ML20072Q390

Rev 2 to Core Operating Limits Rept 066

ML20072Q390
Person / Time
Site:	Oyster Creek
Issue date:	11/20/1990
From:	Boyd G, Dougher J, Furia R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20072Q386	List: ML20072Q382 ML20072Q387 ML20072Q390
References
066, 066-R02, 66, 66-R2, NUDOCS 9012210192
Download: ML20072Q390 (14)

Text

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l Oyster Creek cycle 12 Core Operating Limits Report

'I Topical Report ,,,Qj.it Rev 2

.i BA Number 335400 Dates November 14 '1990 l

Prepared: C.MD obAE C U f14 b0 Engineer Date OC Fuel Projects.

Approvals:

m v' M Manager, I Date

,. tidw OC Fuel Projects i

b //*20* 9e Director,' Date l

! Systems Engineering l

l 9012210192 901213 PDR ADOCK 05000219 p PDR

TR #066 Rev 0 Page 1 of 13 TABLE OF CONTENTS PAGE Introduction 2 References 3 Figure 1 ENC VB Fuel MAPLHGR Limits 4 Figure 2 ENC VB Axial MAPLHGR Hultiplier 5 Figure 3 GE-239 Fuel MAPLHGR Limits 6 Figure 4 GE-265H Fuel MAPLHGR Limits 7 Figure 5 GE-299Z Fuel MAPLHGR Limits 8 Figure 6 GE-2992A Fuel MAPLHOR Limits 9 Figure 7 GE-321B Fuel MAPLHGR 10 Figure 8 MCPR Limits 11 Figure 9 K fFlow Factor 12 Figure 10 LLHGR Limits 13 l

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, 'TR #066 Rev 2 Page 2 of 13-INTRODUCTION i

Generic Letter 88-16 provideo guidance for Technical Specification changen y concerning cycle-specific limite. 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 Technical Specification modification also establishee reporting requiremente and includes definitions supporting theJproposed changes. The COLR, including any mid-cycle revisions, will be provided'for each reload aucle.

This Core operating Limite Report (COLR) has-been prepared.in accordance with the requirements of OC Technical < Specification 6.9.lf. The information.in this report was reviewed and approved for use at oyster Creek by means of the Cycle 12 R? load Information and Safety Analysis Report -(TR-049 - rev 1)' dated August -

1988. The cycle 12 fuel / core operating.llmite were generated using the.NRC approved codes and methodologies identified in References 1 through'll.

For each GE fue?, design the APLHGR limite.provided in the COLR for-four-1 Jy operation are calculated to be the same as the five-loop limite at - all er < = are levele provided the idle loop is unisolaced. If the idle loop has both ice suction and discharge valves closed the loop is leolated as defined in-Reference 7 and a 0.98 KAPLHGR multiplier must be applied at all exposure levels. Requiremente for operation with an idle loop are provided in Technical l Specification 3.3.F.

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

During power operation thermal margine should tx) maintained within the specified limite. If at any time during power operation it le determined by normal surveillance that the licating value forLAPLHOR'(Figures 1-7), LLHGR (Figure 10) or CPR (Figures 8 and 9) le being exceeded action whall be i

initiated to restore operation-to within the prescribed limite as specified in Technical Specification Section 3.10.

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TR #066 l Rev 2 Page 3 of 13 l l

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REFERENCES

1. Letter from J. N. Donohew, Jr. (NRC) to P. B. Fiedler (GPUN) dated November 14, 1986, " Reload Topical Report TR 020, Revision 0 (TAC 60339)."

2. Letter from A. W. Dromerick (NRC) to P. B. Fledler (GPUN) dated September 27, 1987, GPU Nuclear Corp. (GPUN) Topical Report TR 021, Revision 0, "Mathods for the Analysis of Bolling Water Reactors Steady State Physics".

