Text

Non-proprietary Suppl Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 11 Cycle 12
	ML20101B630
Person / Time
Site:	Brunswick
Issue date:	01/31/1996
From:	Hull G, Reda R; GENERAL ELECTRIC CO.
To:	;
Shared Package
ML19355C768	List: BSEP-96-0026, Forwards Rev 0 to NF-2495.0080, Brunswick Unit 2,Cycle 12 Core Operating Limits Rept,non-proprietary Rev 0 to 24A5195, Proprietary Rev 3 to NEDC-31624P & Rev 0 to NEDC-31624P. Encls Withheld (Ref 10CFR2.790); ML20101B624; ML20101B630;
References
	24A5195, 24A5195-R, 24A5195-R00, NUDOCS 9603140402
	Download: ML20101B630 (46)
	v • d • e

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GENuclearEnergy 24A5195 :

i Revision 0 ClassI January 1996 l Supplemental Reload Licensing Report for 1

l Brunswick Steam Electric Plant Unit 2 1

Reload 11 Cycle 12 i

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i 9603140402 960304 PDR ADOCK 05000324 P PDR<

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O GE Nuclear Energy 24A5195 Revision 0 Class I January 1996 24A5195, Rev. O Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 11 Cycle 12 Approved Approved hh R.J. Reda, Manager G.R. Hull Fuel and Facility Licensing Fuel Project Manager

BRUNSWICK 2 24A5195 l Reload 11 Rev.0 Important Notice Regarding Contents of This Report 1

Please Read Carefully ;

1 This report was prepared by General Electric Company (GE) solely for Carolina Power and Light Company (CP&L) for CP&L's use in defining operating limits for the Brunswick j Steam Electric Plant Unit 2. The information contained in this report is believed by GE to be an accurate and true representation of the facts known or obtained or provided to GE at the time this report was prepared.

The only undertakings of GE respecting information in this document are contained in the contract between CP&L and GE for nuclear fuel and related services for the nuclear system for Brunswick Steam Electric Plant Unit 2 and nothing contained in this document I shall be construed as changing said contract. The use of this information except as de-fined 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 GE nor any of the contributors to this document makes any representation or warranty (expressed or im-plied) 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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l BRUNSWICK 2 24A5195

, Reload 11 Rev.0

Acknowledgement i

l The engineering er.d reload licensing analyses, which fonn the technical basis of this Supplemental Reload Licensing Report, wem perfonned by M.R. Morris. The Supplemental Reload Licensing Report was pre-j

. pand by M.R. Morris. This document has been verified by G.N. Marrotte.

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BRUNSWICK 2 24A5195

. Reload 11 Rev.0 i'

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The basis for this mport is GeneralElectric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-11, November,1995; and the U.S. Supplement, NEDE-240ll-P-A-11-US, November 1995.

1. Plant-unique Items

Appendix A: Analysis Conditions

, Appendix B: Main Steamline Isolation Valve Out of Service (MSIVOOS)

Appendix C: Decrease in Core Coolant Temperature Events 4 Appendix D: Feedwater Temperature Reduction (FWTR)

Appendix E: Maximum Extended Operating Domain

] 2. Reload Fuel Bundles Cycle ,

q Fuel Type Loaded Number '

Irradiated: )

i l GE8B-P8DQB323-11GL80M-4WR-150-T (GE8x8EB) 8 8 GE8B-P8DQB317-9GL80M-4WR-150-T (GE8x8EB) 8 16 l GE9B-P8 DWB 329-11 GL80M-150-T (GE8x8NB) 9 36 l l GE10-P8HXB329-12GZ1-100M-150-T (GE8x8NB-3) 10 148 i

GE10-P8H XB322-11 GL70M-150-T (GE8x8NB-3) 11 8 GE10-P8HXB320-11GL100M-150-T (GE8x8NB-3) 11 32 4

GE10-P8HXB324-12GL70M-150-T (GE8x8NB-3) 11 112 Nem i

GE13-P9DTB363-11GL100T-146-T (GE13) 12 136 GE13-P9DTB 363-11 GZ1-100T-146-T (GE13) 12 64 1 Total 560 l

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j 3. Reference Core Loading Pattern 1

! Nominal previous cycle core average exposum at end of cycle: 27988 mwd /MT j ( 25390 mwd /ST)

Minimmn previous cycle core average exposum at end of cycle 27743 mwd /MT from cold shutdown considerations: ( 25168 mwd /ST)

Assumed reload cycle core average exposure at beginning of 15044 mwd /MT

, cycle: ( 13647 mwd /ST) s Assumed reload cycle core average exposure at end of cycle: 27279 mwd /MT

( 24747 mwd /ST)

Reference core loading pattem: Figure 1 Page 4

BRUNSWICK 2 24A5195

, Reload 11 Rev.0 1

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4. Calculated Core Effective Multiplication and Control System Worth -No Voids,20 C Beginning of Cycle, kegeceve l Uncontmiled 1.105 Fully controlled 0.963 Strongest control rod out 0.984 R. Maximum inen:ase in cold core reactivity with exposure into cycle, Ak 0.000

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

(ppm) (20*C, Xenon Free) 660 0.041

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Exposure: BOC12 to EOC12-2000 mwd /MT with Increased Core Flow (ICF)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axist , R-Factor Power Flow MCPR (MWt) (1000lb/hr)

GE8x8NB-3 1.20 1.67 1.40 1.000 7.086 111.8 1.25 GE13 1.45 1.55 1.31 1.020 6.585 110.3 1.36 i

Exposure: EOC12-2000 mwd /MT to EOC12 with ICF l Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (10001b/hr)

GE8x8NB-3 1.20 1.62 1.40 1.000 6.881 113.0 1.29 GE13 1.45 1.59 1.15 1.020 6.726 108.9 1.37 Exposure: BOC12 to EOC12-2000 mwd /MT with Maximum Extended Load Line Limit (MELLL)

