Text

Rev 0 to Core Operating Limits Rept
	ML20042G243
Person / Time
Site:	Oyster Creek
Issue date:	02/22/1990
From:	Dougher J; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20042G230	List: ML20042G229; ML20042G234; ML20042G242; ML20042G243;
References
	066, 066-R0, 66, 66-R, NUDOCS 9005110267
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.-l oyster Creek cycle 12 Core operating Limite Seport Topical Report Qi9.

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Rev 0 F

BA Number 335400 t

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Date:

October 24, 1989

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Prepared - (h 1!M f 90 Engineer Date I

OC Fuel Projects 1.

l Approvals -

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Manager, Date"

-OC Fuel Projects 5

2 2.Yfe Nuclear Analysis &

Date Fuels Director 1

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Rev 0 Page 1 of 13

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1 TABLE OF CONTENTS I-PAGE h,

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. Introduction 2

-References.

3 f

Figure 1, ENC VB Fuel MAPLHGR Limits 4

Figure 2 ENC VB Axial MAPLHGR Multiplier

. Figure' 3 GE-239 Fuel MAPLHGR Limits 6

Figure 4 GE-265H Fuel MAPLHGR Limits 7

Figure 5 CE-2992 Fuel MAPLHGR Limite 8

Figure 6 -CE-2992A Fuel'MAPLHGR LLmits 9

1 Figure 7 GE-321B Fuel MAPLHGR 60 9

l Figure.

8-MCPR Limits 11 E

Figure,-9 Kg Flow Factor

~ 1:2 l

. Figure.10 LLHGR' Limits 13 i

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TR #066 Rev 0 Page 2 of 13 INTRODUCTION Generic Letter 88-16 provides guidance for Technical Specification changes concerning cycle-specific 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 Technical Specification modification also establishes'_ reporting requirements and includes definitions supporting the proposed changes.

The COLR, including i

any mid-cycle' revisions, will be provided for each reload cycle.

'This Core operating Limits Report (COLR) has been prepared in accordance with-

.i' the requirements-of OC Technical Specification 6.9.4f.

The information in this report was reviewed and approved for use at Oyster Creek by means of the Cycle 12 Reload 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 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 suction. and discharge valves closed the loop is isolated as defined. in Reference 7 and a 0.98 MAPLHCR multiplier must be applied at all exposure levels.

Requirement s 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 loop operation.

During power operation thermal margins should be maintained within the 1

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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i TR #066 Rev 0-Page-3 of 13 REFERENCES n

1.

Letter from J. N. Donahew, Jr. (NRC) to P. B. Fiedler (CPUN) 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. (CPUN). ~ 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. FiedlerJ(GPUN) dated March 21,=

1988, GPU-Nuclear Corp (GPUN) Topical-Report TR-033, Revision 0, " Methods for the Generation of Core Kinetics Data for RETRAN-02 (TAC No. r3138)"

4.

Letter from A.

W. Dromerick (NRC) to P. B. Fledler (GPUN) dated March 21, 1988, GPU Nuclear Corp (GPUN) Topical Report TR-040, " Steady State and 1

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, "BWR-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 August 19, 1988.

9.

Letter from A.

W.,

Dromerick (NRC) to E.-E..Fitzpatrick (CPUN), dated October 31, 1988, " Issuance of Amendment" (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 j

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 Ruls, Interim Report," October 1975.

4 l

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FIGURE-1 l

ENC VB FUEL MAXIMUM ALLOWABLE-AVERAGE PLANAR t

LINEAR HEAT GENERATION RATE

{

(FOUR :AND FIVE LOOP OPERATION).

DATA POINTS N 12 i

i h

i i.

i (GWD/MD (KW/FQ i

i i

i iiiiiiiiii EXPOSURE M WLHGR l

1 I

I 0.00 9.88' h

l l

l 0.50 10.65 T_ 13

___..__J_______L______J_______

1.20 10.80 i

I i

y g

1.90

'10.80 h

I i

7.00 10.62

~

b

~

I I

I a.

i l

11.10

-10.55-10 -- -------4--------F--

15 40 0 30 to e

O I

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~

g 23.70-10.03 i

[

l l

1 LLI

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l 32.80 9.89 g

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I 40.00 9.43 9

y 7------

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3 i

i i

2 i.

I I

Q I

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nig 2

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I at 8

.l iil c

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i i

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10

'20 30 40-2.

AVERAGE PLANAR EXPOSURE (GWD/MT)

~

1

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o t

FIGURE 2 AXIAL MAPLHGR MULTIPLIER

~

(ENC VB FUEL ONLY) 1.1

i.,

1 I

I I

I 1

I i

i DATA POINTS

[

1 I

I I

l W

]

l I

I I

I HOGHT MULTIPIER a-1.0

f----[----j I

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o o

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I-2 0.92 l

l.

g g

4 0.96 E

1 I

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6

1.00

@ 0.9

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

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1.00

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-10 1.00

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g g

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1 0.8 r---

r---

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10-12-s, CORE HEIGHT (FT)

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FIGURE 3

- [o GE-P8DRB239 FUEL MAXIMUM-ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION. RATE DATA POINTS 1

{

(FOUR AND' FIVE' LOOP OPERATION)

EXPOSURE.MAPU4GR p12

.i (GWD/M4 (KW/FQ q

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1.10 10.2 0

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11.00 10.2 M

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AVERAGE PLANAR EXPOSURE (GWD/MT)

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~

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FIGURE 4

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GE-P8DRB265H FUEL MAXIMUM ALLOWABLE AVERAGE ' PLANAR-

~

LINEAR HEAT GENERATION RATE DATA POINTS

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{

(FOUR AND FIVE LOOP OPERATION)

) 12 EXPOSURE MAPLNGR

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. (WD/WO '. (m/FO x

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0.22 10.2 1

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10 20 30 40' 50

- 2.

