29
FENOC Perry Nuclear Power Plant 10 Center Road FirstEnergy Nuclear Operating Company Perry Ohio 44081 John K. Wood 440-280-5224 Vice President, Nuclear March 9, 2001 PY-CEI/NRR-2551 L United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Submission of Core Operating Limits Report Ladies and Gentlemen: Enclosed is a copy of the revised Cycle 9 Core Operating Limits Report (COLR) for Unit 1 of the Perry Nuclear Power Plant (PNPP). The COLR is submitted in accordance with Technical Specification Section 5.6.5, "Core Operating Limits Report." If you have questions or require additional information, please contact Mr. Gregory A. Dunn, Manager - Regulatory Affairs, at (440) 280-5305. Very truly yours, Enclosure cc: NRC Project Manager NRC Resident Inspector NRC Region III

Perry Nuclear Power Plant Submission of Core Operating

  • Upload
    others

  • View
    4

  • Download
    0

Embed Size (px)

Citation preview

Page 1: Perry Nuclear Power Plant Submission of Core Operating

FENOC Perry Nuclear Power Plant 10 Center Road

FirstEnergy Nuclear Operating Company Perry Ohio 44081

John K. Wood 440-280-5224

Vice President, Nuclear

March 9, 2001 PY-CEI/NRR-2551 L

United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Perry Nuclear Power Plant Docket No. 50-440 Submission of Core Operating Limits Report

Ladies and Gentlemen:

Enclosed is a copy of the revised Cycle 9 Core Operating Limits Report (COLR)

for Unit 1 of the Perry Nuclear Power Plant (PNPP). The COLR is submitted in

accordance with Technical Specification Section 5.6.5, "Core Operating Limits

Report."

If you have questions or require additional information, please contact

Mr. Gregory A. Dunn, Manager - Regulatory Affairs, at (440) 280-5305.

Very truly yours,

Enclosure

cc: NRC Project Manager NRC Resident Inspector NRC Region III

Page 2: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: i Rev.: 8

PERRY OPERATIONS MANUAL

Plant Data Book Entry

TITLE: CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1

CYCLE 9 (RELOAD 8)

PDB - F0001 /Rev. 8

SUMMARY OF LAST CHANGE:

MPL: J1l EFFECTIVE DATE: 0 -3 0

This incorporates the core thermal limits for Cycle 9.

REFERENCES: PY-CEI-NRR-1104 L; PY-CEI-NRR-1157 L; PY-CEI-NRR-0529;

PY-CEI-NRR-2420 L

COMMITMENTS: L01462, L01960, L02362

PREPARED BY: Patrick J. Curran l/ --- 1-19-01 ,I V wDate

REVIEWED BY: Alla Cq

APPROVED BY: "/4WO R sponsible Manager/Director Date

TAB E, F, G, AND R USE ONLY

PORC MEETING NUMBER: 01[- W4•)

1 Manager, PNPPDAPPROVED BY:

Date

Date

INFORMATIONONLY

Page 3: Perry Nuclear Power Plant Submission of Core Operating

INFORMATION ONLY

PDB-FOO01 Page: i Rev.: 8

PERRY OPERATIONS MANUAL

Plant Data Book Entry

TITLE: CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1

CYCLE 9 (RELOAD 8)

PDB - F0001 /Rev. 8 MPL: Jll EFFECTIVE DATE:

SUMMARY OF LAST CHANGE: This incorporates the core thermal limits for

Cycle 9.

REFERENCES: PY-CEI-NRR-1104 L; PY-CEI-NRR-1157 L; PY-CEI-NRR-0529;

PY-CEI-NRR-2420 L

COMMITMENTS: L0i462, L01960, L02362

PREPARED BY: Patrick J. Curran 1-19-01Date

EFFECTIVE PIC's

3-14-01

Page 4: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 1 Rev.: 8

UNIT 1 CORE OPERATING LIMITS REPORT

INDEX

Specification

INTRODUCTION AND REFERENCES

AVERAGE PLANAR LINEAR HEAT GENERATION RATE

(CORRESPONDS TO TS 3.2.1)

Figure 3.2.1-1 Flow Dependent MAPLHGR Factor (MAPFACf), Fuel Types GEl2 and GEl4

Figure 3.2.1-2 Power Dependent MAPLHGR Factor (MAPFACp), Fuel Types GEl2 and GE14

Figure 3.2.1-3 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI2-PIOSSB399-16GZ-120T-150-T

Figure 3.2.1-4 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI2-PIOSSB399-14GZ-120T-150-T