Peaking Factors

~

Fuel Bundle Bundie Initial Design 14 cal Radial Axial R-Factor Power Flow MCPR (MWt) (1000lb/hr)

GE8x8NB-3 1.20 1.57 1.40 1.000 6.633 79.4 1.18 GE13 1.45 1.44 1.27 1.020 6.080 78.4 1.32 Page 5

_ _ . . - - - - _- . . - . __=~ . _-

. BRUNSWICK 2 24A5195 Reload 11 Rev.0

, Exposure: EOC12-2000 mwd /MT to EOCl2 with MELLL Peaking Factors j Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr) !

j GE8x8NB-3 1.20 1.54 1.40 1.000 6.541 79.8 1.20 l GE13 1.45 1.41 1.32 1.020 5.948 79.6 1.33 Exposure: BOCl2 to EOC12 with ICF and FWTR

) Peaking Factors Fuel Bundle Bundle Initial i Design Local Radial Axial R-Factor Power Flow MCPR i

(MWt) (1000lb/hr)

GE8x8NB-3 1.20 1.73 1.40 1.000 7.317 110.3 1.24 JJ GE13 l 1.45 1.65 1.20 1.020 6.970 107.5 1.35 i j Exposure: BOCl2 to EOC12-2000 mwd /MT with MSIVOOS and ICF

) Peaking Factors Fuel Bundle Bundle Initial j -

Design Local Radial Axial R-Factor Power Flow MCPR

( M W t) (1000lb/hr) l GE8x8NB-3 1.20 1.71 1.40 1.000 7.257 110.9 1.21 GE13 1.45 1.58 1.31 1.020 6.687 109.7 1u j Exposure: EOCl2-2000 mwd /MT to EOC12 with MSIVOOS and ICF

Peaking Factors l Fuel Bundle Bundle Initial l Design Local Radial Axial R-Factor Power Flow MCPR

, (MWt) (1000 lb/hr)

GE8x8NB-3 1.20 1.66 1.40 1.000 7.037 112.1 1.26 GE13 1.45 1.60 1.15 1.020 6.772 108.7 1.36

7. Selected Margin Improvement Options Recirculation pump trip: No

) Thermal powermonitor: Yes Improved scram time: Yes (ODYN Option B)

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) Measured scram time: No i Exposure dependentlimits: Yes l Exposure points analyzed: 2 (EOC12-2000 mwd /MT and EOCl2) i Page 6 4

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. BRUNSWICK 2 24A5195 Reload 11 Rev.0 '

8. Operating Flexibility Optionsi l Single-loop operation: Yes Load line limit: Yes Extended load line limit: Yes Maximum extended load line limit: Yes increased core flow throughout cycle: Yes Flow point analyzed: 105.0 %

increased core flow at EOC: Yes Feedwater temperatum reduction throughout cyde: No ,

1 Final feedwater temperature reduction: Yes l Temperature reduction: 145.0 F l ARTS Program: Yes 4

Maximum extended operating domain: Yes l l

Turbine bypass system OOS: No Safety / relief valves OOS: Yes (credit taken for 9 of 11 valves)

ADS OOS: Yes (2 valves OOS)

EOC RIT OOS: No Main steam isolation valves OOS: Yes

9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS Exposure range: BOC12 to EOCl2-2000 mwd /MT with ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 338 118 0.15 0.27 2 Turbine Trip w/o Bypass 309 118 0.15 0.26 3

1. Note that the reload analysis used 145' of feedwater temperature reduction, but the analysis referenced in Appendix D is only valid up to 130* of feedwater temperature reduction.

Page 7

BRUNSWICK 2 24A5195

, Reload 11 Rev.0 Exposure range: EOC12-2000 mwd /MT to EOC12 with ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Turbine Trip w/o Bypass 339 117 0.19 i).29 4 Load Reject w/o Bypass 345 117 0.19 0.29 5 Exposure range: BOC12 to EOCl2-2000 mwd /MT with MELLL Uncorrected ACPR j Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Turbine Trip w/o Bypass 276 114 0.09 0.22 6 Load Reject w/o Bypass 273 114 0.08 0.22 7 I Exposure range: EOC12-2000 mwd /MT to EOC12 with MELLL Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Turbine Trip w/o Bypass 287 117 0.11 0.24 8 Load Reject w/o Bypass 285 116 0.11 0.24 9 Exposure range: BOC12 to EOC12 with ICF and FWTR Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

FW Controller Failure 190 115 0.11 0.13 10 Load Reject w/o Bypass 292 115 0.15 0.26 11 Turbine Trip w/o Bypass 283 115 0.15 0.25 12 Exposure range: BOC12 to EOCl2-2000 mwd /MT with MSIVOOS and ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 310 116 0.13 0.25 13 hrbine Trip w/o Bypass 304 116 0.12 0.24 14 Page 8

, Reload 11 Rev.0 Exposure range: EOC12-2000 mwd /MT to EOCl2 with MSIVOOS and ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 327 115 0.17 0.28 15

'Ibrbine Trip w/o Bypass 322 114 0.16 0.27 16

10. Local Rod Withdrawal 8rror (With Limiting Instrument Failure) AOO Summary The md withdrawal error event in the maximum extended operating domain was originally analyzed in the GE BWR Licensing Report, Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P, dated Febnlary 1989. The MCPR limit for rod withdrawal erroris bounded by the op-erating limit MCPRs presented in Section 11 of this report for RBM setpoints shown in Tables 10-5(a) or 10-5(b) of NEDC-31654P.

11. Cycle MCPR Values2 ,3 Safety limit: 1.09 Single loop operation safety limit:1.11 Non-oressurization events:

Exposure Range: BOC12 to EOC12 GE8x8NB-3 GE13 Fuel Loading Error (misoriented)

GE10-P8HXB324-12GL70M-150-T 1.33 -

GE10-P8HXB322-11GL70M-150-T 1.21 -

GE10-P8HXB320-11GL100M-150-T 1.22 -

GE13-P9DTB363-11GL106T-146--T -

1.22 GE13-P9DTB363-11GZ1-10Ur-146-T -

1.22 Fuel Loading Ermr (mislocated) 1.25 1.25

2. 'Ihe GE8x8NB 3 fuel type MCPR values bound the GE8x8NB and GE8x8EB MCPR values for all pressurindon events.

