ML20029A315

Rev 0 to 23A6541, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 1 Reload,Cycle 8.

ML20029A315
Person / Time
Site:	Brunswick
Issue date:	01/31/1991
From:	Charnley J, Noble L GENERAL ELECTRIC CO.
To:
Shared Package
ML19310E615	List: ML20029A314 ML20029A315
References
23A6541, 23A6541-R, 23A6541-R00, NUDOCS 9102150238
Download: ML20029A315 (23)

Text

_ ___. _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _

b O

GE Nuclear Energy 23A6541 3 Revision 0 Class I january 1991 O

i 23A6541, Rev. O Supplemental Reload Licensing Report

1. for Brunswick Steam Electric Plant Unit 1 Reload 7 Cycle 8 e

O e

• Approved b .

, Approved by: 4 .

6 A anager L D. Noble, Ma ager M nsin Reload Nuclear Engineering O

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'O Brunswick I mi  !

Reland 7 w-Important Notice Regarding Contents of This Report 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)

O for CP&L's use in defining operating limits for the Brunswick Steam Electric Plant Unit 1. The 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.

O 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 1 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 -

'O for which it is intended, is rat 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 j

-O assume any responsibillty for liability or damage of any kind which may result from such use of such information.- i i

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O Ilrunswick 1 :wai Reload 9 py o Acknowledgment

O The engineering and reload licensing analyses which form the technical basis of this Supple-mental Reload Licensing Report were performed by S. C. Moen of the Fuel Engineering Section.

.O The Supplemental Relead Licensing Report was prepared by P. A. Lambert of Fuel Licensing.

This report was verified by both Fuel Engineering and Fuel Licensing.

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1. Plant unique items' 0

Appendix A: Analyses Values Appendix B: Maximum Extended Operating Domain Appendix C: Main Stearn isolation Valve Out of Service

. Relon Fuel Bundles O

Juel b e_ Cicle12inded hmittt irradiated 0- Bl?8DRB299 (BP8XSR) 5 40 BP8DRB299 (BP8X8R) 6 176 BD339A (OE8X8EB)- 7 60 BD313B (OE8X8EB) ' 7 124 0

New t OE10 P8HXB324120Z 70M 150 T(OE8X8NB 3) 8 52 O_ GE10 P811XB322110Z.70M.150 T(OE8X8NB 3) 8 108 Total 560

3. . Reference Core leading Pattern Nominal previous cycle core average exposure at end of cycle: 22,900 mwd /MT Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations: 22,900 mwd /MT O' Assumed reload cycle core average exposure at beginning of cycle: 13,757 mwd /MT Assumed reload cycle core average exposure at end of cycle: 24,463 mwd /MT

. Core loading pattern: Figure 1 0:

• The basis for this report is General Electric Standard Application for Reactor Fuel.

O -NEDE.24011.P.A 9, September 1988; and the U. S. Supplement, NEDE 24011 P A 9 US,

. September 1988.

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) llrunswick I P.eload 7 am Rev o

4. Cgculated Core Effecilse Stultiplication and Control System Worth No Volds, 20 C

)

Beginning of Cycle, K Uncontrolled 1.100 Fully controlled 0.955 Strongest control rod out 0.983 R, h1aximum increase in cold core reactivity with exposure into cycle, AK 0.004 D

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

(px.m) (20*C. Xenon Free)

D 600 0.037

6. Reload Unique GETAll Anticipated Operational Occurrence (AOO) Analysis initial Condition Parameters D Exposure: HOC 8 to EOC8 2205 mwd /MT Fuel Peaking Factors Bundle Power Bundle Flow initial Design Leal Radial Mial R Factor ( M Wt) . (1.000 lb/hr) MCPR GE8x8NB 3 1.20 1.65 1.40 1.000 6.995 108.0 1.25 p GE8x8EB 1.20 1.56 1.40 1.051 6.632 116.4 1.24 BP8x8R 1.20 1.55 1.40 1.051 6.601 113.9 1.24 Exposure: EOC8 2205 mwd /MT to EOC8 Fuel Peakinc Factors Bundle Power Bundle Flow initial D Design Lsal Radial Mial R Factor (MWt) (1.000 lb/hr) MCPR GE8x8NB 3 1.20 1.55 1.40 1.000 6.573 111.2 1.34 GE8x8EB 1.20 1.47 1.40 1.051 6.247 119.3 1.33 BP8x8R 1.20 1.46 1.40 1.051 6.208 116.9 1.33 D