3. Letter form A. W. Dromerick (NRC) to P. B. Fiedler (GPUN) dated March 21, 1988, GPU Nuclear Corp (GPUN) Topical Report TR-033, Revision 0, " Methods for the Generation of Ccre Kinetics Data for RETRAN-02 (TAC No. 05138)"

4. Letter from A. W. Dromerick (NRC) to P. B. Fiedler (GPUN) dated March 21, 1988, GPU Nuclear Corp (CPUN) Topical Report TR-040, Revision 0 " Steady State and Quasi-Steady State Methods for Analyzing Accidents and l Transients" (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, Revision 0 "BWR-2 Transient Analysis Model using the RETRAN Code" (TAC No. 66358). l

6. NEDE-24195; General Electric Reload Fuel application for Oyster Creek.

Dated May 1984. l

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 August 19, 1988.

l 9. Letter from A. W., Dromerick (NRC) to E. E. Fitzpatrick (GPUN), dated October 31, 1988, " Issuance of Amendment No. 129" (TAC No. 67743).

10. XN-75-55-(A), XN-75-55, Supplement 1-(A), XN-75-55. Supplement 2-(A),

Revision 2, " Exxon Nuclear Company WREM-Based NJP-BWR ECCS Evaluation Model and Application to the Oyster Creek plant," April 1977.

11. XN-75-36 (NP)-(A), XN-75-36 (NP) Supplement 1-(A), " Spray Cooling Heat Transfer phase Test Results, ENC x 8 BWR Fuel 60 and 63 Active Rode, Interim Report," October 1975.

12. NEDE-24011 Revision 9, General Electric Standard Application for Reactor Fuel.

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FIGURE 1 Tech Spec 3.101 i

i ENC VB FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE.

{ -(FOUR AND FIVE LOOP OPERATION)

p12 . . . . . . . . . . . . . . . . . . . DATA POINTS x -

1 I i -

1 l l -

EXPOSURE cr - 1 I I - (" /"O (*

O 1 I I

- - 0.00 - 9.88 .'

i 3 11 _ _ _ _ _ _ J _ _ _ _ ___._ L _ _ _ _ _ _ J _ _ _ _ _ _ _

l I g3 - 3 9,, j I

' Z k ,

I I l

I 1

1.20 '10.80 y y g 1.90 10.80 n_ 1 I 7.00 10.62 l g 10 -- ,--------4-------F--

ii io io 33

.g - 1 I I -

_ 1 I l - 15.40 10.30

! w ' ' ' '

23.70 10.o3 4

l-i i

l l 32.80 ...

I 9 -----

l------ I----- 7------- '

! 40.00 9.43 1

a -

1 I I 2 -

1 I I 4 P i .l l- l  :

1 -

-t

8 . . . . l . . .l .

. . . . lr~. . +g

! 0 10 20 30 40 s. q l

AVERAGE PLANAR EXPOSURE (c"!D/MT) 4 .!

r- ~-+--~-:"

Tech Spec 3.10.A i FIGURE 2 "

AXIAL MAPLHGR MULTIPLIER (ENC VB FUEL ONLY) 1.1 . . , , . . ., ..,,. ,,.,,...

1 I I I I i i i i i -

DATA POINTS Of - 1 I I I I -

1 I I I I HEIGHT MULTIPIER g 1.0 _ ----F'----F--- 1 ' '

o o, d _

I I I I I

_ 2 0.92 2 -

l l l g 3

.4 0.96 Q' -

1 I i 1 6 1.00

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

Q 0.9

_j - 1 I I I i -

8 1.00 O_ l I I I I 10 1.00 y ,- -

I' I I i i 12 1.00 1 I i .1 I 0.8 ----r---r---r---r---r---- 1 1 I l' I I 1 I I I i 1 I' I I i -

N2g

! -1 I I -

kI

=i

- 1 0.7 . . . l ..j...l . l. il...

