ML20236V777

Rev 1 to 24A5180, Supplemental Reload Licensing Rept for LaSalle County Station Unit 1 Reload 7 Cycle 8

ML20236V777
Person / Time
Site:	LaSalle
Issue date:	05/31/1998
From:	Hetzel W, Watford G GENERAL ELECTRIC CO.
To:
Shared Package
ML20236V767	List: ML20236V766 ML20236V770 ML20236V777
References
24A5180, 24A5180-R01, 24A5180-R1, NUDOCS 9808040201
Download: ML20236V777 (37)

Text

I

[\ l

\

)

GENuclearEnemy 24A5180 l Revision 1 Class I  !

May 1998 .

I 24A5180,Rev. I Supplemental Reload Licensing Report for LaSalle County Station Unit 1 Reload 7 Cycle 8 I

l l

Approved Approved k G. A. atford, Manager W. H. Hetzel bM Nuclear Fuel Engineering Fuel Project Manager l

t 9809040201 980728 i PDR ADOCK 05000373 ,

p PDR

I i

i Important Notice Regarding Contents of This Report Please Read Carefully i

! This report was prepared by General Electnc Company (GE) solely for Commonwealth Edison Company (Comed) for Comed's use with the U.S. Nuclear Regulatory Commission (USNRC) l for amending Comed's operating license of the LaSalle County Station Unit 1. The infonnation l '

contained in this report is believed by GE to be an accurate and true representation of the facts known, obtamed or provided to GE at the time this report was prepared.

'Ihe only undertakings of GE respecting information in this document are contained in the con-tract between Commonwealth Edison Company and GE for nuclear fuel and related services for the nuclear system forLaSalle County Station Unit I and nothing contained in this document shall be construed as changing said contract. 'Ihe use of this information except as defined by said con- I l

tract, or for any purpose other than that for which it is intended, is not authodzed; and with respect to any such unauthonzed use, neither GE nor any of the contributors to this document makes any rensentation or warranty (expressed orimplied) as to the completeness, accuracy or usefulness ofi :information contained in this document or that such use of such information may not in-

) fringe privately owned rights; nordo they assume any responsibility forliability or damage of any I

kind which may result from such use of such infonnation.

I i

l l

l l

[

Page 2 i

l i

AcknSwiedgement I l

l The engineering and reload licensing analyses, which fonn the technical basis of this Supplemental Reload Licensing Report, were perfonned by A. F. Alzaben and F. T. Bolger. The Supplemental Reload Licensing -

I Report Rev 1 was prepared by F. T. Bolger. This do Fuel Engineering.

l I

l I

i I

Page 3 l

The basis for this repon is GeneralElectric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-11, November 1995; and the U.S. Supplement. NEDE-24011-P-A-11-US, November 1995. j

1. Plant-unique Items Appendix A: Analysis Conditions j

E Appendix B: Impact of Change to the APRM Fluy Scram Setpoint

2. Reload Fuel Bundles ,

Cycle Fuel Type Loaded Number l IIIndiated. I GE9B-P8CWB303-9GL100M-150-T (GE8x8NB) 5 108 i GE9B-P8CWB 313-9GZ-100M-150-T (GE8x8NB) 6 128 I GE9B-P8CWB314-9GZ-100M-150-T (GE8x8NB) 6 72 GE9B-P8CWB 322-1 IGZ-100M-150-T (GE8x8NB) 7 104 GE9B-P8CWB 320-9GZ3-100M-150-T (GE8 x8NB) 7 104 Ncm GE9B-P8CWB 342-1 OGZ-80M-150-T (GE8x8NB) 8 144 GE9B-P8CWB343-12GZ-80M-150-T (GE8x8NB) 8 104 Tbtal 764

3. Reference Core Loading Pattern Nominal previous cycle core average expon.- 2 end of cycle: This information will be provided by Comed Minimum previous cycle core average exposure at end of cycle This information will be from cold shutdown considerations: pmvided by Comed j Assumed 2eload cycle core average exposure at beginning of 15680 mwd /MT l cycle:

( 14225 mwd /ST)

Assumed reload cycle core average exposure at end of cycle: 27365 mwd /MT

( 24825 mwd /ST)

Reference core loading pattem: Figure 1 I

Page 4 i

i E_________________._

4. Calculated Core Effective Multiplication and Control Syst::m W:rth - No Voids,20 C This infonnation will be provided by Comed.

l L

5. Standby Liquid Control System Shutdown Capabil:ty I

This infonnation will be provided by Comed.

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 12 Exposure: BOC8 to EOC8ICF Peaking Factors  ;

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

( M W t) (1000lb/hr) l l GE8x8NB 1.20 1.65 1.40 1.000 7.021 112.8 1.27 l Exposure: BOC8 to EOC8 ICF & FFWTR Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000lb/hr)

GE8x8NB 1.20 1.70 1.40 1.000 7.220 111.0 1.25 Exposure: BOC8 to EOC8 ICF and RPT Out-of-Service Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000lb/hr)

GE8x8NB 1.20 1.60 1.40 1.000 6.824 114.3 1.31 Exposure: BOC8 to EOC8 ICF and 'Ibrbine Bypass Valves Out-of-Service Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR l (MWt) (1000lb/hr) l GE8x8NB 1.20 1.61 1.40 1.000 6.837 114.2 1.31

1. To prcmde LaSaue County Stanon Urus I wnh operaung anymm. -.;.. en merossed core now up to 105% analysis was performed.

