ML20217K326

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Rev 3 to NFS-0145, Hope Creek Generating Station COLR Cycle 7/Reload 6
ML20217K326
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/08/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML20217K321 List:
References
NFS-0145, NFS-0145-R03, NFS-145, NFS-145-R3, NUDOCS 9710240260
Download: ML20217K326 (25)
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@PS]G a011 September 8,1997 IIOPE CREEK GENERATING STATION CORE OPERATING LIMITS REPORT CYCLE 7 / RELOAD 6 SEPTEMBER 8,1997 l

Prepared By: ~ - Date: 7[7[f7 Reviewed By: /'"'""""*'"f

~

M Senior Staff Eng'

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r Date: (( M Concurrence By: # Date: k HC R&SA U upervf!Ior Approved By: Date:

Y '

7 Manager - Nuclear)ifffel

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9710240260 971017 PDR ADOCK 05000354 P PDR,

+ -- -

OPS 1G fe'n'll September 8,1997

. /

LIST OF EFFECTWE PAGES PAGES REVISION LEVEL 1 3 1a 3 24 2 I

5 3 6 14 2 15 3 16 24 2 Page la of 24

O PSEG fifi'i June 20.1997 TABLE OF CONTENTS 1

Page Section Description

.... ... . . . 5 1.0 INTROD UCTIO N . . . . . . . . . . . . . . . . . . . . .

..... .. . ..6 2.0 LIMITING CONDITIONS FOR OPERATION . . . 7 2.1 AVERAGE PLAN AR LINEAR HEAT GENERATION RATE . 1I 2.2 MINIMUM CRITICAL POWER RATIO . . . . . . . . . . . 14 2.3 LINEAR HEAT GENERATION RATE . . . . . . . . . .

15

3.0 REFERENCES

APPENDIX A Bundle Descriptions and Composite APLHORs for Fuel Bundle

........................... 16 GE9B P8CWB324 90Zl 80M 150T APPENDIX B Bundle Descriptions and Composite APLHORs for Fuel Bundle 19 GE98 P8CWB325 ilGZl 80M 150T . . . . . . . . . . . . . . . . . . . . . . . . . . .

APPENDIX C Bundle Descriptions and Composite APLHORs for Fuel Bundle

........ 22 GE9B P8CWB325 ilGZ2 80M 150T . . . . . . . . . . . . . . . . . .

Page 2 of 24 a

NFS ONS O PSEG Revision 2 June 20.1997 LIST OF FIGURES  !

1 P, ige Figure Title 8

APLilGR Limit for Fuel Bundle GE9B.P8CWB324 9GZl 80M 150T . . . . .

21 9

22 APLilGR Limit for Fuel Bundle GE9B P8CWB325 ilGZl 80M 150T

. 10 23 APLHGR Limit for Fuel Bundle GE9B P8CWB325 llGZ2 80M 150T . . .

........ ..... 12 24 Minimum Critical Power Ratio Operating Limit  ;

13 ,

25 Kf M ultiplier curve . . . . . . . . . . . . . . . . . . . . . . . . . . _ . . . . . . . . . . . t l 17 1

! A1 Lattice Dennitions for Fuel Bundle GE9B P8CWB324 9GZl 80M 150 T . . .

20 B1 Lattice Definitions for Fuel Bundle GE9B P8CWB325 ilGZl 80M 150 T . . .

- 23 s C1 Lattice Dennitions for Fue't Bundle GE98 P8CWB325. lIGZ2 80M 150 T . .

/ age 3 of 24

llf;oi4; l O PSEG June 20.1997 i

l LIST OF TABLES Page Yable Title

. 14 21 LilGR Limits . . . . ................................

.. 18 A1 APLilGR Data for Fuel Bundle GE98 P8CWB324 9GZl 80M 150 T . .

. 21 B1 APLilGR Data for Fuel Bundle GE9B P8CWB325 llGZ180M 150 T .

. . 24

-C1 APLilGR Data for Fuel Bundle GE98 P8CWB325 llGZ2 80M 150 T .

i Page 4 of 24 e

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4

@?S3G fi e'n .$

September 8,1997 1

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for llope Creek Generating Station Unit 1 Cycle 7 / Reload 6 operation. The limits presented here currespond to the core thermal limits for Average Planar Linear lleat Generation Rate (APLliGR), hiinimum Critical Power Ratio (htCPR), htCPR Flow Adjustment Factor (K,), and Linear licat Generation Rate (LliGR).

These operating limit values have been determined using NRC approved methods contained in GESTAR il, NEDE 240ll p A,(latest approved version), and are established such that all applicable fuel thermal mechanical, core thermal hydraulics, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met. hiethods for the cycle specific evaluation of the Safety Limit hiinimum Critical Power Ratio (SLhiCPR) have been submitted for NRC approvalin GESTAR Il Amendment 25, and in Hope Creek License Change Request LCR 1197 05. This revision includes the effects of the Hope Creek Cycle 7 specific evaluation for SLhiCPR, currently administratively controlled via PIRS item

  1. 960416162 CRFA#2 and CROD #2.

Ilope Creek Technical Specifications section 3.2 references this is..", as the source for certain LlhilTINO CONDITIONS FOR OPERATION. These are included in section 2 of this document, llope Creek Technical Specifications section 6.9.1.9 also requires that this report, including any mid cycle acvisions, shall be provided, upon issuance, to the NRC.