0 2 4 6 8 10 12 s CORE HEIGHT (FT) C

I FIGURE 3 t Tech Spec 3.10.A GE-P8DRB239 FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR ~

^

LINEAR HEAT GENERATION RATE DATA POINTS 5 (FOUR AND FIVE LOOP OPERATION)

EXPOSURE WPLHGR p12 . . . . .... .... .... .... (GWD/MD (KW/FD E

I I I i -

0.22 10.2 i i i -

O' - l l l _

1.10 10.2 ,

- 1 I I I -

5.50 10.2

_i11 _____ _____ _____ _____ _____

, ,,gg , g,,

k

~

l i 16.50 I I

[ 10.1 25.00 8.8 g l g Q_ i^ i l 1 27.50. 8.8 g 10 F--- - F - - - - - - l- - - - - - F - - - - - 33,gg ,,,

e -

1 I I I -

g

- 1 I I - 38.50 8.7 w - 1 I I I -

44.00 8.7 l l 1 I l- 1 i I 50.00 8.1 y 9 ----

r---- r- --

r---- r-----

2 i  :

- =

i =~ '

2.

l l g  ; -

l g- -

1 I I I -

u

{3,g

. y . I i i i -

8 ....j....j ...l4 . . . l.... .)

O 10 20 30 40 50 a. -

AVERAGE' PLANAR EXPOSURE (GWD/MT)  ;;;

t i

FIGURE 4 Tech Spec 3.10.A GE-P8DRB265H FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR

^

UNEAR HEAT GENERATION RATE DATA POINTS l- (FOUR AND FIVE LOOP OPERATION) mosuae mma p12 .... .... ....i.... .... (GWDNQ (KW/FQ 3

1 I I I -

0.22 10.2 1 I I I -

g _ g , g g ,

1.10 10.2 O i i l 5.50

_ 1 10.2 3

11

- - - - - l- - - - - - f - - - - - f - - - - - l- - - - - - i i.00 10.i j

( ~

I i

~

16.50 25.00 10.0 8.8 0, I I I- -

27.50 8.8 g 10 - - - - - t- - - - t- - - - - - t- - - - - - l- - - - - -

33.oo 7  ;

g- - , 1 I I -

_ i l I i _ 38.50 8.7 w - -

44.00 8.5 l .. I I I I I I I 50.00 8.4 ,

9 r---- r-y r---- r-----

. -) -

1 I . _1 i l l l .

un 1 -

I i I I -

E. ,g 8 ....l....l..>>l. .>l - "

< 0 10 20 30 40 50 a AVERAGE PLANAR EXPOSURE (GWD/MT) C .l

FIGURE 5 Tech Spec 3.10.A GE-P8DRB299Z FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR

^

LINEAR HEAT GENERATION RATE DATA POINTS 5 (FOUR AND FIVE LOOP OPERATION)

EX.N MAPLHGR p12 . . . . ... .... .... .... (GWD/MQ (KW/FQ M -

1 I I I -

0.22 10.2 1 I i 1 -

g _

i I I I _

1.10 10.2 0 I I I

- 1 5.50 10.2 3

11 _____L_____L_____L_____L----- 11.00 10.2

~

l I I I k

~

l i I I 16.50 10.1 l 20.00 9.0

, l

: i n_ 1 I i -

25.00 8.8 g 10 -----I---- - F - - - - - I- - - - - - I- - - - - -

27.50 8.8 g - 1 I I I -

g _

I l I I I I

I I _ 33.00 8.8 t.t.1 - -

38.50 8.6 4 -

I

~

44.00 8.6 2 9 ----

r----- ----

r---- r-----

_ 50.00 8.4 I

> 1 i I wo ky _

g 1

g I

g-I l

I -

T y$

8 .. . i

l. -

..!.. l.. l....

• 0 10 20 30 40 50 s i

AVERAGE PLANAR EXPOSURE (GWD/MT) E:

~

.i

~

FIGURE 6 Tech Spec 3.10.A -

GE-P8DRB299ZA FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR

^

LINEAR' HEAT GENERATION RATE DATA POINTS 5 (FOUR AND FIVE LOOP OPERATION)

EXPOSURE p12 . . . . .... .. .,.. . .... (GWD/MO (KW f

I I I I -

0.22 10.2 1 I i  : -

.g _ g g g g _

1.10 10.2 h - 1 I I I -

5.50 10.2 l _i11 ----- ----- ----- ----- -----

11.00 10.2 k

~ ~

f l i I I 16.50 10.1 g

- 25.00 8.8

i .:

O. I I I 27.50 8.8 g 10 -----F--- - I- - - - - - I- - - - - - F - - - - -

33,oo ,,,

e - I l- 1 I -

_ l i I _ 38.50 8.6 w ' ' ' '

44.00 8.s I I I I

'1 I I I

~

50.00 8.4 j y 9 ----

F---- F-r---- r-----

a -

1 i -

i i

x

!!  : l l l  ;

y i i i

{* ,[ f

- 1 -

8 . . . . 'l.. .j' .. l....l.... s

!, 0 10- 20 30 40 50 AVERAGE PLANAR EXPOSURE (GWD/MT) C

-~

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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)

)M 12 -

. . . . ....,, .., .. ,,,.. wasme (ow0/vo ( T=

1 I I I -

0.22 10.4 1 I i l -

E _

., I I I _

1.10 10.5

- 1 I I I 5.50 11.0

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

'E ~

l i l i

~ '

4 16.50 11.3 g _- l , l l  : 25.00 ...

O. 1 I I 1 27.50 9.5

g 10 -----F-----F-----F-----F----- 3,oo - ,,3 g -

1 I I I -

p _ i I

i  ! i _ 38.50 9.4 w- I N: I 8 ^

44.00 9.4 l'. I I I

>4 _

I I I I 50.00 8.7 y 9 r---- r---- r---

D 1 I I I ,-

2 i i j g -

i i 1 i

1

. yp y -

I s 1 -

14 8 . . . .l.  !....l.... l . .

s3

0 10 ?O 30 40- 50 o AVERAGE PU.NAR EXPOSURE (GWD/MT)' 2

4 FIGURE 8 Tech Spec 3.10.C MINIMUM CRITICAL POWER RATIO (MCPR) i APRM STATUS MCPR Limit

1. If any two (2) LPRM assemblies which 1.51 are input to the APRM system and are separated in distance by less than three (3) times the control rod pitch

, contain a combination of three (3) out of four (4) detectors located in either the A and B or C and D levels which are failed or bypassed (i.e., APRM channel or LPRM input bypassed or

inoperable.)

2. If any LPRM input to the APRM system 1.51

, at the B, C, or D level is failed or bypassed or any APRM channel is inoperable (or bypassed). y=g I 3

3. All B, C, and D LPRM inputs to the 1.51 -: g APRM system are operating and no g APRM channels are inoperable or g by passed.

FIGURE 9 Tech Spec 3.10.~C r

_ OW TAC-~OR, 4 o

q . . . . . . . . . . . . . . .

DATA POINTS o

g _ _

ROW 107ROWMAX 112 11 (s)7

~

<- 0.3 1.21 1.25 1.28 0.4 1.17 1.20 1.22 O 0.5 1.13 1.16 1.17 F-O 0.6 1.08 1.11 1.13

[O -

e 0.7 1.04 1.07 1.09 g" MANUAL ROW CONTROL 0.8 1.00 1.03 1.05 y SCOOP TUBE POSmON UMITED SUCH THAT ROWMAX = 107.0 m . 0.9 1.00 1.00 1.00

= 112.0 m -!

o = 117.0 m 1.0 1.00 1.00 1.00 o- -

V i

8 3il o

2yg{3 O. 8 I 8 I

• I 8 I 8 i .. g 3 o 1 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 U

FRACTION CORE FLOW

- .. . - - -n,

1 FIGURE 10 Tech Spec 3.10.B LOCAL LINEAR HEAT GENERATION RATE (LLHGR)  ;

i FUEL TYPE LHGR Limit

1. ENC VB LHGR 5 LHGRd 1-fP max LT M = 14.5 kw/ft AP/P = 0.039 (Max power spiking penalty)

LT = 144 inches (Total fuel length)

L = Axiol position above bottom of core  !

2. GE8x8R LHGR $ 13.4 kw/ft GE8x8EB 3

ss u " 8,o .

k C

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