ML20211N424

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Rev 1 to 24A5412, Suppl Reload Licensing Rept for BSEP Unit 2 Reload 12 Cycle 13
ML20211N424
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 10/31/1997
From: Hetzel W, Watford G
GENERAL ELECTRIC CO.
To:
Shared Package
ML20046D886 List:
References
24A5412, 24A5412-R01, 24A5412-R1, NUDOCS 9710160129
Download: ML20211N424 (24)
v • d • e


Text

. - . . .- . - . . .

GE Nuclear Energy 24A5412 Revision 1 Class I October 1997 4

24AS412, Rev.1 Supplemental Reload Licensing Report for Hrunswick S. am Electric Plant Unit 2 i

Reloa312 Cycle 13

~/ /. z/

Approved M'/ Approved

[c G. A. Watf '

, Manager W.H. Hetzel Nuclear Fuel Engineering Fuel Project Manager

' [kO$o0$k-0 $4 P

BRUNSWICK 2 24AS412 Reloaa 12 Rev.1 important Notice Regarding Contents of This Repor:

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 in defining operating limits for the Brunswick 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 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 i

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.

Page 2

3RUNSW1CK 2 24AS412 -

Reload 12 Rev.I ;

Acknowledgement 5

- The engineering and reload licensing analyses, which fonn the technical basis of this Supplemental Reload Licensing Report, were perfonned by 0.M. Baka, HJ. Pearson and H.M. Schrum. The Supplemental Reload Licensing Report was prepared by G.M. Baka. This document has been verified by M.E. Harding.

b Y .

Page 3

BRUNSWICK 2 -

~

24AS412 Reload 12 Rev.1 The basis for this report is General Electric Standard Applicationfor Reactor Fuel. NEDE-2401 l-P-A-l 3, August 1996; and the U.S. Supplement, NEDE-240ll-P-A-13-US. August 1996.

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 Appendix D: Feedwater Temperature Reduction (FWTR)

Appendix E: Maximum Extended Operating Domain (MEOD)

. 2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradi Ad:

G E 10-P8 HXB 329-120Zl-100M-150-T (G E8x 8NB-3) 10 24 GE10-P8HXB322-11 GZ- 70M-150-T (GE8x8NB-3) 11 8 GE10-P8HXB320-11GZ 100M-150-T(GE8x8NB-3) 11 32 GE lo-P8HXB324-120Z-70M-150-T (GE8x8NB-3)  !! _ 112 G E 13-P9DTB 363-i l GZ l-100T-146-T (G E 13) 12 64 GE13-P9DTB363-11 GZ-100T.-146-T (GE13) 12 136 Nrm G E 13-P9 DTB 393-4G 6.0/9G5.0- 100T-146-T (G E 13) 13 104 GE 13-P9DTB 395-12G5.0-100T-146-T (GE 13) 13 80 Total 560

3. Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle: 27753 mwd /MT

( 25177 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 27381 mwd /MT from cold shutdown considerations: ( 24840 mwd /ST)

Assumed reload cycle core average exposure at beginning of 15361 mwd /MT cycle: ( 13935 mwd /ST)

Assumed reload cycle core average exposure at end of cycle: 28148 mwd /MT

( 25535 mwd /ST)

Reference core loading pattem: - Figure 1 l Page 4

BRUNSWICK 2

~

24AS412

}<eloau 12 Rev.1

4. Calculated Core Effective Multiplication and Control System Worth - No Voids,20*C bee inning of Cycle, kenceme Uncontrolled 1.107 Fully controlled 0,964 Strongest control rod out 0.987 R Marimum increase 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 0.038

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Exposure: BOC13 to EOC13-2205 mwd /MT (2000 mwd /ST) with ICF Peaking Factors Fuci Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr)

GE13 - 1.45 1.56 1.35 1.020 6.954 109.1 1.30 Exposure: EOC13-2205 mwd /MT (2000 mwd /ST) to EOC13 with ICF Peaking Factors Fuel Bundle Bundle Initial Design Local