3. The operstmg limit MCPR for two loop operation (TLo) bounds the operating limit MCPR for single loop operation (Slo), therefore, the operating Imut MCPR need not be changed for stD.

Page 9

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Pressurization events:

Exposure range: BOCl2 to EOC12-2000 mwd /MT with ICF Exposure point: EOC12-2000 mwd /MT Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.34 1.41 1.27 1.36 Turbine Trip w/o Bypass 1.34 1.40 1.27 1.35 Exposure range: EOCl2-2000 mwd /MT to EOCl2 with ICF Exposure point: EOCl2 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.34 1.48 1.30 1.40 Turbine Trip w/o Bypass 1.33 1.48 1.29 1.40 Exposure range: BOCl2 to EOCl2-2000 mwd /MT with MELLL Exposure point: EOCl2-2000 mwd /MT Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 i Turbine Trip w/o Bypass 1.27 1.36 1.20 1.31

~

Load Reject w/o Bypass 1.27 1.36 1.20 1.31 Exposure range: EOC12-2000 mwd /MT to EOCl2 with MFLLL Exposure point: EOCl2 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Turbine Trip w/o Bypass 1.25 1.43 1.21 1.35 Load Reject w/o Bypass 1.25 1.43 1.21 1.35 Page 10

. BRUNSWICK 2 24A5195 Reload 11 Rev.0 Exposure range: BOCl2 to EOCl2 with ICF and FWTR Exposure point: EOCl2 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 FW Controller Failure 1.24 1.31 1.21 1.23 Load Reject w/o Bypass 1.30 1.45 1.26 1.37 Turbine Trip w/o Bypass 1.29 1.44 1.25 1.36 Exposure range: BOC12 to EOCl2-2000 mwd /MT with MSIVOOS and ICF Exposure point: EOCl2-2000 mwd /MT Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.32 1.39 1.25 1.34 Turbine Trip w/o Bypass 1.31 1.38 1.24 1.33 Exposure range: EOCl2-2000 mwd /MT to EOCl2 with MSIVOOS and ICF Exposure point: EOC12 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.31 1.47 1.27 1.39 Turbine Trip w/o Bypass 1.31 1.46 1.27 1.38

12. Overpressurization Analysis Summary Psi Py Plant Event (psig) (psig) Response MSIV Closure (Flux Scram) 1240 1276 Figure 17 I

Page 11

BRUNSWICK 2 24A5195

. Reload 11 Rev.0

13. Loading Error Resultsd Variable water gap misoriented bundle analysis: Yes Misoriented Fuel Bundle ACPR G E l G-P8 H X B 324-12GZ-70M-150-T (G E 8 x 8 NB-3) 0.24 GE10- P8HXB322-I lGL70M-150-T (GE8x8NB-3) 0.12 GE 10-P8HXB320'-11GZ-100M-150-T (GE8x8NB-3) 0.13 GE13-P9DTB363-IIGL10(TT-146-T (GE13) 0.13 GE 13-P9DTB 363--I l GZ l-10(fr-146-T (GE 13) 0.13

14. ,ntrol Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control md drop accident analysis is not required. NRC approval is documented in NEDE-240ll-P-A-US.

, 15. Stability Analysis Results GE SII -380 recommendations and GE interim conective actions have been included in the Brunswick Steam Electric Plant Unit 2 operating pmcedures. Regions of restricted operation defined in Attachment I to NRC B ulletin No. 88-D7, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), are applicable to Bmnswick 2.

16. Loss-of-Coolant Accident Results LOCA method used: SAFER /GESTR-LOCA The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of Brunswick Steam ElectricPlant Units 1 and 2 SAFERIGESTAR-LOCA inss--of-Coolant A ccident A nalysis, NEDC-31624P, Revision 2, July 1990, conservatively bound the LOCA analysis of the GE8x8NB-3 fuel types. This analysis yielded a licensing basis peak clad temperature of 1537'F, a peak local oxidation fraction of <0.31 %, and a core-wide metal-wa-ter reaction of 0.036%.

An additional LOCA analysis was performed for the GE13 fuel type. The results, presented in Brunswick Steam Electric Plant Units 1 and 2 SAFERIGESTAR-LOCA L.oss-of-Coolant Accident Analysis: Applica-tion to GE13 Fuel, NEDC-31624P, Supplement 3, Rev. O, January 1996, indicate that the GE13 fuel is bounded by the results from GE8x8EB fuel.

The most and the least limiting MAPLHGRs for the new GE13 fuel designs are as follows:

4. Includes a 0.02 penalty due to vanable water gap R4 actor uncertainty.

Page 12

BRUNSWICK 2 24A5195

, Reload 11 Rev.0

16. Loss-of-Coolant Accident Results (cont)

Bundle Type: GE13-P9DTB363-1IGZl-10(TT-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.34 11.64 0.20 0.22 11.46 11.65 1.00 1.10 11.62 11.71 2.00 2.20 11.70 11.79 3.00 3.31 11.79 11.87 4.00 4.41 11.89 11.96 5.00 5.51 11.99 12.05 6.00 6.61 12.09 12.15 7.00 7.72 12.20 12.26 8.00 8.82 12.32 12.36 9.00 9.92 12.44 12.47 10.00 11.02 12.55 12.57 12.50 13.78 12.57 12.63 15.00 16.53 12.34 12.40 17.50 19.29 12.07 12.14 20.00 22.05 11.81 11.89 25.00 27.56 11.14 11.23 30.00 33.07 10.43 10.51 35.00 38.58 9.73 9.80 40.00 44.09 9.06 9.10 45.00 49.60 8.41 8.44 50.00 55.12 7.73 7.83 55.00 60.63 7.04 7.20 59.23 65.29 6.44 6.66