I

2. Analyses were performed for operauon wuh a reduccan m the feedwater temperature to 320 *F. l Page 5 l

I

Exposure: BOC8 to EOC8 ICF & FFWTR and Thrbine Bypass Valves Out-of-Service l Peaking Factors Fuel Bundle Bundle Initial I7.

Design GE8x8NB Local 1.20 Radial 1.65 Selected Margin Improvement Options Axial 1.40 R-Factor 1.000 Power (14WI) fi.992 (1000lb/hr)

Flow 112.7 MCPR 1.30 l

Recirculation pump trip

Yes l Rod withdrawallimiter: No Thermalpowermonitor: Yes improved scram time: Yes (ODYN Option B)

Measured scram time: No l

Exposure dependent limits: No Exposure points analyzed: 1 (EOC)

8. Operating Flexibility Options Single-loop operation: Yes l Imad lire limit: No i Extended load line limit: Yes Maximum extended load linelimit: No

increased core flow thmughout cycle

Yes I

! Flow point analyzed: 105.0 %

increased core flow at EOC: Yes Feedwater temperature reduction throughout cycle: Yes

Temperature reduction

100.0 F l

l Final feedwater temperature reduction: Yes ARTS Program: No

! age 6 l

1

APRM Setdown Requirement Elimination Yes3 Maximum extended operating domain: No Moisture separator reheater OOS: No i

hrbine bypass system OOS: Yes

• Safety / relief valves OOS: Yes (credit taken for 17 of 18 valves)

ADS valve OOS: Yes EOC RPF OOS: Yes Main steam isolation valves OOS: No TCV slow closure: Yes l

1 I

i i

3. The sumdard APRM Seedowinequuurnents for opersuan at off-reemd power / flow ca*== are clumanned and the fuel thermd -- "- ~1 psenacoon as provided by the asnaustrauon of power and now et MCPR and MAPLHGR lanuts.

l-Page 7

9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXI-PLUS Exporure range: BOC8 to EOC8 ICF Uncorrected ACPR l Event Flux Q/A GE8x8ND Fig.

(%NBR) (%NBR) l Load Reject w/o Bypass 491 119 0.20 2

{

Exposure range: BOC8 to EOC8 ICF & FFWTR Uncorrected ACPR Event Flux Q/A GE8x8NB Fig.

(%NBR) (%NBR)

FW Contmiler Failure 345 121 0.18 3 1

Exposure range: BOC8 to EOC8 ICF nd RPT Out- of-Service l Uncorrected hCPR Event Flux Q/A GE8x8NB Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 595 124 0.24 4 4

Exposure range: BOC8 to EOC8 ICF and 'Ibrbine Bypass Valves Out-of-Service Uncorrected ACPR Event Flux Q/A GE8x8NB Fig.

(%NBR) (%NBR)

FW Controller Failure 529 125 0.24 5 Exposure range: BOC8 to EOC8 ICF & FFWTR and Turbine Bypass Valves Out-of-Service Uncorrected ACPR Event Flux Q/A GE8x8NB Fig.

(%NBR) (%NBR)

FW Controller Failure 467 126 0.23 6 i

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

This infonnation will be provided by Comed.

i Page 8 l .

c_________________ _

11. Cycle MCPR Values 4 t

l Safety limit: 1.07 Single loop operation safety limit: 1.08 Non-Pn==urization events:

This infonnation will be provided by Comed.

l Pr**=nriration events:

Exposure range: BOC8 to EOC8ICF Exposure point: EOC8 Option A Option B GE8x8NB GE8x8NB Load Reject w/o Bypass 1.33 1.29 Exposure range: BOC8 to EOC8 ICF & FFWTR Exposure point: EOC8 Option A Option B GE8x8NB GE8x8NB FW Controller Failure 1.29 1.27 Exposure range: BOC8 to EOC8 ICF and RPT Out-of-Senice Exposure point: EOC8 Option A Option B GE8x8NB GE8x8NB Load Reject w/o Bypass 1.36 1.32 Exposure range: BOC8 to EOC8 ICF and Turbine Bypass Valves Out- of-Service Exposure point: EOC8 Option A Option B GE8x8NB GE8x8NB FW Controller Failure 1.35 1.33 Exposure range: BOC8 to EOC8 ICF & FFWTR and 'Ibrbine Bypass Valves Out-of-Service Exposure point: EOC8 l Option A Option B GE8x8NB GE8x8NB FW Controller Failure  ; 1.34 1.32 l

4. For a sinslo4oup operation, the MCPR opermang hmat is 0.01 greater than the two4oop value.

)

Page 9 l l l l l l

Reloa W ~ ~WeU

12. Overpressurization Analysis Summary 5 Psi Pv Plant Event (psig) (psig) Response l MSIV Closure (Flux Scram) 1260 1296 l Figure 7

13. Loading Error Results i

This information will be provided by Comed.