Figure 3.2.1-5 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI2-PIOSSB369-14GZ-120T-150-T

Figure 3.2.1-6 MAPLHGR Versus Average Planar Exposure, Fuel Type GE12-P1OSSB369-12GZ-120T-150-T

Figure 3.2.1-7 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI4-PlOSNAB415-12G7.0-120T-150-T-3940

Figure 3.2.1-8 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI4-PIOSNAB416-17GZ-120T-150-T-3941

Figure 3.2.1-9 MAPLHGR Versus Average Planar Exposure, Fuel Type GEI4-PlOSNAB416-17GZ-120T-150-T-3942

Figure 3.2.1-10 MAPLHGR Versus Average Planar Exposure, Fuel Type GE14-PlOSNAB415-16GZ-120T-150-T-3943

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page

3

5

6

8

9

10

11

12

13

14

15

Page 5: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 2 Rev.: 8

UNIT 1 CORE OPERATING LIMITS REPORT

INDEX (Continued)

Specification

MINIMUM CRITICAL POWER RATIO (CORRESPONDS TO TS 3.2.2)

Figure 3.2.2-1 Power Dependent MCPR Limit (MCPRp), Fuel Type GE12 (Two Loop Operation)

Figure 3.2.2-1a Power Dependant MCPR Limit (MCPRp) Fuel Type GE14 (Two Loop Operation)

Figure 3.2.2-2 Flow Dependent MCPR Limit (MCPRf), Fuel Type GE12 and GE14 (Two Loop Operation)

Figure 3.2.2-3 Power Dependent MCPR Limit (MCPRp), Fuel Type GE12 (Single Loop Operation)

Figure 3.2.2-3a Power Dependant MCPR Limit (MCPRp) Fuel Type GEl4 (Single Loop Operation)

Figure 3.2.2-4 Flow Dependent MCPR Limit (MCPRf), Fuel Type GE12 and GEl4

(Single Loop Operation)

Page

16

17

18

19

20

21

22

LINEAR HEAT GENERATION RATE (CORRESPONDS TO TS 3.2.3)

Linear Heat Generation Rate of each Fuel Type

REACTOR PROTECTION SYSTEM INSTRUMENTATION

(CORRESPONDS TO TS 3.3.1.1)

Simulated Thermal Power Time Constant

OSCILLATION POWER RANGE MONITOR (OPRM) INSTRUMENTATION

(CORRESPONDS TO TS 3.3.1.3)

ATTACHMENTS

Attachment 1: Cycle 9 MCPR Limits Per Transient

PERRY UNIT 1

23

24

25

26

CYCLE 9 CORE OPERATING LIMITS REPORT

Page 6: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 3 Rev.: 8

INTRODUCTION AND REFERENCES

INTRODUCTION

This Core Operating Limits Report for PNPP Unit 1 Cycle 9 is prepared in

accordance with the requirements of PNPP Technical Specification

Administrative Controls 5.6.5. The core operating limits presented were

developed using NRC-approved methods (Reference 2). Results from the reload

analysis for the General Electric fuel in PNPP Unit 1 for Cycle 9 are

documented in References 3, 4, 19, and 20.

The cycle-specific core operating limits for the following PNPP Unit 1

Technical Specifications are included in this report:

1. Average Planar Linear Heat Generation Rate (APLHGR) Limits for each

fuel/lattice type, including the power and flow dependent MAPFAC curves

with the single loop MAPLHGR reduction factor. (Technical

Specification 3.2.1)

2. Minimum Critical Power Ratio Operating Limit including the power and flow

dependent MCPR curves for Two Loop Operation and Single Loop Operation.

(Technical Specification 3.2.2) For Single Loop Operation the MCPR

operating limits are increased by 0.01. (Reference 3)

3. Linear Heat Generation Rate (LHGR) Limit for each fuel type. (Technical

Specification 3.2.3)

4. The simulated thermal power time constant. (Technical

Specification 3.3.1.1, SR 3.3.1.1.14)

5. Oscillation Power Range Monitor (OPRM) Instrumentation. (Technical

Specification 3.3.1.3)

REFERENCES

1. Perry Nuclear Power Plant Updated Safety Analysis Report, Unit 1,

Appendix 15B-Reload Safety Analysis.

2. "General Electric Standard Application for Reactor Fuel-GESTAR II",

NEDE-24011-P-A-14 and NEDE-24011-P-A-14-US (US Supplement), June 2000.

