ML20065D544

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Rev 1 to Oyster Creek Cycle 12 Core Operating Limits Rept
ML20065D544
Person / Time
Site: Oyster Creek
Issue date: 07/11/1990
From: Dougher J, Furia R
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20065D528 List:
References
066, 066-R01, 66, 66-R1, NUDOCS 9009250274
Download: ML20065D544 (14)
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Text

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-1 oyster Creek cycle 12 >

Core operating Limits Report  ;

e Topical Report R Rev 1 f

- i BA Number 335400 t

Date: July 11, 1990 preparea: submw Wiileo [

LE ngineer O Date OC Fuel Projects ,

. Approvals:

S- T IL 90 Manager, I Dat's

, OC Fuel Projects i t.

$, f/ 19 Nuclear Analysis & Date -

!. Fuels' Director i l r

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TR #066  !

l Rev 0 Page 1 of 13 TABLE OF CONTENTS PAGE Introduction 2 -i References 3- '

Figure 1 ENC VB Fuel MAPLHCR Limits 4  :

Figure 2 ENC VB Axial MAPLHGR Multiplier 5 Figure 3 GE-239 Fuel MAPLHGR Limits 6 Figure 4 GE-265H Fuel MAPLHGR Limits 7 i

Figure 5 CE-2992 Fuel MAPLHGR Limits 8 Figure 6 GE-299EA Fuel MAPLHGR Limits 9 Figure 7 GE-321B Fuel'MAPLHCR 10 Figure 8 MCPR Limits 11 ,

Figure 9 K gFlow Factor 12 Figure 10 LLHGR Limits 13  ;

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TR #066

. i Rev 0 i Page 2 of 13 [

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i INTRODUCTION ,

Generte Letter ~ 88-16 provides guidance for Technical Specification changes concerning cycle-s w eific limits. The generic letter provides a vehicle for the removal of cycle specific parameters from the Technical Specification and the ,

maintenance of these values within a Core Operating Limits Report (COLR). .The 'i Technical Specification modification also establishes reporting requirements l and includes definitions supporting the proposed changes. The COLR, including any mid-cycle revisions, will be provided for each reload cycle. ,

This Core Operating Limits Report (COLR) has been prepared in accordance with

. the requirements of OC Technical Specification 6.9.4f. The infwrmation in this report was reviewed and approved for use at oyster Creek by means of the cycle 12 Reloa.: Information and Safety Analysis Report (TR-049 - rev 1) dated August 1988. The Cycle 12 fuel / core operating limits were generated using the NRC approved codes and methodologies identified in References 1 through 11.

For each GE fuel design the APLHGR limits provided in the COLR for four-loop l operation are calculated to be the same as the five-loop-limits at all exposure levels provided the idle loop is unisolated. If the idle loop has both its (

suction and discharge valves closed the loop is isolated as defined in Reference 7 and a 0.98 MAPLHGR multiplier must be applied at all exposure levels. Requirements for operation with an idle loop are provided in Specification 3.3.F.

The ENC VB fuel five-loop APLHGR limits have been removed and replaced with the more conservative four-loop values for both four and five loep operation. ,

During power operation thermal margins should be maintained within the specified limits. If at any time during power operation it is determined by ,

normal surveillance that the limiting value for APLHGR, LLHGR or CPR is being exceeded action shall be initiated to restore operation to within the prescribed limits as specified in Technical Specification Section 3.10.

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TR #066 Rev 0 Page 3 of 13 REFERENCES

1. Letter from J. N. Donahew, Jr. (NRC) to P. B. Fledler (GPUN) dated November 14, 1986, " Reload Topical Report TR 020 (TAC 60339)."
2. Letter from A. W. Dromerick (NRC) to P. B. Fiedler (GPUN) dated September 27, 1987, GPU Nuclear Corp. (GPUN) Topical Report TR 021, Revision 0,

" Methods for the Analysis of Boiling Water Reactors Steady State Physics".

3. Letter form A. W. Dromerick (NRC) to P. B. Fiedler (GPUN) dated March 21, 198i GPU Nuclear Corp (CPUN) Topical Report TR-033, Revision 0, " Methods for the Generation of Core Kinetics Data for RETRAN-02 (TAC No. 65138)"
4. Letter from A. W. Dromerick (NRC) to P. B. Fiedler (GPUN) dated March 21, 1988, CPU Nuc.' ear Corp (GPUN), Topical Report TR-040, " Steady State.and Quasi-Steady State Methods for Analyzing Accidents and TransientW" (TAC No.

