LR-N07-0228, Core Operating Limits Reports - Cycle 14, Revision 1

Core Operating Limits Reports - Cycle 14, Revision 1

ML072770611
Person / Time
Site:	Hope Creek
Issue date:	09/26/2007
From:	Gaffney M Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N07-0228 NFS-0253, Rev 1
Download: ML072770611 (21)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 PSEG Nuclear LLC TS 6.9.1.9 LR-N07-0228 SEP 2 6 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Core Operating Limits Report - Cycle 14, Revision 1 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear, LLC submits Revision 1 of the Core Operating Limits Report (COLR) for Hope Creek Cycle 14 (NFS-0253, Rev. 1) in Attachment 1 of this letter.

Should you have any questions, please contact Paul Duke at (856) 339-1466.

Sincerely, Michael Gaffney a Regulatory Assurance Manager - Hope Creek Attachment cc: S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - Hope Creek, USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE 95-2168 REV. 7/99

ATTACHMENT 1 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Core Operating Limits Report Cycle 14/Reload 13 NFS-0253, Revision 1

NFS-0253 Revision 1 Hope Creek Generating Station Unit 1 Core Operating Limits Report Cycle 14 / Reload 13 Effective Date: \1 L 7 6o]

Prepared By: Date: 7/ 27 1/7 Amneth W. Buckwheat,

r. Core Design and Methods Engineer Reviewed By Date: / cQ7 o7 Franis J. Safin, Sr. Fuel Project Engineer Approved By Date: c*/2--/02 Donald V. Notigan, Manager - BWR Design & Analysis Page 1 of 19

NFS-0253 Revision 1 Table of Contents Section Description Page

1.0 INTRODUCTION

4 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR 5 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 6 2.2 MINIMUM CRITICAL POWER RATIO 8 2.3 LINEAR HEAT GENERATION RATE 12 2.4 OPRM TRIP SETPOINT 16

3.0 REFERENCES

17 Appendix A: Method of Core Average Scram Speed Calculation 18 Page 2 of 19

NFS-0253 Revision 1 List of Tables Table Description Page Table 2.1-1: APLHGR Data for GE14 Fuel 7 Table 2.1-2: APLHGR Data for SVEA-96+ Fuel 7 Table 2.2-1: Cycle 14 MCPR Operating Limits: Cycle Exposure

• 9755 MWD/MTU

(*8850 MWD/STU) _ 10 Table 2.2-2: Cycle 14 MCPR Operating Limits: Cycle Exposure > 9755 MWD/MTU

(> 8850 MWD/STU) 10 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data 11 Table 2.2-4: Flow Dependent MCPR Limit (MCPRf) 11 Table 2.3-1: LHGR Limit for GE14 14 Table 2.3-2: LHGR Limit for SVEA-96+ 14 Table 2.3-3: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp) 15 Table 2.3-4: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf) - 15 Page 3 of 19

NFS-0253 Revision 1

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit 1 Cycle 14 / Reload 13 operation. This report provides the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), and Linear Heat Generation Rate (LHGR), as well as power and flow dependent adjustments to these limits that support off-rated operation and Single recirculation Loop Operation (SLO). Additionally, this report provides the Allowable Value for the Oscillation Power Range Monitor (OPRM) trip setpoint, and the method of average scram speed determination. Finally, this report provides a reference to the most recent revision of the implemented approved licensing methodology.

These operating limit LCO values have been determined using NRC approved methods contained in GESTAR-II, NEDE-2401 1-P-A (Revision 15) 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.

Hope 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. Hope Creek Technical Specification 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 Hope Creek Generating Station Unit 1 Cycle 14 / Reload 13 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the CrossflowTM correction factor is applied or not applied.