3. "'Supplement Reload Licensing Report for Perry Nuclear Power Plant Unit 1

Reload 8 Cycle 9", GE Document Jll-03754SRLR Rev. 0 (January 2001)

4. "Lattice Dependent MAPLHGR Report for Perry Nuclear Power Plant Unit 1

Reload 7 Cycle 8", GE Document Jll-03371MAP Rev. 0 (January 1999)

5. J. B. Hopkins (USNRC) to R. A. Stratman (Centerior), Amendment No. 61 to

Facility Operating License NPF - 58, June 2, 1994. NRRCEI0719L <L01960>

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 7: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 4 Rev.: 8

6. M. D. Lyster (CEI) to USNRC, Core Operating Limits Report Submittal (Cycle 4), May 22, 1992. CEINRRI495L <L01462>

7. Technical Specification 3.2.1, Average Planar Linear Heat Generation Rate

8. Technical Specification 3.2.2, Minimum Critical Power Ratio

9. Technical Specification 3.2.3, Linear Heat Generation Rate

10. Technical Specification 3.3.1.1, Reactor Protection System Instrumentation

11. Technical Specification 5.6.5, Core Operating Limits Report

12. Technical Specification 2.1.1.2, Safety Limit MCPR

13. GE Design Basis document -- DB-0004.1, "Nuclear Design Basis - Core Design", Rev. 0, dated October 1999.

14. Howard W. Bergendahl (FENOC) to USNRC, "License Amendment Request Pursuant to 10CFR50.90: Implementation of Power Uprate," PY-CEI-NRR-2420L, September 9, 1999.

15. N. Amrhein (GE) to E. M. Root (CEI), "Revision 1 to Final GI-08 ACN: Power Uprate Transient Analysis," GE-PAIP-453, August 4, 1999.

16. F. T. Bolger (GE) "Task Gl-08: Power Uprate Transient Analysis," GE-NE-A2200084-08-01-RI, Revision 1, August 1999.

17. D. V. Pickett (USNRC) to J. K. Wood (FENOC), Amendment 112 to Facility Operating License NPF-58, June 1, 2000.

18. R. Kingston to P. J. Curran, REK:00-006 (January 10, 2001), Off-Rated Limits for GE14,. Perry Cycle 9.

19. "Lattice Dependent MAPLHGR Report for Perry Nuclear Power Plant Unit 1, Reload 6 Cycle 7, GE Document J11-03060MAP, Rev. 0, August 1997.

20. "Lattice Dependent MAPLHGR Report for Perry Nuclear Power Plant Unit 1, Reload 8 Cycle 9, GE Document J11-03754MAP, Rev. 0, January 2001.

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 8: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 5 Rev.: 8

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (TS 3.2.1)

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR values* by the smaller of either the flow dependent MAPLHGR factor (MAPFACf) Figure 3.2.1-1 or the power dependent MAPLHGR factor (MAPFAC,) Figure 3.2.1-2.

These applicable MAPLHGR values are:

1. Those for the respective fuel and lattice type as a function of the average planar exposure (as described by the NRC approved methodology described in GESTAR-II)

or,

2. When hand calculations are required, the MAPLHGR as a function of the average planar exposure for the most limiting lattice shown in Figures 3.2.1-3 through Figure 3.2.1-10 for the applicable type of fuel.

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 9: Perry Nuclear Power Plant Submission of Core Operating

PDB-F0001 Page: 6 Rev.: 8

Flow DeDendent MAPLHGR Factor (MAPFACA) Fuel Types GE12 and GEl4

1.1

1.0

0.9

GE14 - Clamped at 0.80 During SLO

0.8,

GEl 2 - Clamped at 0.77 171 - During SLO

MAPFACf=MIN(1.0,0,4574+0.006758F)

0.6,

0.50 20 40 60 80 100

CORE FLOW (%RATED),F FLOW DEPENDENT MAPLHGR FACTOR

(MAPFAC,)

FUEL TYPES: GE12 and GE14

Figure 3.2.1-1

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

M A P F A C

f

120

Ed-

Page 10: Perry Nuclear Power Plant Submission of Core Operating

PDB-FO001 Page: 7 Rev.: 8

Power Dependent MAPLHGR Factor (MAPFAC.), Fuel Types GE12 and GE14

0.9 I I I I � IMAPFACp=1o.0+0.0052(P-100) 38 %<P<=100%; All core flows

23.8%<=P<=38%; Core Flow <=50% IGE14 - Clamped at 0.80 Durins SLO

I II ItI Itl0i. I'T1[ jIJ I I I'I

I I I I I I I I I I I I

MAPFACp=0.6+0.0021(P-38)

23.8%<=P<=38%; Core Flow >50%

0 20 ;a 60 80 100

CORE THERMAL POWER (%RATED),P POWER DEPENDENT MAPLHGR FACTOR

(MAPFAC.)

