ML20113E367

From kanterella
Revision as of 09:25, 17 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Rev 0 to Byron Unit 1 Cycle 8 Operating Limits Rept
ML20113E367
Person / Time
Site: Byron Constellation icon.png
Issue date: 05/02/1996
From: Redden D, Stauffer G, Wise D
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20113E365 List:
References
NUDOCS 9607050277
Download: ML20113E367 (7)
v • d • e


Text

1 I

Attachment l Byron Unit 1 Cycle 8 1 Operating Limits Report I

l 1

1 l

i l

l l

l I

l l

i 9607050277 960624 PDR ADOCK 05000454 P PDR

I l~ NUCLEAR FUEL SERVICES DEPARTMENT NUCEAR DESIGN INFORMATION TRANSMITTAL l

l' S SAFETY RELATED Originating Organization NDIT No. 960061 O NON-SAFETY RELATED E Nuclear Fuel Services Rev. No. o O REGULATORY RELATED O Other(specify) PageIof7 1

Station Byron Unit 1 Cycle 8 Generic 1 i

l To: G. W. Stauffer Subject Byron Unit I Cvele 8 Operating Limit Report  !

Peter Moravek O Preparer Date Prep [a w's Signature D. J. Wise .) 1.,1 ,

f b Reviewer Date

/ Reviewer ~'s[gnature(/

D R. Redden .- 5/1/H, NFS Supervisor /

pN[J Supervisor's Signature Date l  ;

!- Status ofInformation: S Verified l 0 Unvenfied i O Engineering Judgement l

Method and Schedule of Verification for thiverified NDITs: ,  ;

Description ofInformation Attached is the Byron Unit 1 Cycle 8 Operating Limit Report (OLR) i i

Purpose ofinformation: Byron Station is requested to perform an On Site Review (OSR) of this document. Upon completion of the OSR, Byron Station's Reg. Assurarm will than transmit the OLR to the Nuclear Regulatory Commission pursuare to Technical Specification 6.9.1.9. Plenas preAde NFS with a copy of Dyron f;tation*: completed OSR for incorporation into the BYlC8 reload licensing file.

i Source ofInformation: 1. NFS Calenote NR 21 File BYlC8NDN 10.6,"BYlC8 OLR . Fry Linuts Portion," dated April 30,1994

2. NFS Cakmote SP-19, File BYICENDN 10.6 "BYlC8 SPIL. Evaluation of Unfavorable Exposure Time (UET)," dated l January 22,1996 Supplemernas Distnbution: D. R. Brindle Byron Central file S. Yang B.1. Manges

! K. N. Kovar/S. Ahmed M. Rothenbuchler M. T. lesniak l NDIT File CHRON No:

4 4 l t i 1

i

+ l 4

i 1

I I

I J i I  ;

5,  ;

NUCLEAR IUEL SERVICES DEPARTMENT NDIT No. 96oo6i NUCLEAR des 1GN INFORMATION TRANSMITTAL Rev. No. o j

Page 2 of 7 I

i Byron Unit I Cycle 8 Oneratine Limit Renort - Frv Portion This Radial Peaking Factor Limits Report is provided in accordance with Paragraph 6.9.1.9 of the Byron

, Unit 1 Nuclear Plant Technical Specifications.

I 1 l

l The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 8 shall be: )

1 a: For the lower core region from greater than or equal to 0% to less than or equal to 50%:

1) For all core planes containing bank "D" control rods:

l 1

F,y"" s 1.946 0 s Cycle Burnup 1
2) For all unrodded core planes: l l

F,y" " s 1. h 7 0 s Cycle Burnup < 12,000 MWD /MTU F,y""s 1.707 12,000 s Cycle Burnup b: For the upper core region from greater than 50% to less than or equal to 100%:

1) For all core planes containing bank "D" control rods:

F,y"" s 1.946 0 s Cycle Burnup l

2) For all unrodded core planes:

F,y""s 1.772 0 s Cycle Burnup < 12,000 MWD /MTU F,y""s 1.734 12,000 s Cycle Burnup l These Fxy(z) limits were used to confirm that the heat flux hot channel factor Fe(z) will be limited to the l Techmcal Specification values of:

l

[ Fq(z) s [1M] [K(z)] for P > 0.5 and.

P l Fo(z) s [5.00) [K(z)] for P s 0.5 l

assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures".

WCAP-8403, September,1974. Therefore, these Fxy limits provide assurance that the initial conditions .

l assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.

