ML20094H610

From kanterella
Jump to navigation Jump to search
Rev 3 to Cycle 8 Core Operating Limits Rept
ML20094H610
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/28/1992
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20094H597 List:
References
NUDOCS 9203110146
Download: ML20094H610 (22)
v • d • e


Text

. . - . . . . - - - . . - - . - . . . - . ~ . . _ . - . _ - . . - - - . . - - . - - - - - - - - . ~ . . - . - . - - . -

i.

t 4

t i

t 4

i i

i

?

FLORIDA POWER CORPORATION f

CRYSTAL RIVER UNIT 3  !

r t

I f.

CYCLE 8 r

CORE OPERATING LIMITS REPORT  :

j REVISION 3 t'

l I

t i

r i

l l

l l .

I

(

9203110146 920228 PDR ADOCK 05000302 i P FDR t

'..,,. - - - . . . . . _ , . . . , - - . . --,-,..~-e-- -,.---~~-~.-++~.~.-w-+-~+'w~-~-.~~~-- +-~~~~=,,*c~'#'"~" * * " * * ' "' '

. . - _. - = --

- , Page 1 of 21 l.0 Core Operating Lirrits Core cperating limits for CR3 are established and documented in this CORE OPERAllNG LIMllS REPORI for Cycle 8 for the following:

3.1.1.3.c Negative Hoderator Temperature Coefficient timit l l 3.1.3.6 Regulating Rod Insertion Limits 1 3.1.3.7 Rod Program l 3.1.3.9 Axial Power Shaping Rod Insertion Limits 1 3.2.1 AXIAL POWER IMBALANCE 3.2.4 QUADRANT POWER Till The analytical methods used to determine the core operating limits 1 addressed by the individual Technical Specifications shall be those previously reviewed and approved b/ the NRC, specifically:

1) BAW-10122A Rev.1, " Normal Operating Controls", May 1984.
2) BAW 10ll6A, " Assembly Calculations and fitted Nuclear Data", May 1977 ,
3) BAW 10ll7P A, "l'abcock & Wilcox Version of PDQ User's Manual", January 1977
4) BAW 10ll8A, " Core Calculational Techniques and Procedures", December 1979
5) BAW 10124A, " FLAME 3 A Three Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions", August 1976
6) BAW-10125A, " Verification of ihree Dimensional FLAME Code", August 1976
7) BAW-10152A "NDODLE A Multi-Dimentional Two-Group Reactor Simulator", June 1985
8) BAW-10119. " Power Peaking Nuclear Reliability factors",

June 1977

9) The methodology for Rod Program received NRC approval in the Safety Evaluation Report dated January 31, 1990.

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechani:al limits, core thermal-hydraulic 'itmits ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERAllNG LIMITS REPORT, including any mid-cycle revision or l supplements thereto, shall be provided uoon issuance for each veload cycle l to the NRC Document Control Dask with copies to the Regional Administrator I

and the Resident inspector.

Rev. 3

Page 2 of 21 Crystal River 3. Cycle 8 Regulating Rod Group Insertion Linilts for L four Pump Operation from .

O to 30 410/ 0 EfPD -

! 110 ,

! (52.102) (300,102i l 100 -

(268.102) 90 - (262,92)

SHUTDOWN

  1. KARGINLIMIT
s. 80 -

(240,80)

RESTRICTED

_ 70 -

OPCRAil0N E .o_

y 60

_aur UNACCEPTABLC r.: OPERATION 3 50 - (23,50) (175,50) a

" 40 - -

C

\'

2 30 ~

ACCEPTABLE  :

/ OPERAll0N l 20 10 ,

(0,0) 0 1 i e a  !

O SO 100 150 200 250 300 Rod Irder. % Withdrawn r, . 25 50 75 100 0 25 50 75 100 L L .. 1 1 a t. s 1 e a Group 5 - Group 7 This TIgtere is referred ts by Technical 0 25 50 75 100 ,

Specification L_ l. 1. t .