FUEL TYPES: GE12 and GE14

Figure 3.2.1-2

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

1.1

i l.0

I l l I I i 0l !!~ ~ ~~ ~- U11 ....1... ..

M A P F A C

P

0.7

1 1 1 1 1I I I I I II] HIlMll i ii l l 1 - -- ---

m I

-II GE12- Clamped , at ! ! .. ! ! !! ! i! ! ! !0.77 During sL° O!

Page 11: Perry Nuclear Power Plant Submission of Core Operating

MAPLHGR Versus Average Planar Exposure, Fuel Type GEl2-PlOSSB399-16GZ-120T-150-T

10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GE12-PIOSSB339-16GZ-120T-150-T

50.0 55.0 60.0

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 4.

Figure 3.2.1-3

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

13.5 13.0 12.5

12.0 11.5 11.0 10.5 10.0

9.5 9.0 8.5

8.0 7.5

7.0

6.5

6.0 5.5

0.0

|E12-PI10SSB399-16GZ-120T-150-T j

PERMISSIBLE _

REGION OF OPERATION __ S I I

5.0

Average MAPLHGR

Planar Most

Exposure Limiting

(GWdIST) (kwltt)

0.00 8.84

0.20 8.89

1.00 8.98

2-00 9.10

3.00 9.22

4.00 9.34

5.00 9.46

6.00 9.59

7.00 9.71

8.00 9.84

9.00 9-96

10.00 10.07

11.00 10.15

12.00 10.16

13.00 10.17

14.00 10.17

15.00 10.17

17.00 10.13

20.00 9.94

26.00 9.52

30.00 9.10

35.00 8.63

40.00 8.09

45.00 7.56

50.00 7.04

55.00 6.52

59.07 6.10

Notes: 1.

2.

Rev. : 8 Page: 8PDB-F0001

Page 12: Perry Nuclear Power Plant Submission of Core Operating

MAPLHGR Versus Average Planar Exposure, Fuel Type GE12-PlOSSB399-14GZ-120T-150-T

Z20- Z.0 304.0 35- u 4.1 U .u WasU~~w

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GEI2-PlOSSB339-14GZ-120T-150-T

13.5

13.0

12.5

12.0

11.5

11.0

10.5

10.0 9.5

9.0 6.5

8.0

7.5

7.0 6.5 6.0 5.5

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 4.

Figure 3.2.1-4

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

SG3E12-P 10SS B399-14GZ-120T-150-T

PERM•ISSIBLE RýEGION OF OPERATION '

0.0 10.0 15.0

Notes: I.

2.

Average MAPLHGR

Planar Most

Exposure Limiting (GWd/ST) (kwlf)

0.00 9.05

0.20 9.10

1.00 9.18

2.00 9.29

3.00 9.40

4.00 9.51

5.00 9.62

6.00 9.74

7.00 9.86

8.00 9.97 9.00 10.09

10.00 10.19

11.00 10.27

12-00 10.27 13.00 F 10.27

14.00 10-26

15.00 10.24

17.00 10.16 20.00 9.95

25.00 9.53

30.00 9.11

35.00 8.64

40.00 8.10 45.00 7.57

50.00 7-05

55.00 6.53

59.18 6.09

Rev. : 8 Page: 9PDB-F0001

ZPWJ.I

Page 13: Perry Nuclear Power Plant Submission of Core Operating

Page: 10

MAPLHGR Versus Average Planar Exposure, Fuel Type GE12-PlOSSB369-14GZ-120T-150-T

5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0

AVERAGE PLANAR EXPOSURE (GWd/t)

MAXIMUM AVERAGE PLANAR LINEAR HEAT

GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GEl2-PlOSSB369-14GZ-12OT-150-T

13.5

13.0

12.5

12.0

11.5

11.0

10.5

10.0

9.5

9.0 8.5

8.0 7.5 7.0

6.5 6.0

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 19.

Figure 3.2.1-5

PERRY UNIT 1CYCLE 9 CORE OPERATING LIMITS REPORT

GE12-PIOSSB369-14GZ-120T-1 50-T

OPERMISSIBLE ___" __REGION OF • .