This document is specific to llope Creek Unit 1 Cycle 7 / Reload 6 and shall not be applicable to any other core or cycle design. The current revision of this report covers the operation from the date of issuance to the end of cycle 7 exposure of i1,400 htWD/STU, including the power coastdown following end of effective full power capability. End of full power capability is reached when 100% rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow), at rated feedwater temperature.s, in the all rods-out configuration.

Page 5 of 24

- N",fnll O PSEG ,

June 20,1997 l .

2.0 LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced .

by the l{ ope Creek Technical Specifications.

Tech. Spec Thlt 4

Average Planar Linear l{ eat Generation Rate 3/4.2.1 i 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate i

Page 6 of 24 4

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O PSEG l%$

June 20.1997 2,1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE Li>llTING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as ;. function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in Appendix A Table A 1, Appendix B. Table B 1, and Appendix C. Table C 1 The limits specified shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation.

NOTE The APLHGRs for the P8CWB (GE9B) fuel types are included in Appendix A, B and C to accommodate GE proprietary considerations. The Appendices will be identi6ed to contain GE proprietary data and handled accordingly by the NRC when they receive their copy of the COLR report.

The APLHGR LCOs contained in Appendix A, B and C shall have the same consideration and treatment by PSE&G personnel as if they were in the body of the COLR. In addition, note that the APLHGR LCOs in the appendices are established in the NSSS computer for thermal limits monitoring via approved plant procedures.

When hand calculations are required, all AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in Figures 21 through 2 3. The limits specified shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation.

The accompanying Ogures graphically present the

" Limiting" column of Tables A 1, B 1 and C 1.

Page 7 of 24

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1 NF O PSEG , , , 1 June 20,1997 ,

. ,- i 2,2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the i MCPR limit specined in Figure 2 4 times the Kr curve value specified in Figure 2 5.

The Kf curve requires an aojustment be made to the MCPR limit for bundle flows below 0.

Mlb/ft 2hr. This adjustment has been incorporated in Fig. 2 5.

The MCPR limit must be increased by 3% if the core inlet subcooling exceeds 70 BTU /lbm The MCPR limit is a function core average scram speed,_EOC RPT operability, and Mai Turbine Bypass operability.-

Core average scram speed, t (Tau), is dermed by Hope Creek Technical Specification End of Cycle Recirculation Pump Trip systemi operabi.4/ s defined per Hope Creek Te Specification 3.3.4.2.

Main Turbine Bypass operability is defined per Hope Creek Technical Specification 3.7.

NOTE l l

Methods f., r the cycle specific evaluation of the Safety LLmit l Minimum Critical Power Ratio (SLMCPR) have been l submined for NRC approvalin GESTAR H Amendment 25. and in Hope l Creen: License Change Request LCR H974)5. Figure 24 in this l revision includes the effects of the Hope Creek Cycle 7 specific l evaluation for SLMCPR, currently administratively controlled i l

via PIRS item #960416162 CRFA #1 and CROD #2.

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d fj,foni OPSEG June 20,1997 2.3 LINEAR HEAT GENERATION RATE Lt.\llTING CONDITION FOR OPERATION The LINEAR llEAT GENERATION RATE (LilGR) shall not exceed the limits specined in Table 21.

Table 21 L11GR Limits Euel Tyne LilGR Limit (Kw/ft) i 14.4 GE9B P8CWB324 90Z1 14.4 GE9B P8CWB3251IGZ1 14.4 GE9B P8CWB325110Z2 Page 14 of 24

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@PSEG R%'n1 September 8,1997

3.0 REFERENCES

1. " General Electric Standard Application For Reactor Fuel", General Electric Company, NEDE 240ll P A, Revision 10, February,1991.
2. Nuclear Fuel Section Vendor Technical Document NFU VTDGE91040 00 "Supplem.mtal Reload Licensing Submittal for Hope Creek Generating Station Unit 1 Reload 3. Cycle 4, Supplement 1", General Electric Company,23 A6526AA Rev.0, Supplernent 1. January,1991.

Nuclear Fuel Section Vendor Technical Document NFU VTDGE93 077 00 3.

" Lattice Dependent hlAPLHOR Report for Hope Creek Generating Station Unit 1.

Reload 5, Cycle 6", General Electric Company,23 A7219AA, Rev.0, November, 1993.

4. Nuclear Fuel Section Vendor Technical Document NFU VTDGE9513100

" Supplemental Reload Licensing Report for Hope Creek Generating Station Unit 1, Reload 6 Cycle 7", General Electric Company,24 A5173, Rev 0, November,1995.

5. DEF # DEH 93 00183," Resolution of the TVAPS issue"
6. Nuclear Fuel Section Safety Evaluation HCR.8 0003, approved 1/18/96.
7. Nuclear Fuel Section Safety Evaluation HCR 8-0006, approved 6/5/97.

, 8. R.J.Reda to USNRC Document Control Desk," Proposed Amendment 25 to GE Licensing Topical Report NEDE 240ll P A (GESTAR H) on Cycle Specific Safety Limit hlCPR", RJR 96133, MFN 179 96. December 13,1996 (Copy stored in NFSI 95-432) ,

9. Louis F. Storz to USNRC Document Control Desk," Request for Change to Technical Specifications, Safety Limit Minimum Critical Power Ratio, Hope Creek Generating Station, Facility Operating License NPF 57, Docket No. 50-354", LR N97187, LCR H97 05, March 31,1997,
10. Nuclear Fuel Section Safety Evaluation HCR,8-0007, approved 6/20/9'/.
11. Nuclear Fuel Section Safety Evaluation HCR.8 0008, approved 9/8/97.

Page 15 of 24

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