14. Control Rod Drop Analysis Results This information will be pmvided by Comed.

l

15. Stability Analysis Results GE SIL-380 recommendations have been included in the LaSalle County Station Unit 1 Technical Specifica-tions, therefore no stability analysis is required as documented in the letter, C. O. Thomas (NRC) to H. C.

Pfefferlen (GE), Acceptancefor Referencing ofLicerning Topical Report NEDE-2401) Rev. 6, Amendment '

8, Thermal Hydraulic Stability Amendment to GESTAR 11, April 24,1985.

LaSalle County Station Unit I recognizes the issuance of NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), and will comply with the recommendations contained there-in. LaSalle County Station Unit 1 also recognizes the issuance of NRC Generic Letter 94-02,Long-term Solutions and Upgrade ofInterim Operating Recommendationsfor Thermal-Hydraulic Instabilities in Boll-ing Water Reactors, July 11, 1994, and will comply with the recommendations contained in Letter BWROG-94-078, L. A. England (BWROG) to BWR Owners' Gmup Executive Committee and Primary Representatives, BWR Owners' Guidelinesfor StabiliryInterim Corrective Action, June 6,1994.

t

5. & MSIV Rux scram was performed at 1020 psig dome pressure. All other analyses were performed at 986 paig.

Page 10

b es 16, Loss-of-Coolant Accident Results LOCA rnethod used: SAFEIUGESTR-LOCA Reference the 14alle County Stan'on Ursits I and 2 SAFERIGESTAR-LOCA Loss-of-Coolant Accident Analysis, NEDC-32258P, October 1993. The analysis in the LOCA report yielded a licensing basis peak clad ,

temperature of 1260*F and a peak local oxidation fraction of <0.30%. The following table provides the most limiting and the least limiting MAPLHGRs for the new fuel design. j l

i Page 11

_ _ - - - - _ - - - - - - - - - - - _ - - - - - - - - J

Re16ed7~ ~

' ~'G"i

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

Bundle Type: GE9B-P8CWB343-120Zr80M-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 10.92 11.69 0.20 1 0.22 10.99 11.71 1.00 1.10 11.13 11.78 2.00 2.20 11.33 11.95 3.00 3.31 11.54 12.16 4.00 4.41 11.76 12.40 5.00 5.51 12.00 12.67 6.00 6.61 12.24 12.90 l 7.00 7.72 12.49 13.05 1

8.00 8.82 12.75 13.21 9.00 9.92 13.01 13.37 10.00 11.02 13.22 13.54 12.50 13.78 13.57 13.75 15.00 16.53 13.21 13.48 20.00 22.05 12.37 12.71 25.00 27.56 11.57 11.92 35.00 38.58 10.06 10.36 45.00 49.60 8.64 8.95 51.27 56.52 5.64 6.14 51.30 56.55 -

6.13 52.26 57.61 -

5.70 i

I Page 12

Rel6ad F ~ "QM

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

Bundle Type: GE9B-P8CWB342-10GZ-80M-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.72 12.25 0.20 0.22 11.77 12.28

~

1.00 1.10 11.87 12.35 2.00 2.20 12.00 12.45 3.00 l

3.31 12.13 12.55 4.00 4.41

{

12.27 12.70 l 5.00 5.51 12.41 12.88 6.00 6.61 12.56 13.07 7.00 7.72 12.72 13.27 8.00 8.82 12.88 13.47 9.00 9.92 13.05 13.65 10.00 11.02 13.21 13.76 12.50 13.78 13.31 13.82 1

15.00 16.53 13.05 13.51 20.00 22.05

)

12.45 12.79 l 25.00 27.56 11.63 11.95 35.00 38.58 10.04 10.37 45.00 49.60 8.63 8.%

51.07 56.29 5.69 6.22 51.18 56.42 -

6.16 52.16 57.49 -

5.72 52.16 57.50 -

5.72 l

l I .

Page 13

7- ..

"[Q 0 0 @@@ 00@ 0

D EEG &s H E M s+ss@ M E ll ooMMMMMMMMMMMoo

os@ Hs+sE8E+8MiGE Ms@88E8Mo

MMMPsE8MMi+8MMM88MEs+8  !

mms +sMMMMMMMMMMM&E  !

MMME8MMi+sMMMME8MM8+8

M E8 H M M E8 H M E M M M M M M i

M M M M M M M M M M M M M M M  !

M Fs M Es M s+s M E M s@ M s@ i8 H s+8 ll:MMMi+sME8HMMMMs+sMM +8 i: "M M s+s8+EM M M M M s+Es+8M M*

! **E8 M Ms+EM M M M ME+sM** I

EMMMMMMMMEs l

" M M M EE M s+s &s

• ll l l l l l 1lillIl

! 5 5 7 9 11 13 15 17 19 21 23 F5 27 29 31 53 55 37 59 il 13 95 47 19 51 55 $$ 57 59 Fuel Type A=GE9B-P8CWB322-11GL100M-150-T (Cycle 7) E=GE9B-P8CWB303-9GL100M-150-T (Cycle 5)

B=GE9B-P8CWB3249G23-100M-150-T (Cycle 7) F=GE9B-P8CWB313-9GL100M-1$0-T (Cycle 6)

