ML20128L589

Rev 4 to Oyster Creek Cycle 14 Colr

ML20128L589
Person / Time
Site:	Oyster Creek
Issue date:	12/24/1992
From:	Douglas J GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20128L577	List: ML20128L573 ML20128L589
References
066, 066-R04, 66, 66-R4, NUDOCS 9302190303
Download: ML20128L589 (12)

Text

- _ _ _ _ .

e e, .,,

s= '.

?p . .

• oyster Creek Cycle 14 Core Operating Limite Report-Topical Report -.066 Rev. 4 ._

.,y BA Nure.ber - 335400 s Date: December 22.-1992 Prepared: MD

, Engineer M -

!E Date-OC Fuel Projecto ,

' Approvals: ,

4%

Manager, /

n/ule Dath '

,, OC Fue' Projects-

/ /Z*24-7L._

Director, Date Nuclear Analysis and Fuel 9302190303 930205 PDR ADOCK 05000219-P- _PDR

.y

4

. . s?.

s - ,e

+i' ~

, =l r

W g f DOCUMENT Nov :

TRd 066 ' ' .'

~

• - TITLE L oyster creek' cycle- 14 core operating Ilmits. Report -

t

SUMMARY

OF CHANGE - APPROVAL. DATE:

=

REV:

,1 _ Technical Specification' references were added- 7/11/90, to:each Figure. -

2 Correction to - several typographical- errors - 11/14/90-

..were -made. ,

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 safety anallsis results. APLHGR

.5/1/91' l limits (Figures 8 and 9) for two new' fuel designs were added. Also the MCPR limit.

(Figure 30) changed from 1.51 to 1.48.

4- Revise document to reflect the. Cycle.14-design and safety. analysis-.results.. MAPLHCR limits for ENCVS,_GE-239,-GE-265H:and.GE-

+

/ &&%

299ZA fuel designe were removed. -MCPR limit changed from 1,48 to l.47. _LLHGR limit for ENCVB fuel was removed.

I a

-. }

9 N0036 (03-90) la y

1 4

r n *- -- ---e- - - - -

.__5_.______.___ _________________-___.____.________m___________.____.____-_b__-_____.________'

TR 066 Rev. 4 Page 1 of 10 TABLE OF CONTENTS Pace

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Introduction

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 References 4

Figure 1 GE-299Z Fuel MAPLHGR Limite . . . . . . . . . . . . . . . . . . .

Figure 2 GE-321B Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . . . 5 Figure 3 GE-338-12GZ Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . 6 7

Figure 4 GE-338-11GZ Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . .

Figure 5 M0PR Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Figure 6 F3 Flow Factor . . . . . . . . . . . . . . . . . . . . . . . . . 9 Figure 7 LLHGR Limits . . . . . . . . . . . . . . . . . . . . . . . .. . 10 8

_.________m_ . _ ____

TR 066 Rev. 4 i

page 2 of .)

i l

INTRODUCTION Generic Letter 80-16 provides guidance for Technical specification caanges concerning cycle-specific limits. The generte lettet prcviden a vehicle for the rernoval of cycle specific para.tnoters from the Technical specification and th) reaintenance of those valuuo within a Core Operating Limits Report (COLR). The Technical Specification modification also establishes reporting requirements and includos definitions supporting the proposed changes. The COLR, includinr1 mid-cycle revisienn, 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 f or une at Oyster Creek by means of the Cycle 14 keload Inf ormation and Saf ety Analysis Kaport (TR-90-rev 0) dated Decentser 1992.

The cycle 14 fuel / core operating limits were generated usinct the HRC approved codes ar.d methodologies identified in References 1 through 8.

For each GE fuel design the APLHGR limita provided in the COLR for four-loop -

operation are calculated to be the earte ao the five-loop limits at all exposure lovels provided the idle loop is unisolated. If the idle loop has both its nuct on and discharge valves closed the loop is isolated as defined in He!% snce 6 and a 0.98 MApLilGR multiplier must be applied at all exposure levels.

kequiremento for operation with an id10 loop are provided in Technical Specitication 3.3.F.

Dur ing power operation thermal margine chould be maintained within the specified Irmico. If at any t irte during power eporation it is determined by normal surveillance that the limiting value for APLilGR (Figures 1-4), LLHGR (Figure 7) or CPR (Figuren 5 and 6) is being exceeded action shall be initiated to reetore operation to wit bin the prencribed limito as specified in Technical Specification Section 3.10.

013/018

TR 066 t Rev. 4 j

Page 3 of 10 REFERE!1CES

1. Letter from J. H. Donahew, Jr. ( tlRC ) to P. D. Fiedler (OPUN) dated Noven.ber 14,1986, "Relo:d Topical Rey. ort TR 020, Revision 0 (TAC 60339) .*

2. Letter from A. W. Dromerick (NRC) to P. D. Fiedler (GPUN) dated September 27, 1987, GPt' tauclear Corp. (CPUll) Topical Report TR 021, Revision 0, 'Hothods for the Analysis of Boiling Water Reactors Steady State Physico."

