Text

Supplemental Reload Licensing Rept for Brown Ferry Nuclear Plant Unit 2,Reload 8,Cycle 9
	ML20132B769
Person / Time
Site:	Browns Ferry
Issue date:	05/31/1996
From:	Papandra C, Reda R; GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20132B735	List: ML20132B730; ML20132B740; ML20132B769; ML20132B780;
References
	J11-02761SRLR, J11-02761SRLR-R03, J11-2761SRLR, J11-2761SRLR-R3, NUDOCS 9612170382
	Download: ML20132B769 (36)
	v • d • e

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BFN-13

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GE Nuclear Energy l

l J11-02761SRLR Revision 3 l

Class I l

May 1996 J11-42761SRLR, Rev. 3 Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 8 Cycle 9 Approved Approved RJ. Reda, Manager CJ. Papandrea Fuel and Facility Licensing Fuel Project Manager 9612170382 961211 PDR ADOCK 05000259 P

pon N.2-1

BROWNS FERRY UNIT 2 J11-02761SRLR Reload 8 Rev.3 i

Important Notice Regarding Contents of This Report Please Read Carefully 4

f This report was prepared by General Electric Company (GE) solely for Tennessee Valley Authority for TVA's use in defining operating limits for the Browns Ferry Unit 2. The in-formation contained in this report is believed by GE to be an accurate and true represen-

[

tation of the facts known or obtained ur provided to GE at the time this report was pre-j pared.

l The only undertakings of GE respecting information in this document are contained in

{

Contract between Tennessee Valley Authority and General Electric Companyfor Fuel Bundles andServicesforBrowns Ferry 2, and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with re-2 spect to any such unauthorized use, neither GE nor any of the contributors to this docu-l ment makes any representation or warranty (expressed or implied) as to the complete-l ness, 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 j

responsibility for liability or damage of any kind which may result from such use of such l

information.

i i

i 4

N.2-il Pag <

8 "~ 3 BR{,gS FERRY UNIT 2 J11-02761SRLR e)

Rev. 3 i

l Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by B.R. Fischer and H.M. Schrum. De Supplemental Reload Licensing i

Report was prepared by B.R. Fischer. His document has been verified by W.E. Russell. Revision I has been verified by M.R. Morris Revision 2 has been verified by F.T. Bolger. Revision 3 has been verified by A.F.

Alzaben.

l N.2-iii Page 3

.. ~ _

BROWNS FERRY USTT 2 BW-13 111-02761SRLR Reload 8 Rev.3

[

The basis for this report is General Electric Standard Applicationfor Reactor Fuel. NEDE-240l 1-P-A-11 November 1995; and the U.S. Supplement. NEDE-24011-P-A-11-US. November 1995.

l l

1.

Plant-unique Items l.

Appendix A: Analysis Conditions l

Appendix B: Alternate Analyses For Feedwater Temperature Reduction 2.

Reload Fuel Bundles Cycle FuelType I*

Number i

In duced:

P8DRB284L(P8x8R) 6 64 i

BP8DRB299(BP8x8R) 7 24 l

BP8DRB30lL(BP8x8R) 7 112 1

GE9B-P8DWB326-7GZ-80M-150-T (GE8x8NB) 7 48 GE9B-P8DWB325-10Gb-80M-150-T (GE8x8NB)3 7

72 BP8DRB299(BP8x8R) 8 144 BP8DRB30!L (BP8x8R) 8 4

GE9B-P8DWB 319-9GZ-80M-150-T (GE8x8NB) 8 96 Erm gel l-P9 HUB 367-14GZ-100T-146-T (gel l) 9 88 i

GE l l-P9 HUB 366-12G4.0-100T-146-T (gel l) 9 112 i

Total 764 i

l l

3.

Reference Cost I - " ; Pattern l

l Nommal previous cycle core average exposure at end of cycle:

22959 mwd /MT o

( 20828 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 22723 mwd /MT from cold shutdown considerations:

( 20614 mwd /ST)

Assumed reload cycle core average exposure at begmamg of 14118 mwd /MT cycle:

( 12808 mwd /ST)

Assurned reload cycle core average exposure at end of cycle:

25251 mwd /MT

( 22908 mwd /ST) l Reference core loading panem-Figure 1

}

i. inci.e. e t n i==mn.d in cycw 9 noin cyci. 7.

i N.2-1 Page 4

-I3 BROWNS FERRY UNTT 2 Jl 1-02761SRLR Reload 8 Rev. 3 4.

Calculated Core Effective Multiplication and Control System Worth - No Voids,20'C Beginning of Cycle, ken.cov, Uncontrolled 1.096 l

Fully controlled 0.955 Strongest control rod out 0.981 l

R, Maximum increase in cold core reactivity with exposure into cycle, ok 0.005 i

l 5.

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

(ppm)

(20*C, Xenon Free) 660 0.046 6.

Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Exposure: BOC9 to EOC9 STANDARD - HARD BOTTOM BURN Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lb/hr)

Gell 1.45 1.45 1.52 1.035 6.091 114.6 1.28 GE8x8NB 1.20 1.67 1.40 1.000 7.027 107.3 1.25 BP8x8R 1.20 1.60 1.40 1.051 6.732 113.4 1.23 Exposure: BOC9 to EOC9 STANDARD - HALING Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lb/hr) gel 1 1.45 1.59 1.19 1.035 6.658 108.4 1.27 GE8x8NB 1.20 1.73 1.40 1.000 7.273 105.8 1.20 BP8x8R 1.20 1.65 1.40 1.051 6.950 112.0 1.18 l

t i

l N.2-2 Page5

" -13 BROWNS FERRY UNIT 2 J11-02761SRLR Reload 8 Rev.3

' Exposure: BOC9 to EOC9 FFWTR - HARD BO1 TOM BURN Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lb/hr) gel 1 1.45 1.50 1.53 1.035 6.295 113.6 1.26 GE8x8NB 1.20 1.70 1.40 1.000 7.119 106.7 1.24 BP8x8R 1.20 1.62 1.40 1.051 6.802 112.9 1.23 Exposure: BOC9 to EOC9 FFWTR-HALING Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) -