C=GE98-P8CWB343-12GL40M-150-T (Cycle 8) G=GE9B-P8CWB314-9GL100M-150-T (Cycle 6)

D=GE98-P8CWB342-10GL80M-154-T (Cycle 8)

Figure 1 Reference Core Loading Pattern 1

l Page 14

I l

{

Neuvon Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux - - -

Safety Vah Flow 150.0 -

Coes inlet Flow 300.0

- --- Rehef Valve Flow I

--- Bypass Valve Flow l

s/'k 100.0 *% -

200.0 E

a s-%. E s

E v 7s s '

E

. '%,,~~ 8 50.0 -

• ., 100.0 -

7 - - ,,

I I \ *\

\

/ \

f u--.

0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 Eme (80C) Eme(SeC) 2.0 .

Level (inch-REF-SEP-SKRT) actnnty

. . . . . Vessel Steam Flow ----- r Reacevny 200.0 - --- Turtune Steam Flow ' --

• t,

--- Foodwater Flow ---T I E 1.0 -

l t 100.0 ,- @

' l*. *' .

g a

+

0.0 E '

g ,.

l.

g e . .

e r.% 8 ..,,,.-

i. . '. :

, '. ..... k

.a M---------x ke -1.0 0.0 1--I ----

.l

. . - E

\

\'

I

-100.0 '

-2.0 'I '

l 0.0 3.0 6.0 0.0 3.0 6.0 Eme (SeC) Eme (SeC) l Figure 2 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 ICF) i t

i Page 15 t

l

.. s-r

~ MI i

l l

l 1

Neuron Fbx y* Vessel Press Rese (psi)

- - - - - Ave Surfacfee Flux - - - - - Safety Velve Flow 150.0 --- CorejoistFlow 125.0 - --- Rehof Vale Flow p Cdfo inlet %% --- Bypass Valve Flow

• y .

$00,0 -.....A..--#"U i

., 75.0 -

- ^%

e N e

E E g -

'h. ' g -

rI 1

50.0 - I 25.0 - * """"

-l l l 1

0.0 ' '

-25.0 ' '

O.0 7.0 14.0 0.0 7.0 14.0  ;

Eme(sec) Time (sec) l l

1 l Level (inch-REF4EP-8KRT) Void Reecevity '

- - - - Vessel Sesam Flow - - - - - Doppier Roncavity i'

150.0 - --- Turtune Sasem Flow 1.0 -

--- Scram Remi,tivity

-- Feesheeser4aew - ,

--- TotalReecevny t

\ <n E

y 100.0 a

E

r. ,

f0.0 a

~,-+.-------f,

.r.-

1. ~

1, q 8 '

i l'. :,'. ..

\ .;.. ..' ' , y .s

' .n l Soo -

I: :'. E -1.0 -

l l'.. e I ; . '. .' . E I

i .: .,' l \ .

l l.' N i

' 0.0 ' '-

-2.0 ' ' g O.0 7.0 14.0 0.0 7.0 14.0 Eme (sec) Time (sec) 3 i

I i

)

Figure 3 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF & FFWTR) J l

l I

l i

Page 16 i

l.

1 h

Neueon Flux Vessel Press Rase (psi)

' - - Ave Surface Heat Flux - - - - - Salety Valve Flow 150.0 - --

-- Coro inlet Flow 300.0 - --- Rehof Valve Flow

--- Bypass Alve Flow -

N g 100.0 _. ,' .,s % -

g200.0 lii

%,,- 1ll C ', ,, m g -

50.0 -

- 100.0 -

7--,,,,,,,,,,,

I \,

~

/ \

/ T

/ t---

0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (S8C) hme (SOC)

Level (inch-REF-SEP-SKRT)

- - - - - Vessel Sesam Flow - - - - - Doppler vny 200.0 - --- Turtme Steam Flow 1.0 -

-- Scram R

--- Feedneter Flow Toenl."-- ., _

m E .-

g 100.0 7 , e i, , 0.0 , ,

w .s ..-

- 4. % - -) .,J g .* , *. o l.. . . . ----%. O

b. i . . .

g

..*-- g \

i

,y .

0.0 b.

. .. N 7t \

it -1.0 -

(

• '.r-----------------

C e

l i

~

\

\

i .

-100.0 I

-2.0 l 0.0 3.0 6.0 0.0 3.0 6.0

Time (SOC) Emo (SGC) l Figure 4 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 ICF and RPT l 1

Out-of-Service)

Page 17 l l

l L____________________.__ _

r___- -- __ . _ _ _ _ _ _ _

i l

f Neuron Flux Vessel Press Fbse (psi)

- - - - Ave Surface Heat Flux

\

) . 175.0 - - - - - SaW h Row 150.0 - --- core inlet Flow '

--- Robef Valve Flow

- - - core inist = %

--- Bypass W Flow *

]

,,,,,,, r

', 125.0 -

_,..w '- =-m,\ .

y 100.0 , .

a %A e E E 75.0 y I

g -

l i

. I \

i  ; s 50.0 -

-l g 25.0 -

l

~ I

'1 =

0.0 ' ' ' '

-25.0 O.0 8.5 17.0 0.0 8.5 17.0 Eme (SOC) Eme (Sec)

I Level (inch-REF-SEP-SKRT) Void Reacenty

- - - - - Vessel Steam Flow - - - - - Doppler Reecenty 150.0 - --- Turtune Sum Flow 1.0 - --- Scram Remotiwty

- =" _._"'..

