ML20069Q475

Rev 5 to Topical Rept - 066, Oyster Creek Cycle 14 Colr.

ML20069Q475
Person / Time
Site:	Oyster Creek
Issue date:	05/27/1994
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20069Q463	List: ML20069Q462 ML20069Q475
References
TR-066, TR-066-R05, TR-66, TR-66-R5, NUDOCS 9406270436
Download: ML20069Q475 (12)

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Oyster Creek Cycle 14 Core Operating Limits Report Topical Report - 066 Rev. 5 l

BA Number 335400 Date: 11 Prepared: 13 fngineer 8 Date OC Fuel Projects Approvals:

Tw l Manager, /

sh>lN Datd l OC Fuel Projects i

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Director, 5-27-74 Date i Nuclear Analysis and Fuel i

9406270436 940617 PDR ADOCK 05000219 P PDR

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TR# 066 TITLE oyster Creek Cycle 14 Core Operating Limits Report REV

SUMMARY

OF CHANGE APPROVAL DATE 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 analysis results. APLHGR limits (Figures 8 and 9) for two new fuel designs were added. Also the MCPR limit (Figure 10) changed from 1.51 to 1.48.

4 Revise document to reflect the Cycle 14 design and safety analysis results. MAPLHGR limits for ENCVB, GE-239, GE-265H and GE-2992A fuel designs were removed. MCPR limit changed from 1.48 to 1.47. LLHGR limit for ENCVB fuel was removed.

5 Mid-Cycle 14 revision to the MCPR operating g p-g// 39/

limit. The limit changed from a 1.47 to a /

1.51 based on a re-analysis of EOC14 conditions.

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N0036 (03-90) la l

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TR 066

. Rev. 5 Page 1 of 10 TABLE OF CONTENTS Pace Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 3 Referencen . . . . . . . . . . . . . . . . . . . . . . . . . . , . , , , , 3 Figure 1 GE-299Z Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . . . 4 Figure 2 GE-321B Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . . . 5 Figure 3 GE-338-12GZ Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . 6 Figure 4 GE-338-11GZ Fuel MAPLHGR Limits . . . . . . . . . . . . . . . . . 7 Figure 5 HCPR Limits . . . . . . . . . . . . . . . . . . . . . . . . . . , 8 Figure 6 K, Flow Factor . . . . . . . . . . . . . . . . . . . . . . . . . 9 Figure 7 LLHGR Limits . . . . . . . . . . . . . . . . . . . . . . . . . . 10 t

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. TR 066 l Rev. 5 Page 2 of 10 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 includee definitions supporting the proposed changes. The COLR, including 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 14 Reload Information and Safety Analysis Report (TR-90-rev 0) dated December 1992.

The Cycle 14 fuel / core operating limits were generated using the NRC approved codes and methodologies identified in References 1 through 8.

For each GE fuel design the APLHGR limits 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 Ref erence 6 and a 0.98 MAPLHGR multiplier must be applied at all exposure levels.

Requirements for operation with an idle loop are provided in Technical Specification 3.3.F.

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 1-4), LLHGR (Figure 7) or CPR (Figures 5 and 6) 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. 5 Page 3 of 10 REFERENCES

1. Letter from J. N. Donahew, 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. 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 from 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 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, GPU Nuclear Corp (GPUN) Topical Report TR-040, Revision 0 " Steady State and Quasi-Steady State Methods for Analyzing Accidents and Translents" (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-31462P; " Oyster Creek NGS SAFETY /CORECOOL/GESTR-LOCA LOSS of coolant Accident Analysis. August 1987.

7. GPUN TR-090 Rev. O, " Reload Information and Safety Analysis Report for Oyster Creek Cycle 14 Reload," dated December 1992.

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

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

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

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\

FIGURE 1 Tech Spec 3.10.A GE-P8DRB299Z FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR -

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

EXPOSURE MAPLNGR p12 . . . . ... .... .. .. . (GWD/MO (kW/FQ 1 I I I 0.22 10.2

' ' ~

g [ , l , l _

1.10 10.2 0 l l l 1 5.50 10.2 b

11-

~- - - - - - f - - - - - l- - - - - - h - - - - - f - - - - - ~

11.00 10.2

% l l I I 16.50 10.1 l l ,' 20.00 9.0 a 2:  :

i^ l l I 25.00 8.8 g 10-------F--- -F-----F-----F-----

27.50 8.8 g -

1 I I I -

g _ l l I

l l _ 33.00 8.8 L1J -

38.50 8.6 I I l 44.00 8.6 2 9- -----

r----- ----

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_ 50.00 8.4 1 I i

[: l l l ~; N y y _ l i I I - %p g 8 . . . . l . j .  !.. .l .

