,NRC Bulletin 88-07, Supplement 1, December 30, 1988.
8. Review ofBWYR Owners' Group Guidelinesfor Stability Interim CorrectiveAction, BWROG-02072, November 20,2002.
16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA Analysis is based on the SAFER/GESTR-LOCA methodology. 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 Core-Wide Fuel Type Basis PCT Oxidation Metal-Water (OF) (%) Reaction GE14C 1557 < 1.00 < 0.10 The SAFER/GESTR-LOCA analysis results for the GE14C fuel type are documented in Reference I for GE14C in Section 16.4.

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BRUNSWICK UNIT 2 0000-0028-0680-SRLR D-I-An 1A RIDi;- n IU-IVIII

-\~Jt 16.2 10CFR50.46 Error Evaluation The 10CFR50.46 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 10CFR50.46 Error Notifications Number Subject PCT Impact ('F) 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 volume 0 2003-01 Impact of SAFER level/volume table error on PCT -5 2003-05 Impact of Postulated Hydrogen-Oxygen Recombination 0 Total PCT Adder (OFi) +10 The GE14C Licensing Basis PCT remains below the I OCFR50.46 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. 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 2 0000-0028-0680-SRLR D,-1A 1A P fa IzUIUaU 10 1,t:VIaIUl w Table 16.3-1 MAPL1HGR Limits Bundle Type: GE14-P1 ODNAB425-3G7.0/14G6.0/1 G2.0-1 OOT-1 50-T-2574 Average Planar Exposure MAPLHGR (kWV/ft)

(GWd/ST) (GWd/lMT) Most Limiting Least Limiting 0.00 0.00 9.37 9.48 0.20 0.22 9.44 9.54 1.00 1.10 9.55 9.65 2.00 2.20 9.70 9.79 3.00 3.31 9.85 9.94 4.00 4.41 10.01 10.10 5.00 5.51 10.16 10.26 6.00 6.61 10.30 10.43 7.00 7.72 10.45 10.60 8.00 8.82 10.60 10.72 9.00 9.92 10.70 10.85 10.00 11.02 10.79 10.95 11.00 12.13 10.87 11.07 12.00 13.23 10.87 11.13 13.00 14.33 10.85 11.17 14.00 15.43 10.84 11.21 14.51 16.00 10.84 11.23 15.00 16.53 10.84 11.25 17.00 18.74 10.82 11.23 19.13 21.09 10.72 11.08 20.00 22.05 10.68 11.02 25.00 27.56 10.26 10.51 30.00 33.07 9.82 10.05 35.00 38.58 9.33 9.52 40.00 44.09 8.83 8.95 45.00 49.60 8.35 8.41 50.00 55.12 7.85 7.90 55.00 60.63 5.72 6.49 56.66 62.46 4.90 5.66 57.61 63.50 5.19 57.77 63.68 5.11 58.04 63.98 4.97 Page 16

BRUNSWICK UNIT 2 0000-0028-0680-SRLR 1..-A RP 0 1f RsD-icir- AI Table 163-2 MAPLHGR Limits Bundle Type: GEl 4-P IODNAB439-1 2G6.0-1 OOT-1 50-T-2575 Average Planar Exposure MIAPLHGR (kNV/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 9.68 9.82 0.20 0.22 9.72 9.87 1.00 1.10 9.79 9.95 2.00 2.20 9.89 10.06 3.00 3.31 9.99 10.17 4.00 4.41 10.09 10.29 5.00 5.51 10.20 10.42 6.00 6.61 10.31 10.55 7.00 7.72 10.43 10.68 8.00 8.82 10.55 10.82 9.00 9.92 10.67 10.96 10.00 11.02 10.79 11.10 11.00 12.13 10.92 11.23 12.00 13.23 10.93 11.28 13.00 14.33 10.92 11.30 14.00 15.43 10.90 11.30 14.51 16.00 10.89 11.30 15.00 16.53 10.88 11.29 17.00 18.74 10.81 11.19 19.13 21.09 10.66 11.02 20.00 22.05 10.60 10.95 25.00 27.56 10.18 10.51 30.00 33.07 9.76 10.08 35.00 38.58 9.32 9.62 40.00 44.09 8.87 9.17 45.00 49.60 8.37 8.63 50.00 55.12 7.83 8.09 55.00 60.63 5.54 6.37 56.30 62.06 4.88 5.71 57.61 63.50 _ 5.05 57.74 63.65 4.98 57.79 63.70 _ 4.95 Page 17

