L-11-168, Core Operating Limits Report for Cycle 14

Core Operating Limits Report for Cycle 14

ML11154A102
Person / Time
Site:	Perry
Issue date:	05/24/2011
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-11-168
Download: ML11154A102 (23)

Text

FENOC FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant 10 Center Road Perry, Ohio 44081 M1 VA 440-280-5382 ark B. Bezilla Fax: 440-280-8029 ce President May 24, 2011 L-11-168 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant, Unit No.1 Docket No. 50-440, License No. NPF-58 Core Operatinq Limits Report for Cycle 14 Enclosed please find the Perry Nuclear Power Plant, Unit No. 1 Core Operating Limits Report for Cycle 14, Revision 19. Submittal of this report is in accordance with PNPP Technical Specification 5.6.5, "Core Operating Limits Report (COLR)."

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at (330) 761-6071.

Sincerely, Mark B. Bezilla

Enclosure:

CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 14 (RELOAD 13) cc:

NRC Region III Administrator NRC Resident Inspector NRC Project Manager A.--.,

Enclosure CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 14 (RELOAD 13)

(21 Pages Follow)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 14 (RELOAD 13)

Functional Location (Ji1)

Plant Data Book Effective Date:

5-22-11 Preparer:

Approver:

Patrick Curran

/ 5-21-11 Date Paul W. Bordley

/ 5-21-11 Date

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 1

2 of 21 TABLE OF CONTENTS Page

1.0 INTRODUCTION

3

2.0 REFERENCES

4 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1) 6 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2) 10 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3) 19 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1) 21 7.0 OSCILLATION POWER RANGE MONITOR (OPRM)

INSTRUMENTATION (T.S. 3.3.1.3) 21 8.0 SCOPE OF REVISION 21

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 3 of 21

1.0 INTRODUCTION

This Core Operating Limits Report for PNPP Unit 1 Cycle 14 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 1 and Reference 2).

Results from the reload analysis for the Global Nuclear Fuels fuel in PNPP Unit 1 for Cycle 14 are documented in References 3, 4, and 5.

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)

Additional power dependent MCPR curves for Two Loop Operation and Single Loop Operation are provided for operation with one pressure regulator out of service.

3.

Linear Heat Generation Rate (LHGR) Limits for each fuel/lattice type, including the power and flow dependent MAPFAC curves with the single loop MAPLHGR reduction factor. (Technical Specification 3.2.3)

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)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-F0001 Title Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision: 1 Page:

2.0 REFERENCES

2.1 Discretionary None 2.2 Obligations

1.

General Electric Standard Application for Reactor Fuel-GESTAR II, NEDE-24011-P-A-17 and NEDE-24011-P-A-17 (US Supplement),

September 2010

2.

Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996.

3.

Supplemental Reload Licensing Report for Perry 1 Reload 13 Cycle 14, GNF Document 0000-0088-8470-SRLR, Rev 0, December 2010

4.

Fuel Bundle Information Report for Perry 1 Reload 13 Cycle 14, GNF Document 0000-0088-8470-FBIR, Rev 0, December 2010

5.

Supplemental Reload Licensing Report for Perry Nuclear Power Plant Unit 1 Reload 8 Cycle 9, GNF Document J11-03754SRLR, Rev 1, January 2003

6.

License Amendment 155, Perry Nuclear Power Plant, Unit 1 -

Issuance of Amendment RE: License Amendment to Modify Technical Specification 2.1.1, "Reactor Core SLS," To Incorporate Revised Safety Limit Minimum Critical Power Ratio Values (TAC No. MC ME4925), April 18, 2011.

7.

Calculation FM-012, OPRM Device Settings and Setpoints.

8.

Technical Specification 2.1.1.2, Safety Limit MCPR

9.

Technical Specification 3.2.1, Average Planar Linear Heat Generation Rate

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision: 1 Page:

10.

Technical Specification 3.2.2, Minimum Critical Power Ratio

11.

Technical Specification 3.2.3, Linear Heat Generation Rate

12.