+m!

O 10 20 30 40 50 a AVERAGE PLANAR EXPOSURE (GWD/MT) s

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

MAXIMUM ALLOWABLE AVERAGE PLANAR -

LINEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION)

EXPOSURE MAPLHGR

) 12 , . . . . .. .... .... .,,, (WD/MO (W/FQ f

1 I I I 0.22 10.4 1 I I I -

g _

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5.50 11.0

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l I I I 16.50 11.3 g:

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I 25.00 27.50 9..

9.5 g 10-- - - - - - F - - - - - F - - - - - I- - - - - - I- - - - - - 33,0o ,,3 e _ l i I I _

g _ l l I l _ 38.50 E.4 w l I

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. . . . i... i ii.. i. i =g 0 10 20 30 40 50 a AVERAGE PLANAR EXPOSURE (GWD/MT) s

FIGURE 3 Tech Spec 3.10.A GE-P8DQB338-12GZ FUEL -

MAXIMUM ALLOWABLE AVERAGE PLANAR -

LINEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION) i EXPOSURE MAPLHGR (GWD/MO (W/FQ

) 12 _ . . . .i. i. . . ....

f _

l I I I 0.22 9.93 l l 1.10 g ,

l 10.07

$11----

J 5 50 10 7 l ,'  ; _

11.00 11.50 1

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16.50 10.90 r----- r---- 22.00 9.70 h 10 -

r----. "'

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I 27.50 9.60

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w -

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44.00 8.63 1 I I I 1 I i 1 50.00 7.85 y -

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AVERAGE PLANAR EXPOSURE (GWD/MT) s

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TR o66 Rev. 5 Page 8 of lo 1

FIGURE 5 MINIMUM CRITICAL POWER RATIO (MCPR) - Tech Spec 3.10.C 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 at 1.51 the B, C, or D level is failed or bypassed ,

or any APRM channel is inoperable (or bypassed).  !

3. All B, C, and D LPRM inputs to the APRM 1.51 system are operating and no APRM channels are inoperable or bypassed.

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FIGURE 6 Tech Spec 3.10.C

=

_OW rAC~~O R, 4 O '

q , . . . . . . . . . . . . .,

DATA POINTS  :

O .

ROWuAx (s)

ROW 107 112 117 J 0.3 1.21 1.25 1.28 0.4 1.17 1.20 1.22 0 0.5 1.13 1.18 1.17 C

(O - v-0.6 0.7 1.08 1.04 1.11 1.07 1.13 1.09 g '~ MANUAL ROW CONTROL y SCOOP TUBE POSmON 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 O = 117.0 m 1.0 1.00 1.00 1.00 o- .

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0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 FRACTION CORE FLOW w__- - - - - - - _ _ - - - - -- - - - w

, TR 066

, Rev. 5 I) age 10 of 10 i

FIGURE 7 1.0 CAL LINEAR HEAT GENERATION RATE (LLHGR) - Tech Spec 3.10.B FUEL TYPE LHGR Limit

1. GE8 x 8R LHGR f 13.4 kw/ft GE8 x BEB l

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FIGURE 4 Tech Spec 3.10.A GE-P8DQB338-11GZ FUEL ^

MAXIMUM ALLOWABLE AVERAGE PLANAR -

LINEAR HEAT GENERATION RATE DATA POINTS

{ (FOUR AND FIVE LOOP OPERATION) ,

g12 _ .. . .,....,....,....,....

M E E li" f f

l I I I 0.22 10.22 I I I g _

;  ; i 1.10 10.39

@11- ----- '-- - ' - - - - ' - - - - ' - - - - - - 5.50 11.1s J ~ ' ' ' ~

_ , l  ;  ; 11.00 11.50 Z

1 I I I 16.50 10.90 1 I I 510-O_

r----- ----

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

22.00 9.70

~

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27.50 9.60 l I I I Ld -

33.00 9.60 (3 _ l i I _

g g_______L_____L_____L_____L

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til t

1 I I i 44.00 8.70 l >4 -

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50.00 7.95 l 7 l -

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2 -

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2 _ I l l l - E.I.g 7 . . . . j ...ij...ij....l.. .

0 10 20 30 40 50 s l

AVERAGE PLANAR EXPOSURE (GWD/MT) g

. . . . . . _- -_-- . -- _