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Table 16.3-3 MAPLHGR Limits Bundle Type: GE 14-P I ODNAB413-1 6GZ-1 OOT- 150-T-2660 Average Planar Exposure MIAPLHGR (kWV/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 16.00 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 18

BRUNSWICK UNIT 2 0000-0028-0680-SRLR DpPl_.A I D -:qc-- A

-~:II 1IUall V~:III 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 16.3-4 Initial MCPR and Single Loop Operation PLHGR and MAPLHGR Multiplier Single Loop Operation Fuel Type Initial MCPR PLHGR 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. Bntnswvick-Nuclear Plant Unit 1 and2 ExtendedPoiver Uprate Task 0407 ECCS-LOCA SAFER/GESTR Project Task Report, GE-NE-A22-00113-27-01, Revision 0, June 2001.
2. Supplemental ReloadLicensing Reportfor Brunsivick Steam ElectricPlant Unit 2 Reload 15 Cycle 16, 0000-0005-1282-SRLR, Revision 0, January 2003.
3. Supplemental ReloadLicensing ReportforBnrnswick Steam ElectricPlant Unit 2 Reload 14 Cycle 15, J1 1-03781SRLR, Revision 0, February 2001.

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36 40 r_1 [FE [E] E [E]i [EEGE C [GE]1[CD FG c r G C JDG [CE] G fl [E] [E] F][E OF[3E]

34 [ M1 DlEl M1[ IME el et1E[El~ m~i s1E gm IC]1ID 32 [BE [EJ[HE [CD G- [EE]G EC]mEG] C [E [CD [GE] [GE]CGMFM CM m[GoE]G [D1E][HD EllE 30 [D) [E] [H] M GqFC m [GE 2[ED [GlE] C [GlE] [BE] [BE l M ClMfG1[ FE G C l GD H 28~~~~I l El15ID [E IDl ElPIDB1E 26 Wl MEl m MEl[LIm Ue MUIM1121LE  %] E Ml Ml[ml~ mL [g[5 24 nB[E] [F1E]H [C] [E] DM[G m[CE] ~ C G] [DE] [E] [E lmg(( [Elj[!E] [EC] [E] q rl1 E]

22 D lo [VEl[ol [l(El Vm e M 20 BJ[ElE] g H [DE] [E] [iE]J[ [lElj~ [iE] [E [E] ED] DEl B~l~ ID E1fl 18~E[E [O~ [DT[ m[mC~ Gt Dr [EH Cl F1 1 168 EITE 1EM[E] ONE 107M ID] FID 11-71 0121m 01D i [0g1 I M EgMM E4 14 [ e El 12 E1[3 ON [ - DE1 I IDEl Fl[D mIn FID Mm E~ ei ElmP121 O 10 U 8

2~MI EU1[LD [lMJLEl 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=GE14-PIODNAB399-16GZ-IOOT-150-T-2418 (Cycle 15) F=GE14-PIODNAB439-12G6.0-lOOT-150-T-2575 (Cycle 16)

B=GE14-PIODNAB398-13GZ-IOOT-150-T-2417 (Cycle 15) G=GE14-PIODNAB413-16GZ-IOOT-150-T-2660 (Cycle 17)

C=GE14-PIODNAB420-18GZ-IOOT-150-T-2572 (Cycle 16) H=GE14-PIODNAB425-3G7.0/14G6.0/IG2.0-lOOT-150-T-2574 D=GE14-PIODNAB419-6G7.017G6.0/3G2.0-lOOT-150-T-2573 (Cycle 17)

(Cycle 16) I=GE14-PIODNAB439-12G6.0-IOOT-150-T-2575 (Cycle 17)

E=GE14-PIODNAB425-3G7.0/14G6.0/IG2.0-lOOT-150-T-2574 (Cycle 16)

Figure 1 - Reference Core Loading Pattern Page 20

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Asvco R.1an 1t

.- ~ld I~~lll

-1ai

-s-Vessel Press Rise (psi) 325.0 -c- Total SRV Flow

- Bypass Valte Flow 2750.

