LR-N07-0275, Core Operating Limits Report - Cycle 15

Core Operating Limits Report - Cycle 15

ML073100708
Person / Time
Site:	Hope Creek
Issue date:	10/25/2007
From:	Keenan J Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N07-0275
Download: ML073100708 (19)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC OCT 2 632007 TS 6.9.1.9 LR-N07-0275 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 15 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear, LLC submits the Core Operating Limits Report (COLR) for Hope Creek Cycle 15 in Attachment 1 of this letter.

Should you have any questions, please contact Lee Marabella at (856) 339-1208.

Sincerely, 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'

'4o(

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 15/Reload 14

COLR HOPECREEK 1, REV 0 CORE OPERATING LIMITS REPORT FOR Hope Creek Generating Station Unit 1 RELOAD 14, CYCLE 15 Prepared By: Date: 94~

K. W. Buckwheat Preparer Reviewed By Date:

Giuseppe Rubinaccio Independent Reviewer Approved By Date: /1/~0_Z6'

//* JJ.J lusar Z, nager BWR Design (GNF)

Page I of 17

COLR HOPECREEK 1, REV 0 Table of Contents Page 1.0 Terms and Definitions 4 2.0 References 5 3.0 General Information 6 4.0 Technical Specifications that Reference the COLR 7 4.1 Average Planar Linear Heat Generation Rate 8 4.2 Minimum Critical Power Ratio 9 4.3 Linear Heat Generation Rate 12 4.4 OPRM Trip Setpoint. 15 Appendix A: Method of Core Average Scram Speed Calculation 16 Page 2 of 17

COLR HOPECREEK 1, REV 0 List of Tables TABLE 4.1-1 APLHGR Data for GE14 Fuel ..................................... 8 TABLE 4.1-2 APLHGR Data for SVEA-96+ Fuel ........................................................................ 8 TABLE 4.2-1 MCPR Operating Limits: Cycle Exposure _ 11227 MWD/MTU (< 10185 MWD/STU) .............. 10 TABLE 4.2-2 MCPR Operating Limits: Cycle Exposure > 11227 MWD/MTU (> 10185 MWD/STU) .............. 10 TABLE 4.2-3 Power Dependent MCPR Adjustments and Multiplier (Kp) Data ............................ 11 TABLE 4.2-4 Flow Dependent M CPR Limit (M CPRf) .................................................................. 11 TABLE 4.3-1 LHGR Data for GE14 Fuel ................................................................................... 13 TABLE 4.3-2 LHGR Data for SVEA-96+ Fuel .......................................................................... 13 TABLE 4.3-3 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp) ....... 14 TABLE 4.3-4 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf)............. 14 Page 3 of 17

COLR HOPECREEK 1, REV 0 1.0 Terms And Definitions APLHGR Average Planar Linear Heat Generation Rate ARTS APRM and RBM Technical Specification Analysis COLR Core Operating Limits Report ECCS Emergency Core Cooling Systems EOC-RPT End-Of-Cycle Recirculation Pump Trip LCO Limiting Condition for Operation LHGR Linear Heat Generation Rate LHGRFACf ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFACp ARTS LHGR thermal limit power dependent adjustments and multipliers MCPR* Minimum Critical Power Ratio MCPRp ARTS MCPR thermal limit power dependent adjustments and multipliers MCPRf ARTS MCPR thermal limit flow dependent adjustments and multipliers OPRM Oscillation Power Range Monitor SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TLO Two Loop Operation Page 4 of 17

COLR HOPECREEK 1, REV 0 2.0 References

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

2. "Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 14 Cycle 15 CLTP", Global Nuclear Fuel Document No. 0000-0071-5592-SRLR, Revision 0, October 2007.

3. "Fuel Bundle Information Report for Hope Creek Unit 1 Reload 14, Cycle 15 CLTP", Global Nuclear Fuel Document No. 0000-0071-5592-FBIR, Rev., 0, October 2007.

4. "Technical Specifications and Bases for Hope Creek Generating Station Unit", Docket No. 50-354, License No. NPF-57.