Revision 1 of this report incorporates two administrative changes. The applicability of the report is extended to cover power coastdown operation consistent with existing GESTAR-II, NEDE-2401 1-P-A (Revision 15) bases and to include as additional information the OPRM confirmation counts for the OPRM setpoint (N2) consistent with the documentation requirements of the NRC Safety Evaluation Report which was issued for Hope Creek Generating Station (HCGS) Technical Specification Amendment 159. This report is applicable for Cycle 14 operation from the date of issuance through the end of cycle including consideration of a power coastdown to a core thermal power that shall not go below 40% rated core thermal power. 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 allowable rated feedwater temperatures, in the all-rods-out configuration.

Operation beyond the end of full power capability is defined as power coastdown operation which includes an operating assumption that vessel dome pressure will droop (decrease) during the power coastdown period as steam flow decreases (maintaining constant vessel dome pressure during the power coastdown period was not generically considered by GESATR-II for determining the operating limit LCO values described above).

Page 4 of 19

NFS-0253 Revision 1 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR The TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR presented in this section are referenced by the Hope Creek Techmical Specifications.

Tech. Spec. Title 2.1 Bases Safety Limit Bases 3/4.2.1 Average Planar Linear Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.11 Oscillation Power Range Monitor 3/4.4.1 Recirculation System Recirculation Loops 3/4.2.1 Bases Average Planar Linear Heat Generation Rate 3/4.2.4 Bases Linear Heat Generation Rate 3/4.3.11 Bases Oscillation Power Range Monitor (OPRM) 3/4.4.1 Bases Recirculation System 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 5 of 19

NFS-0253 Revision 1 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in Table 2.1-1 and Table 2.1-2 for Two recirculation Loop Operation (TLO).

When the Technical Specification Section 3/4.4.1 ACTION statement a.1.d is entered from that section's Limiting Condition for Operation, reduce the APLHGR limits to the values specified in Tables 2.1-1 and 2.1-2 for Single recirculation Loop Operation (SLO).

Linear interpolation shall be used to determine APLHGR limits as a function of exposure for intermediate values in Table 2.1-1 and Table 2.1-2.

Page 6 of 19

NFS-0253 Revision 1 Table 2.1-1: APLHGR Data for GE14 Fuel Average Planar Exposure APLHGR Limit MWD/MTU vMLD/STU Two Loop Operation Single Loop Operation 0.00 0.00 12.82 10.26 21090 19130 12.82 10.26 63500 57610 8.00 6.40 70000 63500 5.00 4.00 Table 2.1-2: APLHGR Data for SVEA-96+ Fuel a PAPLHGR Limit Average Planar Exposure JkW/ft MWD/MTU MWD/STU Two Loop Operation Single Loop Operation 0.00 0.00 12.85 10.28 3680 3340 12.85 10.28 16000 14510 10.97 8.78 65000 58970 7.24 5.79 Page 7 of 19

NFS-0253 Revision 1 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 computed from the following steps:

1. Determine r as defined in Appendix A.

NOTE The SLO operating condition MCPR values in Tables 2.2-1, 2.2-2, 2.2-3 and 2.2-4 implement the increase in the MCPR Safety Limit to meet the requirements of Technical Specification Section 3/4.4.1 ACTION statement a. L.c.

2. Linearly interpolate a MCPR value as a function of t from the MCPR value at z = 0 and the MCPR value at T = 1 as specified in Table 2.2-1 and Table 2.2-2 for the appropriate operating condition.

3. For the power dependent MCPR adjustment, when thermal power is > 30% rated core thermal power, determine a Kp value by linearly interpolating a Kp value as a function of core rated thermal power from Table 2.2-3. Multiply the MCPR value obtained from Step 2 by the Kp value to determine the power dependent MCPR limit.

When core thermal power is __25% rated and < 30% rated thermal power, determine the appropriate power dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core thermal power for the appropriate core flow condition using the information in Table 2.2-3.

4. For the flow dependent MCPR adjustment, determine the appropriate flow dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core flow using the information in Table 2.2-4.

5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in steps 2 and 3 as the value for the MCPR limit for the Limiting Condition For Operation.

Note that the MCPR limit is a function of core average scram speed (u), cycle exposure, core thermal power, total core flow, EOC-RPT operability, the number of reactor coolant recirculation loops in operation, and main turbine bypass operability.

