ML20077G894

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Rev 3 to Topical Rept TR-066, Oyster Creek Cycle 13 Core Operating Limits Rept
ML20077G894
Person / Time
Site: Oyster Creek
Issue date: 05/21/1991
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20077G892 List:
References
TR-066, TR-066-R03, TR-66, TR-66-R3, NUDOCS 9107030012
Download: ML20077G894 (17)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

Oyster Creek Cycle 13 Core Operating Limits Report Topical Report _,Q.61 Rev 3 BA Number 335400 Datos Aeril 9. 1901 Prepared: M 4,

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i En'gineer Date OC Fuel Projects Approvals:

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Manager, 1 Date OC Fuel Projects a k f S*2* f/

Directory Date Systems Engineering 4

9107030012 910624 PDR ADOCK G5000219 P PDR

CPU NUCLEAR DOCUMENT NO. TR# 066 TITLE Oyster Creek Cycle 13 Core Operating Limits Report REV

SUMMARY

OF CHANGE APPROVAL DATE 1 Technical Specification references were added to each Figure. 7/11/90 2 Correction to several typographical errors were made. 11/14/90 References to the Figures were provided in the thermal margins discussion in the introduction.

Dates and revision numbers of various references were provided.

3 Revise document to reflect the Cycle 13 design and (R,Y.h' $((4/

safety analysis results. APLHGR limits (Figures 8 8 and 9) for two new fuel designs were added. Also the MCPR limit (Figure 10) changed from 1,51 to 1.48.

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TR #O66 Rev 3 Fage 1 of 15 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-299%A Fuel MAPLHGR Limits 9 Figure 7 GE-321B Fuel MAPLHGR Limits 10 Figure 8 GE-338-12GZ Fuel MAPLHGR Lim.i*g 11 Figure 9 GE-338-11GZ Fuel MAPLHGR Limits 12 Figure 10 MCPR Limita 13 Figure 11 K g Flow Factor 14 Figure 12 LLHGR Limits 15

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9 TR #066 Rev 3 Page 2 of 15 INTRODUCTION Generic Letter 88-16 provides guidance for Technical Specification changes concerning cycle-specific limits. The 99neric 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 establishes reporting requirements and includes definitions supporting the proposed changes. The CC'.R, 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.lf. The information in this report was reviewed and approved for use at Oyster Creek by means of the Cycle 13 Reload Information and Safety Analysis Report (TR-76-rev 0) dated March 1991. The Cycle 13 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 limite provided in the COLR for four-loop 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 auction and discharge valves closed the loop is isolated as defined in Reference 7 and a 0.98 KAPLHGR multiplier must be applied at all exposure levels. Requirements for operation with an idle loop are provided in Technical 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 leop 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 (Figures 1-9), LLHGR (Figure 12) or CPR (Figures 10 and 11) is being exceeded action shall be initiated to restore operation to within the prescribed limits as specified in Technical Specification Section 3.10.

TR #066 Rev 3 Page 3 of 15 REFERENCES

1. Letter from J. N. Donohew, Jr. (NRC) to P. B. Fiedler (CPUN) 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 'IR 0:1, 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, 1988, GPU Nuclear Corp (GPUN) Topical Report TR-031, Revision 0, " Methods for the Generation of Core Kinetics Data for RETRAN-02 (TAC No. 65138)"
4. Letter from A. W. Dremerick (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 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).
6. NEDE-24195; General Electric Reload Fuel application for Oyster Creek.

Daced May 1984.

7. NEDE-31462P; " Oyster Creek NGS SAFETY /CORECOOL/GESTR-LOCA LOSS of coolant Accident Analysis", August 1987.
8. GPUN TR-076 Rev.0, " Reload Information and Safety Analysis Report for Oyster Creek Cycle 13 Reload", dated March 1991.
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 - 8 x 8 BWR Fuel 60 and 63 Active Rods,

! Interim Report," October 1975.

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12. NEDE-24011 Revision 9, General Electric Standard Application for Reactor Fuel.
13. Letter WHO 91-002, W.H. Hetzel (GE) to R. V. Furia (GPUN) dated January 14, 1991, " Oyster Creek Reload 12 MAPLHGR Calculations",

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FIGURE 1 Tech Spec 3.10.A

, i ENC VB FUEL . i

> MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE

{ (FOUR AND FIVE LOOP OPERATION)

DATA POINTS

)M12 -

. . . .. i 1

i, ..

I

....i....