St 175.0 125.0 75.0

.25.0 I 3.0 4.0 5.0 6.0 0.0 1.0 2.0 3.0 40 50 6.0 Time (sec) Time (see)

  • g 75 0 00 1.0 2.0 3.0 40 50 6.0 30 40 Time (sec) Time (sec)

Figure 2 - Plant Response to Load Reject Nv/o Bypass BOC17 to EOFPC17-3145 MAWd/MT (2853 MWd/ST)

ICF-HBB Page 21

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 3750

-- *.-VesselPress Rise (psi) 325.0 -a- Total SRV Flow

-*-Bypass Valve Flow 275 0 225 0 X 175.0 125.0 750 25.0

-25.0 ll 0.0 5.0 10.0 150 20.0 0.0 50 10.0 15.0 20.0 Tlnme (soc) Timfe (sec) t.SI 1.0 0.S

- 00 V

It Ix .0.5 It.-

.1.0

.1.5 0.0 5.0 100 15.0 20.0 0.0 5.0 10.0 15.o 20.0 Time (sec) Time (sec)

Figure 3 - Plant Response to FWV Controller Failure BOC17 to EOFPC17-3145 A1Wd/MT (2853 MWd/ST)

ICF-HBB Page 22

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 25 0 2000 I1 0.0 1.0 2.0 3.0 4.0 50 6.0 0.0 1.0 z0 3.0 4.0 5.0 6.0 Time (see) Time (sec) 200.0 i; 75.0 0.0 1.0 2.0 30 40 5.0 6.0 3.0 4.0 6.0 Time (sec) Time (sec)

Figure 4 - Plant Response to Load Reject v/o Bypass EOFPC17-3145 MWd/MT (2853 MWd/ST) to EEOC17 ICF-HBB Page 23

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reloasd 16 Revision 0 375 0.

_-- Vessel Press Rise (psi) 325 0 -e-Total SRV Flow

-*--Bypass Valve Flow 27504 225.0 4 g 175.0 rax S2 125.04 75.0 25.0 0.0 I -25.0 0.0 50 100 15.0 20.0 0.0 5.0 ¶0.0 15.0 20.0 ii U: Time (sec) Time (sec) 0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 20.0 Time (sec) Time (sec)

Figure 5 - Plant Response to FW Controller Failure EOFPC17-3145 MWdIMT (2853 MWd/ST) to EEOC17 ICF-HBB Page 24

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 250.0, ..l . s2To0 .

-- Neutron Flux

-- *- Core Inlet Flow Core Ilet Subcoolir I 325.0

-*.- Vessel Press Rise (psi)

-- Total SRV Flow

-.- Bypass Valve Flow 2000 2750 225 0 1500

.4

,3 175.0 50 00 or 100.0 125.0 750 50.0 250O o.n I -25.0 ,

0.0 5.0 10.0 15.0 20.0 0.0 5.0 10.0 150 20.(

Time (sec) Time (sec) 1.5 1.0 0.5

& 0.0 I2 4.