1 3.1.3,6 Group 6 I,

Note 1: A rod grous overlap of 2515% betwt.en sequential withdrawn groups 5 and 6, and 6 and 7 stiall be maintained.

Figure 1 .

Rev. 3 i-

, Page 3 of 21 Crystal River 3 Cycle 8 Regulating Rod Group Insert 1on Lluits for I four Pump Opetation ftom 30 +10/ 0 to 100 +10/.0 [fPD 110 _-

(300,102) tno , (268,102) -

UNACC[PTABLE '

- (262,92) 90 OPERATION RES1RICTED OP[ Rail 0N c M *

(240,80) ,

I a 70 - WIN MAkGIN x

l 60 -

e

'E 50 - (40,50) (175,50) sw e 40 -

L

{ 30 A

ACCEPTABLE

,/ OPCRATION 20 (14 ',15) 10 ,

(0.8) 0 e i , . .

tL 50 100 150 200 250 300 l Rod index, I Withdrawn 0 25 50' 75 100

  • 0 25 50 75 100 t i 1 -1 1 t i 1 3 1 Group 5 Group 7 i

This figure I referred to by l Technical 0 25 50 75 100 Specification ' ' ' '

  • 3.1.3.6 Group 6 Note 1: A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Figure 2 Rev. 3

,.-,.-.,,,-,.y---- . , - _ . . - - _ , , , - , - - , . , , , ,

, , - . _ ..sc-, -.,__ey,..,,me. y m- r,_,,. pre-.m--,q.. . , ,

4

< Page 4 of 21 Crystal River 3 Cycle 8 Regulating Rod Group Insertion Limits for four Pump Operation from 100 +10/ 0 to 575 t 10 EfPD 110 (300,102)

(193,102) (268,102)-

UNA(CEPTABLE (262.92) 90 -

OPERAil0N

' 80 RESTRICTED (240,80)

OPERAll0N

' 70 ,. $ HUT 00WN

_ MARGIN I tIH!T

[ 60 -

M '

(112,50) y 50 - (175,50)

"j 40 -

L g 30 -

ACCEPTABLE f 20 ~

OPERAil0N (86.15) 10 -

0,8) 0 ' ' ' ' '

O 53 100 150 200 250 300 Rod Index, 1 Withdrawn .

0 25 50 75 100 0 25 50 75 100 g i n n i t- i a a i Group 5 Group 7 ihis figure referred to by Technical .

Specification 0 25 50 -75 100 3.1-3.6 a i n i i Group 6 Note 1: A rod group overlap of 25 t 5% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Note 2: This figure shall be used up to complete APSR withdrawal per Technical Specification 3.1.3.9.

Figure 3-Rev. 3

,.w ..n.-- - . _ , , - , - . , , . - , , - . , . . - ~ - ..,,we . , - - ,-ry.s , s c. w < + + . -. r,.w., , , , ,e-- i-,-m- -.-w c w w .y

.- Page 5 of 21 Crystal River 3 Cycle H Regulating Rod Group Insertion Limits for four Pump Operation After 520 t 10 EfPD 110 .

(193,102 (3 0,102) 4 100 .

(268.102)"

UNACCEPTABLE (262,92) 90 -

l OPERATION ,

RESTRICTED (240,80) l

g. 80 OPERAil0N l E 70 -

SHUTDOWN MARGIN E60 - LIMII y 50 -

(112.50) (175,50)

)40 -

L'

{ 30 a-ACCEPTABLE OPERATION 20 -

(86,15) 10 0

[(0.8) -

8 a 1 i- 1 0 50 100 150 200 250 300 Rod Index,1 Withdrawn 0 25 50- 75: 100 0 25 50- 75 i i i i 100  ;

_. i a i i i i Group 5 Group 7 This figure referred to by Technical specification 3.1.3.6 j .

2p y 7p 10,0 s

Group 6 Note'1: A rod group _ overlap of 2515% between sequential withdrawn groups 5  :

and 6, and 6 and 7 shall be maintained.

Note-2: This figure shall be used after complete APSR withdrawal per Technical Specification 3.1.3.9.

Figure 4 Rev. 3 .