3. Letter from A. W. Dromerick (flRC) to P. D. Fiedler (GPUti) dated March 21, 1988, CPU Nuclear Corp (GPUll) Topical Report TR-033, Revision 0, "Hethods f or the Generation of Core Kinetics Data f or RETPAN-02 (TAC No. 65138)"

4. Letter from A. W. Dromerick (flRC) to P. B. Fiedler (GPUN) dated March 21, 1988, CPU Nuclear Corp (GPUN) Topical Report TR-040, Revision 0 " Steady -

State and Quasi-Steady State Methods for Analyzing Accidents and Transients" (TAC llo. 65139).

5. Letter from A. W. Dromerick (IIRC) to E. E. Fitzpatrick (GPUN) dated October 12, 1988, GPU Iluelear Corp. (GPUti) Topical Report TR-045, Revision 0 "bwR-2 Transient Analysis Model using the RETPAll Code" (TAC tio . 66358).

6. NEDE-31462P; ' Oyster Creek fich SAFETY /CORECOOL/CESTR-LOCA LO3s of coolant Accident Analysis," August 1987.

7 GPUN TR-090 Rev. O, *- load Information and Saf ety Analysis Report for Oyster Creek Cycle 14 neload," dated Decer.ber 1992.

O. Letter from A. W., Dronerick (11RC ) to E. E. Fitzpatrick ( GPU!!) , dated October 31, 1988, "Insuance of Amendment No. 129" (TAC No. 67743).

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

ruel. _

10. Letter WHO: 91-002, W.H. Hetzel (GE) to R.V. Furia (GPUN) dated January 14, 1991, " Oyster Creek Beload 12 MAPLHGR Calculation".

013/018 l

5

. . .i .

4 t

FIGURE .1 Tech Spec 3.10.A' GE-P8DRB299Z FUEL h

MAXIMUM ALLOWABLE . AVERAGE PLANAR

^

LINEAR HEAT GENERATION RATE DATA POINTS -

(FOUR AND FIVE LOOP OPERATION)

EXPOSURE . MAFLHGR p12 ....i....

......... .... (WD/WQ (W/FQ i -I -

0.22 3 i p 1 10.2 i i i -

i 1.10 10.2 oc _ i i i _

0 i i  ! I - 5.50 10.2 l 7 .-

>- 11 f-----f-----f-----h-----

[ 11.00 10.2

~ -

l $ i i i  : 1s.so 10.1

(

l g-

n.  := =

l i=

l i

l i

l i

2o.=

25.00

..a 8.s L j10- ------.1----- - - - - - - - - - F - - - - -

2m as c - .I I- I i -

.<1 - 1 I I. I - 33.00 a.s E I I- 1 I Lt! . - -

38.50 8.6 l, g- 1 I I. I I 1 I 44.00 8.6 l-1 9-r----- - - - -

N r -- - - -

r - - - - -

- 50.00 a.4 i -

i

.1 -

Mg i i i N ,

v

- 1 I I i -

g a,a 7 ~ ;8

• ]

L ....j....j....j....j....i

+ .

0 10 20- 30 40 50 s.

AVERAGE- PLANAR ' EXPOSURE- (GWD/MT) g

s 4

FIGURE 2 Tech Spec 3.10.A-1 GE-P8DQB321 FUEL .

, MAXIMUM ALLOWABLE. AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS -

l { (FOUR AND FIVE LOOP OPERATION) EXPOSURE MAPuiGR-p12 . . . . . .... .. . ... .... (WD/MQ (W/f-Q M -

1 I I i -

0.22 10.4 1 I I i -

l g _ _g g g _

1.10 10.5

, . - 1 I i  ! - 5.50 11.0

. _J 1 1 ____ _ _L_____L_____L_____L----- 11.00 11.5 i i  ! i I ~

k

~

l. l I i i 16.50 11.3 l:

4:

-O_

l I

l I

l i -

25.00 27.50 9..

9.5 L g10-- - - - - - I- - - - - - t- - - - - i - - - - - - - - -

I 3,oo ,3 g - 1 1 -

< _ 1 I I I - 38.50 9.4 44.00 9.4

~

l l ,

~

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

y -

D 1 I I I ,

2.- -

I I I I i

1 4y 5

I:

I

! l ..

1 I

7p g.

8 -.,.

. .'l . . . . .l . . . .i . . . . l . . . .

=$

L 0 :10 20 13 0 40 50 s,

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

RGURE 3 Tech Spec 3.10.N GE-P8DQB338-12GZ FUEL .

MAXIMUM ALLOWABLE AVERAGE PLANAR

^

LINEAR HEAT GENERATION RATE DATA POINTS -

b (FOUR AND FIVE LOOP OPERATION) exeosuae w wca p12 . . . . .. .. .... .., ....

I (GWD/MQ Q<W/FQ g [ l I

i I

I I

I I

[ 0.22 9.93 g

, g g g 1.10 10.07

$11----

' - - - - - 5.50 10.97

l l , l  : ii.co s i.50 k

z 1

i I I i

I -

16.50 10.90 22.m 9.70 4,10-- ----

r----- ----

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

a. _

l I .

i .