  • Radial Axial R-Factor Power Flow MCPR ,

(MWt) (1000 lb/hr) gel 3 1.45 1.44 1.46 1.020 6.421 114.1 1.33 Exposure: EOC13.-2205 mwd /MT (2000 mwd /ST) to EOC13 with ICF and FWTR Peaking Factors Fuel Bundle Design Bundle Initial Local Radial Axial R-Factor Power F'aw MCPR (MWt) (1000 lb/hr)

GE13 1.45 1.61 1.51 1.020 7.135 111.1 1.19 Page 5

DRUNSWICK 2 24A5412 Reload 12 Revd Exposure: EOCl3-2205 mwd /MT (2000 mwd /ST) to EOCl3 with MSIVOOS and ICF Peaking Factors

- Fuel Hundle Hundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr) gel 3 1.45 1.46 1,46 1.020 6,488 113.7 1.32

7. Selected Margin Improvement Options Recirculation pump trip: No Rod withdrawallimiter: No Thermal power monitor: Yes Improved scram time: Yes (ODYN Option B)

Measured scram time: No Exposure dependent limits: Yes Exposure points analyzed: 2 (EOC13-2205 mwd /MT and EOCl3)

8. Operating Flexibility Options 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: 104.5 %

Increased core flow at EOC: Yes Feedwater temperature reduction throughout cycle: Yes Temperature reduction: 110.3 F Final feedwater temperature reduction: Yes ARTS Program: Yes Maximum extended operating domain: Yes Page 6

' l BRUNSWICK 2 -

24AS412 Reload 12

. Rev.1 Moisture separator reheater OOS: No hrbine bypass system OOS: No Safety / relief valves OOS:

Yes (Additionalesaluations are (credit taken for 9 of 11 valves) required to stipport this option.)

ADS OOS:

Yes (2 valves OOS)

EOC RIrl'OOS: No Main steam isolation valves OOS: -

Yes

9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS Exposure range: SOC 13 to EOC13-2205 mwd /MT (2000 mwd /ST) with ICF Uncorrected ACPR Event Flux Q/A GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 272 114 0.21- 2 Exposure range: EOC13-2205 mwd /MT (2000 mwd /ST) to EOCl3 with ICF '

Uncorrected ACPR Event Flux Q/A GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 335 120 0.24 3 Exposure range: EOC13-2205 mwd /MT (2000 mwd /ST) to EOCl3 with ICF and FWTR Uncorrected ACPR Event Flux Q/A GE13 Fig.

(%NBR) (%NBR)

FW Controller Failure . 183 113 0.10 4 Exposure range: EOC13-2205 mwd /MT (2000 mwd /ST) to EOC13 with MSIVOOS and ICF Uncorrected ACPR Event Flux Q/A GE13 Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 291 118 0.23 5

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 the GE BWR Licensing Report, Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Page 7

BRUNSWICK 2 24AS412 Reload 12 Rev.I Plant, NEDC-31654P, dated February 1989. The MCPR limit for rod withdrawal error is 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. Additionally, the )tBM operability requirements specified in Section 10.5 of NEDC-31654P have been evaluated and shown to be sufficient to ensure that the Safety Limit MCPR and cladding 1% plastic strain criteria will not be exceeded in the event of an un-blocked RWE event.

11. Cycle MCPR Valuest2
agreement with commitments to the NRC (letter from M. A. S mith to Document Control Desk,10CFR Part 21, Reportable Condition, Safety Limit h!CPR Evaluation, Afay 24,1996) a cycle-specific Safety Limit MCPR calculation was performed and is reported in the Safety Limit MCPR shown below. CP&L, however, has elected to retain the current Technical Specification Safety Limit of 1.09 and the Operating Limit MCPR values shown below are based on this value. The cycle-specific single loop operation Safety Limit was calcu-lated to be 0.01 greater than the two loop Safety Limit MCPR as shown below. This cycle specific SLMCPR was determined using the analysis basis documented in GESTAR with the following exceptions:
1. The reference core loading (Figure 1) was analyzed.
2. The actual bundle parameters (e.g., local peaking) were used.
3. The full cycle exposure range was analyzed.