4 Page 6 of 21  !

Crystal River 3, Cycle 8 1

Regulating Rod Group Insertion Limits for i ihree Pump Operation from 0 to 30 +10/ 0 ETP0 110 --

100 1

90

~

(300,/7) ,

g (52,77) (268,77)-

0 l

~

I (262,69 l m "f UNACCEPTABLE

"- OPERATION yl 60 (2t0.60) l 4 RESTRICTED 2 50 - SHUT 00WN OPERAil0N g MARGIN

= LlHIT a 40 -

. (23,38) (175,37.5) c g30 -

20 -

ACCEPTABLE OPERAil0N 10

'(0.6,5) 0 50 100 1 50- 200 250 300 Rod Index, 1 Withdrawn 0 25 50 75 100 0 25 50 75 100 i a a a i i a L. 1 i Group 5 Group 7

~~"

'This figure referred to by 0 25 50 75 100 '

Technical a e I a i Specification Group 6 3.1.3,6 Note 1: A rod group overlap of 25157, between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Figure 5 Rev. 3

Page 7 of 21 Crystal River 3, Cycle 6 Regulating Rod Group Insertion Limits for Three Pump Operation from '

30 <10/.0 to 100 +10/+0 EfPD 110 100 -

90 -

~

(300,77)

O

5. (90,77) (268,77)- I k

A 70 - UNACCEPTABLE RESTRICTED (262,69) g OPERATION OPERATION 2 60 -

(240,60)

SHUIDOWN 3 50 -

MARGIN

% LIMIT cr ,

~

", (40,38)

(175,37.5) >

u 1

j 30 -

a.

i 20 -

ACCEPTABLE OPERATION 10 -

14.11 75)

(0.6.5) 0 * - * * *

  • 0 50 100 150 200 250 300 Rod Index, I Withdra m '

0 25 50 75 100 0 25 50 75 .100 t a n 1

_s a 1 1 i n Group 5 Group 7 .

ThTs~ figure referred to by Technical 0 25 50 75 100 Specification ' ' ' ' '

3.1.3,6 Group 6 Note 1: A rod group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

Figure 6 Rev. 3 J

_., . . - -.. ,,- ,y _ ,, _#, . . _ ...s._,.,, . . . , , . , , , . , , . . ..~ ,_,~ m,.

4 g Page 0 of 21 Crystal River 3. Cycle 8 Regulating Rod Group Insertion Limits for .

Three Pump Operation from ',

100 +10/ 0 to 525 t 10 ErPD 110 =  !

100 -

t 90 -

UNACCEPTABLE (300,77) 80 -

e OPERAi!ON (193,77) (268,77) - ,

b

a. 70 - (262,69) ,

60 - RESTRICTE0 (240,60) g OPERAi!ON SHUTDOWN 50 -

-7 MARGIN e 3 -LIMIT

    • 40 -

(112,38) . 175,37.5)  ;

30 -

g m

20 -

ACCEPTABLE <

OPERAfl0N

  • 10 (86,11.75) -

o (0.6.5) , , , , ,

0 50 100 150 200 250 300 Rcd Index 1 Withdrawn .

I l

0 25 50 75 100 0 25 50 75 100 i i 1 1 1 1 i ,1 -l i 1 i Group 5 Group 7

~~

j..

This-figurc l referred to by o Technical t Specificatien 0 25 50 75 100 t

i. 3.1.3.6 ' ' ' ' '

l Group 6 ,

Note 1: A rod group overlap of 25 i 5% between sequential withdrawn groups 5 <

and 6, and 6 and 7 shall be maintained.

' Note 2: This figure shall be used up to complete APSR withdrawal per Technical Spectfication 3.1.3.9.

Figure 7 Rev. 3 L:. . . . . . - - - - - . -;--.. - , , - - - - . - - . . - . . . . .