--- TotalReacewty

. \ .

a m

\

l E '

g 100.0 --- - ~ ' ~

].i: \i ,',' .*

., . 0.0 -

_ , v n t . ,-; ,7 ! ,

a F .'

i; \ .' '.l ..

t e ' -

I,..'

3 -

1

.. . 2 50.0 I' "

. N -1.0 -

l. .l l '. , h. E l .. .., ,'

L l

l 0.0 ' '

l

-2.0 ' ' I' O.0 8.5 17.0 0.0 8.5 17.0 Eme (S9C) Eme (SOC)

Figure 5 Plant Response to FW Contruller Failure (BOC8 to EOC8 ICF and 'nsrbine Bypass Valves Out-of-Service)

Page 18 f

L

l l

l i

j l Neutron Flux Vessel Press Rase (psi) 1

- - - - - Ave Surfaceyem ( - 175.0 - - - - - Sekty Valve Flow 150.0 -

--- CorpeFlow --- Rehof Valve Flow

, p Gdfo irdet Subcoohng --- Bypass Valve Flow .

125.0 -

_-.....- A-- .:h '.

, y00,0 -

1 .

y ~

_e -T ' . _e l%

e \* m E E 73.0 g

$ ~

N' . $

I

- 1 I

50.0 - I l

2s.O -

1 i I

) _

I 0.0 -25.0 ' I 0.0 7.0 14.0 0.0 7.0 14.0 Eme (S8C) Eme (S8C)

Level (inch-REF SEP-SKRT) Void Reactmry

- - - - - Vessel Steam Flow - - - - Dopp6er Reactmty 150.0 -

--- TurtMne Steam Flow 1.0 - --- Scram Reactmty

- Feesleeter46ew - --- TotalReecevny 3 \ W

\.

n 1 .-

., g  ;

p 1m.0 -

0 r, \. $0 G--..,--p,y<.,,',.

e a _ _ _ . ---

i. ..

, k .'. . . . 3 .,

1: .

, g i

. .a I ., .:. .

50.0 - .

1. . .. , E., -i.0 -

1 i

1: : ... ' . E i I: : . ' \

i.... . .

I,.. ' ,

I .. g g 0.0 '

-2.0 ' '

O.0 7.0 14.0 0.0 7.0 14.0 Eme (SeC) Eme (S8C)

Figure 6 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF & FFWTR and Turbine Bypass Valves Out-of-Service)

I l

Page 19

1 bi Flux Vessel Press Rae (psi) '

---

Ave So tace Heat Flux - - - - - Safety Velve Flow )

160.0 - --- . Core inet Row 300.0 - --- Flohef Velve Flow

--- Bypsu Wwe Flow *

'. l

/,\e rm '

I 100.0 2~ ***

k. *

., 200.0 -

l

. ~ ~~ .

E  % h E

1. ~

?.~, ~ - # -

50.0 -

100.0 -

I o

0.0 ' * '

1 O.0 l 0.0 4.0 8.0 0.0 4.0 8.0 Time (sec) . Time (sec)

Lewi(inch-REF-SEP-SKRT) Void Re

- - - - Vessel Saeem Flow - - - Do r 'ty 200.0 - --- Turtune Sisem Flow 1.0 - ---

m Reactmty 1

--- Feedweier Ficw ---T I Reecevay i G

I us E

.- l

@ 0.0 mg* A \ '

g 100.0 , ,,,, , ,

lii .

. . N

• c ', N -Q g * . ,\ ,-

g . s . -. . , , : ., : -) ...

. N. --

p a \

%. . . . .-. . .xK ~N 0.0 -

's. * * ' - - - - - - - -

E

-1.0 -

l. i 8

\

1, 1i

- 100.0 I '

-2.0 ' \'

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

E Figure 7 Plant Response to MSIV Closure (Flux Scram)

L l

Page 20

Appendix A Analysis Conditions Tb reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle. -

Table A-1 Analysis Value Parameter ICF ICF&FFWTR Thermal power, MWt 3323.0 3323.0 Core flow, Mlb/hr 113.9 113.9 Reactorpressure, psia i

1017.0 1015.8 Inlet enthalpy, BTU /lb 526.1 516.6 Non-fuel power fraction 0.039 0.039 Steam flow analysis, Mlb/hr 14.30 12.62 Dome pressure,psig I

986.3 986.3 Turbine pressure, psig 933.1 945.2 No. of Dual Mode S/R Valves 17 17 Relief mode lowest setpoint, psig 1091.0 1091.0 Safety mode lowest setpoint, psig 1185.0 1185.0 Page 21

Appendix B Impact of Change to the APRM Flux Scrant Setpoint The APRM High Neutron Flux Analytical Limit has been changed from 122.4% to 124.2%. This change has been incorporated into Overpressure Analysis described in Section 12. The review of non-pressurization events required by GEF"AR is the responsibility of Comed. This change will not cause other non-limiting AOO events to become umiting. This change has been incorporated in the the off-rated flow dependent limits defined tu B334)0296-03P, Updated Transient Analysis: AbnormalStart-up ofan idle Recirculation Loop for LaSalle County Nuclear Station, Units 1 and2, March 1998.