EOC-RPT system operability is defined by Hope Creek Technical Specification 3.3.4.2.

Page 8 of 19

NFS-0253 Revision 1 2.2 MINIMUM CRITICAL POWER RATIO (Continued)

Reactor coolant recirculation loop operation is defined by Hope Creek Technical Specification 3.4.1.1.

Main Turbine Bypass operability is defined by Hope Creek Technical Specification 3.7.7.

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NFS-0253 Revision 1 Table 2.2-1: Cycle 14 MCPR Operating Limits:

Cycle Exposure __9755 MWD/MTU (*58850 MWD/STU)

Main Turbine Bypass Operable Operating Condition Scram Speed GE14 SVEA-96+

Option I A 145 1.48 TLO-EOC-RPT Operable B 1.34 1.37 A 1.48 1.49 TLO-EOC-RPT Inoperable B 1.37 1.38 A 1.47 1.50 SLO-EOC-RPT Operable B 1.36 1.39 A 1.50 1.51 SLO-EOC-RPT Inoperable B 1.39 1.40 Scram Speed Option A t = 1, Scram Speed Option B r = 0, TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Table 2.2-2: Cycle 14 MCPR Operating Limits:

Cycle Exposure > 9755 MWD/MTU (> 8850 MWD/STU)

Main Turbine Bypass Operable.

Operating Condition Scram Speed GE14 SVEA-96+

Option TLO-EOC-RPT Operable A 1.57 1.59 B 1.40 1.42 A 1.61 1.62 1.45 TLO-EOC-RPT Inoperable B 1.44 B 1.44 1.45 SLO-EOC-RPT Operable A 1.59 1.61 B 1.42 1.44 A 1. 1.64 SLO-EOC-RPT Inoperable B 1.46 1.47 Scram Speed Option A t = 1, Scram Speed Option B ' = 0, TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Page 10 of 19

NFS-0253 Revision 1 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data Core Thermal Power (% of rated)

Operating Core Flow Condition (% of rated) Ž25 <30 >30 45 60 Ž100 MCPR Limit MCPR Multiplier., Kp

< 60 2.25 2.12 TLO 1.481 1.280 1.150 1.000

> 60 2.93 2.70

< 60 2.27 2.14 SLO 1.481 1.280 1.150 1.000

> 60 2.95 2.72 TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Table 2.2-4: Flow Dependent MCPR Limit (MCPRf)

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NFS-0253 Revision 1 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit computed from the following steps:

1. Determine the exposure dependent LHGR limit for the appropriate fuel design using linear interpolation between the values in Table 2.3-1 and Table 2.3-2.

NOTE For Two recirculation Loop Operation utilize steps 1, 2, 3 and 6 to determine the LCO LHGR limits for Two recirculation Loop Operation (TLO).

When the Technical Specification Section 3/4.4.1 ACTION statement a. i.e is entered from that section's Limiting Condition for Operation (LCO), utilize steps 1, 4, 5 and 6 to determine the LCO LHGR limits for Single recirculation Loop Operation (SLO).

2. For the power dependent LHGR adjustment for TLO, determine a LHGRFACp value by linearly interpolating a LHGRFACP value as a function of rated core thermal power for the core flow condition being evaluated from the TLO entries in Table 2.3-

3. Multiply the LHGR values obtained from Step 1 by the LHGRFACP value to determine the power dependent LHGR limits for each fuel design.

3. For the flow dependent LHGR adjustment for TLO, determine a LHGRFACf value by linearly interpolating a LHGRFACf value as a function of rated core flow from the TLO entries in Table 2.3-4. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limits for each fuel design.

4. For the power dependent LHGR adjustment for SLO, determine a LHGRFACp value by linearly interpolating a LHGRFACP value as a function of rated core thermal power for the core flow condition being evaluated from the SLO entries in Table 2.3-

3. Multiply the LHGR values obtained from Step 1 by the LHGRFACP value to.

determine the power dependent LHGR limits for each fuel design.