I U

l 1

_ EXPOSURE MAPLHGR l

i (GWD/MO (KW/FO e _ i i _

O _ l I I _ 0.00 s.se 3 31_ _______J_______L______J------- I I I 0.50 10.65 k

Z

[ ,

i I l

I 1

1.20 10.80 10.80

- 1.90 g  ;

1 I 7.00 10.62 O_

g 10- --------i-------F-- - -------

33,3o 30.33 I I -

e - 1 i i i 15.40 10.30  ;

i <C _

1 I I '

W -

1 23.70 10.03 I I I 32.80 9.89 I I I i

2 9------


r----- 7------- _ 40.00 9.43 *

) I l I .

2 -

1 I I l X -

1 I i -

Tag

< i i i -

at -

2 -

, , , *4 i

8 . . . . i . . ..i ... .... +g

) 0 10 20 30 40 2.

. AVERAGE PLANAR EXPOSURE (GWD/MT) G

Tech Spec 3.10I

~

FIGURE 2 -

AXIAL MAPLHGR MULTIPLIER 1 (ENC VB FUEL ONLY) 1.1 ... ....... ... ...i...

1 I I i 1 i i i i i -

DATA POINTS I

E .' I I I I i -

d - 1 I I I I -

HEIGHT WULTIPIER

$1.0--

I- -

- - - - F - - - - l- - - - , , ,

o o I I I I 2 0.92 d _

I _

A 0.96 2 -

g i g g g E -

1 I I I 6 1.00

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

_j 0.9 -- 1 I I I I - 8 1.00 Q- 1 I I I I -

10 1.00 i l 1 I i _

7 _

I I I I 12 1.00 I _

I I I I I O.8 - - -

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

1 I I I i 1 I I i l y

1 I I I i -

- 1 I I I i -

%gg ,

~' O 1 0.7 ..

I

. ..i.

I

.I. . . . I. . . .

I

. . . . =g i

0 2 4 6 8 10 12 2.

CORE HEIGHT (FT) G

t FIGURE 3 Tech Spec 3.10X -

GE-P8DRB239 FUEL .

I

-MAXIMUM ALLOWABLE AVERAGE PLANAR  ;

LINEAR HEAT GENERATION RATE DATA POINTS

^

t t (FOUR AND FIVE LOOP OPERATION) EXPOSURE MAPLHGR (WD/MO (W/FO

)M 12 -

1

...i I

I

....i...,

I 0.22 10.2

  • I I 1 I 1.10 10.2

. gr _ l 1 I i _

0 _ l i I I - 5.50 10.2 b 13_______L_____L_____L_____L----- 1 1 I l 11.00 10.2

~

~

i I I 16.50 10.1 2

l I ' I '

_ 25.00 8.8 j _

i l i I 27.50 8.8

. O., -- -

i i i 1

, g 10- ------I---- - F - - - - - I- - - - - - F - - - - - 33.00 8.8 g _ i i i 1 -

_ l l l _ 38.50 8.7  !

I I I I 12J -

44.00 8.7 4 I I I i  ;

>4 I I I I 50.00 8.1  :

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

= -

a -

1 I i Ni _

! 2 -

1 I I I l

X -

I I I I -

ggg 2

I .;

l l l l .

a g

8 . . . . i....i....i....i....

0 10 20 30 40 50 E AVERAGE PLANAR EXPOSURE (GWD/MT) G ,

FIGURE 4 Tech Spec 3.10.K GE-P8DRB265H FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION) EXPOSURE IJAPLHGR

.>.,,... i.... .... ("D/u0 (N/FO p12 - .. . . .

I I i 0.22 10.2 ,

f -

1 1 I I I

1.10 10.2 g ,

i 5.50 10.2 I I -

0 1

_____L_____L_____L_____L_____

, g,,

b 1 1_ I I I I ~

3 3,gg I 16.50 10.0 i

k I

~

l I

' _ 25.00 8.8 I

27.50 8.8

e i I n_

--F-- -F--F----F--- 33.00 8.7 g 10-I I i -

g - 1 38.50 8.7 l l 1 _

<t' _

l E I I I -

44.00 8.5 W -

I I I I

50.00 8.4

<> I i 7 9---- -

I r-I r- -r--r---~ .1 I -

D 1 -

3 -

1 I I

I I i

' ggg X

2 1

l l l E3

  • g l,... .. i... i. .i 8 .... i 40 50 E 0 10 20 30 G

AVERAGE PLANAR EXPOSURE (GWD/MT)

L FIGURE 5 Tech Spec 3.10.A

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GE-P8DRB299Z FUEL ..

