ML20202E167
ML20202E167 | |
Person / Time | |
---|---|
Site: | Byron |
Issue date: | 01/27/1998 |
From: | Gurley J, Redden D, Wurz D COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20202E165 | List: |
References | |
NFS-98-011-01, NFS-98-11-1, NUDOCS 9802180087 | |
Download: ML20202E167 (12) | |
Text
{{#Wiki_filter:a e. Attachment Byron Unit 1 Cycle 9 Operating Limits Report , 4 l l 9802180007 900130 PDR ADOCK 05000454 p PDR l l l (pA98byttrs\980027. doc) l
. , NUCLEAR FUEL SERVICES DEPARTMENT g NUCLEAR DESIGN INPORM ATION TRANSMITTAL 4 @ SAFETY RELATED Originating Organization NDIT No. NFS 98.0ll.01 O NON SAIETY RELATED @ Nuclear Fuci Services O REGULATORY RELATED D Other(specify) PageIof 11 Station flyron Unit I Cycle 9 Genenc To W. O. Kouba (Byron Site Engmeenng Manager)
Subject flyron Unit 1 Cycle 9 0twrating Umits Report D E Wurr .
/4A-r / 7 N rieparer Preparer's Signature Q Date J W Gurtev . . / /f ,Y Reuemer t's Signa re ' bate D Redden ~ - $) h NFS Supenisor NFS Supervisor's "ignature Date i
Status of Information: @ Venfled O Unvenfied O Engineenngjudgement Method and Schedule of Verification for Unvenfied NDITs: Desenption olintormanon: Attached is Rettston i of the Byron Unit 1. Cycle 9 Operaung Umits Report (OLR L This NDIT supersedes NDIT NFS 98.Oll 00. Revision I incorporatet K(Z) and Fxy Radial Peaking Factors into the Section 1.0 desenption of Technical Specificauons affected. Technical Specificanon 4 2.2.2 was added to the title in Section 2.5. Also, Tables I and 2 were revised to add asterisks (*) for denotmg which items were not considered for the surveillance region. Purpose of Inforn.ation: Byron Station is requested to perform an On-Site Review (OSR) of this docunent. Upon completion of the OSR, Hymn Station is to transmit the OLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 6.9.1.9. Please preside NFS (Ench Wurn with a copy of Byron Station's completed OSR and OLR submittal to the NRC. Source of informanon: : I ) PND Calculanon Number NR 19. "BYlC9 Core Operstmg Unuts Report (COLR) Fxy Ponion." Project k BYlC9NDR, dated January 2.1998.
- 2) PND Calculation Number SP-24. "BYlC9 SPIL. Unfavorable Exposure Time." Project BYIC9 Spit, dated November 24.1997
- 3) PND Calculation Number SP-10,"BYlC9 SPIL- Least Negative MTC and Most Positise MDC. With 300 rpm Surveillance MTC SPIL Companson." Project HYlC9 SPildated October R.1997 Supplemental Distnbunon: M. lesmak K. N. Kovar / C A. Cote (BY) B. L. Manges / W. J. Funke E. H. Young H. S. Kim/A. W. Wong Byron Central File DG-CF
l
. NDIT 5TS 98-01101 Page 2 of 1I OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 1s0 OPERATING LIMITS REPORT This Operat;ng Limits Report (OLR) for Byron Station Unit 1 Cycle 9 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
The Technical Specifications affected by this report are listed below: 3/4.1.1.3 Moderator Temperature Coefficient , 3/4.1.3.5 Shutdown Rod Insertion Limit l 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial Flux Difforence 3/4.2.2 Heat Flex Hot Channel Factor and K(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 4.2.2.2 Fxy Radial Peaking Factor 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.1.9. 2.1 i derator Temnerature Coefficient (Specification 3/4.1.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
- a. The BOUARO/HZP MTC shall be less positive than +2.5 x 10 AWW'F,
- b. The EOUARO/RTP-MTC shall be less negative than -4.1 x 10 AWW*F.
