ML20210Q608

Rev 1 to NFS-0145, Hope Creek Generating Station COLR Cycle 7/Reload 6

ML20210Q608
Person / Time
Site:	Hope Creek
Issue date:	06/05/1997
From:	Charles Brown, Safin F Public Service Enterprise Group
To:
Shared Package
ML20210Q600	List: LR-N970537, Forwards Revs 1 & 2 of HCGS Cycle 7/Reload 6 COLR, NFS-0145, IAW TS 6.9.1.9 ML20210Q608 ML20210Q629
References
NFS-0145, NFS-0145-R01, NFS-145, NFS-145-R1, NUDOCS 9709020066
Download: ML20210Q608 (45)

Text

NFS4)l45

[)gl$gj Revision 1 June 5,1997 IIOPE CREEK GENERATING STATION CORE OPERATING LIMITS REPORT CYCLE 7 / RELOAD 6 l

June 5,1997 Date:

• • NIf Prepared By:

Sdnior' Staff Engineer b

!f7 Reviewed By:

Date:

Senloht kineer b r/i7 Date:

Concurrence:

~

IIC R&SA t dpervisor b!r 7

^

Date:

Approved By:

Manager - Nuclear r[el

((0'O$00hk050$$354 PDR p

_ ___d

Rev s on June 5.1997 l

1 TABLE OF CONTENTS Secten Description Page 1.0 I N T RO D U CTI O N.......................................

5 2.0 1.IMITING CONDITIONS FOR OPERATION.....................

6 2.1

- AVERAGE PLANAR LINEAR llEAT GENERATION RATE,,...

7 2.2 MINIMUM CRITICAL POWER RATIO..............,..... I1 2.3 LINEAR HEAT GENERATION RATE.................... 14 3.0 RE F E REN C ES......................................... 15 APPENDIX A Bundle Descriptions and Composite APLHGRs for Fuel Bundle GE98 P8CWB324 9GZl 80M 150T 16' APPENDIX B Bundle Descriptions and Composite PLHORs for Fuel Bundle GE9B P8CWB325-11GZl 80M 150T...........

4 19-APPENDIX C '

Bundle Descriptions and Composite APLHGRs for Fuel Bundle GE9B P8CWB325 1IGZ2 80M 150T,.........................

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E Re sion June 5,1997 LIST OF FIGURES Figure Title Page 21 APLilGR Limit for Fuel Bundle GE9B P8CWB324 90Z180M 150T,.....

8 22 APLilGR Limit for Fuel Bundle GE98 P8CWB3251IGZl 80M 150T.....

9 23 APLilGR Limit for Fuel Bundle GE9B P8CWB325110Z2 80M 150T..... 10 2-4 Minimum Critical Power Ratio Operating Limit 12 25 K f M ul t iplie r Cu rve...........'........................... 13 A1 Lattice Definitions for Fuel Bundle GE9D P8CWB324 90Zl 80M 150 T.... 17 B1 Lattice Definitions for Fuel Bundle GE9B P8CWB325 llGZl 80M 150 T,.

20 C1 Lattice Definitions for Fuel Bundle GE9B P8CWB325110Z2 80M 150 T

.. 23 n

Page 3 of 24

O PSEG

"';Sfon 45 June 5.1997 i

LIST OF TABLES Table Title Page 21 Li l G R Li mit s.......................................... 14 A1 APLilGR Data for Fuel Bundle GE9il P8CWD324 9GZ180M 150 T...... 18 B-1 APLliGR Data for Fuel Bundle GE98 P8CWB3251IGZl 80M 150 T 21 C1 APLilGR Data for Fuel Bundle GE9B P8CWB325 llGZ2 80M 150 T,...

24 M

e Page 4 of 24

O PSEG E8ini s

June 5,1997 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 lleat Generation Rate (LilGR).

These operating limit values have been determined using NRC approved methods contained in GESTAR ll, NEDE 24011.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 l

specific evaluation of the Safety Limit Minimum Critical Power Ratio (SLMCPR) have been j

submitted for NRC approval in GESTAR il Amendment 25, and in llope Creek License l

Change Request LCR 1197 05. This revision includes the effects of the llope Creek Cycle 7 l

specific evaluation for SLMCPR, currently administratively controlled via PIRS item l

1. 960416162 CRFA #2 and CROD #2.

l 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. Ilope 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 NP.C.