OPERATION •

0

Average Planar Exposure MAPLHGR (kW/ft) (GWd/ST) Most Limiting

0.00 9.00

0.20 9.04 1.00 9.12

2.00 9.23

3.00 9.36 4.00 9.50 5.00 9.65

6.00 9.77 7.00 9.89 8.00 10.01

9.00 10.14 10.00 10.26

11.00 10.36 12.00 10.33

13.00 10.28 14.00 10.21 15.00 10.14 17.00 9.97 20.00 9.72

25.00 9.29

30.00 8.86

35.00 8.43 40.00 7.99

45.00 7.52 50.00 7.04

55.00 6.53

58.24 6.19

Notes:

1.

2.

Rev. : 8PDB-F0001

Page 14: Perry Nuclear Power Plant Submission of Core Operating

MAPLHGR Versus Average Planar Exposure, Fuel Type GE12-PlOSSB369-12GZ-120T-150-T

5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0

AVERAGE PLANAR EXPOSURE (GWd/t)

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GEI2-P1OSSB369-12GZ-120T-150-T

13.5 13.0

12.5

12.0

11.5

11.0 10.5

10.0

9.5

9.0 8.5

8.0 7.5 7.0

6.5 6.0

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 19.

Figure 3.2.1-6

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

GE1 2-P1 0SSB369-12GZ-120T-1 50-T

OPERMISSIBLE REGION OF . OPERATION

0

Average Planar Exposure MAPLHGR (kW/ft)

(GWd/ST) Most Limiting

0.00 8.89

0.20 8.94

1.00 9.05

2.00 9.19

3.00 9.32

4.00 9.46

5.00 9.61

6.00 9.75

7.00 9.90

8.00 10.05

9.00 10.19

10.00 10.33

11.00 10.41

12.00 10.38

13.00 10.32

14.00 10.25

15.00 10.17

17.00 10.00

20.00 9.74

25.00 9.31

30.00 8.88

35.00 8.45 40.00 8.00

45.00 7.54

50.00 7.05

55.00 6.54

58.22 6.20

Notes: 1.

2.

Rev. : 8 Page: 11PDB-F0001

Page 15: Perry Nuclear Power Plant Submission of Core Operating

Page: 12

MAPLHGR Versus Average Planar Exposure, Fuel Type GE14-PIOSNAB415-12G7.0-120T-150-T-3940

Notes:

1. 2.

PERRY UNI

1,0 - - GE14-PIOSNAB415-12G7.0-120T"150-T-3940

1 1.0 - *-,. -- ,_._

PERMISSIBLE

7.5 REGION OF-

7.0- OPERATION

6.0 - . .

4.6 0.0 5.0 1 0.0 '15.0 20.0 25.0 30.0 35.0 40.0 45.0 60.0 65.0 00.0

Average Planar

EXPOSUre (GOWdSTJ

0.00 0.2 0 .00

2.00 .00o

"a.0 5-03 6.00 7.00 8.00 9.00 10.00 11.,-00 T2.00 13.00 1-4.0-0 15.00 17.00 20.00 25.00

320.00 35.00 40.00 45.00 60.00 5500 56.15

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT

GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GEl4-PIOSNAB415-120G7.0-120T-150-T-3940

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 20.

Figure 3.2.1-7

:T 1 CYCLE 9 CORE OPERATING

LIMITS REPORT

MAPLHG, Most

Limiting (kw"ft) 9.99 10.03 10.08 10.16 10.23 10.31

0O.38 10.46 10.54 10.62 10.70 10.78 10.86 10.84 10.80 10.76 10.72 10.65 10.47 10.08 9.67 9.16 8.68 8.21 7.73 5.48 4.88

Rev. : 8PDB-F0001

Page 16: Perry Nuclear Power Plant Submission of Core Operating

Rev. : 8 Page: 13

MAPLHGR Versus Average Planar Exposure, Fuel Type GE14-P1OSNAB416-17GZ-120T-150-T-3941

13.0 - -1

SGE14-PIOSNAB416-17GZ-120T-150-T-3941

10.0.

10.0 0.5..

PERMISSIBLE REGION OF

OPERATION

0.0 6.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0

Average Planar

Exposure

0.00 0.20 1.00 2.00

.3.00 4.00 5.Q00 6.00 7.00

9.00 010.00 11.00 172.0-0 13-.00 14IF.00 15.00 17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 55.86

MAPLHGR Most

IUmiting (kwnQt) 9.35

941 SAB 9.60 9.72

9.63 9.94 10.06 10.17 10.29 1041 10.53

10.6 1 10.61 10.61 10.61 10.62 10.60 10.460 10AG 10.07 9.66 9.16 8.68 8.20 7.73 5.31

4.88

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT

GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE

FUEL TYPE GEI4-PlOSNAB416-17GZ-120T-150-T-3941

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 20.