(1000 lb/hr) gel 1 1.45 1.64

'l.20 1.035 6.875 107.2 1.24 i

GE8x8NB 1.20 1.74 1.40 1.000 7.309 105.5 1.21 SP8x8R 1.20 1.66 1.40 1.051 6.988 111.7 1.19 Exposure: BOC9 to EOC9 EI.I I.A - HARD BO1 TOM BURN' Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lb/hr)

Gell 1.45 1,41 1.47 1.035 5.915 94.2 1.28 GE8x8NB 1.20 1.57 1.40 1.000 6.610 89.2 1.25 BP8x8R 1.20 1,54 1.40 1.051 6.474 93.5 1.21 Exposure: BOC9 to EOC9 EI I I. A - HALING Pealdag Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lb/hr) gel 1 1.45 1.53 1.18 1.035 6.393 89.0 1.28 GE8x8NB 1.20 1.67 1.40 1.000 7.014 87.0 1.16 BP8x8R 1.20 1.61 1.40 1.051 6.771 91.8 1.15 N.2-3 Page 6

I BROWNS FERRY UNTT 2 BN-13 111-02761SRLR Reload 8 Rev.3 l

l Exposure: BOC9 to EOC9 ELLLA-FF%TR - HARD BOTTOM BURN Peaking Factors j

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

(MWt)

(1000 IMr) i gel 1 1.45 1.45 1.47 1.035 6.062 93.5 1.27 i

GE8x8NB 1.20 1.60 1.40 1.000 6.728 88.5 1.24 BP8x8R 1.20 1.54 1.40 1.051 6.477 93.4 1.23 Exposure: BOC9 to EOC9 ELLLA-FFWTR - HALING Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR

( M W t)

(1000 IMr) gel 1 1.45 1.57 1.16 1.035 6.568 88.1 1.25 GE8x8NB 1.20 1.67 1.40 1.000 6.989 87.0 1.18 BP8x8R 1.20 1.61 1.40 1.051 6.748 91.9 1.17 7.

Selected Margin Improvement Options Recirculation pump trip:

Yes Rod withdrawal limiter:

No Thermal power monitor:

Yes2 Improved scram time:

Yes (ODYN Option B)

Measured scram time:

No Exposure dependent limits:

No Exposure points analyzed:

1 8.

Operating Flexibility Options l

Single-loop operation:

No Load line limit:

Yes Extended load line limit:

Yes Maximum extended load line limit:

No

2. No cmdat taken for themmi power monster.

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N.2-4 Page 7

8"-l 3 BROWNS FERRY UNIT 2 J11-02761SRLR Reload 8 Rev.3

)

l Increased core flow throughout cycle:

Yes l

i Flow point analyzed:

105.0 %

increased core flow at EOC:

Yes Feedwater temperature reduction throughout cycle:

Yes Temperature reduction:

47.0*F Final feedwater temperature reduction:

Yes

]

ARTS Program:

No Maximum extended operating domain:

No Moisture separator reheater OOS:

No j

Turbine bypass system OOS:

No Safety / relief valves OOS:

Yes3 (credit taken for 12 of 13 valves)

ADS OOS:

No EOC RPT OOS:

No Main steam isolation valves OOS:

No 9.

Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS Exposure rarge: BOC9 to EOC9 STANDARD - HARD BOTTOM BURN Useorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 499 125 0.20 0.18 0.16 2

Load Reject w/o Bypass 626 124 0.21 0.18 0.16 3

Exposure range: BOC9 to EOC9 STANDARD - HALING Uneorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 314 118 0.17 0.13 0.11 4

Load Reject w/o Bypass 427 118 0.20 0.13 0.11 5

3. The unassent analyses assurne one SatV as b, _ _ _ _. bowever, other analyses suppomag S/RVs out of service have act been performed N,2-5 Page 8

BROWNS FERRY UNTT 2 BFN-13 Eeload 8 J11-02761SRLR Rev.3 Exposure range: BOC9 to EOC9 FFWTR - HARD BOTTOM BURN Uncorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 460 126 0.19 0.18 0.16 6

Exposure range: BOC9 to EOC9 FFWTR - HALING l

Uncorrected ACPR Event Flux Q/A Gell GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 312 119 0.17 0.14 0.12 7

Exposure range: BOC9 to EOC9 ELLLA - HARD BOTTOM BURN Uncorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 481 125 0.20 0.16 0.15 8

Load Reject w/o Bypass 594 124 0.22 0.18 0.15 9

Exposure range: BOC9 to EOC9 ELLLA - HALING Uncorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 237 113 0.17 0.09 0.09 10 Load Reject w/o Bypass 324 114 0.20 0.09 0.08 11 Exposure range: BOC9 to EOC9 ELLLA-FFWTR - HARD BOTTOM BURN Uncorrected ACPR Event Flux Q/A GEH GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 466 126 0.20 0.17 0.16 12 Exposure range: BOC9 to EOC9 ELLLA-FFWTR - HALING Uncorrected ACPR Event Flux Q/A GEU GE8x8NB BP8x8R Fig.

(%NBR)

FW Controller Failure 258 116 0.18 0.11 0.10 13 I

N.2-6 Page 9

BROWNS FERRY UNIT 2 sm-U Reload 8 J11-02761SRLR Rev. 3

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary l

d Rod Block Rod Position ACPR Reading, %

(ft withdrawn)

Gell GE8x8NB

' BP8x8R/P8x8R 104 3.0 0.06 0.06 0.07 105 3.5 0.10 0.11 0.11 106 4.0 0.15 0.15 0.15 i

107 4.5 0.15 0.16 0.16 108 4.5 0.15 0.16 0.16 109 5.0 0.16 0.16 0.16 110 5.5 0.17 0.17 0.17 Setpoint selected:

110 %

Limiting rod pattem:

Figure 14

11. Cycle MCPR Values Safety limit:

1.09 In agreement with commitments to the NRC (letter from M.A. Smith to the Document Control Desk,10CFR Part 21. Reponable Condition, Safety limit MCPR Evaluation, May 24,1996) a cycle-specific Safety Limit MCPR calculation was performed, and has been reported in both the Safety Limit MCPR and the Operating Limit MCPR shown below. This cycle specific SLMCPR was detemuned using the analysis basis docu-mented in GESTAR with the following exceptions:

1. The actual core loading was analyzed.

2. 'Ihe actual bundle parameters (e.g. local peakmg) were used.