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 11,200 MWD /STU, including the l

power coastdown following end of effective full power capability. End of effective full power l

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 all rods-out configuration.

Page 5 of 24 4

Re s on June 5,1997 2.0 LIMITING CONDITIONS FOP. OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the llope Creek Technical Specifications.

Tech. Snec Iitic 3/4.2.1 Average Planar Linear IIcat Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear lleat Generation Rate Page 6 of 24 z

NvSm43 O PSEG Revision 1 June 5,1997 l

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 160p operation.

NOTE The APLilGRs for the P8CWB (GE98) fuel types are included in Appendix A B and C to accommodate GE proprietary considerations. The Appendices will be identified to contain GE proprietary data and handled accordingly by the NRC when they receive their copy of the COLR repart.

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 monitoring via approved plant procedures.

When hand calculations are required, all AVERAGE PLANAR LINEAR llEAT GENERATION RATES (APL11GRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the li nits specified in Figures 2-1 through 2 3. The i

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 figures graphically present the

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

Page 7 of 24

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O PSEG x!8fe,45 June 5,1997 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 MCPR limit specified in F;gure 2-4 times the K, 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 2

Mlb/ft.hr. 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 Main Turbine Bypass operability.

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

i End-of Cycle Recirculation Pump Trip system operability is defined per llope Creek Technical l

Specification 3.3.4.2.

j Main Turbine Bypass operability is defined per llope Creek Technical Specification 3.7.7.

NOTE l

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Methods for the cycle specific evaluation of the Safety Limit l

Minimum Critical Power Ratio (SLMCPR) have been submitted l

for NRC approval in GESTAR-II Amendment 25, and in llope l

Creek License Change Request LCR l-197-05. Figure 2 4 in this l

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

cvaluation for SLMCPR, currently administratively controlled l

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

l Page 11 of 24

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O PSEG Jurm 5,1997 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR llEAT GENERATION RATE (LilGR) shall not exceed the limits specified in Table 21.

1 Table 21 1.IIGR Limits Fuel Tvoe LilGR Limit (Kw/fn GE9B P8CWB324-9GZ1 14,4 GE9B P8CWB325110Z1 14,4 GE9B P8CWB325 llGZ2 14,4 Page 14 of 24 1

NFS4145

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Revision I June 5,1997 3.0 REITRENCES 1.

" General Electric Standard Application For Reactor Fuel", General Electric Company, l

NEDE 240ll P A, Revision 10, Febmery,1991.

2.

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

" Supplemental Reload Licensing Submittal for llope 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 Technics; Document NFU VTDGE93-077 00

" Lattice Dependent MAPL 11GR Report for Hope Creek Generating Station Unit 1, q

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

1993.

4.

Nuclear Fuel Section Vendor Technical Document NFU VTDGE95131-00

?

" Supplemental Reload Licensing Report for liope Creek Generating Station Unit 1, l

Reload 6 Cycle 7", General Electric Company,24A5173, Rev 0 November,1995.

5.

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

6.

Nuclear Fuel Section Safety Evaluation llCR.8-0003, approved 1/18/%.

7.

Nuclear Fuel Section Safety Evaluation IICR.8-0006, approved 6/5/97.

l 8.

R.J.Reda to USNRC Document Control Desk,

• Proposed Amendment 25 to GE l

Licensing Topical Report NEDE 240ll P A (GESTAR-il) on Cycle Specific Safety l

Limit MCPR", RJR 96133, MFN 179 96, December 13,1996. (Copy stored in l

NFSI %-432) l 9.

Louis F. Storz to USNRC Document Control Desk, " Request for Change to Technical l

Specifications, Safety Limit Minimum Critical Power Ratio, Hope Creek Generating l

Station, Fxility Operating License NPF 57, Docket No. 50-354", LR N97187, LCR l

H97-05, March 31,1997.

l Page 15 of 24

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