Figure 3.2.1-8

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

PDB-FOO01

Notes: 1.

2.

Page 17: Perry Nuclear Power Plant Submission of Core Operating

MAPLHGR Versus Average Planar Exposure, Fuel Type GEI4-PlOSNAB416-17GZ-120T-150-T-3942

Average Planar

Exposure (GWdI"

0.00 0.20 1.00 L.OO

3.00 4.00 5.00 6.00 7.00 8.00 9.00

10.00 11.00 12.00 13.00 14.00 18.00 17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 65.00 55&85

MAPLHGR *Most

Umiffng (kwfft)

S9.39 9.44

9.53 9.63 9.74 9.84 9.95 10.06 10.18 10.29

S10.41 10.52 10.61 10.60 10.59 10.59 10.59 10.58 10.45 10.07

9.66 9.16

S8.68 8.20 7-73

5.31 4.88

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GE14-PlOSNAB416-17GZ-120T-150-T-3942

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 20.

Figure 3.2.1-9

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Notes: 1.

2.

Rev. : 8 Page: 14PDB-F0001

Page 18: Perry Nuclear Power Plant Submission of Core Operating

Page: 15PDB-FOO01

MAPLHGR Versus Average Planar Exposure, Fuel Type GE14-PlOSNAB415-16GZ-120T-150-T-3943

Average Planmr

Exposure (GWdISTf

0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00

10.00 11.00 12.00 13.00 14.00 15.00

-T17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00

55.93

MAPLHGR Nks

Uming (kwift)

9.64 9.74

9.94 10.05 10.15 10.26 10.37 10.48 10.59 10.67 10.66 10.65 10.64 10.63 10.60 10.S 10.07 9.66 9.16 8.68 8.20 7.73 5.36 4.88

AVERAGE PLANAR EXPOSURE (GWd/ST)

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS

AVERAGE PLANAR EXPOSURE

FUEL TYPE GE14-PlOSNAB415-16GZ-120T-150-T-3943

Intermediate MAPLHGR values are obtained by linear interpolation between adjacent points.

This curve is a composite of the most limiting enriched fuel lattices. For lattice specific values consult Reference 20.

Figure 3.2.1-10

PERRY UNIT 1CYCLE 9 CORE OPERATING LIMITS REPORT

Notes: 1.

2.

Rev. : 8

Page 19: Perry Nuclear Power Plant Submission of Core Operating

PDB-F0001 Page: 16

Rev.: 8

MINIMUM CRITICAL POWER RATIO (TS 3.2.2)

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the

higher of the MCPRf and MCPRp limits at the indicated core flow, THERMAL POWER,

and delta T* as specified in Figures 3.2.2-1 and 3.2.2-2 for Two Loop Operation and Figures 3.2.2-3 and 3.2.2-4 for Single Loop Operation.

The MCPR Safety Limit for Cycle 9 is 1.10. The MCPR Safety Limit for Single

Loop Operation is 1.11 <TECHNICAL SPECIFICATIONS 2.1.1.2>. During Single Loop Operation, the Maximum Fraction of Limiting Critical Power Ratio (MFLCPR)

shall be equal to or less than 0.99. Use FTI-B12 Single Loop Operation implements this revised MFLCPR.

NOTE 1: For Cycle 9 no change to MCPR limits is required for planned

reduction of feedwater temperature to as low as 325.5'F. Final

feedwater temperature may be reduced to 255.5 0 F after all control rods are withdrawn at the end of cycle.

NOTE 2: Planned reduction of rated feedwater temperature from nominal rated feedwater temperature is not permitted during plant operation with

the reactor recirculation system in Single Loop Operation.

NOTE 3: Figures 3.2.2-1, 3.2.2-la, and 3.2.2-2, depict the limiting fuel type

for Two Loop Operation. Figures 3.2.2-3, 3.2.2-3a, and 3.2.2-4 depict the limiting fuel type for Single Loop operation. For fuel

type specific values, consult Reference 3.

Attachment 1 illustrates the limiting transient for each fuel type.

The thermal limits calculation uses whichever is highest (MCPRf or

MCPRp) for the given power and flow condition.

NOTE 4: There are a total of 19 safety/relief valves, the two lowest setpoint valves are assumed to be out-of-service in the transient analysis.

NOTE 5: The MCPR operating limit is increased 0.01 to account for the increase in the single loop MCPR safety limit with the reactor recirculation system in single loop operation.