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59.29 65.35 --

6.44 59.32 65.38 -

6.43 Page 13

BRUNSWICK 2 24A5195

, Reload 11 Rev.0

16. Loss-of-Coolant Accident Results (cont)

Bundle Type: GE13-P9DTB363-11GZ-10(TT-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.39 11.63 0.20 0.22 11.51 11.65 1.00 1.10 11.62 11.71 2.00 2.20 11.71 11.79 3.00 3.31 11.80 11.88 4.00 4.41 11.89 11.97 5.00 5.51 11.99 12.06 6.00 6.61 12.10 12.16 7.00 7.72 12.21 12.27 8.00 8.82 12.33 12.37 9.00 9.92 12.46 12.48 10.00 11.02 12.59 12.62 12.50 13.78 12.60 12.65 15.00 16.53 12.35 12.41 17.50 19.29 12.08 12.15 20.00 22.05 11.82 11.89 25.00 27.56 11.14 11.24 30.00 33.07 10.43 10.51 35.00 38.58 9.74 9.80 40.00 44.09 9.07 9.10 45.00 49.60 8.41 8.45 50.00 55.12 7.73 7.84 55.00 60.63 7.04 7.20 59.21 65.26 6.44 6.67 59.28 65.34 -

6.44 59.31 65.37 -

6.43 Page 14

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"MMMMMMMMM" "HMMMM5 IIIIIIIIIi 1 3 5 7 9 11 13 15 17 19 21 23 25 27 ft 3133 35 37 39 41 43 45 47 49 51 Fuel Type A=GE88-P8DQB323-llGZA0M-4WR-1%T (Cycle 8) F=GE9B-P8DWB329-11GZ.40M-IST (Cycle 9) 1 HXB3 11 70M 1 T ( cle ! ) =G 0-P8HXB 24- Z- 1 T (C le 11)

D=GE10-P8HXB329-12GZl-100M-l%T (Cycle 10) I=G E 13-P9DTB 363-I I GZ.- 10(TT-146-T (Cycle 12)

E=GE8B-P8DQB317-9GZ-80M-4WR-l%T (Cycle 8)

Figure 1 Reference Core Loading Pattern Page 15

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- - Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow 100.0 d

,/

"((\ ', \ -

200.0 -

m - N m C '

s%s' '. C 50.0 -

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y~~~--- _ _

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I 0.0 '

O.0

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O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Eme (sec)

Lewi(inch-REF-SEP-SKRT) oid Reactivity

- - - - - Vessel Steam Flow - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

Scram Reactivity

--- Feedwater Flow -

Total Reactivity E

m

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Figure 2 Plant Response to Load Reject w/o Bypass (BOC12 to EOCl2-2000 mwd /MT with ICF)

Page 16

BRUNSWICK 2 24A5195 Reload 11 Rev.O Neutron Flux Vessel Press Rise (psi)

-- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- - Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow

%'fs j%

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Level (inch-REF-GEP-SKRT) id Reactivity Vessel Steam Flow -

- - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -

Scram Reactivity Feedwater Flow -

Total Reactivity G

m y

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Figure 3 Plant Response to 'Ihrbine Trip w/o Bypass (BOC12 to EOC12-2000 mwd /MT with ICF)

Page 17

BRUNSWICK 2 24A5195

, Reload 11 Rev.0 Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- - Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow tsy* . p\ '

J .g /--

g 100.0 m. , , * '., % Ns 200.0 -

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Time (Sec) Time (sec) l

^ oid Reactivity Lewl(inch-REF-SEP4KRT)

- - - - - Vessel Steam Flow - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

Scram Reactivity

--- Feedwater Flow -- TotalReactivity

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Figure 4 Plant Response to Turbine Trip w/o Bypass (EOCl2-2000 mwd /MT to EOC12 with ICF)

Page 18

BRUNSWICK 2 24A5195

. Reload 11 Rev.O Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - - - - - Safety Vane Flow 150.0 - - -

- Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow

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Level (inch-REF-SEP-SKRT)

^ Void Reactivity

- - - - - Vessel Steam Flow - -

Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -

-- Scram Reactivity

--- Feedwater Flow - - Total Reactivity

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E

\.

[', ,, ,

8 ,

\ .

N 1' ' ' ' . - ,

I \\

0.0 l M *; ,b O ' - - - - - - - - - - - - -

-1.0 -

' *)

C \

. \ .

\

- 100.0 ' ' I I

-if '

O.0 3.0 6.0 0.0 3.0 6.0 Time (Sec) Time (sec)

Figure 5 Plant Response to Load Reject w/o Bypass (EOCl2-2000 mwd /MT to EOC12 with ICF)

Page 19 1

_____.___J

. BRUNSWICK 2 24A5195 Reload 11

. Rev.0 Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - ---

- Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow g 100.0 ,' ',

g 200.0 T

g -lV\ ,~ D -

%~ W g

s _' ~~

~. .

50.0 -

100.0 -

r--------------

I I

0.0 O.0 ' '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) Eme (sec)

Level (incMEF.-SEP-6KRT) oid Reactivity

- - - - Vessel Steam Flow -----

ppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

m Reactivity

--- Feedwater Flow -

Total Reacevity

~a

m ..

y .

y . .-

g 100.0 7 - ---- . ,

0.0 ., ,',

g g, , ,, -.- . - ,

\ ....-

x g

e','

. . . ' ' . ... ~...-..

8 -

'\\

l :I O.0 L, t y - L - - - - - - - - - - - - - - j-1.0

('k g

W \.