3. The full cycle exposuit range was analyzed.

Non-cressurization events:

Exposure range: BOC9 to EOC9 Gell GE8x8NB BP8x8R Rod Withdrawal Error (for RBM Setpoint to 110%)

1.26 1.26 1.26 Fuel Loading Error 1.25 1.30 1.24

4. A Technical specincanon (TS) allowable value of !!2% is supponed by this analyus wah one RBM channel operable and 5% CPR nwgin, or both RBM channels operable N.2-7 Page 10

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BROWNS FERRY UNIT 2 J11-02761SRLR t

Reload 8 Rev.3 Pr.<<nrbtlon events:

Exposure ran8e: BOC9 to EOC9 STANDARD-HARD BOTTOM BURN Exposure point: EOC9 Option A Opdon B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 1.33 133 131 1.30 1.29 1.27 l

Load Reject w/o Bypass 1.34 132 1.30 131 1.28 1.26 1

Exposure ran8e: BOC9 to EOC9 STANDARD - HALING i

Exposure point: EOC9 Opdon A Option B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Contmiler Failure 130 1.27 1.26 1.27 1.23 1.22 Load Reject w/o Bypass 133 1.27 1.26 130 1.23 1.22 4

Exposure ran8e: BOC9 to EOC9 FFWTR - HARD BOTTOM BURN Exposure point: EOC9 OpdonA OpdonB Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 132 132 131 1.29 1.28 1.27 l

j Fw e ran8e: BOC9 to EOC9 FFWTR-HALING Exposure point: EOC9 Opdon A Opdon B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 131 1.29 1.27 1.28 1.25 1.23 l

Exposure range: BOC9 to EOC9 ELLLA - HARD BOTTOM BURN Exposure point: EOC9 Opdon A Option B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 133 131 1.30 130 1.27 1.26 Load Reject w/o Bypass 135 132 1.29 132 1.28 1.25 N.2-8 Page 11

~

BROWNS FERRY UNTT 2 Jil-02761SRLR Reload 8 Rev.3 Exposure range: BOC9 to EOC9 ELLLA - HALING Exposure point: EOC9 Opdon A Option B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 1.30 1.24 1.23 1.27 1.20 1.19 Load Reject w/o Bypass 1.34 1.23

!.22 1.31 1.19 1.18 l

Exposure range: BOC9 to EOC9 ELLLA-FFWTR - HARD BO'ITOM BURN Exposure point: EOC9 Option A Option B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 1.33 1.31 1.31 1.30 1.27 1.27 l

Exposure range: BOC9 to EOC9 ELLLA-FFWTR - HALING Exposure point: EOC9 Option A Option B Gell GE8x8NB BP8x8R Gell GE8x8NB BP8x8R FW Controller Failure 1.31 1.26 1.25 1.28 1.22 1.21 l

11 Overpressurization Analysis Summary Psi Pv Plant Event (psig)

(psig)

Response

MSIV Closure (Flux Scrarn) 1224 1257 Figure 15

13. Loading Error Results Vanable water gap misoriented bundle analysis: Yes5 Miseriented Fuel Bundle ACPR G E l 1 -P9 HUB 366-12G4.0.-100T-146-T 0.16 gel 1-P9 HUB 367-14GZ-100T-146-T 0.16 GE9B-P9DWB319-9GZ-80M-150 -T 0.21 BP8DRB299 0.13 Mislocated Fuel Bundle 0.15

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 docurnented in NEDE-24011-P-A-US.

5. lacindes a 0.02 peanky due to venable water gap R-factor unconaury N.2-9 Page 12

l BROWNS FERRY UNTT 2 J11-02761SRLR U

Reload 8 Rev.3 L

15. Stabuity Analysis Results GE SIL-380 recommendations have been included in the operating procedures; therefore, no stability analy-sis is required. NRC approval for deletion of a cycle-specific stability analysis is documented in NEDE-24011-P-A-US. Browns Ferry Nuclear Plant Unit 2 recognizes the issuance of NRC Bulletin No.

88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), and will comply with the rec-ommendations contained therein.

16. Loss-of-Coolant Accident Results LOCA method useth 5/."CR/GESTR-LOCA Reference LOCA Analyses: Bmwns Ferry Nuclear Plant Units 1, 2 and 3 Safer /GESTR-LOCA Loss-of-Coolant Accident Analysis, S.K. Rhow and C.T. Young NEDC-32484P, Rev.1, February 1996, and Relax.

ation ofEmergency Core Cooling System Parametersfor Bmwns Ferry Nuclear Plant Units 1,2, and 3 (Per.

form Pmgram Phase 1), S.K. Rhow and T.H. Chuang, GE-NE-B13-01755-2, Rev.1, February 1996.

An analysis consistent with Bmwns Ferry Nuclear Plant Units 1, 2 and 3 Single Loop Operation, NEDO-24236, resulted in a single loop operation MAPLHGR multiplier of 0.90 for all of the fuel designs in the current cycle. The MAPLHGR limits for the lattices of each of the new fuel bundles are provided in Lstrice-Dependent MAPLHGR Repon for Bwwns Ferry Nuclear Plant Unit 2, January 1996, J11-02761 MAPL. The least limiting and the most limiting MAPLHGRs for the new fuel is provided in the table on the next page. The core-wide metal water reaction is <0.1%.

l l

N.2-10 Page 13

BROWNS FERRY UNTT 2 l

Reload 8 J11-02761SRLR Rev.3 l

l

16. Loss-of-Coolant Accident Results (cont) l Bundle Type: gel 1-P9 HUB 366-12G4.0-100T-146-T Average Planar Exposun MAPLHGR(kW/ft) l (GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 9.55 9.64 l