5. "Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 13 Cycle 14", Global Nuclear Fuel Document No. 0000-0041-6021-SRLR, Revision 1, March 2006.

6. "Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 12 Cycle 13", Global Nuclear Fuel Document No. 0000-0031-0596-SRLR, Revision 1, December 2004.

7. "Fuel Bundle Information Report for Hope Creek Unit 1 Reload 12, Cycle 13", Global Nuclear Fuel Document No. 0000-0031-0596-FBIR, Rev. 0, December 2004.

8. "Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology",

Westinghouse Document CENPD-397-P-A.,

9. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications",

Global Nuclear Fuel Document NEDO-32465-A.

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COLR HOPECREEK 1, REV 0 3.0 General Information The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit 1 Cycle 15/Reload 14 operation. In addition, this report will provide cycle information on OPRM set points, single recirculation loop operation, nominal scram speed and determination of the Core Maximum Fraction of Limiting Power Density. Finally, this report also provides a reference to the most recent revision of the implemented approved methodology. The limits presented here correspond to the core thermal limits for APLHGR, MCPR, MCPRp, MCPRf and LHGR.

These operating limit values have been determined using NRC approved methods contained in the GESTAR-Il, NEDE-2401 1-P-A (Revision 15, Reference 1) 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. In addition, the operating limits have been determined consistent with the requirements of CENPD-397-P-A (Reference 8) and NEDO-32465-A (Reference 9),

where appropriate.

Various sections of the Hope Creek Technical Specifications reference this COLR. Those sections are listed in section 4 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 15/Reload 14 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. This report is applicable for Cycle 15 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 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 GESTAR-ll for determining the operating limit LCO values described above).

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COLR HOPECREEK 1, REV 0 4.0 Technical Specifications that reference the COLR The following Hope Creek Technical Specifications reference this COLR:

Tech. Spec. Title 2.1 Safety Limit Bases 3/4.2b Power Distribution Bases 3/4.2.1 Average Planar Linear Generation Rate 3/4.2. lb Average Planar Linear Heat 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 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 7 of 17

COLR HOPECREEK 1, REV 0 4.1 MAPLHGR Limits LIMITING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in Table 4.1-1 and Table 4.1-2 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 Table 4.1-1 and Table 4.1-2.

Linear interpolation shall be used to determine APLHGR limits as a function of exposure for intermediate values in Table 4.1-1 and Table 4.1-2 TABLE 4.1-1 APLHGR Data for GEl4 Fuel Average Planar Exposure APLHGR Limit

... .. (kW /ft) -

MWd/MTU MWd/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 4.1-2 APLHGR Data for SVEA-96+ Fuel APLHGR Limit Average Planar Exposure (kW/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 8 of 17

COLR HOPECREEK 1, REV 0 4.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION:

The MINIMUM CRITICAL POWER RATION (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 4.2-1, 4.2-2, 4.2-3, and 4.2-4 implement the increase in the MCPR Safety Limit to meet the requirements of Technical Specification Section 3/4.4.1.1 ACTION statement a. 1.c.

• 2. Linearly interpolate a MCPR value as a function of -rfrom the MCPR value at T=0'and MCPR value

• ' at -r=1 as specified in Table 4.2-1 and Table 4.2-2 for the appropriate 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 4.2-3. 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 4.2-3.

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 4.2-4.

5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in steps 3 and 4 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.

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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COLR HOPECREEK 1, REV 0 TABLE 4.2-1 Cycle 15 MCPR Operating Limits: Cycle Exposure < 11227 MWD/MTU (< 10185 MWD/STU)

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

A 1.48 1.49 TLO-EOC-RPT Operable B 1.37 1.38 A 1.50 1.51 TLO-EOC-RPT Inoperable B 1.39 1.40 A 1.50 1.51 SLO-EOC-RPT Operable B 1.39 1.40 A 1.52 1.53 SLO-EOC-RPT Inoperable

_ _ _ _ _B 1.41 1.42 Scram Speed Opt tion A r = 1, Scram Speed Option B 1 = 0, TLO = Two recirculation Loop Operatic )fSLO Single recirculati on Loop Operation.