65139).

5. Letter from A. W. Dromerick (NRC) to E. E. Fitzpatrick (GPUN) dated October 12, 1988, GPU Nuclear Corp. (GPUN) Topical Report TR-045, "BWF.-2 Transient Analysis Model using the RETRAN Code" (TAC No. 66358).
6. NEDE-24195; General Electric Reload Fuel application for Oyster Creek.
7. NEDE-31462P; " Oyster Creek NGS SAFETY /CORECOOL/GESTR-LOCA LOSS of coolant Accident Analysis", August 1987.
8. GPUN TR-049 Rev.1, " Reload Information and Safety Analysis Report for Oyster Creek Cycle 12 Reload", dated 7.ugust 19, 1988.  !
9. Letter f rom A. W., Dromerick (NRC) to E. E. 'titzpatrick (GPUN), dated October 31, 1988, " Issuance of Amendt ent" (TAO No.'67743).
10. XN-75-55-(A), XN-7$-55, Supplement . .- ( A ) XN-75-55. Supplement 2-(A),  !

Revision 2,." Exxon Nuclear Company WRE.t-B4 sed NJP-BWR ECCS Evaluation Model and Application to the Oyster Creek plaat," April 1977.

( 11. XN-75-36 (NP)-(A), XN-75-36 (NP) Supplement 1-(A), " Spray Cooling Heat ,

Transfer phase Test Results, ENC - 8 x 8 BWR Fuel 60 and 63 Active Rods, Interita Report," October 1975. .

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FIGURE .1 Tech Spec 3.10.A -

ENC VB FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR UNEAR HEAT GENERATION RATE

{ (FOUR AND FIVE LOOP OPERATION)

. . . . . . . DATA POINTS

)M 12 -

1

. . .  : i I

a .

I

!: l l l  : i W I M B" O - 1 I I - Om e.se 3 11- ------ J------

I L______J________

I I ~

n, i n,,

~

i 1.20 10.80 k

z I

i

^

I i

- 1.90 10.80

,  ; g i 1 7.00 10.62 O_

---i------

g 10- --------4-------F-- I 33,3o ,om I I -

o -

15.40 10.30 p _ i i I 23.70 10.0s w -

em N -

i i i s2.a0 y 9------- ,------ r----- 7-------

- 40m s.43 3 -

3 -

1 1

=

g i  ! -

i i i - {gg 2 I I I +

8 . . . . 3

. . .a y  : . . . l s . . .

0 10 20 30 40 s.

AVERAGE PLANAR EXPOSURE (GWD/MT)

3 I

L -  !

! Tech Spec 3.10.A 4

FIGURE 2 t

i AXIAL MAPLHGR MULTIPLIER (ENC VB FUEL ONLY)

I 1.1 -

. ,, .. . ,,. ,, ..i...

1 I I I i -

1 i i i  : -

DATA POINTS-

i. E - 1 I I I I -

W _ i I i i I .

m um i-i 1.0 -

p-

L____L____1 I- 1 I 1

I I

I d _

I I I I I

_ 2 0.92 2 -

g g g l -

4 0.96 ]

! E -

1 I I I 6 1.00

@ 0.9

--F----F----F----F----F----

_J - I I I I i - 8 1.00 Q- 1 I I I I y

_ I I I I I 10 1.00 I I I I i 12 1.00 I I I I I O.8 ---

r--- r--- r--- r--- r---- 1

~ -

l I I I I 1 I I i 1 1 I I I i -- e g

- 1 I I I I - j 0.7 0

...j...l..

2 4 6 l...l...j...

8 10 12

=f s,

CORE HEIGHT ' (FT) . C

i FIGURE 3 Tech Spec 3.10.A - l j

GE-P8DRB239 FUEL  ;

MAXIMUM ALLOWABLE AVERAGE PLANAR

UNEAR HEAT GENERATION RATE DATA POINTS  !

i

{ (FOUR AND FIVE LOOP OPERATION)

N 3 12 , , , , ,,,,,,.,,,,,,,,,,,,, N (N

Y -

1 I i 1 0.22 10.2

' v - g i l l -

(r - 1 I I l .