0.20 0.22 9.62 9.72 l

1.00 1.10 9.80 9.88 2.00 2.20 10.05 10.10 3.00 3.31 10.32 10.34 4.00 4.41 10.58 10.61 5.00 5.51 10.84 10.91 6.00 6.61 11.11 11.22 7.00 7.72 11.39 11.55 l

8.00 8.82 11.67 11.87 9.00 9.92 11.81 12.04

^

10.00 11.02 11.95 12.19 12.50 13.78 11.92 12.16 15.00 16.53 11.72 11.93 17.50 19.29 11.48 11.68 20.00 22.05 11.20 11.38 25.00 27.56 10.51 10.66 30.00 33.07 9.84 9.97 35.00 38.58 9.19 9.31 40.00 44.09 8.55 8.69 45.00 49.60 7.91 8.07 I

50.00 f5.12 7.26 7.46 55.00 60.63 6.59 6.81 56.17 61.92 6.42 6.65 56.94 62.77 6.55 l

i N.2-11 Page 14

l BROWNS FERRY UNIT 2 Jl1-02761SRLR i

Reload 8 Rev.3

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

Bundle Type: GE11-P9 HUB 367-14GZ-100T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 9.I 8 9.64 l

0.20 0.22 9.27 9.72 l

1.00 1.10 9.45 9.88 2.00 2.20 9.72 10.10 3.00 3.31 10.00 10.34 l

l 4.00 4.41 10.30 10.61 5.00 5.51 10.62 10.91 6.00 6.61 10.95 11.22 j

7.00 7.72 11.31 11.55 8.00 8.82 11.67 11.87 9.00 9.92 11.81 12.04 10.00 11.02 11.95 12.19 12.50 13.78 11.92 12.16 15.00 16.53 11.72 11.93 17.50 19.29 11.48 11.68 20.00 22.05 11.20 11.38 l

i 25.00 27.56 10.51 10.66 30.00 33.07 9.84 9.97 35.00 38.58 9.19 9.31 40.00 44.09 8.55 8.69 45.00 49.60 7.91 8.07 50.00 55.12 7.26 7.46 55.00 60.63 6.59 6.81 56.17 61.92 6.42 6.65 56.89 62.71 6.56 56.94 62.77 6.55 I

1 l

N.2-12 Page 15

8U-I3 BROWNS FERRY UNTT 2 111-02761SRLR Relord 8 Rev.3 l

l eMMMMMMMs l

~!MMMMMMMMME ssM M M M M M M M M M Mss sMMMMMMMMMMMMMs

MMMMMMMMMMMMMMM l

M M M M M M M M M M M M M M M l

l::MMMMMMMMMMMMMMM ll: M M M M M M M M M M M M M M M

M M M M M M M M M M M M M M M

'::HMMMMMMMMMMMMMM ll "HMMMMMMMMMMMM"

- HMMMMMMMMMM**

IMMMMMMMMME "MMMMMMM" l IIIIIIIIIIIII 1 5 5 7 9 11 15 !$ 17 19 21 28 25 27 29 31 33 85 37 IS 41 48 45 47 49 51 53 55 57 59 i

Fuel Type A=BP8DRB299 (BP8x8R - Cycle 7)

F=BP8DRB301L (BP8x8R -Cycle 8)

B=BP8DRB30lL (BP8x8R-Cycle 7)

G=P8DRB284L (P8x8R - Cycle 6) l C=GE9B-P8DWB3W7GZ-80M-150-T (Cycle 7)

H=GE98-P8DWB319-9GZ,-80M-150-T (Cycle 8)

D=GE98-P8DWB325-10G7A0M-150-T(Cycle 7)

!= gel 1-P9 HUB 3412G4S10GT-14T (Cycle 9)

E=BPDRB299L (BP8x8R - Cycle 8)

J= gel 1-P9 HUB 367-14GZ-100T-14T (Cycle 9)

Figure 1 Reference Core Loading Pattern N.2-13 Page 16

l BFN-13 BROWNS FERRY UNTT 2 Jl1-02761SRLR Reload 8 Rev.3 I

i l

,\\

Vessel Press Rise (psi)

/

Neutron Flux

- - Ave Surface Heat Flux

- - - - - Safety Velve Flow f

150.0 - --- core trat Flow

\\

125.0 - --- Rehef Velve Flow

- -- core iret Subcoohng

\\,,

--- Bypese Velve Flow

-J.

]- 7" ' * ~~

~

100.0 75.0 IN l

e

~

t.

E l

l E

N e

V Y

~

1 y

I

\\

50.0 25.0 I

I I

\\

-.s... L.

0.0

- 25.0 00 20.0 0.0 20.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKMT)

Void ReactMty

..... Vessel Steam Flow

- - - - - Doppier ReactMty 150.0 - --- Turbine Steam Flow 1.0 - --- Scram ReactMey

--- - - Festgater Sg.,,

--- Total ReactMty G

l g 100.0

(

~~-

0.0

. r., y,

,, 7,- -- - ' /

E l d...,i t

~

T r

t Y

't

.'a.

I 2

50.0 E. '...

h-1.0

i....

e i

E

(,' 'I',~..,'('?..

l E'

\\

0.0

- 2.0 O.0 20.0 0.0 20.0 Time (SGC)

Time (SOC)

Figure 2 Plant Response to FW Controller Failure (BOC9 to EOC9 STANDARD - HARD i

l BOTTOM BURN)

I l

N.2-14 Page 17

GFN-13 BROWNS FERRY UNTT 2 Jil-02761SRLR Reload 8 Rev.3 l

l 1

1 Neutron Flux Veneel Presa Ree (pel)

- - - Ave Surface Heat Flux

- - - - Safety Veno Flow 150.0

- -- Core Itht Flow 300.0 - --- Renef Veno Flow

--- Bypene Veno Fbw l

.s,.

30 g 100.0 200 g

e.,

E

\\. '..

y W

g i

50.0 M~~~..'-

100.0 l

/

I

)

\\

I O.0 O.0 0.0 3.0 6.0 0.0 3.0 M

Time (sec)

Levol(inch-REF-SEP-SKRT)

..... Veenei Steam Flow ReactNety

--- Turt#w Steam Flow 1.0 200.0

--- Feedwater Flow

--T Reactivity g

I 1

e

\\

g 100.0 g 0.0 a

a ?.N. %"...