See the attached Tables I and 2, and Figures land 2 for [ Fo(z) x P,,,] vs. Axial Core Height information.

i e i

I

~

NDIT No. 960061 NUCLEAR FUEL SERVICES DEPARTMENT Rev. No. O NUCLEAR DESIGN INFORAf ATION TRANSMITTAL Page 3 of 7 Byrom Unit 1 Cycle 8 Operatine Limit Renon - MTC Portion l

j a) The Moderator Temperature Coefficient (MTC) limits are:

1) The BOUARO/HZP-MTC shall be less positive than +3.813 x 10~5Ak/k/ F.

l

2) The EOUARO/RTP-MTC shall be less negative th:.n -4.1 x 10" Ak/k/'F.

l l

b) The MTC surveillance limit is:

l

! The 300 ppm /ARO/RTP-MTC should be less negative than or equal to

-3.2 x 10" Ak/k/*F.

where: BOL stands for Beginning of Cycle Life ARO stands for AllRods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER i

l l

l

i i

WUCLEAR FUEL SERVICES DEPARTMENT KDTT No. 960061 NUCLEAR DESIGN INFORMATION TRANSMITTAL Rev. No. O l

Page 4 of 7 l

Byrom Unit 1 Cycle 8 Operating Limit Report Table I - Maximum Fo

  • P vs. Axial Core Heieht Durine Normal Operation Cycle Burnuo Ranee of 0 MWD /MTU to < 12.000 MWD /MTU i

l VENUS Core Height Maximum FoSPIL Axial Point (feet) Fo*P Limit BOTTOM 1 0.2504 0.6368 2.5000 l 2 0.6259 1.7579 2.5000  !

3 0.8763 2.1788 2.5000 4 1.1267 2.3758 2.5000 5 1.3771 2.4638 2.5000 6 1.6274 2.4997 2.5000

! s7r 11.8778? ' 2.4924 r 12.5000 a x8t~ -c 2.12821 2.29271 e 2.50004 l

t94> c 2.3786L e 2.3636 em ^ :r2.5000 s ,

l 10:4 - b2.6289

  • s v2.3787o .*N2.5000 ? I l

s11T S2.8793 e 2.3588m V 2.5000 :::  ;

mi 112 7 :s 3.:1297s 12.35424 :52.50003 l

! . s:13 m: - e3.38012 w + 2.3608e > <

e2.5000 a 414r ' r3.6304m + 2.3886c <

  • 2.5000 e l i
  • 2.5000m l aw 15e m we3.8808
  • E2.1813$ re .

216 * ~ s4:1312 % r 2.3661 E '

re s2.60003:

}

N 17.E *

  • v4.3816 6+ 9*m2.3567M m2.5000; 1 l

n18we

  • 4.6320E - >2.3469 L c2.5000 ;  !

a195 4 4.8823 a  ; 2.3333 s m:2 5000?

s 20 u r* 2.5 1327:: z 2.3159 4 - 12.50009

  • C216 4 38311  : 2.2944 r >

> < 2.50001 s 22 :t 26 8335 e -12.0956 x x2.5000 :s

" 123s - + e 5.7838 9 2.2656z <

32.5000&

m - 24 + - < e 6.1W2 < w -; 2.3229 e m:t2.49674 s . :i 25 *s: <

  • 6.3844. 5 '

x2.3143 3 < ^2.4878 c l

s :263 26.6350% > 2.3120--.  : 2.4799s i 27c: ~ - :6.88532 2.33144- a 2.4720 4 428 i: w ~ t 7.1357u = 2.3567 4 3 2.4640 c s291 ~ x 7.3861 e  ; 2.2267c :2.4561'

! ~

-- 30 / ' 7.6365 e 2.3948.- s2.4482 l 31c .: 7.8868 e >
2 4022:  ; 2.4402:::

s32 - + ' 8.1372; c 2.4128 - w 2.4323 :-

133 s s 8.3876:-  : 2.4178 J 2.4244 :-

a34 - 8.6380 < .-2.4162 - 2.4165-:

l r35x < 8.8883 : ^ 2.36412 -2.4085 >

~ 36

  • 9.1387i 2.2739- + :2.4006 s

( -

=37N 9.3891 ' > 2.3417 : 2.3927 i

!  : 38

9.6395 <  : 2.2920 r 2.3847 i + <39 + ' av 9.8899 r 2.2252 2.3758 =

s40x4 -10.140 - ' 2.2371:: ^ 2.3689 +

l 41 10.391 2.2155 2.3610 i 42 10.641 2.0784 2.3530 j 43 10.891 2.0091 2.3451 i 44 11.142 1.8724 2.3372 j 45 11.392 1.5177 2.3292 i

TOP 46 11.768 0.5966 2.3174

! Shaded area shows surveillance region.

Unshaded area (top and bottom 15%) is ignored for this surveillance.

f 1

  1. I NUCLEAR IUEL SERVICES DEPARTMENT NDIT No. 960061 ,

NUCLEAR DESIGN INFORMATION TRANSMrITAL Rev. No. O I l Page 5 of 7 l

Byron Unit 1 Cycle 8 Operating Limit Report Finure 1: Fo (Z)

  • P versus Core Height Cycle Burnup Ranee of 0 MWD /MTU to < 12.000 MWD /MTU (8.0.2.50) 2.6000 t.

2.4000 '

_L s ."

I

" " s'a m a I I sme s s m X'l _-

sam m' i

l l (12.0,2.3 1)

a , a "m .