1.10 10.2 l

- 1 I I I - 5.50 10.2 a ll -----F-----F-----F-----F----- ii.00 10.2

y  : i i i  : , 2 0.,

l 3-O,. - -

l I

l I

l I

==

27.50

=

8.8

g 10 -----F--- -F-----F-----F----- no, ,,, j l c - 1 I I i -

j g - 1 I I- - 38.50 8.7 -

l w -

3 3 3 -

M.00' 8.7 i I I i -

I I I I 50.00 8.1 2 9 ----

F---- F-F---- F-----

D 1 1 i r~. '

i _

2 -

I 't I I g -

1 I I I - im y - 1 I I I 8 . , , ,

l , , ,

l , , . -t , , , ,

M)g 0 10 20 30 40 50 s AVERAGE PLANAR EXPOSURE- (GWD/MT) c

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

,_- . - _ . . - - - _-__.I

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L FIGURE 4 Tech Spec 3.10.A L

GE-P8DRB265H FUEL . 4 MAXIMUM ALLOWABLE AVERAGE P'Ai:AR UNEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION)

EXPOSU E i

)M 12 . . . . .... ....i ... .; . (GWDM 1 I I I 0.22 10.2  ;

1 I I I -

g , g g g , ,

1.10 10.2 ,

- 1 I I I - 5.50 10.2

! _s11 _ _ _ __L_____L_____L_____L_____ 3 3,,, ,,,,

I I I I ,

k

~

l i I i 16.50 10.0 j

Z I I I I am u i j -

< r I I I I l 1 -

I i  !

27.50 8.8  ;

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--F-- -

F-----F-----F-----

nao ,,.7

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- 1 I I I - 38.50 8.7  ;

w .I I' I i

I I I I M.00 M t i

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I I I I 50.00 8.4 l 7 9 r---- r- - -

r---- r-----

0 D

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1 I I j

y y

1 1

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kgn  ;

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0

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10 20 30 40 50

  1. }

s, l

l AVERAGE PLANAR EXPOSURE (GWD/MT)  ;;

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--g -- -w., -.- ..r, , . . _._f .i.,.. .% ,

a ...<.__.% _ ., ...,._%___ _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . , _ . _ , . , , . _ , . . , . _ _ _ _ , _ _ _ _ .

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. i FIGURE 5 Tech Spec -3.10.A  !

4 GE-P8DRB299Z FUEL i MAXIMUM ALLOWABLE AVERAGE PLANAR  ;

' UNEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION)

N,12 3

....,....,, ..,...,,.... (

. Y -

I I I I 0.22 10.2 I I I I I -

g , g g g g _

1.10 10.2  !

- 1 I I I - 5.50 10.2

_a 11 _____L_____L_____L_____L----- 11.00 10.2 I I I I k

~ ~

f I I I I 16.50 10.1

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l ir l

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I l

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=c~

25.00 co 8.8 l g 10- ------1---- - F - - - - - F .- - - - - F - - - - -

27.50 as l c - 1 I I I -

g - 1 I I I - 33.00 a.a

~ - -

= '

l ~

l l l l ~

l I I 44.00 8.6 l'

2 9 - - --- -

r----- ----

r---- r----- 50.00 8.4 s- - - i N!

g l l l ~; N_

$p

g -

1 1 I I -

I 8 . . . . I. ....I i ....I , . . . . i . ... =

0 10 20 30 40 50 s.

AVERAGE PLANAR EXPOSURE (GWD/MT) c

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

_ , . _ _ , _ - . _ - _ _ _ _ , . . , . . . . ,,..n. ~ , . , , a <<, -.......w, , ,.v:

u ~ - ----m - - - - - - - - - - - - - - - - -- .

1 FIGURE 6 Tech Spec 3.10.A l i

GE-P8DRB299ZA FUEL  !

! MAXIMUM ALLOWABLE- AVERAGE PLANAR

! UNEAR HEAT GENERATION RATE DATA POINTS

p (FOUR AND FIVE LOOP OPERATION)
\,12 ........................ (

M -

1 I I- I 0.22 10.2 '

i -

1 I I 1 1&2 1.10 tr - 1 I I I -

I I I 5.50 10.2 l

@ - 1

_____L_____L_____L_____L-----

_i11 I I I I 11m 10.2 I; k

1 I I i 18.50 10.1 Z I I I I 25.00 8.8 l

j i i I I (1. w I I I 27.50 8.8 g 10- - - - - - - F - - - N -I F - - - - -l-F - - - - -I I- - - - - - non g, l c - 1 -

g - 1 I

I

- 38.50 8.8 i w - -

44m 8.8 g ,

I I

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50.00 8.4 y 9 ----

r---- r- --

r---- r-----

' ' ~

~'

N!