AVERAGE PLANAR EXPOSURE (GWD/MT) t:

L s@'

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2.V FIGURE 5

~ ~ '

GE-P8DRB299Z FUEL MAXIMUM ALLOWABLE' AVERAGE PLANAR LINEAR HEAT GENERATION. RATE DATA POINTSL

{

(FOUR ' AND FIVE LOOP OPERATION).

) 12

-e n suar.,u m 4

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AVERAGE-PLANAR EXPOSURE (GWD/MT)-

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i FIGURE 6 GE-P8DRB299ZA FUEL

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

{

-(FOUR AND. FIVE: LOOP OPERATION) p12 EXPOSURE WUK3R i

.-iiiiii

>>iii>>i (WDNQ (W/FO i

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gr i

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. _ _ _ _ _ L - - - - - l- - - - - -

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ng 0

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~ 20 30

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AVERAGE PLANAR EXPOSURE (GWD/MT) t;

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

, w-s 4 98

s

a.

FIGURE 7 GE-BD321 B FUEL-MAXIMUM-ALLOWABLE AVERAGE -PLANAR-LINEAR HEAT GENERATION RATE DATA POINTS.

{

(FOUR AND FIVE LOOP OPERATION) 1 p12

-EXPOSURE MAPuiGR

("S/"O (*/M M

1 I

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0.22 10.4 1

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I 5.50 11.0 3

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31 E

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11.00 11.5 1

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16.50 11.3

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l 25.00 9.6 g

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27.50 9.5 10

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

33.00 9.5 g

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l l

l 38.50 9.4 m

l l

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- - - - - - lr - - - - - lr - - - -

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50.00 8.7 9-a r----

r---

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S{g 7 3il l

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

s:

o

~

0 10 20.

30 40.

50 o

. AVERAGE PLANAR EXPOSURE (GWD/MT).

g.

o

.m.

~..L,

e..

t FIGURE 8 MINIMUM CRITICAL POWER RATIO (MCPR)

APRM STATUS MCPR Limit 1.

If any two (2) LPfm assemblies which 1.51 f

are input to the APfW system and are j

separated In distance by less than-i three (3) times the control rod pitch I

contain a combination of three (3) out of four (4) detectors located in either i

the A and B or C and D levels which t

are failed or bypassed i.e.,

APfW

{

channel or LPfW input bypassed or inoperable.

2.

If any LPfW input to the APfW system 1.51 l

at the B C, or D level is failed or bypassed or any APfW channel is inoperable (or bypassed).

{ {il 3.

All B, C, and D LPfW inputs to the 1.51 l

APfW system are operating and no

_og APfW channels are inoperable or by passed.

[

f

.i.-

FIGURE 9

= _O W TA C-~O R,

Kr 1

O O.

i i

e i

i i

DATA POINTS FLOWMAX (s)

h. _

ROW 107 112 117 v- '

O.3 1.21 1.25 1.28 0.4 1.17 1.20 1.22 O

0.5 1.13 1.16 1.17 WU O O.6 1.08 1.11 1.13

[e -

4 0.7 1.04 1.07 1.09 g"

MANUAL ROW CONmOL i

y SCOOP TUBE POSm0N 0.8 1.00 1.03 1.05

?

UMITED SUCH THAT ROWMAX = 107.0 s 0.9 1.00 1.00 1.00

= 112.0 m i

O

= 117.0 s 10 1.00 1.00 1.00 o-5 P

k i

O8 O

o3 CD, G$

e i

i i

I i

O o

O.20 0.30 0.40 0.50 0.60

. 0.70 0.80 0.90 1.00 FRACTION CORE R_OW U

+

o m.

.m

.m m

_ _ _ _ _ _ _ _ _ _. _ _ - -____.____s.___.___m___,m

-m.

_,.__m_. _ _ +..

.m z

.. 4

FIGURE.10 LOCAL LINEAR HEAT GENERATION RATE (LHGR)

FUEL TYPE LHGR LIMIT 1.

ENC V8 LHGR 1 LHGR

~1 AP,

rL,-

d P

'LT>-

3 LHERd = 14.5 kw/f t AP/P = 0.039 Max power spiking penalty)

LT = 144 inches (Total fuel length)

L = Axial position above bottom of core 2.

GE8x8A LHGR s 13.4 kw/ft GE8x8EB g<

G G

t

_ = -.. -,.

-.

ML20042G243

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