\'

) ,

\'

100.0 ' I '

~ 2.0 I' ' '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) Eme (sec)

Figure 6 Plant Response to ibrbine Trip w/o Bypass (BOCl2 to EOC12-2000 mwd /MT with MELLL) l Page 20

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Neutron Rux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -.- - CoreinletFlow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow 100.0 ,e 200.0 -

e '

m ' % ~._. e e ,

7 '. ~ ~ ~ ~ ~ , ,

50.0 - '

100.0 -

7 - - -. - _. _ ._ _ ._ _ _ __

I I

0.0 O.0 ' ' '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) Time (sec)

Level (inch-REF-SEP-SKRT) id Reactivity

- - - - Vessel Steam Flow --- - ppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -

am Reactivity

--- Feedwater Flow -

Total Reactivity a

.S ...

m -

y . .

p 100.0 ,

-. % , 0.0 ., ,'

n ;, ... -,

\ .

m j', '

,.,, l '... ... ....... 6 \,...

l. ,

', l k

.a

\,

\

0.0 M sr -l- U- - - - - - - - - - - - - . } -1.0 -

'i

$\

m i.

\

II l'

- 100.0 '

-2.0 I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Eme (sec)

Figure 7 Plant Response to Load Reject w/o Bypass (BOC12 to EOC12-2000 mwd /MT with MELLL)

Page 21

_a

BRUNSWICK 2 24A5195

, Reload 11 Rev.0 t

Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - ---

- CoreInletFlow 300.0 - --- Relief Valve Flow

--- Gypass Valve Flow g 100.0 ,', '., g200.0 E

g f 9 ,J <'m. y , E g -

50.0 -

100.0 -

( ~ ~ ~ - -

I I

0.0 O.0 ' ' '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) v Level (inch-REF-SEP-SKRT) id Reactmty

- - - - - Vessel Steam Flow - - -

oppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - --

m Reactivity

--- Feedwater Flow -

otal Reactivity

. E ' ~~

m /

E . ..

g .-

t 100.0 y' o 0.0 g i, ---.%----.- ,,

y .,,.. ',

E '

l . . . . - . . ,

6 ,

\

\W M,a;. u - ' '- - - - - - - - - - - - - - j -1.0

?

O.0 ,

a

\'{

)

r.

)

t

\.

' I

-100.0 ' '

-2.0 ' I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 8 Plant Response to Turbine Trip w/o Bypass (EOCl2-2000 mwd /MT to EOC12 with MELLL)

Page 22

BRUNSWICK 2 Reload i1 24A5195 Rev.O Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 - --- - CoreinletFlow 300.0 - --- Relief Valw Flow

--- Bypass Valve Flow 100.0 ,,' ', 200.0 -

/V\ ,/

b x $

g g

.7 % ~ ~

50.0 - '*

.. ., 100.0 - I p.------- _._

I I

0.0 O.0 I '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) mme (sec)

Level (inch-REF-SEP--SKRT) id Reac[vity

- - - - Vessel Steam Flow -- -- ppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - --

am Reactivity

--- Feedwater Flow -

otal Reactivity G -

m *.-

2 t3 100.0 g

0.0 g (, ... '

,.J--.- N . ..

x ,' '. ., * - ...- ......

~; ', ..

3 '

s f \.

0.0 1 4 l._ _ a _ _ _ _. _ _ _ _ _. _ _ _ _ .

5O -1.0 -

g x \.

~

I

\

- 100.0 ' l '

-2.0 \ I '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) mme (sec)

Figure 9 Plant Response to Load Reject w/o Bypass (EOC12-2000 mwd /MT to EOC12 with MELLL)

Page 23

BRUNSWICK 2 24A5195 Reload 11 Rev.0

. X-Neutron FIV .

Vessel Press Rise (psi)

- - - - - Avgeace Hea: Flux - - - - - Safety Valve Flow 150.0 -

.- Core inlet Flow 125.0

- --- Relief Valve Flow

- -- Core inlet Subcooling --- Bypass Valve Flow

- g~~- .:.: 5

'r ' ,N* ~ ~

g 100.0

'. 75.0 -

w w E C g -

g -

50.0 -

25.0 -

0.0 ' ' '

-25.0 ' '

O.0 7.0 14.0 0.0 7.0 14.0 Eme (Sec) Eme (SeC)

Level (inch-REF-SEP-SKRT)

- - - - - Vessel Steam Flow Void Reactivity Y

- - - - Doppler Reactvity 150.0 - -.-- Turbine S_ team Flow 1.0 - --- Scram Reactivity

--- Feedwater Flow '

--- TotalReactivity

. 5en s ,

o' a

g 100.0 -

0.0 -

x Q ,,l---- ,'

1, dd..\'-

l ',

6 a

x

.2:

50.0 -

l'- . N. -1.0

" L

~

!" \ -

~ h l" gi l' I 0.0 3 I' ' l I

- 2.0 '

0.0 7.0 14.0 0.0 7.0 14.0 Eme (sec) Eme (sec)

Figure 10 Plant Response to FW Controller Failure (BOC12 to EOCl2 with ICF and i

FWTR) l 1

Page 24

__ o

- BRUNSWICK 2 24A5195

, Reload 11 Rev.0 Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - ---

Safety Valve Flow 150.0 - - - - Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow t -

_, j

/ "\ - Js

/ s

N g 100.0 , ,

sN y 200.0 -

m

- s s

Sce C ',

- N s C

$ ., %s $

50.0 -

100.0 -

,/ \

/ t-_

0.0 '

O.0 # I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Level (inch-REF-SEP-SKRT) oid Reactivity

- - - - - Vessel Steam Flow ---

- Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

Scram Reactivity

--- Feedwater Flow -- Total Reactivity E

m

. /\

s .... -

g ..

u 100.0 -

0.0 ,, ,

$ t---------.___. .- \

C j. ,

' o \

g . .. ,

. c _

},

.g

)-

a \

.A 0.0 j',7.,------------------

' .- g -1.0 1

, p, C l

\ >

g

\

-100.0 ' l '

-2.0 I ' I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 11 Plant Response to Load Reject w/o Bypass (B9C12 to EOC12 with ICF and FWTR) 1 l

l Page 25 i

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Neutron Flux Vessel Fross Rise (psi)

- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- - Core inlet Flow 300.0 - --- Reliet Valve Flow

--- Bypass Valve Flow

_ ./ wl k. .

r ~N N g 100.0

.,' '., g 200.0 u -

s a xm e s

. x g -

., g -

50.0 -

. 100.0 -

. / \-

r I \

' i --

0.0 O.0

' / l '

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) Time (sec)

Level (inch-REF-SEP-SKRT) id Reactivity

- - - - - Vessel Sesam Flow ----- ppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

Scram Reactivity

--- Feeduater Flow -

Total Reactivity 3 . ,1 -

us ' . *.

y ,..

t 100.0 k ,.

o 0.0 -*.,) '

$ r------------- ~

@ \

W ~

l. ,

8 _

\

,- ,. '& \.

l' , . '

. ,, .2: I

\

i 11 0.0 L,' .w. y, - - a s , - - - - - - - - - -

e -1.0 e

f E \.Y'

\

\ .