~

3 _ _

g -

l l l ~; N . ,

7 - 1 I I I i

- lp -w 8 ....i....i....i

. . . . . . . . . ... =g 0 10 20 30 40 50 s.

AVERAGE PLANAR EXPOSURE (GWD/MT) c

-l

~ . _ _ .

1

- t FIGURE 7 Tech spec 3.10.A GE-P8DQB321 FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT- GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION)

N g 12 a
: a g ia s : [ 3 a s I s i s I a u ( ,

! M '

I I I I -

0.22 10.4 1 I I I -

g , , g , ,

1.10 10.5 O _ l i I I - 5.50 11.0 b 11- --- - L____ L_____L_____L-----

I I 11.00 11.5 l 1 I ~

k

, 1 I I 16.50 11.3 l

l 8-

n. -

l 1

I l

I l

I

= oc 27.50 c

9.5 g 10- ------F-----F- ---F-----F----- nao g3 e - I I I I -

p _ l i I i *~; I I _ 38.50 9.4 w I '

1 ^

44.00 9.4 l i I I I I I I 50.00 8.7 y 9 ----

r---- r---- r---- r--- -

3 1 I I I ,

2 -

1 I I I q -

i I

I I

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1 I

y

$gg JE *

.1 8 a s a s l s a  : s I 1

y a a a

- i g s s :

i I a i s u

.g

-0 ..'10 20 30 40 50 AVERAGE PLANAR EXPOSURE (GWD/MT) u

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

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L FIGURE 8 Tech Spec 3.10.C q g

MINIMUM CRITICAL POWER RATIO-(MCPR) l

~

l~ APRM STATUS MCPR Limit V

1. If any two (2) LPRM assemblies which 1.51 ore input to the APRM system and are separated in distance by. less than e three (3) times the control rod pitch l contain a combination of three (3) out i

of four (4) detectors located in either

! the A and B or C and D levels which

! ore failed or bypwd (i.e., APRM channel or LPRM input bypassed or inoperable.) q

2. If any LPRM input to the APRM system 1.51 j at the B, C, or D level is failed or bypassed .or any APRM channel is inoperable (or bypassed). i
g
3. All B, C, and D LPRM inputs to the 1.51 4h

-: E APRM system are operating and no g APRM channels are inoperable or g by possed.

l

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

j FIGURE 9 Tech Spec 3.10.C-ILOW FACTOR, Q o  :

n, . . . . . . . . . . . . . .. j DATA POINTS  !

o _ _

FLOW 107R.OWMAX 112 11 (s)7 4 0.3 1.21 1.25 1.28 f 0.4 1.17 1.20 1.22 i (E  !

O 0.5 1.13 1.16 1.17 1 Oo 0.6 1.08 1.11 1.13

' de

  • 0.7 1.04 1.07 1.09 i g" MANUAL FLOW CONTROL i

1 y SCOOP TUBE POSmON 0.8 1.00 1.03 1.05 ,

UMTED SUCH THAT .

FLOWMAX = 107.0 s 0.9 1.00 1.00 1.00 i

= 112.0 m  !

o = 117.0 s 1.0 1.00 1.00 1.00 o--

t

$5 o 4 G. i i .. i . i i i . . i . i. Gg 0.20 0.30 0.40 .O.50 0.60 0.70 0.80 0.90 1.00  %

FRACTION CORE FLOW G 1 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - = _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ - . . . _ _ - _ .- _ . - - . -

q

s. .

FIGURE 10 Tech Spec 3.10.8 LOCAL LINEAR HEAT GENERATION RATE (LLHGR)

FUEL TYPE LHGR Umit 1

. 1. ENC VB LHGR < LHGRd -

(Pj max (LTj  !

tr4Gffs = 14.5 kw/ft AP/P = 0.039 (Max power spadng penalty) '

LT = 144 inches (Total fusi length) '

L = Axial position ateve bottom of core e.

! 2. GE8x8R LHGR < 13.4 kw/ft i

GE8x8EB l

i 12g Mk i

=2 s &

h S.

4 4

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

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