MAXIMUM ALLOWABLE. AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS

^

t (FOUR AND FIVE LOOP OPERATION) EXPOSURE MAPUiGR (WD/MD (N/F-Q p12 . . . . . .... . .. ....

I 0.22 10.2

. M 1 I I 1 I I I g

1.10 10.2 g , , g g _

0 _ i I i I _ 5.50 10.2 3 11 _____L_____L_____L_____L-----

~

11.00 10.2

~

l I i 16.50 10.1

% ' ' ' 9.0 2 I

_ 20.00 l j  ::

l i I I

I I

25.00 8.8

[

i 1

O_

g 10-------I---- - - - - - F - - - - - - - - - 27.50 8.8 ,

I i 1 -

e - 1 I I I 33.00 8.8  :

<C _ 1 _

E I I I I -

38.50 8.6 b.I -

l 1 I I I I 44.00 8.6  !

I I 2 9- -----

r----- - - - -

r---- r - - - - --_ 50.00 8.4 3

' ,N ,. .

?  : l l l ~; N m at

< i i i I ~

2 -

  • 3-8 . . . . i....i....i i i ...i. i .. =g l 0 10 20 30 40 50 R '

'i AVERAGE PLANAR EXPOSURE (GWD/MT) G I

FIGURE 6 Tech Spec 3.10.A' GE-P8DRB299ZA FUEL ..

MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS j

{' (FOUR AND FIVE LOOP OPERATION) EXPOSURE MAPuiGR (GWD/MO (W/FO p12 . . . . i ... .... .... .... '

g 0.22 10.2 1 I I I 1 I I i -

1.10 10.2 6 I

g _ g g g g ,

- 1 I I I - 5.50 10.2

_J 1 1_ ______L_____L_____L_____L-----

I I I I ~

11.00 10.2 k

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l l I I 16.50 10.1 i 25.00 8.8 l l _

I 27.50 8.8 a i 1 I ,

10-- - - - - - I- - - - - F - - - - - I- - - - -- F - - - - - 33.00 8.8  !

g I I -

I o - 1 i i i 38.50 8.6 ,

<C _

% I i I i -

44.00 8.6 i IB -

I I I I ~

>4 I I l I 50.00 8.4 7 9 -----

r---- r\1-- r---- r------ -

O 1 i i i ii<  : l l l ~; N S ,I l i I I 8 . . ..

I i .. .Ii...

f i . . . .

I i . ... =g 0 10 20 30 40 50 a r,;

AVERAGE PLANAR EXPOSURE (GWD/MT)

I FIGURE 7 --

-ch Spec 3.10.A 4

i -

GE-P8DQB321 FUEL .

MAXIMUM ALLOWABLE AVERAGE PLANAR '

LINEAR HEAT GENERATION RATE DATA POINTS C

h-(FOUR AND FIVE LOOP OPERATION) EXPOSURE E i p12 .........,....

I I

(G40NO (K*

0.22 10.4 M -

1 I [

I I I -

I 1

l 1.10 10.5 l tr - I I i -

l C - 1 i i 1 - 5.50 11.0  !

0 11 -- -L_____L_____L_____L----- 1i.00 11.5

! 1 1 I I -

11.3

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i i I I 16.50 l z  ; i i 1 25.00 s.s  !

j i l i I 27.50 9.5

{

O_

1 I i 1  ;

r g 10 - - - - - i- - - - - - r - - - - - - i- - - - - - i- - - - - - yog ,,

I ' I I -

g -

, _ l i I I - 38.50 9.4 g _

l I

~_i ^

44.00 9.4 i i i i l

<> f I I I mm E7 l

, y 9 ----

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

D I I I i ,

}

j 2 -

i i I i -

a X -

1 I I I -

img i l'

4 7 - I I I . -

h 8 ... j....j....j....j.... si  !

0 10 20 30 40 50 .

l; AVERAGE PLANAR EXPOSURE (GWD/MT)

  • i
i

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FIGURE 8 Tech Spec 3.10 A i

GE-P8DQB338-12GZ FUEL ..

MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA PGINTS j

{ (FOUR AND FIVE LOOP OPERATION) exmue

("M (

12 ~

.: .. . .... ....i. . ..

M l i I I O.22 9.93  !

