ML20210Q629

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Rev 2 to NFS-0145, Hope Creek Generating Station COLR Cycle 7/Reload 6
ML20210Q629
Person / Time
Site: Hope Creek 
Issue date: 06/20/1997
From: Charles Brown, Safin F
Public Service Enterprise Group
To:
Shared Package
ML20210Q600 List:
References
NFS-0145, NFS-0145-R02, NFS-145, NFS-145-R2, NUDOCS 9709020075
Download: ML20210Q629 (45)
v • d • e


Text

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O PSEG inl N1 4

June 20,1997 l

IIOPE CREEK GENERATING STATION CORE OPERATING LIMITS REPORT I

CYCLE 7 / RELOAD 6 i

June 20,1997 i

I I

~7 Date:

a ^! '?? 7 Prepared By:

Sent$r dtIff Engineer

/ob0h7

/2 dab N

Date:

Reviewed o,y:

/~ Senior Sta Engidder.

d/#!N7 l

Concurrence.

Date:

IIC R&SA IJ ip$upervisor f

~~ -

7 2

Date:

Approved By:

Manager - Nuclear /uel 9709020075 970826 PDR ADOCK 05000354 P

PDR

Re s on 2 June 20,1997 TABLE OF CONTENTS Section Description Page 1.0 INTRO D U CTIO N.......................................

5 2.0 LIMITING CONDITIONS FOR OPERATION.....................

6 2.1 AVERAGE PLANAR LINEAR llEAT GENERATION RATE.....

7 2.2 MINIMUM CRITICAL POWER RATIO.................... I1 2.3 LINEAR llEAT GENERATION RATE..............-.,.... 14 3.0 RE FE REN C ES......................................... 15 APPENDIX A Bundle Descriptions and Composite APLilGRs for Fuel Bundle GE9B P8CWB324 90Zl 80M 150T..................

16 APPENDIX B Bundle Descriptions and Composite APLilGRs for Fuel Bundle GE9B P8CWB325 llGZl-80M 150T.....,,................., 19 APPENDIX C Bundle Descriptions and Composite APL11GRs for Fuel Bundle GE9B P8CWB325 IIGZ2 80M 150T........................... 22 Page 2 of 24

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Re 5 on June 20,1997 LIST OF FIGURES Figure Title Page 21 API.11GR Limit for Fuel Bundle GE9B P8CWB324 9GZl 80M 150T,.....

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-22 APLilGR Limit for Fuel Bundle GE9B P8CWB3251IGZl 80M 150T,....

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23 APLilGR Limit for Fuel Bundle GE9B P8CWB325 llGZ2 80M 150T..... 10 24' Minimum Critical Power Ratio Operating Limit 12 25 Kf Multiplier Curve...................................... 13 A1 Lattice Definitions for Fuel Bundle GE98 P8CWB324 9GZl 80M 150 T.... 17 B1 Lattice Definitions for Fuel Bundle GE9B P8CWB325 IlGZl 80M 150 T... 20 C-1 Lattice Definitions for Fuel Bundle GE9B P8CWB325 IIGZ2-80M 150-T... 23 Page 3 of 24

k O PSIEG l,'1f14l June 20,1997 LIST OF TABLES v

Table Title Page l

21 Li l G R Limi t s......................................,.. 14 A1 APL11GR Data for Fuel Bundle GE9B F8CWB324 9GZl 80M 150 T.,.... 18 i

B1 APLilGR Data for Fuel Bundle GE98 P8CWB3251IGZl 80M 150 T....

21 C1 APLilGR Data for Fuel Bundle GE9B P8CWB325 llGZ2 80M 150 T..... 24 i

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Page 4 of 24 l

Re s on June 20,1997

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for the llope Creek Generating Station Unit 1 Cycle 7 / Reload 6 operation. The limits presented here correspond to the core thermal limits for Average Planar Linear lleat Generation Rate (APLilGR),

Minimum Critical Power Ratio (MCPR), MCPR Flow Adjustment Factor (K,), and Linear ileat Generation Rate (LilGR).

These operating limit values have been determined using NRC approved methods contained in GESTAR II, NEDE-240ll P A, (latest approved version), and are established such that all applicable fuel thermal mechanical, core thermal hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met. Methods for the cycle specific evaluation of the Safety Litch Minimum Critical Power Ratio (SLMCPR) have been submitted for NRC approval in GESTAR Il Arnendment 25, and in llope Creek License Change Request LCR 1197 05. This revision includes the effects of the l{ ope Creek Cycle 7 specific evaluation for SLMCPR, currently administratively controlled via PlRS item

  1. 960,116162 CRFA #2 arx! CROD #2.