Exposure: BOC8 to EOC8 with main steam isolation valve out of senice (MSIVOOS)

Fuel Peaking Facters Bundle Power Bundle Flow Initial Design . Local Radial Mini R Factor (MWt) (1.000 lb/hr) MCPR p GE8x8NB 3 1.20 1.56 1.40 1.000 6.611 110.9 1.33 GE8x8EB 1.20 1.48 1.40 1.051 6.274 119.1 1.32 BP8x8R 1.20 1.47 1.40 1.051 6.256 116.5 1.32 l' age 5

P'

) IlftltlSWlCk l 2WM

[ Reload 7 _

Rev o i

7. Selected Margin Imr...,vement Options I Recirculation pump trip: No Rod withdrawallimiter: No Thermal power monitor: Yes Improved scram time: No

> Exposure dependent limits: Yes Exposure points analyzed: 2 (EOC8 2205 htWd/ hit and EOC8)

8. Operating Flexlh811ty Options

> Single loop operation: Yes Load line limit: Yes Extended load line limit: Yes hinximum extended load line limit: Yes

> Increased core flow: Yes (throughout the cycle)

Flow point analyzed: 105 %

Feedwater temperature reduction: No ARTS Program: Yes

> hinximum extended operating domain': Yes Equipment out of senice": Yes (htSIVOOS)

9. Core. wide AOO Analysis Results

> hiethods ur.ed: GEh11NI ano GEXL PLUS Uncorrected ACPR Flux O/A Event (4 NBR) (% NBR) GE8x8NB 3 GE8x8EB DP8x8R Eiguts

> Exposure range: 110C8 to EOC8 Inadvertent 122 119 0.18 0.17 0.17 9 activation of HPCI Exposure range: 110C8 to EOC8 2205 htWd/ sit Load rejection 445 120 0.17 0.17 0.17 2 without bypass Feedwater 260 115 0.12 0.11 0.11 3 controller

> failure

• See Appendix II. " See Appendix C.

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) Ilrunswick I muu Reload 7 , Rev o l

9. Core wide AOO Analysis Results (enntinued)

) Uncorrected AG)R Flux O/A

,, Event (9 NBR) (Ec b'l}E) QEh$b'l},3 OE8x8 Ell BP8x8R Eigns Exposure range: EOC8 2205 mwd /MT to EOC8

.)

Load rejection 663 128 0.27 0.26 0.25 4 without bypass Feedwater 506 125 0 21 0.22 0 22 5 controller

) failure Exposure riinge: HOC 8 to EOC8 wIth MSIVOOS Load rejection 579 126 0.26 0.25 0.25 6

) without bypass Feedwater 392 122 0.21 0.21 0.20 7 controller failure

)

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The rod withdrawal error event in the maximum extended operating domain was originally

.) analyzed in General Electric BWR Licensiag Report, Maximum Extended Operating Domain Anabsu for Bnuuwick 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, rage 7

O lirunswick 1 :wm Keland 7 Ret c

11. Cycle MCPR Values O Safety limit: 1.07 Single loop operation safety limit: 1.08' O Non. pressurization events Esposure range: HOC 8 to EOC8 OII8x8NB 3 GII8x5tEll DP8x8R o Fuelloading error 1.27 1.25 -

IIPCI 1.25 1.24 1.24 Pressurization events Ontion A Option B GE8dNB.3 GE8sSEB BP8sSR GE8dNU 3 GE8 DEB 11I148 Exposure range: HOC 8 to EOC8 2205 mwd /MT O

Load rejection without 1.34 1.34 1.34 1.27 1.27 1.27 bypass Feedwater controller 1.24 1.24 1.24 1.22 1.22 1.22 g failure Exposuit range: EOC8 2205 mwd /MT to EOC8 Load rejection without 139 138 138 1.35 134 134 bypass O Feedwater controller 133 133 133 130 1.30 130 failure Exposure range: HOC 8 to EOC8 with MSIVOOS (see Appendix C) g ._ Load rejection without 1.39 138 137 135 134 1.34 bypass Feedwater controller 133 132 1.32 130 1.29 1.29 failure

' Operating limit MCPR for two loop operation (TLO) bounds the operating limit MCPR for single O loop operation (SLO): ACPR(SLO) <(ACPR(TLO) ,01), therefore, operating limit MCPR need not be changed for SLO.