2.1.2 The EOUARO/RTP MTC Surveillance limit is: The 300 ppm /ARO/RTP-MTC should be less negative than er equal to 3.2 x 10 AWW* F. l l where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out l HZP stands for Hot Zero Thermal Power l EOL stands for End of Cycle Life ! RTP stands for RATED THERMAL POWER 2.2 Shutdown Rod Insertion Limit (Specification 3'J.1.3.5) 2.2.1 All shutdown banks shall be withdrawn to at least 228 steps. 2.3 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.3.1 The control banks shall be limited in physical insertion as shown in Figure 1. l l
- NDIT NFS 98 Oll 01 Page 3 of 11 OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 '
2.4 dvlal Flux Difference (Specification 3/4.2.1) i 2.4.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +3,12% of the target flux ditference. 2.4.2 The AFD Acceptable Operation Limits are provided in Figure 2. 2.5 Heat Flux Hot Channel Factor (Specifications 3/4.2.2 and 4.2.2.2)
-2.5.1 Fo(Z) s [FS/P][K(Z)] for P > 0.5 Fo(Z) s [FS/0.5][K(Z)] for P s 0.5 where: P = . the ratio of THERMAL POWER to RATED THERMAL POWER FS'" = 2.60 ~ ~"
K(Z) is provided la Figure 3, 2.5.2 F.'y = fy"[1 + 0.2(1 - P)] fy' limits within specified core planes shall be: For Core Life from greater than or equal to O MWD /MTU to less than or equal to 5,000 MWD /MTU:
- a. For the lower core region from greater than or equal to 0% to less than or equal to 50%:
- 1) - fy" s 2.271 for all core planes containing bank 'D' control rods -
- 2) fy" s 1.930 for all unrodded core planes
- b. For the upper core region from greater than 50% to less than or equal to 100%:
- 1) fy" s 2.271 for all' core planes containing bank 'D' control rods
- 2) fy" s 1.892 for all unroddad core planes
*. NDIT NFS 9841101 Page 4 of 11 - OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 For Core Life from greater than 5000 MWD /MTU to End of Core Life:
- c. For the lower core region from greater than or equal to 0% to less than or equal to 50%:
- 1) F"y" s 2.271 for all core planes containing bank "D" control rods
- 2) F"y" s 1.846 for all unrodded core planes
- d. For the upper core region from greater than 50% to less than or equal to 100%: ,
- 1) F"y" s 2.271 for all core planes containing bank "D" control rods
- 2) F"y" 51.914 for all unrodded core planes 2.5.3 . A plot of [Fa(z)
- Pn.i] vs Axial Core Height for burnups greater than or equal to O MWD /MTU and less than or equal to 5,000 MWD /MTU is provided in Figure 4 and Table 1 contains the data plotted in Figure 4.
A plot of [Fo(z)
- Pn.i] vs Axial Core Height for burnups greater than 5,000
' MWD /MTU to End of Core Life is provided in Figure 5 and Table 2 contains the data plotted in Figure 5.
2.6 Nuclear Enthalov Rise Hot Channel Factor (Specification 3/4.2.3) F7s s F"4'[1,0 + PFas(1.0 - P)} , where: P = the ratio of THERMAL POWER to R\TED THERMAL POWER ! F"4" = 1,70 ! PF3s = 0.3 I \
f Page 5 of 11
, OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 Figure 1: ' Control Bank Insertion Limits Versus Percent Rated Thermal Power i (29 %,228) (79 %,228) 22 / / , / /
BANK B 180 i y (100 %,161) (0%,162) l T 140 , i E. k120 / lBANKCl / c h 8
$ / /
1 / / BANK D 60
/ / < l(0%,47) l 20 (30%,0) l 0 -
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent) _ - _ _ _ _ _ _ _ _ 1
a b'JL@nh@RPJFtPA ,, Page 6 of11 OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 FIGURE 2: Axlal Flux Difference Limits As A Function of Rated . Thermal Power 100-( 11,90) (11,90) UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION _ 80 - I g . n. e E ; 80 -
] ACCEPTABLE li OPERATION m
o N. (.31,50) (31,50) 40 - 20 - 50 40 30 20 -10 0 to 20 30 40 50 Flux Difference (af) %
ll' l' = i
- illJ , za5 MY'@9,2 F ;2 $U @msd2O C7} mh2 b E 5 DOZ ch __
- OlnC
)
5 2 9 1 2
. 1 0
2 1 ( 1 1 P t h 0 OT 1 g i e H e "e r p 9 o o C le v f o n E n g n i o i t 8 t c im n i L u A F i C A 0 O 7 s 1 L
" R
( A 0 .
