ML20058P875
| ML20058P875 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/31/1993 |
| From: | Klapproth J, Kunz C GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19311B274 | List: |
| References | |
| 23A7211, 23A7211-R, 23A7211-R00, NUDOCS 9312270314 | |
| Download: ML20058P875 (23) | |
Text
C GENuclearEnergy 175 Cunner Annue SanJose, CA 95725
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23A7211
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Revision 0 i
ClassI July 1993 l
l 23A7211, Rev. O Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 8 Cycle 9 t
Approved by:
'F Appmved by:
J. F. Klapproth, fanager C. L Kunz, Manager Fuel Licensing Reload Nuclear Engineering l
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i 9312270314 931217 t
r PDR ADOCK 05000325 FDR 1
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Brunswick 1 23AE1 Reload 8 Rev.0
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Important Notice Regarding Contents of This Report
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Please Read Carefully This report was prepared by General Electric Company (GE) solely for Carolina Power and Light Company (CP&L) for CP&L's use with the U. S. Nuclear Regulatory Commission (USNRC)
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for CP&L's use in defining operating limits for the Brunswick Steam Electric Plant Unit 1. De in-formation contained in this report is believed by GE to be an accurate and true representation of the facts known, obtained by or provided to GE at the time this report was prepared.
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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 Brunswick Steam Electric Plant Unit I and nothing contained in this document shall be construed as changing said contract.
The use of this information except as defined by said contract, or for any purpose other than that
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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 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
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assume any responsibility for liability or damage of any kind which may result from such use of such information.
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Page 2
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Brunswick 1 nAmi Reload 8 Rev.0 j
Acknowledgment l
The engineering and reload licensing analyses which form the technical basis of this Supple-mental Reload Licensing Report were performed by F. T. Bolger of the Fuel Engineering Section.
l The Supplemental Reload Licensing Report was prepared by P. A. Lambert of Fuel Licensing.
j This report was verified by Fuel Engineering and J. L Rash of Fuel Licensing.
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i Brunswick 1 uAmi Reload 8 Rev 0 The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-10, February 1991; and the U. S. Supplement, NEDE-24011-P-A.10-US, March 1991.
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Plant-unique Items Appendix A: Analyses Values Appendix B: Maximum Extended Operating Domain Appendix C: Main Steamline Isolation Valve Out of Service Appendix D: Reload Unique Anticipated Operational Occurrence (AOO) Analysis Input Appendix E: Feedwater Controller Failure Analysis 2.
Reload Fuel Bundles Fuel Tvoe Cvele Imaded Number Irradiated
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BP8DRB299 (BP8X8R) 6 92 G E8B-P8DOB339-11 GZ-80M-4 WR-150-T (BD339A) (G E8x8EB) 7 60 GE8B-P8DOB323-10GZ-80M-4 WR-150-T (BD323B) (GE8x8EB) 7 124
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GE10-P8HXB324-12GZ-70M-150-T (GE8x8NB-3) 8 52 GE10-P8HXB322-11GZ-70M-150-T (GE8x8NB-3) 8 108 New
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GE10-P8HXB322-11GZ-70M-150-T (GE8x8NB-3) 9 56 OE10-P8HXB320-110Z-100M-150-T (GE8x8NB-3) 9
_.6.3 Total 560 3.
Reference Core Leading Pattern Nominal previous cycle core average exposure at end of cycle:
20,057 22,109 Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations:
j 20,057 22,109 Assumed reload cycle core average exposure at beginning of cycle:
13,722 15,126 Assumed reload cycle core average exposure at end of cycle:
23,522 25,929
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Core loading pattern:
Figure 1 Page 4
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l Brunswick 1 2mmt Reload 8 Rev.0 4.
Calculated Core Effective Multiplication and Control System Worth - No Voids, l
200C l
l Beginning of Cycle, K,n.