1 Page 22

, AdditionalInformation Regarding

! the Supplemental Reload Licensing Report Rev L for

! LaSalle 1 Reload 7 Cycle 8 Section 2. Reference Core Loading Pattern Cycle N-1 incremental exposure (nominal) 11,100 mwd /ST Cycle N exposure increment 10,600 mwd /ST Cycle N full power capability (if different fmm above) same l

Section 9 Core-wide AOO Analysis Results Increased Core Flow PV PV PV Limiting Power Flow Flux Q/A (PSL) (Dome) (Bottom)

Exposure 1Yansient (%NBR) (%NBR) (%NBR) (%NBR) (psig) (psig) (psig) l EOC LRNBP 100 105 491 119 1152 1162 1190 EOC MSIVF 102 105 467 130 1260 1264 12 %

1 l l Increased Core Flow and Reduced Feedwater Temperature PV PV PV '

Limiting Power Flow Flux Q/A (PSL) (Dome) (Bottom)

Expcsure Transient (%NBR) (%NBR) (%NBR) (%NBR) (psig) (psig) (psig)

EOC FWCF 100 105 345 121 1116 1118 1145 Increased Core Flow and RPT Out-of-Service 1 l

' PV PV PV Limiting Power Flow Flux Q/A (PSL) (Dome) (Bottom)

Exposure Transient (%NBR) (%NBR) (%NBR) (%NBR) (psig) (psig) (psig)

EOC LRNBP 100 105 595 124 1154 1163 1200 Increased Core Flow and Turbine Bypass Valves Out-of-Service l PV PV PV l Limiting Power Flow Flux Q/A (PSL) (Dome) (Bottom)

Exposure Transient (%NBR) (%NBR) (%NBR) (%NBR) (psig) (psig) (psig)

EOC FWCF 100 105 529 125 1154 1162 1190 Page A-1 l

t

L, l l

ICF & FFWTR cnd 'Ibrbine Bypass V:lves Out-of-Service PV PV PV Lhniting Power Flow Flex Q/A (PSL) (Dome) (Bottoon)

Exposure Tr== ale =t (%NBR) (%NBR) (%NBR) (%NBR) (psig) (psig) (psig)

EOC FWCF 100 105 467 126 1148 1157 1184 Were all resolved OPI 3 values used for safety and relief valve characteristics? Yes Assumed MSIV closure characteristics:

Time (sEc) MSIV Area (nerunit) l l

0.0 1.0 (fully opened) 0.6 1.0 l l 1.7 0.01 l 3.0 0.0 (fully closed) l Section 15. Stability Analysis Results!

, Rodhne Analyzed: Extrapolated rod block l

l Decay Ratio: See Figure A-1 Reactor core stability ratio. X2/Xo : 0.78

, Channel hydrodynamic perfonnance decay ratio, X2/XO :

1 l

Hot Channel Decay Ratio I-GE 8x8NB 0.65 l

1. This stability snalysis was perfonned using verified and NRC-reviewed codes, and the current reload analysis ivhe. This is not intended to be a boundmg analysis however, and the calculated value for the core and channel decay ratios may not be indicative of plant stability under some conditions. Oscillations may occur in spite of decay j ratios which are calculasM to be significantly less that 1.0. For this reason, Commonwealth Edison Company should j not rely on this calculated decay ratio as a basis for avoiding or delaying implementation of the latest GE and NRC  !

guidance in this area. '

The main usefulness of these analysis results is to provide a compenson with previous cycle analysis results relative to cxwe and fuel design differences.

l Page A-2 m

t A, Natural Circulation B IM%RMUm C Ultimate Performance Limit -

1.00 l

o 'A R~

0.75 l x

_o.

x

>=

< 0.50 v

w C

t

(

l t

I j 0.25 l

0.00 0.0 20.0 40.0 60.0 80.0 100.0 120.0

(.

PERCENT POVER l

~

l i

Figure A-1 Reactor Decay Ratio -

l l

l l

l i

. \

l Page A-3

Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results Attachment 3 ARTS Improvement Program Analysis, Supplement 1 (Excerpts) 1 3

LaSalle Unit 1 Cycle C July 1998

l Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results l

Attachment 3 ARTS Improvement Program Analysis, Supplement 1 (Excerpts)

Summary of Core Wide Transient Results AOO initial Peak Neutron Peak Heat Flux Equipment Out GE9B ACPR Power / Flow Flux (% NBR) (% initial) of Service l ICF / Normal Feedwater i Temp l LRNBP 100/105 491 119 None 0.20 I LRNBP 100/105 595 124 RPT 0.24 FWCF 100/105 529 125 TBV 0.24 ICF / Reduced l Feedwater l l