.ID

-1.5

-2.0 4 20.0 0.0 5.0 10.0 15.0 20.0 Time (sec) Time (soc)

Figure 6 - Plant Response to FW Controller Failure BOC17 to EEOC17 ICF-FWTR-TBVOOS-UB Page 25

BRUNSWICK UNIT 2 0000-0028-0680-SRLR D-1-A I aZ 1XI1uvau IUV, aIUII A~iim

.-.-- Vessel Press Rise (psi) 325 0 -a- Total SRV Flow

--- Bypass Valve Flow 275.0 22S.0

  • Z 175.0 12.0 7S0 25.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 0.0 1.0 2.0 30 40 6.0 6.0 7.0 Time (sec) Time (sec)
  • 2 75.0 rw I-00 1.0 2.0 3.0 4 0 0.0 6.0 7.0 0.0 1.0 2.0 3.0 4.0 s0 6.0 7.0 Tire (sec) Time (sec)

Figure 7 - Plant Response to MSIV Closure Flux Scram Page 26

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 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 Analysis Value Parameter NFVT RFNNT Thermal power, MWt 2923.0 2923.0 Core flow, Mlb/hr 80.5 80.5 Reactor pressure, psia 1057.8 1035.8 Inlet enthalpy, BTU/lb 528.7. 512.5 Non-fuel power fraction I8 Steam flow, Mlb/hr 12.73 11.06 Dome pressure, psig 1029.3 1008.6 Turbine pressure, psig 963.5 958.2 No. 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 18 Not available in the TRACG output files.

19Bounds operation with off-site power source for reload licensing events for Cycle 17.

Page 27

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Appendix B Decrease in Core Coolant Temperature Events The Loss of Feedwater Heating (LFWH) event was analyzed for Brunswick Steam Electric Plant Unit 2 Cycle 17 at 100% rated Extended Power Uprate (EPU) using the BWR Simulator Code. The use of this code is permitted in GESTAR II. 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 Steam Electric Plant Unit 2 Cycle 17 in accordance with Reference B-I.

Reference B-I. DeterminationofLiniting Cold WaterEvent, NEDC-32538P-A, February 1996.

Page 28

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Appendix C Operating Flexibility Options Reference C-1 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 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 I1. FWTR 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 11.

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 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. Due to a safety limit change for Brunswick Unit 2 Cycle 17 from the reference safety limits used in References C-6, C-3 and C-5, there will be a required adjustment to the MCPR(p) below P-bypass limits, a required adjustment to the MCPR(f) limits, and a validation of the required minimum GE14 OLMCPR for the recirculation pump seizure event. Further, the implementation of TRACG (Reference C-7) requires an adjustment to the K(P) above P-bypass.

MCPR(p) below P-bypass is increased for a Safety Limit of 1.11 by the ratio of 1-9.

The limit figures are as follows for all fuel types in the core:

Page 29

BRUNSWICK UNIT 2 0000-0028-0680-SRLR D.1,n-1 I r RP-vici- nJ 3.50 II> 50% FlowI N I I

-c 3.25 3.00 -

2.75 -

'S5C% Flow I II II I I I 1I I 1 I E-2.50 -

-4 .- _ Operating Limit MCPR (P) = K(P)

  • Operating Limit MCPR (100)
a. For P < 23%: No Thermal Limits Required C.)

O 2.25 - For 23% < P < 26%, > 50% Flow:

C OLMCPR(P) = 3.13+ 0.0900.(26% - P) c- I For 23% S P < 26%, < 50% Flow:

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

For 26% S P < 45%: K(P) = 1.28 + 0.0135.(45% - P) 1.75 - , For 45% s P < 60%: K(P) = 1.18 + 0.00667.(60% - P)

For 60% < P: K(P) = 1.00 + 0.00450.(100% - P) I 1.50 -1 I

1.25 I I7 -I I I I I I I I i .0 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

Figure C Power Dependent MCPR for Brunswick Unit 2 Cycle 17 Page 30

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 1.10 1.00 0.90 0.80

_ 0.70 0.

M 0.60 ___ ___ MAPLHGR(P) = MAPFAC(P).MAPLHGRstd MAPLHGRstd = Rated MAPLHGR limits S50%

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

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

0.40 . _~ - -For _ 23%

  • P < 26%, S 50% Flow:

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

> 50% For 26%

  • P:

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

0.30 0.20 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (%Rated)

Figure C Power Dependent MAPLHGR Factor for Brunswick Unit 2 Cycle 17 Page 31

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 The Reference C-3 MCPR(f) limits are increased for a Safety Limit of 1.11 by the ratio of (-)I. The 1T.07) h following coefficients apply:

Maximum Core Maximu CoreFlow Intercept Flow A(I) B(i) Flof Ratep MCPR

(% of 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 The flow-dependent MAPLHGR limit multiplier, MAPFAC(f), is not altered for Brunswick Unit 2 Cycle 17.