Technical Specification 3.3.1.1, Reactor Protection System Instrumentation

13.

Technical Specification 5.6.5, Core Operating Limits Report

14.

Perry Nuclear Power Plant Updated Safety Analysis Report, Unit 1, Appendix 1 5B-Reload Safety Analysis

15.

Neutron Monitoring System Design Specification, 22A3739 Commitments addressed in this document:

None

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision: 1Page:

3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1)

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR limit, Figure 3.2.1-1, by the smaller of either the flow dependent MAPLHGR factor (MAPFACf), Figure 3.2.1-2 or the power dependent MAPLHGR factor (MAPFACp) Figure 3.2.1-3.

MAPLHGR Limits and MAPFACf and MAPFACp are defined in Reference 3.

For Two Loop Operation, MAPFACf and MAPFACp shall not exceed 1.0.

For Single Loop Operation, MAPFACf and MAPFACp shall not exceed 0.8.

The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.

Use FTI-B001 2 Single Loop Operation to implement the revised MAPLHGR Limits.

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01 Titie:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

_19 7 of 21 Figure 3.2.1-1 MAPLHGR Versus Average Planar Exposure Fuel Type GE14 14 12 10 U-I

-J 0U 8

6 F

GE14 ECCS MAPLHGR Limit]

I I

I_

MAPLHGR = 12.82 for Exposures </= 19.13 MAPLHGR = 12.82 + (-0.12526) * (Exposure - 19.13) for 19.13 < Exposures </= 57.61 MAPLHGR = 8.00 + (-0.50934) * (Exposure - 57.61) for 57.61 < Exposures </= 63.50 4

2 0

0 5

10 15 20 25 30 35 40 45 50 Average Planar Exposure (GWDIST) 55 60 65 70

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

__19 8 of 21 Figure 3.2.1-2 Flow Dependent MAPLHGR Factor (MAPFACf)

Fuel Type GE14 1.1 1.0 T

GE14 - Clamped at 0.80 During SLO I

/

J-IL. 0.8,+

0.7, 0.6.

0.5

/

I MAPFACf=MIN(1.0,0.4574+0.006758F)

E t

I' V

I I

0 20 40 60 80 100 120 CORE FLOW (% RATED)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision: 1 Page:

Figure 3.2.1-3 Power Dependent MAPLHGR Factor (MAPFACp)

Fuel Type GE14 C.,

LL.

0.

0 20 40 60 80 CORE THERMAL POWER (% RATED) 100

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-F0001

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

lPage:

19 10 of 21 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2)

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the higher of the flow dependent MCPR (MCPRf) and power dependent MCPR (MCPRp) limits at the indicated core flow and THERMAL POWER.

The MCPR Safety Limit for Cycle 14 for Two Loop Operation is 1.10 and the MCPR Safety Limit for Single Loop Operation is 1.11 <TECHNICAL SPECIFICATIONS 2.1.1.2> (Reference 3 and 6). The change in Safety Limit from Two Loop Operations to Single Loop Operations is accomplished by increasing the Cycle 14 MCPRf and MCPRp limits by 0.01.

3DMONICORE PANACEA Version 11 uses this approach to calculate Single Loop Operation Limits.

The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.

Use FTI-B0012 Single Loop Operation to implement the revised MCPR Limits.

During Two Loop Operation, the resulting limit from MCPRf and MCPRp shall not be less than the OLMCPR of 1.35. During Single Loop Operation, the resulting limit from MCPRf and MCPRp shall not be less than the OLMCPR of 1.36.

For Cycle 14 no change to MCPR limits is required for planned reduction of feedwater temperature to as low as 325.50 F. Final feedwater temperature may be reduced to 255.50 F after all control rods are withdrawn at the end of cycle if the OPRMs are OPERABLE.

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.

The 3DMONICORE Computer software should automatically shift between 2 LOOP ON and ONE LOOP ON modes of operation on transfer to Single Loop Operations. As such the Safety Limit change should occur automatically. The guidance in FTI-B0012 can be used to verify proper

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 11 of 21 functioning of the 3DMONICORE System. If the 3DMONICORE System is not functioning properly, FTI-B0012 will implement administrative limits until such time as 3DMONICORE is properly calculating MCPR values.