Safety limit: 1.08 calculated 1.09 assumed Single loop operation safety limit:1.09 calculated 1.10 assumed Non-pressurization events:

. Exposure Range: BOC13 to EOC13 GE13 Fuel Loading Error (misoriented) 1.29 Rod Withdrawal Error (for RBM setpoint of 108%) 1.25 Pressurization events: _

Exposure range: BOC13 to FJOC13-2205 mwd /MT (2000 mwd /ST) with ICF3

, Exposure point: EOC13-2205 mwd /MT (2000 mwd /ST)

Option A Option B GE13 GE13 Load Reject w/o Bypass 1.35 1.30 i

1. The Operating Limit MCPR for two loop operation (TLO) bounds the Operating Linut MCPR for single loop operation (SLO); therefore, the Operating Limit MCPR need not be changed for SLO, a

2, The gel 3 fuel type MCPR values bound the GE8x8NB-3 MCPR values for all events.

3. The ICF Operating Limits for the exposure range of BOCl3 to EOCl3-220s mwd /MT(2000 Mwd /ST) bound the Operating Limits for the following domains: MELLL. ICF and FWTR. MSIVOOS and ICF.

Page 8

BR}UNSWICK Re oad 12 2 24A5412 Revd Exposure range: EOCl3-2205 mwd /MT (2000 mwd /ST) to EOCl3 with ICid Exposure point: EOCl3 Option A Option B GE13 GE13 Load Reject w/o Bypass 1.43 1.35

, Exposure range: EOCl3-2205 mwd /MT (2000 mwd /ST) to EOC13 with ICF and FWTH Exposure point: EOC13 Option A Option B GE13 GE13 FW Controller Failure 1.29 1.21 Exposure range: EOCl3-2205 mwd /MT (2000 mwd /ST) to EOCl3 with MSIVOOS and ICF Exposure point: EOCl3 Option A Option B GE13 GE13 Load Reject w/o Bypass 1.41 1.33 4

12. Overpressurization Analysis Summary Psi Pv Plant Event (psig) (psig) Response MSIV Closure (Flux Scram) 1286 1322 Figure 6
13. Loading Error Results Variable water gap misoriented bundle analysis: Yess Misoriented Fuel Bundle ACPR G E 13-P9DTB 363-11 GZl-100T-146-T (G E 13) 0.13 GE13-P9DTB363-l lG7 100T-146-T (GE13) 0.13 GE 13-P9DTB395-12G5.0-100T-146-T (GE13) 0.19 G E 13-P9DTB 393-4G6.0/9G5.0-100T- 146-T (GE 13) 0.20
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-24011-P-A-US.
4. The ICF Operanng Limits for the exposure range of EOCl3-2205 Mwd /Nrr (2000 MwWST) to EOCl3 bound the Operating Limits for the kELLL domain.
5. Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

Page 9

Bgae SyICK 2 24g54l{

4

15. Stability Analysis Results GE SIL-380 recommendations and GE interim corrective actions have been included in the B runswick Steam Electric Plant Unit 2 operasing procedures. Regions of restricted operation defined in Attachment I to NRC
  • Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), are applicable to Brunswick 2.