5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACf value by linearly interpolating a LHGRFACf value as a function of rated core flow from the SLO entries in Table 2.3-4. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limits for each fuel design.

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NFS-0253 Revision 1 2.3 LINEAR HEAT GENERATION RATE (Continued)

6. Choose the most limiting (lowest value) of the power and flow dependent LHGR limits determined in steps 2 and 3 (TLO) or 4 and 5 (SLO) as the value for the LHGR limit for the Limiting Condition For Operation.

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NFS-0253 Revision 1 Table 2.3-1: LHGR Limit for GE14 Peak Pellet Exposure LHGR Limit MWD/MTU MWD/STU kW/ft 0.0 0.0 13.40 16000 14510 13.40 63500 57610 8.00 70000 63500 5.00 Table 2.3-2: LHGR Limit for SVEA-96+

Peak Pellet Exposure LHGR Limit MWD/MTU MWD/STU kW/ft 0.0 0.0 13.41 16000 14510 10.97 65000 58970 7.24 Page 14 of 19

NFS-0253 Revision 1 Table 2.3-3: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACP)

.1 .1 Core Thermal Power (% of rated)

Operating Core Flow

_25 < 30 1 30 61.7 70 ŽT100 Condition (% of rated)

LHGRFACn Multinlier

<60 0.577 0.590 TLO ___ _ 0.634

> 60 0.476 0.502

_<60 0.577 0.590 SLO 0.634

> 60 0.476 0.502 Table 2.3-4: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf)

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NFS-0253 Revision 1 2.4 OPRM TRIP SETPOINT LIMITING CONDITION FOR OPERATION Four channels of the OPRM instrumentation shall be OPERABLE. Each OPRM channel period based algorithm amplitude trip setpoint (Sp) shall be less than or equal to the Allowable Value of 1.08.

Additional hiformation.

The NRC Safety Evaluation Report, dated 12/22/04, which was issued for Technical Specification Amendment Number 159 required that the period based algorithm amplitude trip setpoint (Sp) and confirmation counts be documented in the COLR. The confirmation counts are docmnented below.

Number of successive confirmation counts for OPRM setpoint (N,) = 11 Page 16 of 19

NFS-0253 Revision 1

3.0 REFERENCES

1. Nuclear Fuel Section Design Input File HCG.5-0002,"General Electric Standard Application for Reactor Fuel," General Electric Company, NEDE-2401 1-P-A-15, and the U.S. Supplement NEDE-2401 I-P-A- 15-US.

2. Nuclear Fuel Section Design Input File, HCG.5-0041, "Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 13 Cycle 14" GE Nuclear Energy 0000-0041-6021-SRLR, Rev. 1, March 2006.

3. Nuclear Fuel Section Design Input File HCG.5-0041, "Fuel Bundle Information Report for Hope Creek Unit 1 Reload 13 Cycle 14," 0000-0041-6021-FBIR, Rev. 0 February 2006.

4. Nuclear Fuel Section Correspondence, NFS06-049, Revised OPRM Period Based Algorithm Trip Setpoint for Cycle 14, 12/20/06.

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NFS-0253 Revision 1 Appendix A: Method of Core Average Scram Speed Calculation Page 18 of 19

NFS-0253 Revision 1 Method of Core Average Scram Speed, T, Calculation r is defined as (T-.," - TO)

TA - TB where:

TA = 0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.3.3 "r=0.672+1.651-71 (0.1016)

Si=1

'ave ,

n = number of surveillance tests performed to date in cycle, N. = number of active control rods measured in the ith surveillance test, i =average scram time to notch 39 of all rods measured in the ih surveillance test, and N1 = total number of active rods measured in Specification 4.1.3.2.a.

If Vave < 7' , set r = 0 to apply Option B OLMCPR.

V" shall be 1.0 (r = 1.0) prior to performance of the initial scram time measurements for the cycle in accordance with Specification 4.1.3.2.

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