2.2000 ,  ; ,

8 l 8 $. "

8 a a:

w 2.0000 IE  :

o .

a
n. 1.8000 .

g { s Fxy Limit Analysis Points

{

l.6000 LOCA 1.imiting Envelope ,'

w  :

  • Bottom Surveillance Limit a

$1.4000 { - + Top Surveillance Limit R

y .

u. 1.2000 l  :

1.0000 0.8000 ,

0.6000 I '

0 I 2 3 4 5 6 7 8 9 10 11 12 I

gggg, CORE HEIGHT (FT)

TOP 1

l l

NUCLEAR FUEL SERVICES DEPARTMENT N M No. 960061 NUCLEAR DESIGN INFORMATION TRANSMITTAL Rev. No. O Page 6 of 7 Byron Unit 1 Cycle 8 Operating Limit Report Table 2: Maximum Fo

  • P vs. Axial Core Heicht Durine Normal Operation Cycle Burnup Ranee of 212,000 MWD /MTU VENUS Core Height Maximum FoSPIL Axial Point (feet) Fo*P Limit BOTTOM 1 0.2504 0.6365 2.5000 2 0.6259 1.7573 2.5000 3 0.8763 2.1779 2.5000 4 1.1267 2.3748 2.5000 5 1.3771 2.4628 2.5000 6 1.6274 2.4987 2.5000 s:7 e -:;1.8778 *  :

2.4915 W2.5000-3 e a r8' ~ c 2.1282:1 s 2.2918' ' 2.5000 wi~

s

s 9 a

~

  • 2.3786 :>  ?: 2.3tGB c  ;:2.50003

-:>-10 / t2.6289 / t 2.3778 6 wc2.5000me 911e s 2.8793 c u 2.3578 e - 2.5000 m +

s-4 s:.12 a ~ e3;1297s s 2.35322 92.5000t 4- *t t 3 * ^

13.3801* 8 2.3699 a %2.5000 t l w st14 u3.6304a v2.38573 +

22.5000 c2 1 l

@ *158* we se3.88063 m 2.1805h + S2.5000 Hu 1016ce v4.131.2ti *2.3651: '

x 2.50009 we 317 w:n o4.3816* x2.3558 n 4 2.5000 e ser i181 44.63201 < a2.3469d 52.5000 e -

e 319 h a 74.8823 9 <- *2.3323 e 2:2.5000:i: >

s r20s *5.1327x v 2.3150 t a2.50009 e a21 c: 25.3831is: - s x 2.2935'.< v 2.50004 c22: '

s 5.6335e 62.1250 > u2.5000:::a a 23 e w n5.8838 e s2.2983 e na 2.5000a w #24 e >

-s 6.1342e 12.3324 er 2.4957s ei 9254 >

v:6.3846 + 2.3238 :> ^ : 2.4878 ei >

-e 26 w- <

< 6.6350 0: . . 2.3215o 2.4799 a Y27- >< s 6 8853 e A 2.3410 4 c 2 4720 t

., n:23 4 4 c 7:13572 -2.1420- 2 4640:<-

293 s 7.3861t 2.2137 '  : 2.45611 me e30e t7.6365> c 2.3808.. 12.4482?

< 31 + x 07.8668i :2.3881 -2.44021 4323 8.1372 e 2.4127e  : 2.4323o

< c 33 ') 8.38764 2.4177- ^ 2.4244 ;

34

  • 8.6380 a < s2.4161; 2.4165 i e :35? < 8 8883 a x 2.3640-- s2.4085 :-

v36n w 9.1387 - 2.2738 ' 2.4006 -

t-373 9.3891:  : 2.3416' ' 2.3927-n38n 9.6395:- 2.2919- 4  :

2.3847 >

e 391 -  : 9.8899 - 2.2251-  : 2.3768 8--

40 ' :10.140s ' 2.2370 2.3689 '

41 10.391 2.2154 2.3610 42 10.641 2.0783 2.3530 i 43 10.891 2.0130 2.3451 44 11.142 1.8884 2.3372 45 11.392 1.5316 2.3292 TOP 46 11.768 0.6062 2.3174 4

i Shaded area shows surveillarme region.

l Unshaded area (top and bottom 15%) is ignored for this sun eillans.c.

I I

. n .

l o

NUCLEAR FUEL SERVICES DEPARTME?R PCIT No. 960061 NUCLEAR DESIGN INFORMATION TRANShi!TTAL Rev. No. O Page 7 of 7 Byron Unit 1 Cycle 8 Operating Limit Report 1

Fleure 2: Fn (Z)

  • P versus Core Height I Cvele Burnun Ranee of 212.000 MWD /MTU l l

l l

l 2.6000 f (6.0.2.50) 4 I  :  !

d.

l (12.0 :2.3 2.4000 a7 1 N

m 33 "u s mus unu s , ""

, sge n s 8 m 2.2000 , , " E'"

m

  • . g i E2 o

.0000 l "

n. 1.8000 l i W '  : a Fxy Limit Analysis Points j l 1.6000 LOCA Limiting Envelope j 1 w  : - * -Bottom Surveillance Limit  ; e

$1.4000 { + Top Surveillance Limit

{  !

R

- l

. l 81.2000 1.0000  :

  • 1 . .

0-0_

. i. i .

O 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM ORE HEIGHT R TOP 1

s i

4 i

1

Retrieved from "https://kanterella.com/w/index.php?title=ML20113E367&oldid=2810947"