Page 9 of 21

' ~

Crystal River 3 Cycle B l

Regulathg Rod Group Insertion Limits for Three Pump Operation After

$25 t 10 [fPD 110 --- - - - - -

100 -

90 l

(300,77)  :

80 '

$ llNACCEPTABLE IU3*77)/ (268,77)^ m R 70 -

OPERAil0N

.- (26?,69) i

$ 60 y -

(240,60)

>:- AESTRICTED  ;

3 . SHUTDOWN i' OPERATION 50 4

MARGIN y

-LlHIT

", . 40 (117,38) (j75,37,$)

i

' c 30 - / l ACCEPTABLE  :

20 - OPERATION 10 - (86,M.75) 0 8

-: 8 8 i ' >

0 50 100 1 50 200 2!4 300 Rod Index, 5 Withdrawn- "

0 25 50 75 100 0 PS 50 /5 100 y n a a t- i 1- n y Group 5 Group 7 This figure referred to by Technical specification 0 25 50 75 100 3.1.3.6- i e i i n Group 6-Note 1: A rod group overlap of 25 i 5% between sequential withdrawn Groups 5 and 6, and 6 and 7 shall be maintained.

Note 2: This figure shall be used after complete APSR withdrawal per Technical Specification 3.1.3.9. -

figure 8 Rev. 3 ,

_ _ _ . . _ . . . _ _ . . _ . ~ _ _ _ _ _ . _ . - _ _ . _ _ - _ . _ . _ _ _ _ .

p

. Page 10 of 21  ;

Crystal River 3. Cycle 8 Control Rod Locations and Group Designations X

fuel Transfer l Canal )

A 8 1 6 1  ;

C 3 5 5 3 L D  ? 8 7 8 7 3 $ 4 5 3 E

, [4 F 1 8 6 2 6 8 1 G 5 4 2 2 4 5 W" 0 I E 2 Y 0 ~Y H

K 5 4' 2 2 4 5 l L 1 8 6 2 l6 '8 1 11 , 3 5 4 4l $ 3 N l 7 8 7I l8 /

i 0 _.

l 3 5 5l 3

=

P i l 1 6 l1 l R ,

e i l 1 ,

1 2 3 4 5 6 7 8 9 10, 11 12 13 14 15 X Group Number Grovo No. of Rods function ThTITigure' 1 8 Safety referred to by 2 8 54 fe ty Technical 3 8 Sa f ety Specification a 8 Safety 3.1.3.7 5 12 control 6 8 Control 7 8 Contrcl

(- 8 8 AP!As figure 9 Rev. 3

t Page 11 of 21

. Crystal River 3 Cycle 8 AX1Al. POWER SHAPING R00 INSER110N LlHITS Up to 515 EfPD, the APSR's may be positioned as necessary. The AP$R's shall be completely withdrawn (100%) by $35 (fPD. Between 515 and 535 [fPD, the APSR's may be withdrawn, llowever, ence withdrawn during this period, the APSR's shall not be reinserted.

i r

lhese limits are -

referred to by Technical i specification 3.1.3.9 9

A Rev. 3 L

. - . - . . . - . . . -.--- ~

, Page 12 of 21 Crysts) River 3. Cycle 8 Axial Power Imbalance Envelope for four Pump Operation from 0 to 30 +10/-0 [fPD 110.-

( 20.102) (23,102) g, , , .

(?0.7.92) '

90- -

< (23.9,92)

(-23.2,80) 80 < -

(30.4,80)

UNACCEPTADLE 3 70- -

ACCEPTABLE UNACCEPTABLE OPERATION c OPEMTION OPERATION ,

T '

(-28,50) ' j 50.- - - >(33.5,50) o

,. 40 - ..

A 30 20 "

10- - ,

g. i. i i o n. , i s. i a 40 30 10 0 to 20 30 40 50 Axial Power Imbalance, 1 Tliis 71glire- ->

referred to by .

Technical Specification 3.2.1 l '

l_ figure 10 >

Rev. 3 w- , m - e- - , - , - - , , , - - - n.ny , ,, - -e-- e v -e- , r -w - - , - ,-,.7 --- , , ,,-, , ,

Page 13 of 21 Crystal River 3 Cycle 8 l

Axial Power Imbalance Envelope for four Pump Operation from 30 +10/ 0 to 100 +10/ 0 EfPD 110 -

^

(-20,102) 4 gg _ .-  ;(25.102)

(-20.7.92 ,

(25.7.92)  ;

90 - - .