- T
) 6 H Z (
( G o 6 I E F H d E e R i z O l a 5 C m r o N -
) 4 Z
( K 3 e r 3 u g i F 2
- 0) 1 M 1 O T
T
- 0. O 0
( B 0 1 1 9 8 7 6 5 4 3 2 1 0 1 0 0 0 0 0 0 0 0 0 2 j%Eg GE 1 l'
e Figure 4: FQ(Z)*P versus Core IIcight Cycle Burnup Range of U MWD /MTU to S 5(HNI MWD /MTU
^
(6.0,2.60) 2 (.0
-J 4*y g f .
H N p h = [- ( o b (12.0,2.405) 2.20 l~ d I h
- 2.(X) ,
; C 1 e : :
- k j
.W l.80 ---
- m
- ; ; b E o . .
3
- c. 1.60 w : LOCA Limiting Envelope ;c H
; -m-Fxy Limit Analysis Points g p 1.10 * * -- * -- Bottom Surveillance Limit j f {
W l.20
~ -- + --Top Surveillance Limit p
- w g 1.00 -
o O .U : : . z
' O.80 ,
h g
. . q 0.60 : : -
- 9 0.40 [5
. . m . . e 0.20 : .
0.00 8.0 11.0 12.0 m 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 9.0 10.0 P. CORE IIEIGIIT(FT) mp C BOTrohl
i NDIT NFS 98-01101 Page 9 of 11 OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 Table 1 [F9(z)'Prel] vs. Axial Core lleight Cycle Burnup Range of 0 MWD /MTU to s 5000 MWD /MTU No. Core Heeght (fcot) Max. FO*e Fq Umst 1* 0.2504 0 8338 2.6000 2* 06259 2 0909 2.6000 3* 08763 2.4527 2.6000 4* 1.1267 2.5115 2.6000 5' 1.3771 2.5094 2.6000 6* 1.6275 2.5386 2 6000 7 1.8778 2.5758 2.6000 8 2.1282 2.3952 2.6000 9 2.3786 2.5128 2.6000 10 2.6290 2.5486 2.6000 11 2.8793 2.5570 2.6000 12 3 1297 2.5648 2.6000 13 3 3801 2.5725 2.6000 14 3 6305 2.5820 2.6000 15 3 MrA 2 3916 2.6000 16 4 1312 2 5912 2 6000 17 4 3816 2.5976 2.6000 18 4 6320 2.5925 2.6000 19 4 8824 2.5834 2.6000 20 5.1327 2.5691 2.6000 21 5.3831 2.5455 2.6000 22 56335 2.3250 2,6000 23 5.8839 2.5016 2.6000 24 6,1343 2.4482 2.5956 25 6.3846 2.4690 2.5875 26 6 6350 2.4931 2.5794 27 6 8854 2.5127 2.5712 28 7.1358 2.5110 2.5631 29 7.3862 2.3682 ?.5550 30 7.6365 2.5401 2.5d68 31 7.6869 2.5366 2.5387 32 8.1373 2.5250 2.5305 33 8.3877 2.5045 2.5224 34 8 6380 2.4776 2.5143 35 8.8884 2.4094 2.5061 36 9.1388 2.2954 2.4980 37 9.3892 2.3765 2.4899 38 9.63 % 2.3411 2.4817 39 9 8899 2.3032 2.4736 40 10.1400 2.2922 2.4654 41* 10.3910 2.2558 2.4573 42* 10.6410 2.0909 2.4492 43* 10 8910 2.0363 2.4410 44* 11.1420 2.0207 2.4329 45* 11.3920 1.7355 2.4248 46' 11.7680 0.7541 2.4125 Asterisked (*) itenu (top and tnxtom 15%) are not considered for the survedl,4.nce repm.