The MCPRf and MCPRp Limits are based on whether the plant is operating in Two Loop or Single Loop Operations and whether Two Pressure Regulators or One Pressure Regulator is in service. Select MCPRf/

MCPRp Limit Curves based on plant conditions:

MCPRf Figure 3.2.2-1, Figure 3.2.2-2, MCPRp Figure 3.2.2-3, Figure 3.2.2-4, Figure 3.2.2-5, Figure 3.2.2-6, Figure 3.2.2-7 MCPRf-Two Loop Operations MCPRf-Single Loop Operations MCPRp-Two Loop Operations MCPRp-Single Loop Operations MCPRp-Two Loop Operations / Pressure Regulator Out of Service MCPRp-Single Loop Operations / Pressure Regulator Out of Service Maximum Fraction Limiting Critical Power Ratio Limit (MFLCPR) With One Pressure Regulator Out Of Service The 3DMONICORE Software will not automatically shift to the Pressure Regulator Out of Service Thermal Limits. The 3DMONICORE databank will be manually changed using a software change request. Until such time as 3DMONICORE databank is updated for the Pressure Regulator Out of Service Thermal Limits, an MFLCPR Administrative Limit will be issued to Operations. Figure 3.2.2-7 can be used as a guide in establishing the MFLCPR Administrative Limit. The graph is the ratio of MCPRp to MCPRp - Pressure Regulator Out Of Service.

The Cycle 14 COLR depicted MCPRf curves are slightly greater than the data tables contained in Cycle 14 Supplemental Reload Licensing Report (SRLR) (Reference 3). The Cycle 14 SRLR used a double round down to estimate the value for MCPRf at 30% flow. The Cycle 14 COLR uses the equation contained in the Cycle 9 Supplemental Reload Licensing Report (Reference 5).

Using the equation provides for slightly greater values of MCPRf which are more conservative.

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 112 of 21 Figure 3.2.2-1 Flow Dependent MCPR (MCPRf) - Two Loop Operation Fuel Type GE14 1.8 1.7 0

0

.0 0

00C 0

0 1.6 1.5 PERMISSIBLEL REGION OF OPERATION/

MCPR1 MX

[1.351M/1.07

(.8134-0.006948F)*(1.10/1.07)]

-~ ~

~

~

~

=0---....

OLCPR =

S3 1.4 1.3 1.2 0

20 40 60 80 100 120 CORE FLOW (% RATED)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

page:

19 13 of 21 Figure 3.2.2-2 Flow Dependent MCPR (MCPRj) - Single Loop Operation Fuel Type GEl4 1.8 1.7 0

2 1.6 Q.

0 0

0 0

-J 81 S1.5 C._.

1.4 1.3 1.2 20 40 60 80 100 CORE FLOW (% RATED) 120

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 14 f2 0

.4-CL 0.

0 0.

0 I-0~

M.

Figure 3.2.2-3 Power Dependent MCPR Limit (MCPRp) - Two Loop Operation Fuel Type GEI4 2.5 2.4 2.3 2.2 MCPRp = 2.02 + 0.0246(38-P)

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

2.1 MCPRp = 1.99 + 0.0162(38 - P)

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

MCPRp 1.35 [1.448 + 0.007(50.0 - P)]

REGION OF For 38% < P <=50.0%; Core Flow <=105%I OPERATION 1.8, 1.6*

Rp = 1.35 * [1.223 + 0.004(66.7-P)]

For 50.0% < P <=66.7%; Core Flow <=105%

1.5, 1.4 MCPRp = 1.35 * [1 +0.005(100 - P)]

For 66.7% < P<= 100%; Core Flow <=105%

1.3 1.2 0

20 40 60 80 100 CORE THERMAL POWER (% RATED)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 i1 15 of 21 Figure 3.2.2-4 Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Fuel Type GE14 0

4.2 CL 0.0.

0.

