ML20062H649

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Rev 0 to Supplemental Reload Licensing Submittal for River Bend Station Reload 3 Cycle 4
ML20062H649
Person / Time
Site: River Bend Entergy icon.png
Issue date: 05/31/1990
From: Albertson D, Charnley J
GENERAL ELECTRIC CO.
To:
Shared Package
ML20062H643 List:
References
23A6503, 23A6503-R, 23A6503-R00, NUDOCS 9012050207
Download: ML20062H649 (19)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _

23A6503 Revision 0 Class I May 1990

~

23A6503, Rev. 0 Supplemental Reload Licensing Submittal for River Bend Station Reload 3 Cycle 4

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Approved:

k e2M Approv d: '

a ley, Man D.

Ibertson, Manager el Licensing Rel lear Engineering ory r

c. c 9

I GENuclearEnemy l75 Curtner Annye San Jose. CA 95125 lE

d River Bend mm Reload 3 Ro 0 Important Notice Regarding Contents of This Report Please Read Carefully a

w This report was prepared by General Electric Company (GE) solely for Gulf States Utilities Company (GSU) for GSU's use with the U. S. Nuclear Regulatory Commission (USNRC) for 3

amending GSU's operating license of the River Bend Station. The information contained in this report is believed by GE to be an accurate and true representation of the facts known obtained or provided to GE at the time this report was prepared.

4 3

The only undertakings of GE respecting information in this document are contained in the contract between OSU and GE fu fuel bundle fabrication and related services for River Bend Station and nothing contained in this document shall be construed as changing said contract. The use of this information, except as defined by said contract, by anyone other than GSU for any purpose other than that for which it is intended, is not authorized; and with respect to any

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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 3

infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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Page 2 o

River Bend anco3 Reinad 3 Rev o Acknowledgment The engineering and reload licensing analyses which form the technical basis of this Supple-mental Reload Licensing Submittal, were performed by P. K. Wu of Fuel Engineering. The Supplemental Reload Licensing Submittal was prepared by P. A. Lambert and verified by R. T.

Hill of Regulatory and Analysis Services.

Page 3

River B:nd 2aco3 Reload 3 Rev.0 1.

Plant unique Items (1.0)*

Appendix A:

. Analysis Conditions 1

Appendix B:

Basis for Analysis of Lass-of feedwater Heater Event 1

2.

Reload Fuel Bundles (1.0 and 2.0)

Fuel Tme Cvele Loaded Number 1rradiated:

BP8 SRB 278 1

12 BP8 SRB 248 1

24 Y

BP8 SRB 248 1

24 BP8 SRB 305 2

52 BP8SIG299 2

112 BS322C 3

96

')

{i BS322B 3

128 i

New:

GE8B P8 SOB 331-110Z 120M-4WR 150 T 4

16

- GE8B P8SQB33310GZ 120M 4WR-150 T 4

1(

- Total.

624

[.ol

. +Y 3.

Reference Core Imding Pattern (3.2.1)

Nominal previous cyc' core average exposure at end of cycle:

20,652 mwd /MT -

< Minimum previous cycle core average exposure at end of cycle from co!d shutdown considerations:

20,211 mwd /MT i)

Assumed reload cycle core average exposure et end of cycle:

22,655 mwd /MT Core loading pattern:

Figure 1 o

i b-i

  • ( ) refers to area of discussion in General Electric Standard Application for Reactor Fuel, NEDE 24011 P A 9, September 1988;- a letter "S" preceding the number refers to the U.S. Sup-plement, NEDE 240ll P-A 9 US, September 1988.

l l

L, Page 4 r

)

. River Bend.

zwse i

Reload 3 Rev.0 4.

Calculated Core Effective Multiplication and Control System Worth No Volds,20*C (3.2.4.1 and 3.2.4.2)

.,y

. Beginnirig.' ycle, K, Uncontrolled -

1.123 i

Fully controlled 0.954

)

Strongest control rod out 0.986 R, Maximum increase in cold core reactivity with exposure Into cycle, AK.

0.003 5.

Standby Liquid Control System Shutdown Capability (3.2.4.3)

Boron Shutdown Margin (AK)

(pp.m)

(20'C. Xenon Free) 660 0.027 6.

Reload Unique Anticipated Operational Occurrem (AOO) Analysis Input (3.2.3 and i

43.1.2.2) i

>-y b

. Values normally reported in this secticn are REDY inputs. Th ere were no transients analyzed l

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. using REDY, i-b; ;j; T

7.