Ilope Creek Technical Specifications section 3.2 references this report as the source for certain LIMITING 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 revisions, shall be provided, upon issuance, to the NRC.

This document is specific to llope Creek Unit 1 Cycle 7 / Reload 6 atx! 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 11,200 MWD /STU, including tlw power coastdown following end of effective full power capability. End of effective 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 temperatures, in the a'

  • s out configuration.

Page 5 of 24

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Re s on June 20,1997 2.0 LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the llope Creek Technical Specifications.

Iech. Spec Ihlg l

3/4.2.1 Average Planar Linear lleat Generation Rate 3/4.2.3 Minimum Critical Power Ratio l

3/4,2.4 Linear lleat Geriaation Rate l

Page 6 of 24

O PSEG

  1. 8t'd June 20,1997 2.1 AVERAGE PLANAR LINEAR llEAT GENERATION RATE LIMITING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR llEAT GENERATION RATES (APLilGRs) for each type of fuel as a 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 APL11GRs for the P8CWB (GE9B) fuel types are included in Appendix A, B and C to accommodate GE proprietary considerations. The Appendices will be identified to i

contain GE proprietnv data and handled accordingly by the NRC when they receive their copy of the COLR report.

The APLilGR 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 APLilGR LCOs in the appendices are established in the NSSS computer for thermal limits rionitoring via approved plant procedures.

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

The accompanying Ogures graphically present the

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

1 j

Page 7 of 24

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' O PSEG e, on June 20,1997 2,2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit specified in Figure 2-4 times the Kr curve value specified in Figure 2-5.

The Kf curve requires an adjustment be made to the MCPR limit for bundle flows below 0.4 Mlb/ft -hr. This adjustment has been incorporated in Fig. 2-5.

2 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 Main Turbine Bypass operability.

Core average scram speed, t (Tau), is defined by llope Creek Technical Specification 3.2.3.

End-of-Cycle Recirculation Pump Trip system operability is defined per llope Creek Technical Specification 3.3.4.2, Main Turbine Bypass operability is defined per llope Creek Technical Specification 3.7.7.

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Minimum Critical Power Ratio (SLMCPR) have been submitted j

for NRC approval in GESTAR II Amendment '25, and in 11 ope l

Creek License Change Request LCR H97-05. Figure 2-4 in this l

revision includes the effects of the llope Creek Cycle 7 specific l

evaluation for SLMCPR, currently administratively coritrolled j

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

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" O PSEG "0 14i e

June 20,1997 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LilGR) shall not exceed the limits specified in Table 2-1.

Table 21 LHGR Limits Euel Tyoc LHGR Limit (Kw/ft)

GE9B P8CWB324-90Z1 14 4 GE9B-P8CWB3251IGZ1 14,4 GE9B-P8CWB325-1IGZ2 14,4 Page 14 of 24 d

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< O PSEG

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June 20,1997 3,0 REFERENCES.

1.

" General Electric Standard Application For Reactor Fuel, General Electric Company, NEDE-24011-P A, Revision 10. February,1991.

2.

Nuclear Fuel Section Vendor Technical Document NFU-VTDGE91-040-00

- Supplemental Reload Licensing Submittal for Hope Creek Generating Station Unit 1 Reload 3, Cycle 4 Supplement 1", General Electric Company, 23A6526AA, Rev.0, Supplement 1, January,1991, 3.

Nuclear Fuel Section Vendor Technical Document NFU VTDGE93-077-00 t

" Lattice-Dependent MAPLHGR Report for Hope Creek Generating Station Unit 1, Reload 5, Cycle 6", General Electric Company, 23A7219AA, Rev.0, November, 1993.

1 4,

Nuclear Fuel Section Vendor Technical Document NFU-VTDGE95131-00

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

l 5.

DEF # DEH 93-00183, " Resolution of the TVAPS issue".

6.

Nuclear Fuel Section Safety Evaluation HCR.8-0003, approved 1/18/95.

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-II) on Cycle Specific Safety Limit MCPR", RJR-96-133, MFN-179-96, December 13,1996. (Copy stored in NFSI %-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 6/20/97.

Page 15 of 24

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