\

100,0 - I '

-2.0 I ' I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 12 Plant Response to 'Ibrbine Trip w/o Bypass (BOCl2 to EOC12 with ICF and FWTR) i l

I l

Page 26

. BRUNSWICK 2 24A5195 l Reload 11 Rev.0 l

Neutron Flux Vessel Press Rise (psi) .

- Ave Surface Heat Flux - - - - - Safety Valve Flow I 150.0 - -- Core inlet Flow 300.0 - --- Relief Valve Flow l

--- Bypass Valve Flow ;

1

)

N nr'y l

, s u 100.0 .' , , N s r3 200.0 -

v -

% 6 A

m -

' s E C -

' N ,. ~ C

. 's $ ~

50.0 100.0

. I

( %

' ' ' I '

0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec) I Level (inch-REF-SEP-4KRT) Void Reactivity

- - - - Vessel Steam Flow Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - - -f - Scram Reactivity

--- Feedwater Flow -- Total Reactivity a .

.) ....

m y '

V 100.0 8 0.0 i.

n \. - --. . ----- . .'.

.% : m - . . . . -

N. ~.' -

.i '. ,

/ '.. 8 .

s\.(.

%. l n

.a: \

I 0.0 .1 - 'i----------------- E. -1.0

\.

C g

. . \ ,

\ \

\ l I

-100.0 ' '

- 2.0 L I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 13 Plant Response to Load Reject w/o Bypass (BOC12 to EOC12-2000 mwd /MT with MSIVOOS and ICF)

Page 27

BRUNSWICK 2 24A5195

, Reload 11 Rev.0 1

i Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- - Core Inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow g ,\M,/ %

g 100.0 ,,' '., p 200.0 C ',

. %s% s C

$ ~~-,,,

~

$ ~

50.0 -

100.0 -

I t %

0.0 ' '

O.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Level (inch 4EF-SEP-SKRT) id Reactivity

- - - - - Vessel Steam Flow ---

Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -

- Scram Reactivity

--- Feedwater Flow -- TotalReactivity G

ms .

,.=.. -

m / ..-

E f *.

8 . \

v 100.0 y'. .-

-r n .---.

0 .0 -

s '.g....

e \. .. . .. ,

e s g ,

e O - N g

l A \'

O.0 L ---------------- - 1.0 - I o

s g s

\

t-

\

-100.0 ' '

-2.0 L I 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 14 Plant Response to 'Ibrbine Trip w/o Bypass (BOC12 to EOC12-2000 mwd /MT with MSIVOOS and ICF) i I

l Page 28 1

BRUNSWICK 2 24A5195 i

, Reload 11 Rev.0 I Neutron Flux Vessel Press Rise (psi) I

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -

- - Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow

\

-/s' J . \

g 100.0 . ,/ '., '

g 200.0 N

. s E E N E

%s' '- $ ~

50.0 -

. 100.0 -

. I l \,

f ,

0.0 '

O.0 'I I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (Sec) Time (sec)

Level (inch-REF-SEP-SKRT) v Void Reac

- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - - - Scram Reactivity

- - - Feedwater Flow -- TotalReactivity S

f' , ..

~

2 g

t 100.0 os i.

0.0 E

E \ -.% e*

, D.*. . . . ,* \ '. .,.- #

, \

g i s ,

0.0 1- - - - - - - - - - - - - - - - -

I

- 1.0 -

\\

C \ 1

. \

\ .

I

-100.0 ' ' ' I j

-2.0 I '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 15 Plant Response to Load Reject w/o Bypass (EOC12-2000 mwd /MT to EOC12 with MSIVOOS and ICF)

Page 29

BRUNSWICK 2 24A5195

, Reload 11 Rev.O Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - - - Core Inlet Fkw 300.0

- --- Relief Valve Flow

--- Bypass Valve Flow t '\'y .s h

) * '

, \

,/ N g 100.0 .

g 200.0 -

5 '. % ,, E E '

- N %

C Y

50.0 '

, 100,0 -

-~~

I

/

/ \'

O.0 O.0 " l '

O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Level (inch-REF-SEP-SKRT)

- - - - - Vessel Steam Flow Void Rek 200.0 - ---

Turbine Steam Flow 1.0 - - -f- - Doppler

- Scram Reactivity Reactivity

--- Feedwater Flow -- TotalReactivity

- $m .

[i . .

E g

p 100.0 a

7. , g 0.0 , ,

I. ,,

'... M .....- E \ '

C g' .' '

3 %

N 0.0 1-- h. - - - - - - - - - - - - - - - - m] -1.0 I 'g g

i .

. \

\

\'

-100.0 ' '

-2.0 I I '

O.0 ?3 6.0 0.0 3.0 6.0 Tit,e (sec) Time (sec)

Figure 16 Plant Response to lbrbine Trip w/o Bypass (EOC12-2000 mwd /MT to EOCl2 with MSIVOOS and ICF)

Page 30

. __ ___ _ i

- .. - _ .=_- _ _ - . -.