TABLE 4. 2-2 Cycle 15 MCPR Operating Limits: Cycle Exposure > 11227 MWD/MTU (> 10185 MWDISTIJ)

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

A 1.59 1.60 TLO-EOC-RPT Operable B 1.42 1.43 A 1.62 1.63 TLO-EOC-RPT Inoperable B 1.45 1.46 A 1.61 1.62 SLO-EOC-RPT Operable B 1.44 1.45 A 1.64 1.65 SLO-EOC-RPT Inoperable B 1.47 1.48 Scram Speed Option At =1, Scram Speed Option B t = 0, TLO = Two recirculation Loop Operation, SLO =

Single recirculation Loop Operation.

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COLR HOPECREEK 1, REV 0 TABLE 4.2-3 Power Dependent MCPR Adjustments and Multiplier (Kp) Data Core Thermal Power (% of Rated)

Operating Core Flow 10T Condition (%of Rated) Ž25 <30 Ž30 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 Kp is LinearlyInterpolated.between Core Thermal Powers. TLO =-Tworecirculation Loop Operatio;ý SLO=

Single recirculation Loop Operation.

TABLE 4.2-4 Flow Dependent MCPR Limit (MCPRf)

Core Flow (% of Rated)

Operating Condition 30 60 77 105 MCPR Limit TLO 1.53 SLO 1.55 Page 11 of 17

COLR HOPECREEK 1, REV 0 4.3 Linear Heat Generation Rate Limits 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 4.3-1 and Table 4.3-2.

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

When the Technical Specification Section 3/4.4.1.1 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 4.3-3. 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 thermal flow from the TLO entries in Table 4.3-4. 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 4.3-3. 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 thermal flow from the SLO entries in Table 4.3-4. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limits for each fuel design.

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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COLR HOPECREEK 1, REV 0 TABLE 4.3-1 LHGR Data for GE14 Fuel Peak Pellet Exposure LHGR Limit MWd/MTU MWd/STU KW/ft 0.00 0.00 13.40 16000 14510 13.40 63500 57610 8.00 70000 63500 5.00 TABLE 4.3-2 LHGR Data for SVEA-96+ Fuel Peak Pellet Exposure LHGR Limit MWd/MTU MWd/STU KW/ft 0.00 0.00 13.41 16000 14510 10.97 65000 58970 7.24 Page 13 of 17

COLR HOPECREEK 1, REV 0 TABLE 4.3-3 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACP)

Core Thermal Power (% of Rated)

Operating Core Flow Condition (%of Rated) >25 <30 Ž 30 61.7 70 Ž100 LHGRFACp Multiplier

• 60 0.577 0.590 TLO 0.634 1.000

> 60 0.476 0.502

• 60 0.577 0.590 4

SLO 4

0.634 0.800 0.800

> 60 0.476 0.502 TABLE 4.3-4 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf)

Core Flow (% of Rated)

Operating Condition 30 50 52.7 1 60 82.2 105 LHGRFACf Multiplier TLO 0.500 0.782 1.000 1 1.000 SLO 0.500 0.782 1 0.800 1 0.800 Page 14 of 17

COLR HOPECREEK 1, REV 0 4.4 Stability Protection Setpoints 4.4.1 1.0 Hz Corner Frequency Setpoints 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 1.13.

Additional Information.

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 documented below.

Number of successive confirmation counts for OPRM setpoint (N2) = 15 4.4.2 1.5 Hz Corner Frequency Setpoints 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 1.14.

Additional Information.

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 documented below.

Number of successive confirmation counts for OPRM setpoint (N 2) = 16 Page 15 of 17

COLR HOPECREEK 1, REV 0 Appendix A: Method of Core Average Scram Speed Calculation Page 16 of 17

COLR HOPECREEK 1, REV 0 Method of Core Average Scram Speed, -c,Calculation r is defined as r(rave - B)

TA - TB where:

rA =0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.3.3

=0.672+1.65r lN (0.016)

Nirij nZN Tave =n Ni=

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

If rave < rB ,set r = 0 to apply Option B OLMCPR.

r 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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