Uncontrolled 1.106 Fully controlled 0.%1 Strongest control rod out 0.989 R, Maximum increase in cold core reactivity with exposure into cycle, AK 0.001
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Standby Liquid Control System Shutdown Capability Boron Shutdown Margin (AK) i (pyn1)
(20*C. Xenon Free)
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600 0.031 l
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Releid Unique GETAB Anticipated Operational Occurance (AOO) Analysis Initial Condinon Parameters i
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Exposure:
BOC9 to EOC9-2866 mwd /MT Fuel Peakinc Factors Bundle Power Bundle Flow Initial Design Local Radial Mial E-Ersio.t (MWt)
(1.000 lb/hr)
MCPR GE8x8NB-3 1.20 1.63 1.40 1.000 6.938 109.4 1.26-
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GE8x8EB/
1.20 1.55 1.40 1.051 6.577' 117.2 1.25 i
BP8x8R Exposure:
EOC9-2866 mwd /MT to EOC9 l
Fuel Peakinc Factors Bundle Power Bundle Flow Initial Design Local Radial Apj R-Factor (MWt) '
(1.000 lb/hr)
MCPR I
i GE8x8NB-3 1.20 1.58 1.40 1.000 6.690 111.2 132 GE8x8EB/
1.20 1.50 1.40 1.051-6352 118.9 130 BP8x8R Exposure:
BOC9 to EOC9 with Main Steam Isolation Valve Out of Service (MSIVOOS) '
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Fuel Peakinc Factors Bundle Power Bundle Flow Initial Design Local Radial &lal R-Factor (MWt)
(1.000 lb/hr)
MCPR GE8x8NB-3 1.20 1.58 1.40 1.000 6.712 111.1 131 GE8x8EB/
1.20 1.50 1.40 1.051 6375 118.7 130
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BP8x8R r
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1 Pap 5 i
Brunswick 1 Reload 8 zumt Rev.0 7.
Selected Margin Improvement Options Recirculation pump trip:
No Rod withdrawallimiter:
No Thermal power monitor:
Yes Improved scram time:
No Exposure dependent limits:
Yes Exposure points analyzed:
2 (EOC9-2866 mwd /MT and EOC9) 8.
Operating Flexibility Options Single-loop operation:
Yes i
loadlinc limit:
Yes Extended load linelimit:
Yes Maximum extendedload linelimit:
Yes Increased core flow throughout the cycle:
Yes Increased core flow at end of cycle:
Yes Flow point analyzed:
105%
Feedwater temperature reduction throughout the cycle:
No l
Final feedwater temperature reduction:
No Temperature reduction AT:
N/A ARTS Program:
Yes Maximum extended operating domain:
Yes(1)
ADS valve out of service:
I Yes (2 valves)
Srfen/ relief valve out of service:
Yes Main steam isolation valve out of service:
Yes(2)
Turbine bypass out of service:
No EOC Recirculation pump trip out of service:
No i
1 See Appendix B.
( See Appendix C.
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i Brunswick 1 2mmi Reload 8 Rev.0 l
9.
Core-wide AOO Analysis Results i
i Methods used: GEMINI and GEXL-PLUS i
Uncorrected ACPR Flux O/A Event
(% NBR)
(% NBR)
GE8x8NB-3 GE8x8EB\\BP8x8R Figure Exposure range: BOC9 to EOC9 i
Inadvertent 119 119 0.16 0.15 2
l activation ofHPCI i
Exposuit range: BOC9 to EOC9-2866 mwd /MT Load rejection 480 121 0.19 0.18 3
without bypass i
Exposure range: EOC9-2866 mwd /MT to EOC9
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l Load rejection 661 126 0.25 0.23 4
without bypass Exposure range: BOC9 to EOC9 with MSIVOOS
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Load rejection 556 125 0.24 0.23 5
without bypass For cold water injection event inputs, see Appendix D; for feedwater controller failure analysis, see Appendix E.
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Imal Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary 10.
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The rod withdrawal error event in the maximum extended operating domain was originally
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analyzed in General Electric BWR Licensing Report, Maximum Ertended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P, dated February 1989.
The MCPR limit for rod withdrawal error is bounded by the operating 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.
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Page 7
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~.... -,, - -... -, -
Brunswick 1 zumi Reload 8 Rev.0
- 11. Cycle MCPR Values I
Safetylimit: 1.07 Single loop operation safetylimit: 1.08(3)
Non-oressurization events Exposure range: BOC9 to EOC9 GE8x8NB-3 GE8x8EB/BP8x8R l
Fuelloading error:
GE10-P8HXB324-12GZ-70M-150-T 131 GE10-P8HXB322-11GZ-70M-150-T/
1.20 GE10-P8HXB320-11GZ-100M-150-T IIPCI 1.23 1.22
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Pressurization events Ontion A Ontion B GE8dNB-3 GE8 DEB /BP8x8R GE8x8NB-3 GERxREB/BP8x8R Exposure range: BOC9 to EOC9-2866 mwd /MT Imad rejection without 136 135 1.29 1.28 1
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hpass Exposure range: EOC9-2866 mwd /MT to EOC9 Load rejection without 137 136 133 132 Dpass Exposure range: BOC9 to EOC9 with MSIVOOS(2)
Load rejection without 137 135 133 131 bypass
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(*) Brunswick Steam Elec:ric Plant Units 1 and 2 Single Loop Operation NEDC 31776P D ecember 1989, Opemting limit MCPRfor two loop opemtion (TLO) bounds the opemting limit MCPRforsingle loop opemtion (SLO): DCPR(SLO) <(DCPR(TLO).01), therefore, opemtinglimit MCPR need not be
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bygedforSLO.