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Mt. m Flux Vessel Press Rise (psi)

- Ave Eurface Heat Flux - - - - - Safety Valve Flow 150.0 - ---- Core plet Flow '

300.0 -

--- Relief Valve Flow

--- Bypass Valve Flow

_ _ _---_ s %, g ~. .

y 100.0 g, ,, 7 200.0 a s c. s e w a

~

'1~,~~,

50.0 - -

100.0 -

t I

' I # I 0.0 0.0 '

O.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (sec)

. - - Level (inch-REF-SEP-SKRT) Void Reachv

- - - - - Vessel Steam Flow - - - - Do ler ctivity 200.0 - --- Turbine Steam 1%w 1.0 -

- - - Scr R crivity I

--- Feedwater Flow - - - To I 'vity G

(, '....

g u 100.0 8 .

e --s %.,. Da -

-s .-

m

.s

.s s q..l..----

%. w . _ . . .

.s..s

, '., 3 x ..- ..

~

\

% e ,' ,' ~~-

.y a \p n_ ; .. '. _,.0 9

e f

O.

~ ~

\

l.

_ioo.o __

-2.0 - - - - I' '

O.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (sec)

Figure 17 P' ant Response to MSIV Closure (Flux Ecram) a Page 31

, BRUNSWICK 2 24A5195 Reload 11 Rev.O <

\

Appendix A Analysis Conditions l To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle. j i

l Table A-1 l

Analysis Value i Parameter ICF MELLL ICF and MSIVOOS FWTR and ICF Thennal power, MWt 2436.0 2436.0 2436.0 2436.0 Core flow, MitVhr 80.8 57.8 80.8 80.8

}

Reactor pressure, psia 1036.0 1030.5 1018.2 1036.0 l 1

Inlet enthalpy, BTU /lb 528.0 519.9 512.4 528.0 i Non-fuel power fraction 0.037 0.037 0.037 0.037 Steam flow analysis, Mlb/hr 10.48 10.45 8.79 10.48 ,

Dome pressure, psig 1005.0 1005.0 988.8 1020.0 Turbine pressure, psig 949.3 949.6 949.3 925.7 No. of Safety / Relief Valves 9 9 9 11 Relief mode lowest setpoint, psig 1116.0 1116.0 1116.0 1116.0 Recirculation pump power source on-sites on-sites on-sites on-sites Turbine control valve mode of operation Partial arc Partial arc Paraal arc Partial arc l

{

l 5 Boundi operation wuh oft-sae power source for ockmd hcensing everne for cyde 12.

I Page 32 J

. BRUNSWICK 2 24A5195 Reload 11 Rev.0 Appendix B Main Steamline isolation Valve Out of Service Reference B-1 pmvided a basis for operation of 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 this mode of operation in BSEP Unit 2 throughout Cycle 12, the MCPR limits presented in Section 11 of this report are bounding and should be applied when operating in the MSIVOOS mode at any time during the cycle.The peak steamline and peak vessel pressures for the limiting overpressurization event (MSIV clo- l sure with flux scram) were not calculated for the MSIVOOS mode of operation. In this mode of operation it is required that all S/RVs be operational versus the assumed 2 S/RVs OOS for the events evaluated during l

normal plant operatior.. Previous cycles analyses have shown that the MSIV closure with flux scram, eva- !

luated in the MSIVOOS mode, has resulted in the peak vessel pressure being reduced by more than 25 psi, I when compared to the same case evaluated with all (four) steamlines operational.

l Reference B-1. Main Steamline isolation Valve Out ofServicefor the Brunswick Steam Electric Plant, EAS-117-0987, GE Nuclear Energy, April 1988.

l 1

l l

l 1

1 l

l l

l Page 33

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Appendix C Decrease in Core Coolant Temperature Events The Loss of Feedwater Heater (LFWH) event and the HPCI inadvenent stan-up event are the only cold water injection A00s checked on a cycle-by-cycle basis. A Cycle 11 analysis showed a LFWH ACPR of0.13 and a Cycle 10 analysis showed a HPCI inadvenent stan-up ACPR of 0.15. There is no reason why these events l would be expected to be mom severe for Cycle 12.The results of the AOOs presented in Section 11 of this mpon s ficiently bound the expected results of the LFWH and HPCIinadvenent stan-up events, themfore i these events wem not analyzed for Cycle 12. l i

l l

Page 34

BRUNSWICK 2 24A5195 Reload 11 Rev.0 Appendix D Feedwater Temperature Reduction (FWTR)

Reference D-1 provides the basis for operation of the Brunswick Steam Electric Plant with FWTR. The MCPR limits presented in Section 11 of this report are bounding and should be applied when operating with FWTR Previous analysis has shown the FWCF event is most severe at ICF and FWTR.

Reference D-1. Feedwater Temperature Reduction with Maximum Extended Load Line Limit andincreased Core Flow for Brunswick Steam Electric Plant Units 1 and 2, NEDC-32457P, Revision 1, December 1995.

l i

Page 35 J

^

BRUNSWICK 2 24A5195 l Reload 11 Rev.0 Appendix E Maximum Extended Operating Domain i

Reference E-1 provided a basis for operation of the Brunswick Steam Electric Plant in the Maximum Ex-tended Operating Domain (MEOD). The reload licensing analysis performed for Cycle 12 and docrmi nted herein is consistent with and provide the cycle-specific update to the reference E-1 analysis. ApF_auon of the GEXI.cPLUS correlation to the reload fuel has been confirmed as requi . a .n reference E-1.The applica-bility of GE13 was addressed and found acceptable.

Reference E-1. Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P, GE Nuclear Energy (Proprietary), February 1989.

I Page 36

1

,o g .

ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT f

AFFIDAVIT FROM GENERAL ELECTRIC NUCLEAR ENERGY REGARDING WITHHOLDING FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.790

GENuclearEnergy l ca nunraww f 0 Bar1Rt WinwgM.hC 2MU I

Affidavit I, James F Klapproth, being duly swom, depose and state as follows:

(1) I am Manager, Product Defmition, General Electric Company ("GE") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be l withheld, and have been authorized to apply for its withholding. 1 (2) The information sought to be withheld is contained in the document Loss-of-Coolant Accident Analysis Reportfor Brunswick Steam Electric Plant Unit 2 Reload 11 Cycle 12, NEDC-31624P, Supplement 2, Revision 3, January 1996.