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,) lirunswick I zwm Rtiged 7 , , Rn0

12. Overpressurization Analysis Summary f Event Pa (p.s;)

Pv (mk) Elant ResoonK MSlY elosure 1260 1289 Figure 8 (flux scram)

13. Imading Error Results Veriable water gap misoriented bundle analysis: Yes Event LCEB Misoriented fuel bundle 0.20'

14. Control Rod Drop Analysis Results Brunswick Steam Electric Plant Unit 1 is a gioup notch plant operating in the banked position withdrawal sequence; therefore, the control rod drop accident analysis is not required NRC approvalis documented in NEDE 24011 P A 9 US, September 1988.

15. Stability Analysis Results OE 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 I to NRC Bulletin No. 88 07 Supplement 1 are applicable to Brunswick 1 Reload 7/ Cycle 8.

' ACPR penalty of 0.02 for the tilted misoriented bundle has been applied.

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) Ilrunswick 1 nm l Etioad 7 nn o i

16. less of coolant Accident Results

> LOCA method used: SAFER /GESTR LOCA The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of Brunswick Steam Electric Plant Units I and 2 SAFER /GESTR LOCA Loss of Coolant Accident Analysis P NEDC 31624P, Revision 2. February 1990, conservatively bounds the LOCA analysis of th-GESx8NB 3 fuel types. This analysis yielded a licensing basis peak clad temperature of 1533*F, a peak local oxidation fraction of <0.307c, and a core wide metal water reaction of 0.046 cc. The most limiting and the least limiting MAPLilGRs for the GE8x8NH 3 fuel

> designs are as follows:

Bundle Type: GE10 P811XB324120Z 70M 150 T (GE8x8NB 3)

Average Plannr Exoosure M APlilG R (KW/ft)

Kuhl/IT) (GWd/MT) Most Limiting Least Limiting 0.0 0.0 10.75 iL79 0.2 0.2 10.78 i1.85 1.0 1.I 10.87 11.94 2.0 2.2 11.07 12.08 3.0 3.3 11.32 12.23 4.0 4.4 11.62 12.39 5.0 5.5 11.83 12.56 6.0 6.6 12.02 12.72 7.0 7.7 12.22 12.91 8.0 8.8 12.44 13.13 9.0 9.9 12.70 13.12 10.0 11.0 12.96 13.I9 12.5 13.8 13.17 13.28 15.0 16.5 12.93 12.95 20.0 22.0 12.27 12.42 25.0 27.6 11.62 11.89 35.0 38.6 10.27 10.49 45.0 49.6 8.78 9.06 50.66 55.84 5.94 6.26 51.64 56.92 -

5.78 Page 10

mm m mi -

p llrunswick I mai Reload 7 Rev 0

16. Lass-of coolant Accident Results (cantinued)

O Bundle Type: GE10 P811XB322 llOZ 70M 150 T (GE8x8NB 3)

Average Planar Emosure MAPLllOR (KW/ft1

1. (OWd/ST) . (OWd/MTi Most Limiting Least Limiting 0.0 0.0 10.S4 11.92 0.2 0.2 10.88 11.98 1.0 1.1 10.95 12.04 g 2.0 2.2 1'.08 12.14 3.0 3.3 11.21 12.25 4.0 4.4 11.35 12.39 5.0 5.5 )1.50 12.53 g 6.0 6.6 11.67 12.68 7.0 7.7 11.92 12.74 8.0 8.8 12.26 12.88 9.0 9.9 12.61 13.11 g 10.0 11.0 12.95 13.23 12.5 13.8 13.12 13.27 15.0 16.5 12.89 12.95 20.0 22.0 12.29 12.38 g 25.0 27.6 11.67 11.85 35.0 38.6 10.26 10.47 45.0 49.6 8.78 9.04 50.86 56.06 5.87 6.23 51.71 57.00 5.82 3 --