Temp FWCF 100/105 345 121 None 0.18 FWCF 100/105 467 126 TBV 0.23 OLMCPR and Kp Requirements i Limiting Power Equipment OLMCPR OLMCPR Calculated Generic Kp

AOO Out of (Opt. A) (Opt. B) K, Service l LRNBP 100 No EOOS 1.33 1.29 1.0 1.0 LRNBP 100 RPT OOS 1.37 1.33 1.0 1.0 l FWCF 100 TBV OOS 1.35 1.33 1.0 1.0 l

TOP / MOP and MAPFACp Requirements l

Limiting Power Equipment TOP MOP Calculated Generic AOO Out of MAPFACp MAPFACp Service LRNBP 100 No EOOS 24.9 25.2 1.0 1.0 LRNBP 100 RPT OOS 30.3 30.6 1.0 1.0 FWCF 100 TBV OOS 28.7 30.0 1.0 1.0 l

usaiie Unit 1 Cycle 8 A3-2 July 1998

i Administrative Technical Requirements - Appendix A  !

r L1C8 Reload Transient Analysis Results i l

i l

1 1

Attachment 4 TCV Slow Closure Analysis (Excerpts) 1 1

l i

l 1

l Lasalle Unr.1 Cycle 8 July 1998

Administrative Technical Requirements - Appandix A L1C8 Reload Transient Analysis Results Attachment 4 TCV Slow Closure Analysis (Excerpts)

Table 1 - Key Peak Values for the LRNBP Transient Events at Rated Power t

All TCV Fast Closure, 2 Seconds Slow Direct Scram and Closure, Flux Scram EOC-RPT and EOC-RPT OOS Neutron Flux (%) 491 421

! Heat Flux (%) 119.5 124.4 l Dome Pressure (Psig) 1162 1168 l

Vessel Pressure (Psig) 1190 1207 Table 2 - MCPR Operating Limits for LRNBP Event at Rated Power Uncorrected ACPR Option A Option B All TCV Fast Closure, Direct 0.20 1.33 1.29

Scram and EOC-RPT 2 Seconds Slow Closure, Flux 0.25 1.37 1.33 Scram and EOC-RPT OOS Generic EOC-RPT OOS --

1.37 1.33 (Reference 2) l I

LaSalle Unit 1 Cycle 8 A4 2 July 1998 l

Administrative Technical Requirements - Appundix A L1C8 Reload Transiant Analysis Results l Attachment 4 ,

l TCV Slow Closure Analysis (Excerpts)

Table 3. - Key Peak Values for the Off-Rated Transient Events LRNBP, One TCV Slow LRNEP, All TCV Slow Closure at 50%/s,3 TCV Closure at 19%/s  !

Fast Closure Neutron Flux (%) 170 109 Heat Flux (%) 62.0 75.1 1 Dome Pressure (psig) 1093 1125 l

l l Vessel Pressure (psig) 1120 1158 I

l l

l i

i LaSalle Unit 1 Cycle 8 A4-3 July 1998 i

I l

' Administrative Technical Requircm:nts - Appendix A L1C8 Reload Transiant Analysis Rcsults Attachment 4

~

l TCV Slow Closure Analysis (Excerpts) l Table 4. - ACPR, TOP and MOP Values for the Off-rated Transient Events l

LRNBP, One TCV Slow .LRNBP, All TCV Slow Closure at 50%/s,3 TCV Closure at 19%/s Fast Closure Calculated ACPR 0.2648 0.6329 l

Calculated TOP 26.17 49.27 Calculated MOP 26.17 55.30 Adjusted ACPR 0.7420 l

Required MCPR Non-limiting 1.8120 Reference MCPR No Evaluation 1.33 (a)

Required K(p) Performed 1.36 i

Limiting K(p) 1.53 (b)

Adjusted MOP 60.83 1

Required MOP 38.0 L

Required MAPFAC 0.62 Limiting MACFAC 0.60 (c)

Nste : (a) Based on the bounding event (LRNBP with one TCV closing at 2 seconds) Option 8 MCPR vs.ae.

(b) Based on Figure 5.

(c) Based on Figure 6.

LaSalle Unit 1 Cycle 8 A4-4 July 1998 L- -- _ - - - - - - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - -

Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results Attachment 4 j TGV Slow Closure Analysis (Excerpts) l l 1 NEUTRollFLUX 1 YESSEL PREB5 RISE (PSI) i 2 AVE Sul: FACE HEAT FLUK 2 SAF TV VALVE FLOW a core iiur roow aggg gg gg l

, .. 4,\ ...

k

=

N

~

~ i...

(- -

'v

'4.. ... ... ... 'k.---- --

... ... i..

TINC (SECONOCl TIME (SEcouDil 1 LEVEL (: NCH-REF-SEP-S(Ril  ! VO!D RI ACTIVITY 2 VESSEL STEAMFLOW 2 00PPLEI REACTIVITY

, , , mH#PJ'F,'E" ,.,  ! 'Hi" l liHim' f

t

/s  ! ...; )

g 7

• w s z

_x =

...  ; ; l; _1 .  ;  ;

% . E . ..