From Reference C-5, the SLO OLMCPR was determined to be 1.40 with a SLO SLMCPR of 1.12. The initial power for the licensing basis pump seizure event is 2143 MWt, 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 seizure event for GE14 fuel for a SLO SLMCPR of 1.12. After EPU, the licensing basis GE14 pump seizure initial power in MWt is unchanged, but represents about 73.3% of licensed thermal power, resulting in a K(P) of about 1.12 (See Figure C-l). Since the SLO SLMCPR is 1.13 for Unit 2 Cycle 17, the SLO OLMCPR must be greater than or equal to 1.40*(1.13/1.12) = 1.41 for the pump seizure event.

Therefore, the minimum GE14 OLMCPR of 1.33 (See Section 11) is conservative for the SLO pump seizure event (1.33*K(73.3) = 1.33*1.12 = 1.49 > 1.41).

Power Load Unbalance (PLU) Impact on ARTS Power Dependent Limits A recent 10 CFR Part 21 Communication regarding ARTS off-rated power dependent limits is documented in Reference C-8. This communication concluded:

1. GENE has confirmed that the ARTS off-rated K(P) limits are not affected as long as
  • TCV fast closure and direct scram are initiated for load rejection events with no turbine bypass for reactor power above P-bypass, or
  • The load rejection event occurs at up to -40% of rated thermal power with normal off-rated feedwater temperature and with credit for greater than or equal to 20.5% rated steam flow capability.
2. If a plant's turbine bypass capacity exceeds the power level where the PLU device will not generate a TCV fast closure, then the turbine bypass will effectively mitigate the load rejection event and the ARTS off-rated K(P) limits are not affected.

Page 32

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 If the above conditions cannot be satisfied, the below P-bypass limits (at the P-bypass power level) may be applied between the range of P-bypass and the power level where the PLU device will not generate a TCV fast closure. Application of below P-bypass limits bounds FWTR operation provided the limits are applied at the core power level corresponding to the power level where the PLU will generate a TCV fast closure under FWTR conditions.

Note, since the PLU is based on pressure that is proportional to turbine power, operation with FWVTR and the associated reduced steam flow rate may reduce the turbine power compared to the core power. This can result in a higher core power to achieve the turbine power where the PLU device will generate a fast closure signal. At this higher core power, the K(P) value is lower, and the generic off-rated limits may no longer provide the required protection with FWTR. The best method to determine the relationship of the PLU turbine power is from plant measurement or turbine heat balance data at normal and reduced feedwater temperature conditions.

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

C-2. FeedivaterTemperatureReduction with Maximum Extended LoadLine Limit and Increased Core FlowforBrunswick Steam ElectricPlants Units I and 2, NEDC-32457P, Revision 1, GE Nuclear Energy (Proprietary), December 1995.

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

C4. Turbine Bypass Out of Service Analysisfor CarolinaPower & Light Company s Brunswick NuclearPlants Units I and 2, NEDC-32813, Revision 3, GE Nuclear Energy (Proprietary),

June 1998.

C-5. GEJ4 FuelDesign Cycle-IndependentAnalyses for Bnrnswick Steam Electric Plant Units I and 2, GE-NE-L12-00876-00-OP, Revision 1, GE Nuclear Energy (Proprietary),

February 2001.

C-6. Safety Analysis Reportfor Bnmswick Steam ElectricPlant Units I and 2 ExtendedPower Uprate,NEDC-33039P, GE Nuclear Energy (Proprietary), August 2001.

C-7. Brunswick NuclearStation TRA CG 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.

Page 33

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 Revision 0 Appendix D Implementation of TRACG AOO Methodology Reference D-1 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 GE14 fuel.Section II of this report presents the MCPR limits based on the methodology of Reference D-2.