O 3

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Brunscick 1 mai Reload 7 Rev o 52 TsD TE T E EE TsD 50 QEG00f00EG88 7 T 48 --888J08080050E08E58 Y T 7 7 46 Q E E D0 00 0 06% 006000f800 7

M M M M M M M M M 8+s M

eMMMMMMMMMMMe it: M E M M s+s M M M M M M M M l': M E M M M M M M M M M M M 28-800E 7 T EJ 0E EE 0_A E EE EE EE BO SE B0 05

, 26- E 0 0 E E'% C % E% 0'@ 6 % d b G % C b fE G b G %

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IIIIIIIIII 1 3 5 7 911131517192123252729313335373941'4345474951 FUEL TYPE D

A = BP80RB299 (Cycle 5) D = BD323B B = BP80RB299 (Cycle 6) E = GE10-P8HXB322-11GZ-70M-150-T C = B0339A F = GE10-P8HXB324 12GZ 70M-150-T m

Figure 1 Reference Core Imading Pattern I

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Figure 2 Plant Response to Generator IAnd Rejection Without Bypass O (BOC8 to EOC8 2205 mwd /MT)

Page 13

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Page16 4

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Figure 6 Plant Response to Generator Load Rejection Without Bypass D with MSIVOOS (BOC8 to EOC8)

Page 17 9

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fig (st:oes) tig (ucoes) o Figure 7 Plant Response to Feedwater Contmiler Failure O with MSIVOOS (HOC 8 to EOC8) r., a 1

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1. Figure 9 Plant Paponse inadvertent Activation of HPCI

D Ilninswick I zw.m Edond 7 i'n o Appendix A O

Analyses Values G To reflect actual plant parameters accurately, the values shown in Table A 1 were used this qcle.

Table A 1 4

Parameter Analysis Value Thermal power, MWt 2436 Dome pressure, psig 1006 O Steam flow, Mlb/hr 10.48 Turbine pressure, psig 950 Core now, Mlb/hr 80.85 Reactor pressure, psia 1036 O Inlet enthalpy, BTU /lb 528 Non fuelpower fraction 0.038 No.of Safety / Relief Valves 9' O L w setp int, psig 1116 Recire pump power source" On site O

O 9

• Cycle 8 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 8.

Page 21 0

l IlrunSWick I mW t Relond 7 Rn O Appendix 11

)

Maximum Extended Operating Domain O Reference B 1 provided a basis for operation of the Brunswick Steam Electric Plant in the hintimum Extended Operating Domain (htEOD). He reload licensing analyses performed for Cycle 8 and documented herein are consistent with and provide the cycle specific update to the reference B 1 analyris. Application of the GEXL PLUS correlation to the reload fuel has been D confirmed as required by Reference B 1.

Reference B1 Afaximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant, NEDC 31654P, GE Nuclear Energy (Proprietary), February 1989.

D D

8 9

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0- Brur,swick 1 zw.m -l Reload 7 Rev 0 LAppendix C  ;

O!

Main Steumline Isolation Valve Out of Service l Oj Reference C 1 provided a hasis for operation of Brunswick Steam Electric Plant (BSEP) with V 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 8, the EOC8 2205 mwd /MT to SOCS MCPR limits presented in Section 11 of the body of this report lO: - are bounding and should be applied when operating in the MSIVOOS mode at any time during the 7

cycle. The peak steam'line and peak vessel pressures for the limiting overpressurkunon eveat (MSIV closure with flux scram) in the MclVOOS mode are 1230 psig and 1263 psig, respectively, l

!O L Reference .

' C 1. blain 'Steamline Isolation l'alve Out of Service for Brunswick Steam Electric Plant.

EAS 117 0987, GE Nuclear Energy, April 1988.

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