I

27.50 9.60 111- - -

33.00 9.60 (3 _ l I I _

9------ '---- '---- ' 38.50 9.e w

u.oo

e.s3 1 I I I 1 I I I -

50.00 7.85 y -

1 I I I o 8------ r---- r---- r---- r---- ,

g

i i i i  :

y _

i i i 1 -

7 2 -

l l l l

%pi 7 ... . . .... .... .... .... =g 0 10 20 30 40 . 50 s AVERAGE PLANAR EXPOSURE (GWD/MT) s  :

e+

i R.

FIGURE 4 Tech Spec 3.10.N

GE-P8DQB338-11GZ FUEL . .

MAXIMUM ALLOWABLE - AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS -

{ (FOUR AND FIVE LOOP OPERATION). .,

- unma i

[ 12 _

. . . . .... .... .........j (GWD/WO (N/FD l l i i 6 __

1 I

I I 0.22 10.22 ,

., . g , , , ,

1.10 10.30

} { l11_ ______L__ _ _ L _ _ _ _ _I_ _ _ _ _ _ L _ _ _ _ - 5.M 11.18

[ l l_ [ 11.00 11.50 kZ '-

I 1

! I I

I I

16.50 10.90 i

22.00 s.70 310-O_

~

r-----

I I r----

l ,

r-----

I 27.50 9.00 i

tt!

33.00 s.60 (3 ._

l 1 -l -

@9 ---- '---- '-------- ' ----- 38.50 s.* -

' I' '

. LLI . 44.00 8.70  :

1 I -I I -

-I 50.00 7.95

• 1 I I -

y -

1 l' I I o 8------ r---- r---- r---- r---- , ,

1

~- - '

5c I '4 i- I ozig -

, , , i at t 2 -

I

• • • t 7 .... . . .. I. . . . . ii- ,' . .. . . . . . .

I.

i- . . . .

i. u O 10 12 0. '30 40 50 s. t 1 AVERAGE PLANAR EXPOSURE (GWD/MT) g

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

j TR #066- l Rev. 4- 1 Page 8 of 10 FIGURE 5

. MINIMUM CRITICAL POWER RATIO (MCPR) - TECH SPEC-3.10.C i l

i APRM. STATUS MCPR. LIMIT- l

\

1. Ir ANY TWO (2) LPRM ASSEMBLIES WHICH- 1.47 j

ARE INPUT TO THE APRM-SYSTEM AND ARE SEPARATED IN DISTANCE BY LESS THAN l THREE (3) TIMES THE CONTROL ROD PITCH  !

-CONTAIN A COMBINATION OF THREE (3) OUT Or ,

FOUR (4) . Dr.TECTORS 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.) l

2. IF ANY LPRM INPUT TO THE-APRM SYSTEM AT 1.47 THE B, C, 'OR D LEVEL IS FAILED: 0R BYPASSED ' '

OR ANY APRM CHANNEL IS INOPERADLE (OR BYPASSED)..

1

3. ALL B, C, AND D LPRM IHPUTS TO THE APRM 1.47 4 SYSTEM ARE OPERATING AND NO APRM CHANNELS ARE INOPERADLE OR BYPASSED.

V -

i f

l 1

)

=-

e ,a . - . , --,,,....,,..,.,~n.~-,. .--------n-...,-.. .,-,,-.c , + -

).

F  : -

FIGURE 6 Tech Spec 3.10.C-r OW TAC OR, 4

O

• 37

!9 . . . i i e i . . . . . . . . .

j. DATA' POINTS' O _ _

ROW 107ROWMAX 112 11 (s)7

, 0.3 1.21 1.25 1.28 0.4 1.17 1.20 1.22 (Y-O 0.5 1.13- 1.16 1.17 W

Oo_

<C ,_

k -

0.6 0.7 1.08 1.04 1.11 1.07 1.13 1.09 g '~ MANUAL ROW CONTROL y SCOOP. TUBE POSITION O.8 1.00 1.03 1.05 UMiTED SUCH TrMT

- ROWMAX - - 107.0 s 0.9 1.00' 1.00 1.00

= .112.0 m O

= 117.0 s 1.0 1.00 1.00 1.00 C] _ -

~

i o.

m, O

i i . i . i i i i i .. . ..

i

%~$

=

S, 0.20.:0.30 0.40 0.50 0.60 :0.70 0.80. 0.90 1.00 .

O FRACTION 1 CORE FLOW

, e. ~ w - -

. -e+ . n -w- .,r- ..re-~ e 4 =- , - + r. - - .

t TR #066 i Rev. 4 Page 10 of 10 FIGURE 7 1& CAL LINEAR ' HEAT" GENERATION " RATE ~ (LL11GR) - TECH SPEC 3.10.B FUEL TYPE LHGR LIMIT

1. GE8 x BR LHGR s 13.4 kw/rr GE8 x BEB k