0

(;5 (1

9 20 40 60 80 CORE THERMAL POWER (% RATED) 100

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 116 of 21 Figure 3.2.2-5 Power Dependent MCPR Limit (MCPRp) - Two Loop Operation Pressure Regulator Out Of Service / Fuel Type GE14 2.5 2.4 2.3 2.2 0

2.1 00, 2.0 0(-

4) 1.9 0.

0 CL 0

1.8 o

0

-J 0

g.1.7 L) 1.6 1.6 1.4 1.3 1.2 0

20 40 60 80 CORE THERMAL POWER (% RATED) 100

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 117 of 21 Figure 3.2.2-6 Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Pressure Regulator Out Of Service / Fuel Type GE14 2.5 2.4 2.3 2.2 0

2.1 0

.2C" 2.0

, 1.9 04-0 0 1.8

-J

.0 1.7

0. 1.6 Q3 1.5 1.4 1.3 1.2 0

20 40 60 80 CORE THERMAL POWER (% RATED) 100

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 118 of 21 Figure 3.2.2-7 Maximum Fraction Limiting Critical Power Ratio Limit (MFLCPR)

With One Pressure Regulator Out Of Service / Fuel Type GE14 000 0.

0 U.

I-

_j

-J U.2E 20 25 30 36 40 45 50 55 60 65 70 75 80 85 90 95 100 CORE THERMAL POWER (% RATED)

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 i

19 of 21 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3)

All LINEAR HEAT GENERATION RATES (LHGRs) shall not exceed the result obtained from multiplying the applicable LHGR limit, Figure 3.2.3-1, by the smaller of either the flow dependent MAPLHGR factor (MAPFACf),

Figure 3.2.1-2 or the power dependent MAPLHGR factor (MAPFACp)

Figure 3.2.1-3.

LHGR Limits and MAPFACf and MAPFACp are defined in References 3 and 4.

For Two Loop Operation, MAPFACf and MAPFACp shall not exceed 1.0.

For Single Loop Operation, MAPFACf and MAPFACp shall not exceed 0.8.

The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.

Use FTI-B0012 Single Loop Operation to implement the revised MAPLHGR Limits.

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 720 of 21 Figure 3.2.3-1 LHGR Versus Peak Pellet Exposure Fuel Type GE14 U.

E 14_

12 10-_____

8 U02/Gd LHGR LIMIT

-411-UO2 LHGR LIMIT 4

U02 LHGR LIMIT LHGR =1 3.40 for Exposures <1= 14.51 LHGR =1 3.40 + (-0.12529) (Exposure - 14.51) for 14.51 < Exposures </= 57.61 LHGR = 8.00 + (-0.50934) * (Exposure - 57.61) for 57.61 < Exposures </= 63.50 2

U02/Gd LHGR LIMIT LHGR =12.00 for Exposures </= 12.17 LHGR =12.00 + (-0.11410) (Exposure - 12.17) for 12.17 < Exposures <1= 54.59 LHGR = 7.16 + (-0.46207) (Exposure - 54.59) for 54.95 < Exposures </= 60.39 0

0 10 20 30 40 50 60 Peak Pellet Exposure (GWD/ST) 70

PERRY NUCLEAR POWER PLANT Procedure Number:

PDB-FOO01

Title:

Use Category:

Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 14 (Reload 13)

Revision:

Page:

19 121 of 21 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1)

The simulated thermal power time constant shall be 6 +/-0.6 seconds (Reference 15).

7.0 OSCILLATION POWER RANGE MONITOR (OPRM)

INSTRUMENTATION (T.S. 3.3.1.3)

These are the Cycle 14 OPRM setpoints for operable OPRMs.

Current Settings:

1.

Confirmation Count Setpoint (Np = N2): 12

2.

Amplitude Setpoint (Sp): 1.10

Reference:

Calculation: FM-012, Revision 4, Addendum 1 8.0 SCOPE OF REVISION Rev. 19

1.

Corrected page numbers in the Table of Contrents.

2.

On Page 11 corrected MCPRf to MCPRf and added "(SRLR)"

in the text.