I i

- 16. Loss-of-Coolant Accident Results 3 - LOCA method used: SAFER /GESTR-LOCA The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of Brunswick Steam Electric Plant Units

+

l and2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis NEDC-31624P, Revision 2, luly I990, 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 i 1

Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis: Application  !

to GE13 Fuel, NEDC-31624P, Supplement 3, Rev. 0, 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:

Page 10

BRUNSWICK 2 24A5412 Reload 12 Rev.1

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

Bundle Type: gel 3-P9DTB395-12G5.0 -100T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.15 11.28 0.20 C.22 11.24 11.34 1.00 1.10 11.38 11.42 2.00 2.20 11.50 11.53 3.00 3.31 11.57 11.66 4.00 4.41 11.66 11.75 5.00 5.51 11.74 11.83 6.00 6.61 11.83 11.92 7.00 7.72 11.92 12.02 8.00 8.82 12.02 12.11 9.00 9.92 12.11 12.21 10.00 11.02 12.21 12.31 12.50 13.78 12.21 12.33 15.00 16.53 12.04 12.13 17.50 19.29 11.78 11.86 20.00 22.05 11.51 11.59 25.00 27.56 10.98 11.06 30.00 33.07 10.44 10.53 35.00 38.58 9.73 9.89 40.00 44.09 9.03 9.18 45.00 49.60 8.33 8.49 50.00 55.12 7.64 7.82 55.00 60.63 6.95 7.16 58.32 64.28 6.49 6.70 58.75- 64.76 . -

6.64 Page 11

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

e ad'1 e.

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

Bundle Type: gel 3-P9DTB393-406.0/90$.0-100T-146-T Average Planar Exposure MAPLHGR(kW/ft)  :

(GWd/ST) (GWd/MT) Most Limiting Least Limiting

~

0.00 0.00 11.03 11.09 l

0.20 0.22 11.09 11.12 1.00 1.10 11.19 11.21 2.00 2.20 11.28 11.32 3.00 3.31 11.37 11,42 4.00 4.41 11,47 11.52 5.00 5.51 11,57 11.63 i 6.00 6.61 11.67 11.74 i

7.00 7.72 11.78 11.85 8.00 8.82 11.89 11.97 9.00 9.92 12.00 12.09 10.00 11.02 12.11 12.22 12.50 13.78 12.12 12.25 15.00 16.53 12.00 12.10 17.50 19.29 11.76 11.84 20.00 22.05 11.50 11.57 25.00 27.56 10.96 11,04 i i

30.00 33.07 10.28 10.43 35.00 38.58 9.54 9.71 40.00 44.09 8.85 9.00 45.00 49.60 8.19 8.31 50.00 55.12 7.55 7.62 55.00 60.63 6.92 6.93 58.18 64.14 6.48 6.51 58.60 64.60 -

6.46 Page 12

311UNSWICK 2

1cJgad 12 24AS412 Rev.1 l

l 5

W Y I e

mMMMMMBsMMMm
HMMMMMMMMBsM
mMEMMMMMMMMMm
MMMMMMMMMMMMM
MMMMMMMMMMMMM
MEMMMMMMMMMMM
MMMMMMMMMMMMM
M E M M M M M M M Bs M M M
MMMMMMMMMMM*
MMMMMMMMMBsE
*MMMMMMMMM*
*MMMMM*

IIIIiiIIII i i 8 5 7 9 it il il 17 10 !! ti il !? 19 31 Il il if it il 43 45 41 49 11 Fuel Type A=GE13-P9DTH36bilGZl 107T-346-T (Cycle 12) E=G E 13-P9 DTB 393-4G6.0/9G5.0- 10(TT- 146-T (Cycle 13)

B=GElo-P8HXB322-ilGZ-70M-150-T (Cycle 11) F=GE 10.-P8 H XB 320-I l GZ-100M-150-T (Cycle 11)

C=GElo-P8HXB329-120Zl-100M-154T (Cycle 10) O=GE10-P8HXB324-120Z-70M-150-T (Cycle 11)

D=G E I )-P9 DTB 395-12G5.0- 100T- 346.-T (Cycle 13) H= gel 3-P9DTB363-llGZ-100T-146-T (Cycle 12)

Figure 1 Reference Core Loading Pattern Page 13

3RUNSWICK 2 34A5412

, Aeload 12 Rev,1 Neutron Flux Vessel Press Rise (psi)

  • Ave Surface Heat Flus *
  • Safety Valve Flow 160.0 - --- - Core treet Flow 3040 -

--- Relief Valve Flow

--- Bypass Valve Flow

-. )

) Gl ~\ %

-* s 100.0 , ,

's, 200.0 -

'., ., *s s I t

  • s .,,, ' * % $

.,*.a.