. ~.

E l.

N%

\\

g I

l

,'Y-------------

e l

0.0 Q

- 1,0

\\\\

e 4

l

\\.

l(

\\l i'

-100.0

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

Time (sec)

Figure 3 Plant Response to Load Reject w/o Bypass (BOC9 to EOC9 STANDARD -

HARD BOTTOM BURN)

N.2-15 Page 18

=_

l BFN-13 BROWNS FERRY UNTT 2 Jil-02761SRLR Reload 8 Rev.3 l

i h

[\\

Neutron Aux VeseW Prus Ram (pel) l

- - - Ave surtece Heat Rux

- - - - safety veNe Row f

l 150.0 - --- core irst Row 125.0 - --- RWeef Veno Row

- -- Core inlet Subcoohng

--- Bypass VeNe Row

-).

j 3, p"' ~ ~ ~ _. -----

y',

75.0 g 100.0 E

5 C

h C

\\s

~

I 1

50.0 25.0

~'

I I

0.0

- 25.0 0.0 20.0 0.0 20.0 Time (sec) tme(sec) i v-l Level (inch-REF-SEP-SKRT)

Void ReactMay

{

..... Vened Steam Row

- - - - - Doppler Reecevny 150.0 - --- Turtaine steem Row 1.0 - --- serem Reecevny

}

--- - - Eeghgater 83.,

--- Total Reecevity G

w

,a l

.-:y.- g=,- f g 100.0

(

0.0

-w

-~~

E P.

P' E

$lt 1

t;.\\:.,,,

3 1

50.0

- 1.0 U..a..

l e

e..: x c

L.

h

\\

- 2.0 t

0.0 0.0 20.0 0.0 20.0 Time (sec)

Time (sec)

Figure 4 Plant Response to FW Controller Failure (BOC9 to EOC9 STANDARD -

HALING) l l

N.2-16 Page 19

I BFN-13 i

BROWNS FERRY USTr 2 J11-02761SRLR Reload 8 Rev.3 i

I l

l I

Neutron Fkrx Vessel Press Rise (psi) l

- - - Ave Surface Heat Flux

- - - - Safety Velve Flow l

150.0

- -- Core inlet Flow 300.0 - --- W Velve Flow

--- sypees ve#ve now

.\\,' ',

g 100.0

- \\

~

.f\\, ',

g 200.0 W

-" \\

W l

C Y'.

C Y

~

%.7~

l

.,,, ~.

50.0 100.0 r--------

I

\\

I

\\

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

Time (sec)

Level (inch-MEF-SEP-SKRT)

..... Vessel Steam Flow ReacNty i

200.0 - --- Turime steem now 1.0 Reecwey

--- Feedweser Flow

-- otal ReactMty G.-

~

\\

I g 100.0 0.0 g, }s,...

y 1.

,N.

g C

[.

i i

~

g g

i 0.0 h - 'r M A - - - - - - - - - - - - -

- 1.0

\\

ij

\\.

\\\\

-100.0

- 2.0 i

0.0 3.0 6.0 0.0 3.0 6.0 t

l Time (sec)

Time (sec) l l

r Figure 5 Plant Response to Load Reject w/o Bypass (BOC9 to EOC9 STANDARD -

HALING) t N.2-17 Page 20

B7N-13 BROWNS FERRY UbTT 2 Reload 8 111-02761SRLR Rev.3 l

l 4

\\

/

Vasel Press Rise (pei)

Neutmn Flux

- - - - - Ave Surface Heat Flux

- - - Safety Valve P.ow 150.0 - --- Core inlet Flow 125.0 - --- Reisef Valve Flow

- -- core Iret subcooing

--- Bypass Valve Flow

\\

i

,=

)

--q i

-.____ g-g 100.0 75.0

\\ g,i l

C Y

~

R.

C Y

~

50.0 25.0 F ~l ~~~""

I i

I

_a...

0.0 I

- 25.0 i

0.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void Reecevity

- - - - - Vessel Stearn Flow

- - - - - Doppier Reecevity 150.0

--- Turtme Steam Flow 1.0 - --- Scram Reecevity l

- m-v s-s EeeeneterSom..

--- Total Reecevity G

\\

] 100.0

}

0.0

- m.-r-,-,y

,g E

8' i

E

I g

r \\,,'..

0

.\\

b l

'E

\\

c*

I,',

E -1.0 50.0 l.*,,,,.

g l*.',..*

g.,,,.

I g,. /

l>.. (

\\

a S

0.0 l

- 2.0 I

O.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (sec)

Figure 6 Plant Response to FW Controller Failure (BOC9 to EOC9 FFWTR - HARD BOTTOM BURN) i i

N.2-18 Page 21

?

l

BFN-l3 BROWNS FERRY UbTT 2 J11-02761SRLR Reload 8 Rev. 3 Ave Surface Heat Flux

<f Neutron Flux Vessel Press Rise (pei)

- - - - Safety Velve Flow 150.0 - --- core Irkt Flow 125.0 - --- Re6ef Veive Flow

- -- core tret Subcochng

--- sypees Velve Flow

/.

.#./.

e, 7

s l

~

] 100.0

] 75.0 "eg C

Y N

E

\\

Y n

?

I

$0.0 25.0 F~D

.,o I

J l

0.0

- 25.0 I

0.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void ReactMty Vessel Steam Flow

- - - - Doppler ReactMiy 150.0 - --- Turbine Steam Flow 1.0 - --- Scram ReecevMy

--, - s.eew n men..

--- Toiel ReecevMy

\\

G.

l e

1 0.0 g 100.0 t,.

- e.

5

.c

)

r,,

~

i

.2:

I!

50.0 l'.;;j, j -1.0 a.

g

[ '. .