RelaN Unlque GETAB AOO Analysis initial Condition Parameters (S.2.3) k,\\

N Exposure range: BOC4 to EOC4

,:4 N'

Fuel

_. Pettine Factors Bundle Power. Bundle Flow Initial ll "'

Desism Lordu Radial Asia!

' R. Factor _JMWt)

(L000 lb/hr)

MCPR GE8x8EB 1.20-1.55 1.40 1.051 7.025 106.5

'1;13 i

!;;.k BP6xsii-1.20 1.55 1.40 1.051 7.034-106.4

1.13 ' '

H%

o l.

H s

y' F

p Page5 l

,I i

. River Bend zwem y

. Reload 3 Rev.0 8.

Selected Margin Improvement Options (S.5.1) j Recirculation pump trip:

Yes t

Rod withdrawallimiter:

Yes Thermal power monitor:

Yes Improved scram time:

No y'

Exposure dependent limits:

No Exposure points analyzed:

1 (EOC) 9.

Operating Flexibility Options (S.5.2)

Single loop operation:

Yes y

Load line limit:

No 1-l Extended load line limit:

No j

Increased core flow:

No

^'

Flow point analyzed:

N/A Feedwater temperature reduction:

No Feedwater heaters out of service:

Yes i

wv ARTS Program:

No

' Maximum extended operating domain:

No i

2 5

y

10. Core wide AOO Analysis Results (S.2.2).

LJ bi l

Methods used:: GEMINI and GEXL PLUS

- D L

Flux O/A-ACPR t

'(% NBR).

(fcEE.8)-

GE8x82 BP8x8R Figure

' Event

. BOC4 to EOC4

-(

Expon unnge:

K Pressure regulator :

'145-104-0.04 0.04-2 g.

failure downscale.-

[

i Load rejection without 300 108 0.06 0.06 3

w y j R; bypass -

)'y.fy 1-Feedwater controller.

.216~

107 0.05 0.05 4

pf failure '

q

.g,'

M Loss of feedwater.

0.11 0.11

' 4 heating.

,u

.[

'See Appendix B U,

t!(>

9 Page 6 -

f L;-

+

7 n.

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River Bend mm

~O Egload 3 Rev 0 11 local Rod Withdrawal Error (With Limiting 1nstrument Failure) AOO Summary (S.2.2.1.5)

O --

The generic bounding BWR/6 rod withdrawal error analysis described in NEDE 24011 P A 9.US is applied; the resulting ACPR is 0.11.

l l

l

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12. Cycle MCPR Values (43.1 and S.2.2)*

Safety limit: 1.07 Exposure range: BOC4 to EOC4

'O Non.nressurization events:

GE8X8EB BPJX&B Loss of 100'F feedwater heating 1.18 1.18

.O-Rod withdrawal error 1.18 1.18 Pressurization events:

GE8X8EB BP8h*8R

-O Pressure regulator failure downscale 1.12 1.11 Load rejection without bypass 1.14 1.14 Feedwater controller failure 1.13 1.13 O

J i,

13. - Overpressurization Analy:Is Summary (SJ) -

Pd Pv i

Event f,ps,ig)

{pjg)

Plant Resnonse

.0; MSIV closure 1211 1254 Figure 5 (tlux scram) i O

1

  • GEMINI ODYN adjustment factors are provided in the letter from J. S. Charn ey (GE) to M. W.

i Hodges (NRC), GEMINI ODYNAdjturment Factorsfor BWR/6, dated July 6,1987. The limiting transients for River Bend Station, Cycle 4, are rod withdrawal error and loss of 100'F feedwater-O-

heating.

Page 7 O-

=

O

-River Bend m oo3 Reload 3 Rev.0 4

l 14.

Imading Error Results (S.2.2.3.7) l Os Lording error results are not applicable to BWR/6 plants. NRC approval of the non applicability of loading errors to BWR/6 plants is documented in Section S.2.2.3.6 ;f NEDE 24011 P A 9 US.

l Q;

.15.

Contml Rod Dmp Analysis Results (S.2.2.3.1)

River Bend Station is a banked position withdrawal sequence plant, therefore, the control w

rod drop accident analysis is not required. NRC approval is documented in u

NEDE 24011-P A 9 US, September 1988.

16.

Stability Analysis Results (S.4)

O '

GE SIL 380 recommendations have been included in the River Bend Station operating -

procedures and Technical Specifications; therefore. :b stability analysis is not required.