See Appendix C.
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Brunswick 1 2uazu Reload 8 Rn0 l
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- 12. Overpressurization Analysis Summary Psi Pv Event (giigl
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Plant Resoonse MSIV closure 1261 1289 Figure 6 l
(flux scram)
- 13. Imading Ertur Results Variable water gap misoriented bundle analysis: Yer i
Event ACPR l
Misoriented fuel hundle:
l GE10-P8HXB324-12GZ-70M-150-T 0.240)
GE10-P8HXB32211GZ-70M-150-T/
0.13 )
0 GE10-P8HXB320-11GZ-100M-150-T
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- 14. Control Rod Drop Analysis Results Brunswick Steam Electric Plant Unit 1 is a group notch plant operating in the banked position withdrawal sequence; therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-24011 P-A-10-US, March 1991.
- 15. Stability Analysis Results
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GE SIL-380 recommendations and GE interim corrective actions have been included in the Brunswick Steam Electric Plant Unit 1 operating procedures. Regions of restricted operation defined in Attachment 1 to NRC Bulletin No. 88-07 Supplement I are applicable
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to Brunswick 1 Rebad 8 Cycle 9.
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U)ACPR penalty of 0.02 for the tilted misoriented bundle has been applied.
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Brunswick 1 naml Reload 8 Rev.0 16, Loss-ofcoolant Accident Results LOCA method used: SAFER /GESTR LOCA l
The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of Bnmswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis NEDC-31624P, Revision 2, July 1990, conservatively bounds the LOCA analysis of the GE8x8NB-3 fuel types. This analysis yielded a licensing basis peak clad temperature of 1533*F, a peak local oxidation fraction of <030%, and a core-wide metal-water reaction of l
0.046%. "Ihe most limiting and the least limiting MAPLHGRs for the new GE8x8NB-3 fuel design is as follows:
t Bundle Type: GE10-P8HXB320-11GZ-100M-150-T (GE8x8NB-3)
Averace Planar Err >osure MAPLHGR (KW/ft)
(GWd/ST)
(GWd/MT)
Most Limiting Least Limiting 0.0 0.0 10.81 11.71 0.2 0.2 10.87 11.74 1.0 1.1 10.97 11.82 2.0 2.2 11.10 11.93 3.0 33 11.24 12.05 4.0 4.4 1139 12.17 5.0 5.5 11.53 1230 6.0 6.6 11.68 12.44 7.0 7.7 11.84 12.57 8.0 8.8 12.00 12.72 9.0 9.9 12.16 12.86 10.0 11.0 1233 13.00 12.5 13.8 12.52 13.19 15.0 16.5 12.40 12.92 20.0 22.0 11.93 12.28 25.0 27.6 11.44 11.66 35.0 38.6 10.26 10.26 I
45.0 49.6 8.68 8.77 50.49 55.66 5.91 6.05 50.86 56.06 5.87 Page 10 l
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FUEL TYPE D-G 0PH
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Figure 1 Reference Core Imading Pattern Page 11
Brunswick I mmi Reload 8
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Figure 2 Plant Response Inadvertent Activation of HPCI
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(BOC9 to EOC9)
Page 12
Brunswick I man i
Reload 8 g,o
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!$; kN I!n!kt I'!k $NF$N utal FLUr tt m: ;m
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Figure 3 Plant Response to Generator Imad Rejection Without Bypass
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(BOC9 to EOC9 2866 mwd /MT) i Page 13
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Brunswick 1 nann i
Reload 8 Rev.0 l
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Figure 4 Plant Response to Generator IAad Rejection Without Bypass
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(EOC9 2866 mwd /MT to EOC9) l J
Page 14
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Brunswick I us2n Reload 8 Red was-imag we>
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fear (sa mes) fig (scoes) t i
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Figure 5 Plant Response to Generator IAad Rejection Without Bypass
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with MSIVOOS (BOC9 to EOC9) t l
Page 15
Brunswick I my,,
Reload 8 g, g h
N Suns 6 7 Flux
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ist (stimes) 7 E (stcmes) 1 i
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Figure 6 Plant Response to MSIV Closure, Flux Scram Page 16
l Brunswick 1 2nmi Reload 8 Rev.0 1
Appendix A Analyses Values
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To reflect actual plant parameters accurately, the values shown in Table A-1 were used for the base analysis this cycle.