References D-1. Brunswick NuclearStation TRACG Implementationfor ReloadLicensing TransientAnalysis, GE-NE-0000-0022-8180-RO, GE Nuclear Energy (Proprietary), February 2004.

D-2. TRACGApplicationforAnticipated OperationalOccurrences TransientAnalysis, NEDE-32906P-A, Revision 1, April 2003.

Page 34

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 RCvision 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 2 Cycle 17.

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 1 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 EPU/MELLLA+ operation, the Detect and Suppress Solution - Confirmation Density (DSS-CD) is the licensing basis for Brunswick Unit 2 Cycle 17. The reload checklist as outlined in Reference E-2 is used to confirm that the DSS-CD is applicable to Brunswick Unit 2 Cycle 17 EPU/MELLLA+ operation.

DSS-CD Plant Specific Applicability Checklist Parameter j.'-"WCriterion: -Aceptance BWR Product Line BWR/3-6 design as of July 2002 Yes (BWR/4)

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

< EPU/MELLLA+ including BVR/3-6 Operating Domain licensed operational flexibility features Yes as of July 2002 Rated TFW < 1200 F (EPU/MELLLA)

Reduction No TFW Reduction (MELLLA+ Yes (110F) extension)

OLMCPRRatd - SLMCPR MCPR Margin OLMCPRRated 0.067 Yes (0.165)

Page 35

BRUNSWICK UNIT 2 0000-0028-0680-SRLR Reload 16 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 2 Cycle 17 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 Bnrnswick Steam ElectricPlant Units 1 and 2 Maximum Extended LoadLine Limit Analysis Plus, NEDC-33063P, GE Nuclear Energy (Proprietary),

November 2002.

E-2. GeneralElectric Boiling Water ReactorDetect andSuppress Solution - ConfirmationDensity Licensing Topical Report, NEDC-33075P, Revision 4, July 2004.

E-3. DSS-CD Backup Stability ProtectionEvaluationfor Brunswick Unit 2 Cycle 17, GENE-0000-0034-1491-RO, January 2005.

E-4. Brunswick NuclearPlant Unit I and2 MELLLA + Task 0407 ECCS-LOCA SAFER/GESTR Project TaskReport, GE-NE-A22-00113-83-01, Revision 0, September 2002.

E-5. GESTR-LOCA andSAFER Modelsfor Evaluation of Loss-of-Coolant Accident Volume III, Supplement 1, Additional Informationfor UpperBound PCTCalculation,NEDE-23785P-A, Volume III, Supplement 1, Revision 1, March 2002.

Page 36

BRUNSWICK UNIT 2 0000-0028-0680-SRLR PDI-An If A~orn B UNICK

.R UNIT 2 OOO008 SLR Appendix F 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 I00/OPower / 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 Bum HBB Hard Bottom Burn HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection HTSP High Trip Setpoint Page 37

BRUNSWICK UNIT 2 0000-0028-0680-SRLR R-I--A 1{ D..;C:-- n zlwuau Au . scvnansln a Acronym Description ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix 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 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 Bum 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 RFWT Reduced Feedwater Temperature RPS Reactor Protection System Page 38

BRUNSWICK UNIT 2 0000-0028-0680-SRLR PD-1-rA nxt.Uat. h1 LU AZMrcn ixt:V1iaUii V Acronym Description 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 SRV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State STU Short Tons (or Standard Tons) of Uranium TBPOOS Turbine Bypass Out of Service 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 TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Burn Page 39

BSEP 05-0024 Enclosure 4 Global Nuclear Fuels Affidavit Regarding Withholding NEDC-31624P, Supplement 2, Revision 9, From Public Disclosure

Affidavit Affidavit I, Margaret E. Harding, 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 2, Revision 9, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17", January 2005.

GNF proprietary information is indicated by enclosing it in double brackets. In each case, the superscript notation (3) 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 "4confidential 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 Project v. Nuclear Regulatory 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.

Affidavit 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 18th day of January, 2005.

Margaret E. Harding Global Nuclear Fuel - Americas, LLC

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