(3) In making this application for withholding of proprietary information of which it is the owner, GE relies upon the exemption from disclosure set forth in the Freedom ofInformation Act ("FOIA"), j 5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulations 10 '

CFR 9.17(a)(4), 2.790(a)(4), and 2.790(d)(1) 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 "trat secret," within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Enerev Project v. Nuclear Reculatory Commission,975F2d871 (DC Cir.1992), and Public Citizen Health Research Group v. FDA. 704F2dl280 (DC Cir.1983).

l (4) Some examples of categories of information which fit into the definition of proprietary 1 information are.

a. Information that discloses a process, method, or apparatus, including supporting data !

and analyses, where prevention of its use by General Electric's competitors without license from General Electric 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 General Electric, its customers, or its suppliers;

d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric; 5

c. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

Page!

I l

, l Affidtvit ,

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

(5) The information sought to be withheld is being submitted to NRC in confidence. The information is of a soit customarily held in confidence by GE, and is in fact so held. Its initial designation as proprietary infornetion, and the subsequent steps taken to prevent its unauthorized disclosure, are 1 as set forth in (6) and (7) following. The information sought to be withheld has, to the best of my l knowledge and belief, consistently been held in confidence by GE, 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 )

i provisions or proprietary agreements which provide for maintenance of the information in I confidence i'

(6) Initial approval of proprietary treatment of a document is made by the manager of the originatmg !

component, the person most likely to be acquainted with the value and sensitivity of the

information in relation to industry knowledge. Access to such hmaats within GE 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 GE are limited to regulatory bodies, customers, and potential

! customers, and their agents, suppliers, and licensees, and others with a legitimate need for the 1

information, and then only in accordance with appropriate regulatory provisions or proprietary agreements. ;

l (8) The information identified in paragraph (2) is classified as proprietary because it would provide <

other parties, including competitors, with information related to details of GE fuel designs, analysis results and potential commercial offerings which GE has developed at considerable expense. ;

The testing, development and approval of these fuel designs was achieved at a significant cost, on the order of several million dollars, to GE.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportunities.

The fuel design is part of GE'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 arid money by GE.

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.

Page 2

Affid: vit GE's competitive advantage will be lost ifits competitors are able to use the results of the GE 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 infonnation to GE would be lost if the information were disclosed to the public.

i Making such information available to competitors without their having been required to undertake J

! a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive j GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large l investinent in developing these very valuable analytical tools.

State of North Carolina ) 33',

County of New Hanover )

James F. Klapproth, being duly sworn, deposes and says:

That he has read the foregoing aflidavit and the matters stated therein are true and correct to the he t of his knowledge, infornution, and belief.

Executed at Wilmington, North Carolina, this Yday of30ww 1 tu .19$

0 c% ~ T~VAsg -

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James F. Klapproth : .- - -

General Electric Corapany f NOTARY .

., PUBLIC /j ig$;;g$p/

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Subscribed and sworn before me thisF day ofIla A # u . 19 J

No Public, State of North Carolina

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ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT l

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! AFFIDAVIT FROM GENERAL ELECTRIC NUCLEAR ENERGY l REGARDING WITHHOLDING FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.790 l l

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_ . _ _ _ _ _ _ _ . . _ _ . - ~ _ _ _ _. . . . . __. _- __

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GENuclearEnergy GeneralDaws Conqueny F. O. Bar?mt l%ngan NC 2NQ Affidavit l

I, James F. Klapproth, being duly sworn, depose and state as follows: I (1) I am Manager, Product Definition, General Electric Company ("GE") _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. l (2'; The information sought to be withheld is contained in the document Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis: Application to GE13 Fuel, NEDC-31624P, Supplement 3, Revision 0, January 1996.

(3) In making this application for withholding of proprietary information of which it is tim owner, GE l relies upon the exemption from disclosure set forth in the Freedom ofInforraation 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), 2.790(a)(4), and 2.790(d)(1) 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 FOLi Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatory Commiss. ion. 975F2d871 (DC Cir.1992), and Public Citizen Health Research Group v. FDA,704F2dl280 (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 General Electric's competitors without license from General Electric 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 General Electric, its customers, or its suppliers;

d. Information which reveals aspects of past, present, or future General Electric custonwr-funded development plans and programs, of potential commercial value to General Electric;

c. Information which discloses patentable subject matter for which it may be desirable to obtain patst protection.

Pagei

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

(5) The information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GE, 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 GE, 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 originatmg component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within GE 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, piaject 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 GE 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.

i (8) The information identified in paragraph (2) is classified as proprietary because it would provide other parties, including competitors, with information related to detailed results of analytical models, methods and processes, including computer codes, which GE has developed, requested NRC approval of, and applied to perform evaluations of the BWR. The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GE asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportunities.

The fuel design is part of GE'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 detennine 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 GE.

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.

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

Page 2

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< l Affidivit The value of this information to GE would be lost if the information were disclosed to the public. !

Making such information available to competitors without their hasing been required to undertake )

a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.

State of North Carolina ) 33,~

County of New Hanover )

James F. Klapproth, being duly sworn, deposes and says:

That he has read the foregoing afUdavit and the matters stned therein are true and correct to the best of his knowledge, information, and belief.

Executed at Wilmington, North Carolina, this Nday of dumvt A . 19h d

,,. o m e,,,,

/ $ * *e d w v# \- 4 .

James F. Klapproth I NOTARY *** 1 General Electric Compaig j 1

PUBLIC /g 5 bh[,R b Subscribed and sworn before me this 3Q*_ day ofbaua a n .19 a

pgh. L Notary Public, State of North Carolina !

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ML20101B630

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