l Figure 5: FQ(Z)*P versus Core IIcight l Cycle Burnup of > S(NN) MWD /MTU (6.0, 2.60) ; e , 2.60
?-- r- -- F* f % w - m- Q 2_49 -
v 5 m y 1: en y 2.20 f : M .
'9 0 2.0,2.405) d z \ o 2.00 ,
cs
- O crl
_W l.80 8 d
- 1 .
- E 5 : -
g
- 1.60
- LOCA Limitmg Envelope x y : -1 p 1.40 -{ ,
l l Fxy Limit Ana~ysis Points
-- * -- Bottom Surveillance Limit g
j { { Q
. . + . . Top Surveillance Limit f g 1.20 ,
tgp M g 1.00
! y m : : A o 5
- A 0.80 : E
- : :i 0.60 .
- O O -
0.40
- : E .
0.20 f f
- ;?
0.00 .:. : nf 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 5 O BOTTOM CORE IIEIGIIT(FT) mp 3
** NDIT NFS-98 01101 ~
Page 11 of 11 OPERATING LIMITS REPORT (OLR) for BYRON UNIT 1 CYCLE 9 Tab 1e 2 [Fo(z)*Prd) vs. Axial Core Height Cycle Bumup of > 5000 MWD /MTU
~
No. Corc Height (feet) Max. FO*P Fq Umst l' O.2504 0.9100 2.6000 2' O.6259 1.9599 2.6000 j 3' O.8763 23418 2.6000 l 4' l.1267 23066 2.6000 f 5' l.3771 2.5755 2.6000 6' l.6275 2.5985 2.6000 7 1.8778 2.5883 2.6000 8 2.1282 23812 2.6000 9 23786 2.4659 2.6000 10 2.6290 2.4484 2.6000 11 2.8793 2.4284 2.6000 12 3.1297 2.4325 2.6000 13 33801 2.4398 2.6000 14 3.6305 2.4487 2.6000 15 3.8809 2.2588 2.6000 16 4.1312 2.4455 2,6000 17 43816 2.4496 2.6000 18 4.6320 2.4431 2.6000 19 4.8824 2.4332 2.6000 20 5.1327 2.4186 2.6000 21 53831 23956 2.6000 22 5 6335 2.1877 2.6000 23 5.8839 23532 2.6000 24 6.1343 2.4630 2.5956 25 6.3846 2.4687 2.5875 26 6.6350 2.4813 2.5794 27 6.8554 2.5013 2.5712 28 7.1358 2.5008 2.5631 29 7.3862 23606 2.5550 30 7.6365 2.5149 2.5468 31 7.8869 2.5358 2.5387 32 8.1373 2.5288 2.5305 33 83877 2.5132 2.5224 34 8.6380 2.4916 2.5143 35 8.8884 2.4241 2.5( 51 36 9.1388 23354 2.4980 37 93892 2.4179 2.4899 38 9.6396 2.3897 2.4817 39 9.8899 2.4266 2.4736 40 10.1400 2.4563 2.4654 41' 10.3910 2.4530 2.4573 42' 10.6410 23319 2.4492 43' 10.8910 2.2767 2.4410 44' 11.1420 2.1625 2.4329 45* 11.3920 1.8261 2.4248 46' 11.7680 0.9037 2.4125 Astensked (*) 'tems (top and bottom 15%) are not considered far the surveillance region.
. .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .}}