NRC ' approval for deletion of a cycle specific stability analysis is documented in -

NEDE-24011 P A 9 US. River Bend Station recognizes the issuance of NRC Bulletin No.

,O' 88 07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), and will comply i

with the recommendations contained therein.

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Page 8 loc

c:

River Bend.

u r63o3 i,

Reload 3 Rev.0 17.

14ss of coolant Accident Results (S.2.2.3.2)*

LOCA method used:

SAFE /REFLOOD (see River Bend Station Final Safety g

Analysis Report)"

Bundle Type: OE8B P8SQB33310GZ 120M 4WR 150 T MAPLHOR (kW/ft) 0:

Average Planar Exmsure Most Least Oxidation (GWd/ST) = (gwc /M*ll Limiting Limiting PCT ('FT

. Fractinn 0.0 0.0 11.29 11.80 0.2 0.2 1135 11.84 1960 0.042 0-1.0 1.1 11.48 11.95 1971 0.041 1

2.0 2.2 11.67 12.12 3.0 3.3 11.87 12.28 4.0 4.4 12.07 12.45 O

5.0 5.5 12.29 12.64' 2036 0.044 1.

6.0 6.6 12.53 12.79 n

7.0 7.7 12.71 12.92 2

8.0 8.8 12.87 13.05 2088 0.052 i

?O t-9.0 9.9 13.02 13.17 10.0 11.0 13.15 13.27 2123 0.058 3

12.5 13.8' 13.19 13.22 2127 0.059 -

15.0 16.5 12.90 12.92 2086 0.051

'O, 20.0 22.0 12.29 12.31 2011 0.040 25.0-27.6 11.69 11.70 1944 0.032:

35.0 38.6 10.44 10.46 1806 0.017 45.0 49.6

8.98 -

9.07 1673 0.005 O'

50.0 55.1 6.45 6.55 1604 0.003

'For format explanction, see letter, J. S. Charnley (GE) to M. W. Hodge-(NRC),

Recommended MAPLl:GR Technical Specificattom for Multiple Lattice Fuel Designs, March 9, 1987. Most Limiting and Least Limiting refer to the lowest and highest limits, respectively, of any enriched lattice m the bundle.

"As madified by GE Report EAS 66-1088, ECCS Evaluation for ?O Second Diesel Generator Start

!O?

Timesfor River Bend Station, (R. U. Fortney and J. L Jacobs), August 1989.

Page 9

< River Bend 2 m so3 0

neio.a 3 m,. 9 27 Imss of coolant Accident Results (S.2.2.3.2)*(continued)

O" Bundle Type: GE8B P8 SOB 331110Z-120M 4WR 150 T MAPLHGR (kW/ft)

Average Phnar Ex:>osure Most Least Oxidation (GWd/ST) (GWd/MT)

LimitinF Limiting PCI' (' F)

_ Fraction -

.0 0.0 0.0 11.16 11.61-0.2 0.2 11.23 11.67 1894 0.032 1.0 1.1 11.36 11.79 1907 0.032 2.0 2.2 11.52 11.94

.i 3.0 3.3 11.71 12.10 4.0 4.4 11.89-12.26 5.0 5.5 12.08 12.42 1995 0.042 6.0' 6.6 12.26 12.58 OL 7.0 7.7 12.45

-12.74 8.0 8.8 12.62 12.88 2056 0.046 9.0 9.9 12.78 13.00 10.0 11.0 12.93 13.10 2099 0.054

.L ID, 12.5 13.8 12.96

.13.02 2099 0.054 15.0 16.5 12.70-12.71 2059 0.047 20.0 22.0 12.08.

12.09 1981 0.036 25.0 -

27.6-11.46 -

11.47 1911 0.028 bI 35.0 38.6

.10.19 10.21 1778 0.014 m

45.0 49.6 8.45 8.57 1659-0.004

'50.0 55.1 5.95 6.07 1603 0.003' d

e O-w i

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  • For' format explanation, see letter, J. S. Charnley (GE) to M. W. Hodge (NRC),

n Recommended MAPLHGR Technicd Specifications for Multiple k.: ice Fuel Designs, March 9,.

3 1987. Most Limiting and Least Li Mg refer to the lowest and highest limits, respectively, of g

. any enriched lattice in the bundIc.