60.0 -

.***., - .. 100.0 -

r-~~--~~~

/

I 0.0 O0 l I '

00 3.0 6.0 0.0 30 6.0 Time (sec) Time (sec)

^ I Level (inch-REF-SEP-SKRT) Void Reactivity

+ Vessel Steam Flow - N DopplerReactivity-200.0 -

--- Turtaine Steam Flow 1.0 -' -- Scram Reactivity

--- Feedwater Flow -- Total ReactMty 9-_ 5. ..... ..

s p

100 0 - - ' ~ , j 00

  • g,

, _,_.~

\

j', ...

,,,, l . ... ...... d \

0.0 .t ', ,t--.t,I_.--.-.--.----.

k \'

- i .0 - \

\1

\l '.

- 100.0 ' ' '

lj

- 2.0 -- '

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

Figure 2 Plant Response to Load Reject w/o Bypass (HOC 13 to EOC13-2205 mwd /MT (2000 mwd /ST) with ICF)

Page 14 -

i 1RUNSWICK 2 24A5412 i

- Jeload 12 ,,

Rev.! '

l Neutron Rux Veseel Pren Rise (pW)

Ave Surface Heat Flus * * * *

  • Safety Valve Flow 150.0 - .-- - core ingt now 300.0 -

--- Rehet vwve now

--- pypeu vwve now 100.0

~ dj/'s'%

. s' ',', 200.0 -

E g

'"* s d s~~~ g -

.,~. ,

50 0 -

100.0 -

j------

I I

0.0 '

O.0

' I '

0.0 3.0 6.0 0.0 3.0 '

6.0 Eme (SeC) Eme(Sec) o6d Me 'vity

~

Level (inch-REF-SEP-SKRT) -

. + *

  • Vessel Steam Flow Doppler vity

--- Turbine Steam now 200.0 -

1.0 -

- Scram ReactMty

--- Foodwater flow -

Total ReactMty G-4

't E

3 g

.100.0>'-.7-._.

\< .. - 30.0 5 .'.. ...'

  • ~.
  • q l' l.., .' '

.. ....... d 5 \'

0_0 1 4 yl L' . ._ .

E i.0 -

t ,i

& \L

'\

t

.i00.0 ,

t -

2.0 \l 'I 1 -

0.0 3.0 - 6.0 0.0 3.0 6.0 Eme(sec)- Eme (sec)

Figure 3 Plant Response to Load Reject w/o Bypass (EOC13_2205 mwd /MT (2000 mwd /ST) to EOC13 with ICF)

Page 15

3RUNSWICK 2 24A5412

3eload 12

, Rev, I- i 1

t i

}

160.0 Neutron Mu3, * # ~ '

  • * * *
  • Avpece Heat Fluu co,e inist now

\, Vessel Press Rise (psi)

  • * * *
  • Safety Valve Flow

\ 125 0 -

--- Rehof Valve Mow

, - -- Core inlet Subcooling -- - Bypass Valve Flow i

~

i f

1 g*f e.- - " ^ *N't, ,9 _

  • Y ' % ,

i

e . 2 .