  • ~

I i I

10.07 4

! - 1.10 E _

i i i I _

'-- ' - - - - ' - - - - - s.50 10.97 i

$11-

_3 -

I I I I -

11.00 11.50

- 1 I I i -

I I 16.50 10.90 l  % -

1  ;

l l

f 10 2 CL

~

'r-----

l i r----

i _

r-----

i 22.00 27.50 9.70 9.80

! i i 9.00

! w -

33.00 l  ! I l c _

38.50 9.40

! < g _____L_____L_____L______L ____ l I E I I I I ~

l W -

44.00 8.63 i I I I I -

>4 -

1 I I I -

30.00 7.85 l

i i i l 2 1 l 2 8 ----

r---- r---- r---- r---- ,

i l 2 ~

I I I I ng

! R ~

I I I i at i I I I T.

y _

- i 7 .... l....l....j....l.... [$

0 10 20 30 40 50 o i

AVERAGE PLANAR EXPOSURE (GWD/MT) 2 i

i <

! . j f

I 1 FIGURE 9 Tech Spec 3.10.A

~

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i GE-P8DQB338-11GZ FUEL .

a 1

i i MAXIMUM ALLOWABLE AVERAGE PLANAR

! UNEAR HEAT GENERATION RATE DATA POINTS 6

l

{ (FOUR AND FIVE LOOP OPERATION) t e s.c (GWD/WO (m/FQ

) 12 .... .... .... .... ....

[

g [ t i I

I I

I I

0.22 10.22

.10 10.30 fr _ I I I i _

(


'-- - '---- '---- '----- s.50 t i.ia

! @ 11 ' ' "

[ g g [ 11.00 11.50 kZ -

1 1

I I I

I i

16.50 22.m 10.90 9.7o l

$ 10 ----r----.----r----r----- 9.00

! Q.

~

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I _

! [ 27.50 f I

I I I 1

id -

1 -

33.00 9.00 i-j I I 4 o _ I, saso c 40

! &9 -


L-----

[ 44.00 a.7o l -

1 I I I i

1 I I I -

50.00 7.95 I I I l 2 1 a 8 ----

r---- r---- r---- r---- ~

! 2 ~

l I 1 i [

l k' [ I I I I [ ygg 2 -

' ' ' ' - 2

) 7 ....i,...j....j....j ...

50 n"f i 0 1G 20 30 40 o i AVERAGE PLANAR EXPOSURE (GWD/MT) 2  !

s t

FIGURE 10 Tech Spec 3.10.C .

MINIMUM CRITICAL POWER RATIO (MCPR)

APRM STATUS MCPR Limit

1. If any two (2) LPRM assemblies which 1,4g l 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 1.48 i

ot the B, C, or D level is failed or bypassed or any APRM channel is inoperable (or bypassed). g il "  ;

3. All B, C, and D LPRM inptds to the 1.48 g !

APRM system ore operating and no g APRM channels are inoperable or g by passed.

l

Tech Spec 3.10.C.

FIGURE 11

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l r _ OW AC~OR, 4 O . . . . . . . . ..

n, i i i i .

DATA POINTS FLOW 107FLOWMAX 112 11 (m)7 O _

0.3 1.21 1.25 1.28 0.4 1.17 1.20 1.22 fr 0.5 1.13 1.16 1.17 O 1.08 1.11 1.13  ;

F- 0.6 O

l

<O 0.7 1.04 1.07 1.09 I g '- MANUAL FLOW CONTROL SCOOP TUBE POSmON 0.8 1.00 1.03 1.05 y 1.00 1.00 1.00 UMITED SUCri THAT 0.9 FLOWMAX = 107.0 z

= 112.0 m i.00 2.00 1.00 o

- i i7.0 . -y._= i.0 q_

O Ne.;8 e O i e i a i i 1 5 1 i I$

9 i i 1 a

o O

0.40 0.50 0.60 0.70 0.80 0.90 1.00 0.20 0.30 G FRACTION CORE FLOW

I FIGURE 12 Tech Spec 3.10.8

! LOCAL LINEAR HEAT GENERATION RATE (LLHGR) i i

FUEL T(PE LHGR Limit l -

1. ENC VB LHGR < LHGR d

_1\.-be/ "= \. _

{ M = 14.5 kw/ft

^

AP/P = 0.039 (Max power spiking penotty)

LT = 144 inches (Total fuel length)

L = Axiol position above bottom of core l.

i

2. GE8x8R LHGR _<; 13.4 kw/ft GE8x8EB l
s m 's
v. .

k G

,m__ , , s - - - - , ---.-,,,-r, -- e v -

w --

~~w- - - - ~ , . - + < - - - - - - - - - - ~ - -