Page 10

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6

O River Bend 2 woo 3 Reland 3 Rev 0 i

56

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JEMMMMMMo oMEMMMMMEL oMMMMMMMMMMMo O

H M M M M M M M M M M M M.

i'- o M M M M M M M M M M M M M o i;:!M M M M M M M M M M M M ME

!!: E M M M M M M M M M M M M M E

:iH M M M M M M M M M M M ME O

i'-" M M M M M M M M M M M M M "

MMMMMMMMMMMMM c

"MMMMMMMMMMH" "MMMMMMMMM" I

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l I I I I l-1 I 1 3 5 7 91113151719212325272931333537394143454749515355 O:

l FUEL TYPE A = BS3228 F = BP85RB278 B = BS322C G = BP85RB248 LO.

C = GE88 P8SQB333-10GZ-120M-4WR-150-T H = BP8 SRB 299 D = GE88-P850B331-llGZ-120M-4WR-150-T I = BP85RB305 E = BP8 SRB 248 Figure 1 Reference Core leading Pattern

,O; Page 11

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4 3-River Bend mem Reland 3 Bar 9 D

jpyg=

!)

g F""

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~

t r,... M a

j

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A s

a

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=:

4.

Ian (MCabes).

Ills (EM)

.1,,

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1 i

eviiv 3

IN!I?"

4 LDW 4

QTAL ttV!TY 3

3 r

(',

~

i ee m,.

s.e

> ii; i.

-n. =

s

+%..

s..

tia (somes).

tia (scoes).

i'.

-2 i

Figure 2 Plant Response to Pressure Regulator Failure Downscale (BOC4 to EOC4) -

,1 J:

Pap 12 l,0-

T River Bend 2ncos 1

v. --

yp,i 3 n,y o

),

!?

SYM "*

$El[T' k.

I,..... ArN

=

.Y, m

\\

~

c 1

f

\\

w.

..w.=== =

8.; -

=

..i :

= q.

tid (straes) tis cucmas) f

!Ed<i@...

1, f\\ /

\\IM,e,,,,in" /

~

V

(

j 1[...

[

A, ~,,

. x.-

N v.

1....

~

v y~

\\

s..

tis <xcess) tin <scoes) k

. Figure 3 Plant Response to Generator Imad Rejection Without Bypass (BOC4 to EOC4) i.

r Page 13

  • IJ

River Bend -

mm 2

R'-'3 Rev. 0 v

(

f f,.;

~

N

^

Tin (EC985)

IlE (ECOSS) 7.sar) l voi

,-g;p

=

i i

}

r m1 l d 9

I

\\,h

)

j 3

l i...

I

/

i

-...d..

u aa Tid (EESM)

Ild (SESM) w Figure 4 Plant Response to Feedwater Controller Failure (BOC4 to EOC4)

==

Page 14

)

-.......2 River Bend uuse Reland 3 Rev 0 rtT' "

i 4

ASS vat V! Flow g,,

~

t-I N

e.a.,

s.e

..q '.s Y

s.e '

m 1:a (Ecmes) tia (scoes) g(-g -EP- *RT)

/

1vooqAgg MdW*

l le ;%Ml4 s

^

A r

,/

.e es WN-

_ la

[.

~

=

k

~4..

+s..

..e tia (stsees) tia (scess)

)

4 Figure 5 Plant Response to MSIV Closure, Fit:x Scram m

Page 15

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38 River Bend m ssoa Reload 3 Rev.o Appendix A D

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

Table A 1 h:

Parameter Analysis Value Thermal power, MWt 2894 Dome pressure, psig 1025 Q

Rated steam flow, Mlb/hr 12.45

. Turbine pressure, psig 986 Core flow, Mlb/hr.

84.5 Reactor pressure, psia 1055 l Inlet enthalpy, BTU /lb 527.9 Non fuel power fraction.

0.038 9

No. of Dual Mode Safety / Relief Valves -

16

. Relief mode low setpoint, psig 1133 Safety mode low setpoint, psig 1177 Capacity,~ Ib/hr -

869,000

- (Ref, pressure, psig)

(1130)_

Page 16

e

):. - '-

River Beid zum Eglead 3 Rev.0 Appendix B

).

1 Basis for Analysis of Loss of feedwater Heater Event The loss of feedwater heating event was analyzed with the 3D BWR simulator code J

3-described in NEDE 24011 P 9 US. The transient analysis inputs normally reported in Section 6 of the licensing submittal are ir:'ernally calculated in the 3D BWR simulator code and in ODYN. He transient plots, flux, and O/A normally reported in Section 10 are not outputs of the 3D BWR simulator code; therefore, these items are not included in this document. This event was analyzed

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at an initial power of 102% of rated.

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