Y. '

. Y 60.0 -

25.0 - '

O

~

i

' I '

0.0 --

~ 25.0 ' '

O0 8.5 17.0 0.0 8.5 17.0 Time (sec) Time (sec) e Level (inctAEF-SEP-SKRT) Void 9eactMty f

  • * * *
  • Vessel Steam Flow * * * *
  • Doppler ReactMty 150.0 -

--- Turbine Steam Flow 1.0 -

--- Scram ReactMty

--- Foodwater Flow - - - Total ReactMty

. . .- . , g y ..'

i e' 0.0 71000

~

e g , ,',, ,  ! ~ +.-e . .-l-y,y} ,,-

g I.....

  • 3 -

g ,' I 50.0 -

- 1.0 f

ll .

t .

I-

\, i' O0 - '

- 2.0 - ' ' '

O.0 8.5 17.0 0.0 8.5 17.0 Time (sec) Time (sec) '

Figure 4 Plant Response to FW Controller Failure (EOC13-2205 mwd /MT (2000 mwd /ST) to EOC13 with ICF and FWTR)

Page 16

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

1RUNSWICK 3 24A5412 (eload 12 Rey,1 4

- Neutron Flux Vessel Press Rise (psi)

- + Ave Surface Heat Flux * * *

  • Safety Valve f;ow
150.0 - - - - Con, Inlet Flow 300.0 -

--- Rollef Valve Flow

--- Bypass Valve Flow .

r

'M V% i

, 100.0 ..' '. \ % 200 .0 -

h *

%s~ h

%s,~ $

8 - '

.., ~~~_ 8 3

60.0 -

100.0 -

1 r___-_____

I _\

l '

I 0.0 0.0 .

> I

  • l 0.0 3.0 6.0 0,0 3.0 60 Time (sec) Time (sec)

Level (inch-REF-SEP-SKRT) old Re . vity

. *

  • Vessel Steam Flow *
  • Doppler eactMty 200.0 -

--- Turt>ine Steam Flow 1.0 - -

Scram Re

--- Foodwater Flow -- TotalReactivity g .

'.......+'

4)

g. L0 I

g 100.0 a \ ,, . - --- . . . .. . .r.- . . .n. . . . .... .

<. \

s......-

1. . . d g I \a Ca_ i :. _ _ _ _ _ _ , _ _ _ _ _ _ _ _ .

s _,.0 _ gd

@ \. .,

\\

\'

-100.0 ' ' '

I

- 2.0 '

O.0 3.0 6.0 0.0 30 6.0 Time (sec) Time (sec)

- Figure 5 Plant Response to Load Heject w/o Hypass (EOC13--2205 mwd /MT (2000 mwd /ST) to EOC13 with MSIVOOS and ICF)

Page 17

_m.__.__._.______._.__..._._~ ..

a1 e e, i

++ -

h m Fluu

. Meaafface Heat Flux Vessel Press Rue (psi)

  • * *
  • Safety Valve Flow 160.0 -' - --- Core lalet Flow 300.0 -

--- Reht Valve Flow

--- Bypase Valve Flow s

100 0 I ~ ' ), % %\g', 200.0 -

n M. m *% '

Y. '

Y

?. .% , ~ ~ .

60.0 -

.**. 100.0 -

g---~~ . ,

I I

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

Level (inch REF-SEP-SKRT) . Void

. . . . Vessel Steam Flow =***D r etMty 200.0 -

--- Turbine Steam Flow - 1.0 -

- - - Se etMty

-- - Feedwater Flow ~--T activtty G

v . ,.*..

y ' .... *

] 100.0

-e t - -- *

, s .-

}10.0 n- g

  • g

'. N

,d.,.

.s

.%~._.

j , s i.

,g\,,..'

a,

% " .'. l. s N-

,, ~~~~ -

$ \)\\.

} .,.0 -

- A r.

l'

\

-100.0 ' ' ' I

- 2.0 ' '

O.0 4.0 8.0 0.0 ' 4.0 80 Time (sec) - Time (sec)

Figure 6 Plant Response to MSIV Closure (Flux Scram)

Page 18

3.'tUNSWICK 2 24AS412

<eload 12 Rev.1 Appendix A Analysis Conditions His is the first reload core for B mnswick Unit 2 which will operate at an uprate<l power of 105 % (2558 MWt).