* This delta T refers to the planned reduction of rated feedwater temperature

from nominal rated feedwater temperature (425.5'F), such as prolonged

removal of feedwater heater(s) from service.

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 20: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 17 Rev.: 8

Power Dependent MCPR Limit (MCPRP), Fuel Type GE12 (Two Loop Operation)*

2.9

LA.

2.3

2.2

2.1

2.0

1.9PERMISSIBLE H

REGION OF OPERATION

1.8

1.7

1.8CPRp = 1.32[l.223 + 0.004(66.7

For 38% <P <=66.7%; All Core Flow

I I

MCPRp = 1.32[1 +0.005(100 - P)J For 66.7% < P<= 100%; All Core Flows

I I I I I I I

1.4

1.3

1.2, 0 20 40 60

CORE THERMAL POWER (%RATED),P POWER DEPENDENT MCPR LIMIT

(MCPRp)

FUEL TYPE GE12 (TWO LOOP OPERATION)

* Refer to NOTE 3 on Page 16

Figure 3.2.2-1

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

8D 100

MCPRp = [2.02 + 0.0246(38 - P)j For 23.8 <= P <= 38%; Core Flow > 50%

MCPRp = [1.99 + 0.0162(38 - P)] For 23.8%<= P <=38%; Core Flow<=50%

1.0 •

Page 21: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 18 Rev.: 8

Power Dependent MCPR Limit (MCP,), Fuel Type GE14 (Two Loop Operation)*

F MCPRp = [2.02+ 0.0246(38 - P)]

I MCPRp = [1.99 + 0.0162(38 P)] For 23.8%<= P <=38%; Core Flow<=50%

PERMISSIBLE REGION OF

-IOPERATION i

I I I I II

1.41

1.2.

1.24"

0

SMCPRp = 1.3611 +0.005(100- P}] For 66.7% < P<= 100%; All Core Flows

20 40 60

CORE THERMAL POWER (%RATED),P POWER DEPENDENT MCPR LIMIT

(MCPRP)

FUEL TYPE GE14 (TWO LOOP OPERATION)

* Refer to NOTE 3 on Page 16

Figure 3.2.2-1aPERRY UNIT 1 CYCLE 9

CORE OPERATING LIMITS REPORT

2.5,

2.4

2.3,

2.2

2.1

Z.U.

1.9

1 .

1.7

1.64,MCPRp = 1.3611.223 + 0.004(66.7 - P)j For 38% < P <66.7%; All Core Flows

1.01

80 1;0

m

m

I

I]

Page 22: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 19 Rev.: 8

Flow Dependent MCPR Limit (MCPRf), Fuel Type GE12 and GEl4 (Two Loop Operation)*

M C P R

f

1.7,

1113., H i lIPER11 11 1M ISSIBLE REGION OF OERATION

I 1-l40LMCPR1 = 1,3 1

1.3, ~ ~ ~ ~ ~ 1 L(.83-101111'1101071

For Gl2 an G~l4FueIGE14 0LMCPR =1.36

0 20 40 60 80 100

CORE FLOW (%RATED),F POWER DEPENDENT MCPRLIMIT

(MCPRf)

FUEL TYPE GE12 and GE14 (TWO LOOP OPERATION)

* Refer to NOTE 3 on Page 16

Figure 3.2.2-2PERRY UNIT 1 CYCLE 9

CORE OPERATING LIMITS REPORT

120

Page 23: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 20 Rev.: 8

Power Dependent MCPR Limit (MCPR),Fuel Type GE12 (Sinale Loon Operation)*

MCPRp = [2.02 + 0.0246(38 - P)] + 0.01 For 23.8 <= P <= 38%; Core Flow> 50%

lilIllIllMCPRp = [1.99 + 0.0162(38 - P)] + 0.01

For 23.8% <= P<= 38%; Care Flow~= 50%

'i i l""ii

J

10080

CORE THERMAL POWER (%RATED),P

POWER DEPENDENT MCPR LIMIT (MCPR,)

FUEL TYPE GEl2 (SINGLE LOOP OPERATION)

* Refer to NOTE 3 and NOTE 5 on Page 16

Figure 3.2.2-3

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

2.,

2.4'

2.3

2.2

II_

2.0.

1.9.

1.8.