P, lU N

l i>-

l 0.0

- 2.0 I

O.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (sec) l Figure 7 Plant Response to FW Controller Failure (BOC9 to EOC9 FFWTR - HALING) i N.2-19 Page 22

~

BROWNS FERRY UNrr 2 11l-02761SRLR i

Reload 8 Rev.3 l

l l

Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux

~

125.0 - --- Relief Valve Flow

- - - Safety Veno Flow 150.0 * --- Core inlet Flow

- -- Core in6et Subcoadog

--- Bypass VaNo Flow a

-****'~~~

g 100 0 j

75.0 IN 2

.______________a f

I e

h, ct l

i N ',

~

j g

t

(

s-W' t

i 50.0 25.0 "Y

(

\\

i I

\\

'_.2..

1.

0.0

- 25.0 l

0.0 20.0 0.0 20.0 Time (54C)

Time (Sec) l i

Level (inch-REF-SEP-SKRT)

Void ReactMty

..... Vessel Smem FN

- - - - - Dopp6er ReactMty 150.0 - --- Turtin Steam Flow 1.0

--- Scram Reecevity

Essensterfler..

--- Total ReecevMy g

e y 100.0

( {

0.0

- v.+.=.v. =.g*,,

lii l

s

-w m

2

~

'll l

t.,

l E :.

50.0 F.,;,,l '

$ -i.0 Y

i e

l C......

E

\\

0.0

- 2.0 O.0 20.0 0.0 20.0 Time (seC)

Time (sec)

Figure 8 Plant Response to FW Controller Failure (BOC9 to EOC9 ELLLA - HARD BOTTOM BURN)

N.2-20 Page 23 I

8 BROWNS FERRY UNTT 2 J t 1.-02761SRLR Reload 8 Rev.3 Neutmn Flux Vessel Press Race (pea)

... AW Surface Heat Rux

-..-- W m now 150.0

- -- core iniet now 300.0 - -- - Reaiet m pw

--- eypees vow Row g

g 100.0 i'

200.0

/

~\\

E

\\ /\\,

E e

y _ %

s.

e 50.0

- :g %.

100.0 I

I j

\\

t 0.0 O.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (SOC)

Eme(SOC)

Lewi(inch-REF-SEP-SKRT)

- -... Vessed Steam Flow

r '

~ " M' 200.0 - --- Turtune Steam Row 1.0

--- Feedwater Flotv ReactMay a.

l CA g

yM w

l'.

g i ;,. _.'

N; '..' '..*'..

i l:

g I

(\\h L

4p a.'

0.0

- 1.0

.f v

1

\\.

g I

-100.0

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

Eme(sec) l Figure 9 Plant Response to Load Reject w/o Bypass (BOC9 to EOC9 ELLLA - HARD BOTTOM BURN)

N.2-21 Page 24 l

l

l BFS-13 BROWNS FERRY UNTT 2 J11-02761SRLR Reload 8 Rev.3 l

Neutron Rux

/

Vessel Press Rm (psi)

)

- - - - - Ave Surface Heat Flux

/

- - - - Safety Veive Flow 150.0

--- Core in6et Flow 125.0 - --- Relief Veive Flow

- - - core iniet subcoo66ng

- - - sypass velv. Fiow

,,,,,,,,,. s.

I i o l

-- - -- -'j b, ioo.o E, 75.o

}

_ _ _ _ _ _ _ _ _ _ _ __ _ _ It b,.

C C

~

l

., m I

A 25.0

'M.

50.0 l

\\

I l

0.0

- 25.0 O.0 20.0 0.0 20.0 Time (sec)

Time (sec) l 1

Levei0ncti-REF-SEP-SKRT)

Void ReeceMiy

..... v.eem siasm mow

- - - - - ooppier ReaciMty l

150.0 - --- Turbine Steam Flow 1.0 - --- Scram ReactMty

)

l

--- Eendnattef2m.

--- Total ReactMey 3,

ao g 100.0

(

0.0

., v re.

,t.-

- - ~ ~

5 U

l,'

( \\.

~

t E

s t

i l.t i

E..'

l

- 1.0 50.0 f.,,

C..*

>::o,' l,' 4\\.

\\

l

(' s q

f l

0.0

- 2.0 j

0.0 20.0 0.0 20.0 Time (sec)

Time (sec) l Figure 10 Plant Response to FW Controller Failure (BOC9 to EOC9 ELLLA - HALING)

N 2-22 Page 25 i

-I3 BROWNS FERRY UNIT 2 J11-0276 t SRLR Reload 8 R; s. 3

)

i Neutron Flux Vescel Press Rise (psi)

- - Ave Surface Heat Flux

- - - - - Safety V No Flow 150.0

- Core truet Fbw 300.0 - --- Relief Veno Flow

--- Bypass Veno Flow g 100.0

,t*

200.0 C

\\

Y

~

(.- g *.

C

\\,.,

Y 100.0 50.0 I

r------

I h

j I

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

Time (Sec) v Levei0nch-REF-SEP-SKRT)

V ReactMty

..... vesem smem Fio.

Rescuty 200.0 - --- Turtme Steam Flow 1.0 ReacWty

--- Feedwater Flow Tota! ReactNity c

0.0 g 100.0 w g.

l j.

,x

-.-s, f

I

\\

\\,

4p.9a;.------------.

y

,.0

\\g 0.0 e

1

\\\\

\\,

\\A

-100.0

- 2.0 1

0.0 3.0 6.0 0.0 3.0 6.0 I

Time (sec)

Time (sec) i Figure 11 Plant Response to Load Reject w/o Bypass (BOC9 to EOC9 ELLLA - HALING)

N.2-23 Page 26

BM heTa S FERRY UNTT 2 J11-02761SRLR Rev.3 Neutron Rux Vessel Press Rise (psi)