(-23.2.80) , 80 - -

(30.4.80) a$ 70 -

UNACCEPTABLE ACCEPTABLE UNACCEPTABLE OPERATION OPERATION OPERAil0N j 60 - -  ;

(-28,50) < .

'S 50 - ,.

o(33.5.50)

?

ce e 40 -

  • C g 30 - -

o.

20 - - ,

10 - -

, , , , , 0 i , a i j 40 20 -10 0 10 20 30 40 50 Axial Power Imbalance, 5 IEis figure .;

referred to by Technical ,

- Specification l 3.2.1 Figure 11 Rev. 3

- ~ _ _ _ _ _ _ _ _ _ . _ - . _ . - _ . _ . _ ,

Page 14 of 21

]

Crystal River 3, Cycle 8 l Axial Power 1mbalance Envelope for  !

Tour Pump Operation from ,

i 100 +10/ 0 to $25 1 10 [fPD i

110 ..  :

i

(-22.5.102) ,

(25.102)

(-23,92) g, ,

(25.7.92)

(-25.6,30) ' 80 - - (31.2,80) ,

m k

... 70 - -

ACCEPTABLE UKACCEPTABLE UKACCEPTABL E E OPERATION OPERAi10N OPERATION Jj 60 -

he

(.30,50) i ,

3 50 - -

>(34.5.50)

A

      • 4 0 .< -

u I 30 -

a.

20 -

10 - -

t 1 a_ ,O L ___,  ; i a i ,

-10 10 20 30 40 50 50 30 -20 0 Axial Power lab 41ance. 1 Tfit's figure referred to by Technical l Specification 3.2.1 figure 12 l

Rev. 3

Page 15 of 21 Crystal kiver 3, Cycle 8 Axial Power Imbalance En'velope for four4 ump Operation After 525 1 10 EFPD 110 --

(-22.5,102L -

100 , ,

(-23,92) v

}(27.102)

(28.5,92) j 90 - -

}

(-25.6,80)J go - - ,(32.8,90) u UNACCEPTABLE o-l 70 - - ACCEPTABLE UKACCEPTABLE OPERATION OPERATION OPERATION j -

J g 60 -

E

(-30,50) < , "W- -

<>(36.5,50)

T t

a 40 ~ -

e

$-I 30 --

h .

20 1.

10 - -

i e i 0 i i e i ,,,,,3 40 -30 10 0 10 20 30 40 50 Aylal Power 1mbalance, 5

~

This Tigura referred to by Technici.1 Specification 3.2.1 Figure 13 I Rev. 3

^

Pago 16 of 21 Crystal River 3, Cycle 8 Axici Power Imbalance Envelope for ihree Pump Operation from 0 to 30 +10/-0 EfPD 110 - -

100 - -

go - -

~ ~

(-20,77)p- - ,(23,77)

(-20.7,69) i -

(23.9,69)

{ 70 -

n.

(-23.2,60) g .60 - - ,(30.4,60)

E UNACCEPTABLE y ACCEPTABLE UNACCEPTABLE OPERATION

  • 50 - -

OPERATION OPERATION T

  • 40 - -

(-28,37.5)i E >(33.5,37.5)

", 30 - .

5.

h 20 - -

10 - -

  • i i t i , 0 ,_ .. -i i ,

40 -30 -10 0 10 20 30 40 50 Ax!al Power Imbalance,1 P

This figure re ferred to of Technical Specification 3.2.1 ,

Figure 14 Rev. 3

o o .. i Page 17 of 21 Crystal River 3, Cycle 8 Axial Power Imbalance Envelope for

-Three Pump Operation from 30 +10/-0 to 100 410/-0 EfPD 110 .

100- -

90 g.