\

, n

• • • L. ... ... ... ** i . . ... ... ...

f!ut (SECON0tl f!ME (SECONDI)

Figure 1. LRNBP from Rated Power, All TCV Fast Closure, Direct Scram, EOC-RPT LaSalle Unit 1 Cycle 8 A4-5 July 1998 E-_____-.______-.____.- - - - - - - . - - _ - _ -. - - - - _

i Administrative Tcchnical Requirem::nts - Appendix A L1C8 Reload Transiant Analysis Results Attachment 4 TCV Slow Closure Analysis (Excerpts) l

/ 1 NEUTRoll FLUX 1 VESBEL PREBB RIBE (PSI)

$C0hE$bEkF VALVEFh0W

,,, i

,,, 5. TPitt a!ELkh VU VF fl RM ,

=

,. . . 4_

it

.. k ..

i s

N /

m. A i .. -- -

/

l '

t

'4.. ... ... ... *t..----- . i. ,

Trut istconosi tint asse0most 1 LEVEL (: NCH-REF-SEP-S(RT) VOID RI AtTIVITY 2 WESSEL STEAMFLOW OPPLEI aEA l

,,,,, !MC! ,lifi E'0"'

,,,  ! Tif ! g

!;cy{TIVITY E

3 sm. - h - '

/W T V t N s T s s s

... - .  ;  ;  ;  ;

• i ..

I i

-8"4.. ... ...

!!ME (SECONOS) T!nE tlEcotDS)

~

Figure 2. LRNBP from Rated Power, One TCV Slow Closure (50%/second)/Three TCV Fast Closure, Flux Scram, EOC-RPT OOS Lasalle Unit 1 Cycle 8 A4-6 July 1998

1 Administrative Tcchnical Requiramnnts - AppSndix A l L1C8 Roload Transinnt Analysis Results 1

I l Attachment 4 l TCV Slow Closure Analysis (Excerpts)

[ J NEUIRON FI'd i VEEiEL PRESS RISE (PSI) i 2 AVE SURrt.CE HEAT FLUX 2 SAF ETY VALVE FLOW i-8 CORL INLET FLOW 3Rg] VA g i

It

....#A_ ..

I '

l W .

k

...,,, ,,, g,,, ...),.. ... . . , . * "

5.. ..

TIME 18EC0h08) TIME (SEC6H083 l 1 LEV!L(INCH-REF-SEP-SKAT) i VOI) REACTIVITY

' 2 WESlEL 81EAMFLOW 2 D0PDLER REACTIVITY

,,,,, !MSI'r!'li E'"" '

,,, l 'W"!!iHi!!!!

a 5

l .... g

=

...1 Uh /

i 1 t o

\ \

.  ?

g

... L:

W R W =c i ....

I

~... ... -'*

?!ME (SECONDE) TIME ttEtelCE)

Figure 3. LRNBP from 50% Power, One TCV Slow Closure (50%/second)fThree TCV Fast Closure, Flux Scram LaSalle Unit 1 Cycle 8 A4-7 July 1998 I

I o -- -- -- -- - - - -

l l

Administrative Tcchnical Requirements - Appendix A L1C8 Reload Transiant Analysis Results Attachment 4 TCV Slow Closure Analysis (Excerpts)

F HEAT FLUX 5 CDR E INLET FLOW h hr' h h h h (PSI) 5REL lEF VALVE FLOW 1H.. gg,g 4 styp Let WAt vr rt nu h # ;

^

--4

$ IM.. . M. . .

k E

W E

s. .. ,

no.. -

r= 3

'** ~

... ..e i... 1.. ' ' - " " '

f ..

l Tint istconos) Tint istConD81 l 1 LEVEL (INCH-REF-SEP-SKRil i VOI ) REACTIVITY i 2 VESiEL STEAMFLOW 2 00P'LER REACTIVITY l

,,,,, !M 5,!4,T' " ,..

! SE,"!MIM s l

i... = =

l t

+

i E

~-N .L-

;  ; ;a G

(

-i..

1

~... ... .... -='... ... ,...

f!Mt 18tCON08) t!Mt ($2 CON 081 Figure 4. LRNBP from 50% Power, All TCV Closure at 19%/second, Pressure Scram LaSalle Unit 1 Cycle 8 A4-8 July 1998 i

l l Administrative Technical Requirements - Appendix A

! L1C8 Reload Transient Analysis Results l

l l

l

)

l l

Attachment 5 Additional Reload Transient Analysis Information (Excerpts) i l \

l i

l l

l l

l l

l l

l' r

LaSalle Unit 1 Cycle 8 July 1998

! Administrative Technical Requiromants - Appsndix A L1C8 Reload Transient Analysis Results l

Attachment 5 l

Additional Reload Transient Analysis Information (Excerpts)

Rod Withdrawal Error Analysis Rod Pattern

Excerpted from Comed NFS Calculation BNDL:95-025 "A CPR RWE for LaSalle 1 Cycle 8", dated 10-13-95 0 0 0 0 24 0 0 0 0 0 0 20 28 28 20 0 14 10 10 14 0

{

0 20 0 0 20 0 0 14 10 10 14 0 20 28 28 20 j 0 0 0 0 0 0 j 24 ~

0 0 0 0 l

I LaSalle Unit 1 Cycle 8 AS-2 July 1998