Ave Surface Heat Rux

- - - -

Safety Valve Flow 150.0

--- Core irnet Flow p.W 125.0 - --- Renef Valve Flow

- -- Core trnet Summ%ng

--- Bypass Valve Flow

/

~~~'~~

100.0 E

75.0 N

w

._ _ _ __ _ _ _ _ _ _ _ _ _ _ sl E

l a

C

\\g,.

m l

g at T ',

at I

I s ',

l I

'e f

50.0 25.0 F ~l

l I

i I

- a....

0.0

- 25.0 I

i O.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (;<x:)

Level (inch-REF-SEP-SKRT)

Voed ReactMty

- - - Vessel Steam Row

-. - -. Doppier Reactrvely 150.0

--- Turtine Steam Row 1.0 - --- Scram Reecevtty

}

- seemmuama..

--- Tom Reecovny

\\

g

\\

7 100.0 3}

- e.-...-- f,{ '.'

0.0

=

lii e

r:s\\

e

+

i,.

't ne 1 . ' '

\\

l':.

I

] -i.0 d

50.0 l.,.: '..' : l.. &

i l'.'.,

1 l ',' ' A j

\\

i..

r.: I

\\

- 2.0 I

0.0 0.0 9.0 18.0 0.0 9.0 18.0 Time (sec)

Time (sec) l Figure 12 Plant Response to FW Controller Failure (BOC9 to EOC9 ELLLA-FFWTR -

HARD BOTTOM BURN)

N.2-24 Page 27

B* U BROWNS FERRY UNIT 2 Jl1-0276iSRLR l

Reload 8 Rev.3 i

Neutron Flux Vessel Press Rise (pai)

* - - Ave Surface Heat Flux

- - - Safety Velve Row 150 0 - --- core wet Row,

.J 125.0 - - _ _ Row,veveRow

- -- core w.t sacciang

--- syp.e veve Row

~ ~ ' '

- M *******

100.0 e 75.0 C

k.

g Y

~

\\s y

r-l 50.0 25.0 F ~ "I"'"

a I

?

I 0.0 I

25.0 0.0 9.C 18.0 0.0 9.0 18 0

)

l Time (SOC)

Eme (SOC) l l

l Leve4(~WEF-SEP-SKRT)

Void ReactMty

.. - - Vessel Steam Row

-... - Doppier Reecevity 150.0 - --- Turtune Steam Row 1.0 - --- Scram ReactMiy

}

.- c= - seeenew sion..

--- Tom Reecevity G

l

'{

i

\\

a 1

g

- - esw--

,-- -- y,{

0.0 g 100.0 h*

3 1 g{

'c'.

\\.

l 1

p '. \\

)

~

l k

50.0 E ,,'.,d

- 1.0 p;, i. ',' \\

l e

i.

l l:,'.,

l N

i t

0.0

-10 O.0 9.0 18.0 0.0 9.0 18.0 Time (SOC)

Time (SOC)

Figure 13 Plant Response to FW Controller Failure (BOC9 to EOC9 ELLLA-FFWTR -

HALING)

N.2-25 Page 28

BROWNS FERRY UNIT 2 Reload 8 J11-02761SRLR Rev.3 l

2 6

10 14 18 22 26 30 34 38 42 46 50 54 58 I

59 55 0

0 51 38 0

38 47 12 0

0 12 43 0

39 12 0

16 16 0

12 35 38 0-38 31 0

16 0

0 16 0

27 38 0

38 23 12 0

16 16 0

12 19 0

15 12 0

0 12 11 38 0

38 7

0 0

3 Notes: 1. Number indicates number of nou:hes withdrawn out of 48. Blank is a fully withdrawn rod.

2. Error rod is (l8,39).

Figure 14 Limiting Rod Pattern i

l N.2-26 Page 29

IIllllt!:

!lJ; I

I.,

l.ll,

't l

,l(illl Il!

lll lIl!

+

3t Cgy a C.

RB t

eR 1

1 2

1 1

l 0

0 0

5 0

5 oO 0

o.

0 0

adW 0

o 0

0 0

8N 0

S F

E R

1 i

',,' W,,,,

R

.FTvL CA Y

F s

i g

umo(

ov v

r e U

mi e4 e

gu n

b sW e

T nu r

e T

ir T

ef e,s ow E

i w

m Fe l

T aF t

m c

u 2

n l

5 e 4 1

~

x e

.4 owH

( 0 I

N

(

0 w n n F-e P

s s

o wS e

s a

o l

e t

a c

w E

c N.-

P ulF

)

n

)

s,-

x t

S R

K e

R L-s T

)

p o

B n

N F

s N

e

.w N

1 to 3

2 8

8 M

0 0

2 7

S 2g 5 g ;;

R E.

3 I

V 1

2 3

0 0

1 0

0 0

0 C

2 0

0 1

0 0

l 0

0 o

0 0

su n

(F l

u x

Ts@oi y eae V

BRSV e

S s

r p

l ef s i

s e

d

'III aet c

N

\\'

m R

s fy ei r

ig R

e T

VaV P e

s V a

T eee m

l ar eRc l

e i

m m

. %,\\ g i

avl ev v

e s e 4 e cn e4 I

eF s

\\

cev l F

)

v ey 0

Fol R J

0

(

H v s

ow oa l

w e 1

1 s

y H y

e e

c w

c

)

p(

0 P

)

i 2

e a

)

g 7

e 6

3 1

0 RS eR vL 3R 8

8 0

0 ll 11jI!;

I1

,l l

i BROWNS FERRY UNIT 2 j

Reload 8 111-0276tSRLR Rev.3 l

4 j

Appendix A j

Analysis Conditions l

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

1 i

Table A-1 a

?

1 STANDARD-HARD BOTTOM BURN Parameter Analysis Value Thermal power, MWt 3293.0

+

Core flow, Mlb/hr 107.6 Reactor pressure, psia 1036.0 Inlet enthalpy, BTU /lb 522.9

,i j

Non-fuel power fraction 0.038 j.

Steam flow analysis, Mlb/hr 13.39 Dome pmssure, psig 1005.0 Turbine pressure, psig

% 2.9 Number of Safety / Relief Valves (Analysis assumes one 13 S/RV is out-of-service, or 12 values in-service) b Relief mode lowest setpoint, psig 1138.2

}

Safety mode lowest setpoint, psig i,

j STANDARD-HALING j

Parameter Analysis Value

'Ihermal power, MWt 3293.0 1

Core flow, Mlb/hr 107.6 Reactor pressure, psia 1036.0 j

Inlet enthalpy, BTU /lb 522.9 j

Non-fuel power fraction 0.038 l

Steam flow analysis, Mlb/hr 13.39 Dcme pressure, psig 1005.0

]

'Ibrbine pressure, psig

%2.9 1

Number of Saicey/ Relief Valves (Analysis assumes one 13 j

S/RV is out-of-serdce, or 12 values in-service)

Relief mode lowest setpoint, psig i138.2 Safety mode lowest setpoint, peg i

E N.2-28

l

~-

- - - - - - ~

'i BFN-13 BROWNS FERRY UNTT 2 Jl1-02761SRLR Reload 8 Rev.3 FFWTR-HARD BOTTOM BURN Parameter Analysis Value l

Thermal power, MWt 3293.0 Core flow, Mlb/hr 107.6 Reactor pressure, psia 1029.0 Inlet enthalpy, BTU /lb 517.5 l

Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.65 l

Dome pressure, psig 998.0 Turbine pressure, psig 960.2 Number of Safety / Relief Valves (Analysis assumes one 13 l

S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpoint, psig 1138.2 Safety mode lowest setpoint, psig FFWTR-HALING l

Parameter Analysis Value l

Thermal power, MWt 3293.0 Core flow, Mlb/hr 107.6 Reactor pressure, psia 1029.0 Inletenthalpy BTU /lb 517.5 Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.65 Dome pressure, psig 998.0 hrbine pressure, psig 960.2 Number of Safety / Relief Valves (Analysis assumes one 13 S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpoint, psig 1138.2 Safety mode lowest setpoint, psig l

l i

N.2-29 Page 32

l l

BKOWNS FERRY UNIT 2 0 -

Reload 8 Jl1-02761SRLR t

Rev.3 l

l ELLLA - HARD BOTTOM BURN Parameter Analysis Value Thermal power, MWt 3293.0 Core flow, Mint 89.2 Reactor pressure, psia 1032.6 Inlet enthalpy, BTU /lb 517.7 Non-fuel power fraction 0.038 Steam flow analysis. MIMr 13.37 Dome pressure, psig 1005.0 Turbine pressure, psig

% 3.0 Number of Safety / Relief Valves (Analysis assumes one 13 S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpoint, psig 1138.2 Safety mode lowest setpoint, psig l

ELLLA - HALING Parameter Analysis Value Thermal power MWt 3293.0 Core flow, MIMr 89.2 Reactor pressure, psia 1032.6 Inlet enthalpy, BTU /lb 517.7 Non-fuel power fraction 0.038 i

Steam flow analysis, MIMr 13.37 Dome pressure, psig 1005.0 Turbine pressure, psig

%3.0 Number of Safety / Relief Valves (Analysis assumes one 13 S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpoint, psig 1138.2 Safety mode lowest setpoint, psig l

l N.2-30 Page 33

- BrN-l.3 BROWNS FERRY UNTI 2 111-02761SRLR Reload 8 Rev. 3 l

i EI I.I 4-FFWTR-HARD BOTTOM BURN i

Parameter Analysis Value Thermal power, MWt 3293.0

{

Core flow, Mlb/hr 89.2 l

Reactor pressure, psia 1025.6 Inlet enthalpy, BTU /lb 511.5

)

Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.63 i

Dome pressure, psig 998.0 Tuttine pressure, psig 960.3 Number of Safety /Relbf Valves (Analysis assumes one 13 l

S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpoint, psig 1138.2 Safety mode lowest setpoint, psig

)

i RI.I.I.A-FFWTR - HALING i

l Parameter Analysis Value j

Thermal power, MWt 3293.0 v

l Core flow, Mlb/hr 89.2 2

Reactor pressure, psia 1025.6 i.

Inlet enthalpy, BTU /lb 511.5 Non-fuel power fraction 0.038 i

j*

Steam flow analysis, Mlb/br 12.63 4

i-Dome pressure, psig 998.0 t

1brbine pressure, psig 960.3 Number of Safety / Relief Valves (Analysis assumes one 13 l-S/RV is out-of-service, or 12 values in-service)

Relief mode lowest setpost, psig i133.2 t-Safety mode lowest setpoint, psig ei-i i

i -

4 N,2-31 Page 34 4

e w

n-,--.-

a-n n

g

.. -. =.. -.

i BROWNS FERRY UNIT 2 BFN-13 t

Reload 8 111-02761SRLR Rev. 3 J

}

Appendix B j

Alternate Analyses for Feedwater

]

Temperature Reduction 4

,i To provide for improved operating flexibility and cycle extension for Cycle 9, expanded operating domain i

analyses were priormed forincreased core flow (ICF) at 105% rated and intermittent use of final feedwater temperature reduetion (FFWTR) to a temperature (at full power) of 330*F. The analyses for cycle extension I

withICFwere performed at the EOC96 exposure point achieved with ICF using appropriate thermal hydrau-1 j

lic conditions. The analyses for cycle extension with ICFand FFWTR were performed at the extended EOC9 j

(EEOC)7 exposure point echieved with ICF and FFWTR using appropriate thermal hydraulic conditions.

i For cycle extension operation with ICFand FFWTR, the transient MCPR values are given in Section 11. The MCPR operstmg limits for ODYN option A will be fuel dependent and are 1.35 (gel 1),1.33 (GE8x8NB), l and 1.31 (BP8x8R) and for ODYN Option B they are 1.32 (GE11),1.30 (GE8x8NB), and 1.27 (BP8x8R These limits are applicable for the exposure range BOC8 throught EEOC8 The analyses for ICF and FFWTR l

bound the intermittent concurrent use of FFWTR from BOC to the EEOC operation with ICF and FFWTR.

i i

4 4

4 i

i

6. EOC is the assumsd reload cycle cose average esposure used for lxeasing the scanaal Cycle 9 and is specs 6ed la Section 3.

7. EEOC idsmones t'ie resed pcmr operance poest an==ahle using ICF and FPWTR. For Cycle 9, the EBOC exposure = 25527 Mwd /MT.

8. Based on a enfer;luun of 1.o9.

N.2-32 Page 35

. _ = _. _ _. _ _ _ _ _. _.. ~... _ _... _ _. _.

f 1

ENCLOOURE 5 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 i

ENGINEERING JUSTIFICATION i

i k

i

}

l 1

ML20132B769

Text

Response

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