Table A-1 Parameter Analysis Value
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Thermal power, MWt 2436 Dome pressure, psig 1006 (1020 used for MSIVOOS)
Steam flow, Mlb/hr 10.48 Turbine pressure, psig 950
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Core flow, Mlb/hr 80.850)
Reactor pressure, psia 1036 Inlet enthalpy, BTU /lb 528 Non-fuel power fraction 0.038
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No. of Safety / Relief Valves 9(2)
Low setpoint, psig 1116
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Recirc pump power so~ rce On-site (3) u Turbine control valves Full are(4) 1
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(2)At increased (105%) core flow.
(3} Cycle 9 analyses performed assuming 2 S/RVs out of service except for the MSIVOOS analysis.
Bounds operation with off-site power source for reload licensing events for Cycle 9.
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( ) Bounds operation with partial are turbine control valves and results in generator load rejection without bypass bounding the turbine trip without bypass event.
Page 17
Brunswick 1 2 ann Reload 8 Rev.0 Appendix B Maximum Extended Operating Domain Reference B-1 provided a basis for operation of the Brunswick Steam Electric Plant in the Maximum Extended Operating Domain (MEOD). He reload licensing analyses performed for Cycle 9 and documented herein are consistent with and provide the cycle-specific update to the reference B-1 analysis Application of the GEXL-PLUS correlation to the reload fuel has been confirmed as required by Reference B-1.
Reference I
B-1 Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant, NEDC-31654P, GE Nuclear Energy (Proprietary), February 1989.
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l Brunswick I mnn Reload 8 Rev.0 Appendix C Main Steamline Isolation Valve Out of Service Reference C-1 provided 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 1 throughout Cycle 9, the.
EOC9-2866 mwd /MT to EOC9 MCPR limits presented in Section 11 of the body of this report 3
are bounding and should be applied when operating in the MSIVOOS mode at any time during the cycle. 'Ihe peak steam line and peak vessel pressures for the limiting overpressurization event (MSIV closure with flux scram) in the MSIVOOS mode are 1222 psig and 1257 psig, respectively.
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Reference C-1. Main Steamline Isolation Valve Out of Service for Brunswick Steam Electric Plant, EAS-117-0987, GE Nuclear Energy, April 1988.
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Page 19
Brunswick 1 zumi Reload 8 Rev.0 Appendix D Reload Unique Anticipated Operational Occurrence (AOO) Analysis Input Inadvertent Activation of HPCI Event BOC9 Void fraction, %
49.03 l
Average fuel temperature, *F 1091 Void coefficient N/AU), /% Rg
-10.17/-12.71 Doppler coefficient N/AO), /*F
-0.205/-0.195 Scram worth N/AU) $
--(2) 1 EOC9 Void fraction, %
49.03 Average fuel temperature 'F 1091 V,id coefficient N/AO) p/% Rg
-12.02/-15.03 Dopp er coefficient N/AO), /*F
-0.243/-0.231 i
Scram w 'rth N/AO) $
-(2) i
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U)N = Nuclear input data; A = Used in transient analysis.
( ) Generic exposure-independent values are used in General Electric StandardApplicatio 1
or Reactor Fuel, NEDE-24011 P-A-10, February 1991.
Page 20 h
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Brunswick 1 mnu Reload 8
%o Appendix E Feedwater Controller Failure Analysis The Feedwater Controller Failure analysis (FWCF) (maximum demand) AOO is an increase
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in coolant inventory event normally checked on a cycle-by-cycle basis to determine if this AOO c >.dd potentially alter the cycle MCPR operating limit.
i This analysis was run for Cycle 8 and provided resultant Option B ACPR values of 0.23. The
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limiting AOO for Cycle 8 was load rejection without bypass with Option B ACPR of 0.28. The bounding nature of the load rejection without bypass relative to the feedwater controller fail:.re was confirmed by comparison of the ODYN pressurization transients for these events for Cycle 9.
Therefore, this AOO will not be limiting for Cycle 9 and the ACPR was not determined.
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