To reflect actual plant parameters accurately, the values shown in Table A-1 were used for this cycle.

Table A-1 Analysis Value Parameter ICF ICF and FWTR MSIVOOS and ICF Thermal power, MWt 2558.0 2558.0 2558.0 Core flow, Mlb/hr 80.5 80.5 80.5 Reactor pressure, psia 1060.9 1059.6 1060.9 Inlet enthalpy, BTU /lb 530.7 519.4 530,7 Non-fuel power fraction 0.037 0.037 0.037 Steam flow analysis, Mlb/hr 11.09 9.67 11.09 Dome pressure, psig 1030.0 1030.0 1045.0 hrbine pressure, psig 969.0 984.2 941.6 No. of Safety / Relief Valves 9 9 II Relief mode lowest setpoint, prig i164.0 1164.0 1164.0 Recirculation pump power source on-sitc6 on-site 6 on-site 6 hrbine control valve mode of operation Partial arc Partial arc Partial are j

6. Bounds operation with ofr-site power source for reload licensing events for Cycle 13.

Page 19

MNa"diyImS 2gsg12 e

Appendix B Main Steamilne Isolation Valve Out of Service (MSlVOOS)

Reference B-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 2 throughout Cycle 13, 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-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 normal plant operation. 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 p:1 when compared to the same case evaluated with all (four) steamlines operational.

Reference B-1. Main dreamline holation Valve Out ofSeniceforIhe Brunswick Steam Electric Plant, EAS-117-0987 OE Nuclear Energy, April 1988.

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!' jeTad 1ylCK 2 34A5412 Rev.1 I

Appendix C l Decrease in Core Coolant Temperature Events u

The Loss of Feedwater lleater (LFWil) event and the llPCl inadvertent start-up event are the only cold water 1

i injection AOOs checked on a cycle-by-cycle basis. A Cycle 11 analysis showed a LFWil ACPR of 0.13 and  ;

j a Cycl 10 analysis showed a 11PCI inadvertent start-up ACPR of 0.15. As was the case for Cycle 12 also, I there is no reason why these events would be expected to be more severe for Cycle 13.The results of the AOOs presented in Section 11 of this report sufficiently bound the expected results of the LFWii and IIPClinadver.

tent start-up events, therefore these events were not analyzed for Cycle 13. ,

I.

i i

)

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{,T3qs,ylCK 2 24 A3412_

, Rev.I Appendix D Feedwater Temperature Reduction (FWTR)

Reference D-1 provides the basis for operation of the Bmnswick 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 ExtendedLoadUne umirandincreased Core Flon for Brunswick Steam Electric Plant Units 1 and 2, NEDC-32457P, Revision I, December 1995.

i

  1. 1 Page 22

l$,Ns,ylCK e 2 24AS412

.. Rev. i l

Appendix E Maximum Extended Operating Domain (MEOD)

Reference E-1 provided a basis for operation of the Brunswick Steam Electric Plant in the Maximum Ex.

tended Operating Domain (MEOD). 'Ihe reload licensing analysis performed for Cycle 13 and documented l

herein is consistent with and provides the cycle-specific update to the reference B-1 analysis. Application i

of the GEXL-PLUS correlation to the reload fuel has been confirmed as required in reference E-1. The appil-

, cability of GE13 was addressed and found acceptable.

Reference B-1. Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant. NEDC-31654P.

GE Nuclear Energy (Proprietary), February 1989.

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ENCLOSURE 3 HRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO, !0 324 LICENSE NO. DPR 62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPOP.T AND LOSS OF COOLANT ACCIDENT ANALYSIS REPORT NEDC 31624P, SUPPLEMENT 2 REVISION 4 LOSS OF COOLANT ACCIDENT ANALYSIS REPORT FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 RELOAD 12 CYCLE 13

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