, (-20,77) & . ~  ; (25,77)

(-20.7,69), 70- - (25.7,69)

(-23.2,60) 60 . (30.4,60)

UNACCEPTABLE ACCEPTABLE UNACCEPTABLE OPERATION  % 50- - OPERAi10N OPERATION E

(-28,37.5)' "I40 .

' ' - (33. 5. 37. 5 )'

-1

% 30- -

ne L

c 20- -

E

a. 10- -

i i s. i 0 s i n i i

- -40 10 0 10 20 30 40 50 Axial Power imbalance, 1 -!

1.

L This figure referred to by L Technical Specification l- 3.2.1 Figure 15 Rev. 3

7 ,;. , . - ,

Page 18 of 21 Crystal River 3, Cycle 8 .

Axial Power Inhalance Envelope for Three Pump Operation from-100 410/-0 to 525 t 10 EfPD 110 ,- -

100 - -

90

.k

(-22.5,77) ,  ; (25,77)

(.23,69) , 70 - -

,(25.7,69) -

(-25.6,60) '

60 . , (31,2,60) k UNACCEPTABLE ACCEPTABLE UNACCEPTABLE OPERATION  ; 50 - OPERATION OPERATION E

E 40 - -

.(-30,37.5) o w i(34,5,37.5)

-330- -

H L

. 20 - - '

a. 10 - -

a 1 J . 1 -1 0;  ! i- a n- 's s

-50 . 40 20 -10 0 10 20 30 40 50 Axial Power Imbalance, %

This figure referred to by Technical Specification 3.2.1 figure 16 Rev. 3

. . , , . Page-19 of-21 Crystal River 3. Cycle 8 Axial Power Imbalance Envelope for Three Pump Operation After ,

525 1 10 EfPD 110 -

100 - -

90 - -

~ ~

(-22.5,77),

q(27.77)

(-23,69) , 70 - - (28.5,69)

(-25.6,60) 60 - - (32.8,60)

A UNACCEPTABLE 6 UNACCEPTABLE OPERATION

    • M ' ' ACCEPTADLE OPERATION OPERATION

(-30,37.5) < .

40 - -

f,(36.5.37,5) 3 L  % 30 -

D4

. 20 ~ ~

f.

t

' k 10 -

n. -

i e i i i0 e i e i i 40 -30 10' O 10 20 30 40 50 L Axial Power Imbalance, _1 f

This figure refe: red to by

i. Technical l Specification 3.2.1 Figure !?

Rev. 3

.g .

Page 20 of 21 Crystal River 3, Cycle 8 4

QUADRANT POWER TILT LIMITS FOR DIERMAL POWER s 50% FULL POWER

..EADY STA10 TRANSIENT HAXIMUM '

LIMLL_ LIMJ1 LIMIL QUADRANT POWER TILT as measured by:

Symmetrical incore 7.50 12.0 20.0 Detector System Power Range Channels 5.16 9.75 20.0 Hinimum incore 2.43* 4.95 20.0 Detector System Heasurement independent 8.d8 14.50 20.0 QUADRANT POWER TILT LIMITS FOR THERMAL POWER > 50% TULL POWER STEADY STATE TRANSIENT MAXIHUM LIMIT LIMIT Llhll_

QUADRANT POWER TIL1 as measured by:

Symmetrical Incore 4.25 10.03 20.0 Detector Systcm Power Range Channels 1.96 6.96 20.0 Minimum-Incore 't.50' 4.40 20.0 Detector System Measurement Independent 4.92 11.07 20.0 This table is referred to by Technical Specification 3.2.4 Contains detectors that exceed 60% depletion criteria for minimum incore systems.

Rev. 3

E ,

s. , .
o. .

Page 21 of 21 Crystal River 3, Cycle 8 MODERATOR TEMPERATURE COEfflCIENT LIMITS The uderator temperature coefficient (MTC) at RATED THERMAL POWER r. hall be less negative than:

Moderator Temperature Coefficient at HFP -3.24x10 ak/k/* f This limit is referred to by Technical Specification 3.1,1.3 P

Rev. 3

Retrieved from "https://kanterella.com/w/index.php?title=ML20094H610&oldid=2786999"