1.7,

PERMISSIBLE I REGION OF |OPERATION

II1 F %

4 Vt -I - . . . . . . . . . . . .

t-E1.01

1.4]

I I I

17Ii I

I I rII I I I

0., ,. 0 20 40 s0

'PRp = 1.3211.223 + 0.004(66.7.- P)] + 0.01 _ __ For 38% < P<=66.7%; All Core Flows

MCPRp = 1.3211 + 0.0051100 - P)] + 0.01

4 For 66.71% < P <=1000%; All Core FlowIs

1 .4 1

Page 24: Perry Nuclear Power Plant Submission of Core Operating

PDB-F0001 Page: 21 Rev.: 8

Power Dependent MCPR Limit (MCPp),L Fuel Type GE14 (Sinqle Loop Operation)*

MCPRp = [2.02 + 0.0246(38 - P)] + 0.01 For 23.8 <= P <= 38%; Core Flow> 50%

MCPRp = [1.99 + 0.0162(38 - P)] + 0.01 For 23.8% <= P<= 38%; Core Flow<= 50%

i i i i i i i i i i i i i i 1 i i d i i

A.0.

2.4.

2.3.

2.2.

2.1.

2.0.

1.9.

1.8.

1.7.

1.5,

1.4 ,

. i i

20 40 60 80 100

CORE THERMAL POWER (%RATED),P POWER DEPENDENT MCPR LIMIT

(MCPR,)

FUEL TYPE GEl4 (SINGLE LOOP OPERATION)

* Refer to NOTE 3 and NOTE 5 on Page 16

Figure 3.2.2-3a

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

PERMISSIBLE REGION OF

[PERATONM C P R

P

0

MCPRp = 1.3610.223 + 0.004(66.7 - P)] + 0.01

C MCPRp =1.3611 + 0.005(100 - P)] + 0.01 I For 6'6.7%' < P <--I00%; All Core Flows

1.3,

d •

I I i I I T-T i F-T

LL

Page 25: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 22 Rev.: 8

Flow Dependent MCPR Limit (MCPRE) , Fuel Type GE12 and GE14 (Single Loop Operation)*

H il1.8,II I II I

PERMISSIBE REGION OF4 OPERATION

1.5 1

1.4-M illGE140OLMCPR =1.37

MCPRf =MAX [OLMCPR,I Wil

1.3((1.8134-0.006948F)*(t.1;1.07)+0.01)] 11 • For GE12 and GE14 Fuel _GEl20LMCPR =1.33"

1.2,

a 20 40 60 80 100 120

CORE FLOW (%RATED),F POWER DEPENDENT MCPR LIMIT

(MCPRf)

FUEL TYPE GEl2 and GEl4 (SINGLE LOOP OPERATION)*

* Refer to NOTE 3 and NOTE 5 on Page 16

Figure 3.2.2-4

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

M C P R

f

Page 26: Perry Nuclear Power Plant Submission of Core Operating

PDB-F0001 Page: 23 Rev.: 8

LINEAR HEAT GENERATION RATE (TS 3.2.3)

The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed:

a. 13.4 kw/ft. for the following fuel types:

I. "2. 3. 4.

GE14-PIOSNAB415-12G7.0-120T-150-T-3940 GEI4-PIOSNAB416-17GZ-120T-150-T-3941 GE14-PIOSNAB416-17GZ-120T-150-T-3942 GE14-PIOSNAB415-16GZ-120T-150-T-3943

(GE14) (GE14) (GE14) (GEl4)

b. 11.8 kw/ft. for the following fuel types:

1. 2. 3. 4.

GEI2-PlOSSB399-16GZ-120T-150-T GE12-PIOSSB399-14GZ-120T-150-T GE12-PIOSSB369-14GZ-120T-150-T GE12-PIOSSB369-12GZ-120T-150-T

(GE12) (GE12) (GEl2) (GE12)

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 27: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 24 Rev.: 8

REACTOR PROTECTION SYSTEM INSTRUMENTATION (TS 3.3.1.1)

The simulated thermal power time constant shall be 6+/-0.6 seconds.

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 28: Perry Nuclear Power Plant Submission of Core Operating

PDB-FOO01 Page: 25 Rev.: 8

OSCILATION POWER RANGE MONITOR (OPRM) INSTRUMENTATION (TS 3.3.1.3)

1. Confirmation Count Setpoint (Np = N2 ): 12

2. Amplitude Setoint (Sp): 1.09

Reference: Calculation: FMI2, Revision 0

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT

Page 29: Perry Nuclear Power Plant Submission of Core Operating

Attachment 1 PDB-FOO01 Page: 26 - LAST Rev.: 8

Cycle 9 MCPR Limits

1.4

1.35

1.3

1.25

1.2

1.15

1.1

GE14

* RWE

M FLE, misorientated

O FLE, mislocated

A LFWH

*[email protected]

[email protected]

GE12

PERRY UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT