SVP-02-064, Core Operating Limits Report for Cycle 17A

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Core Operating Limits Report for Cycle 17A
ML022380190
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 08/09/2002
From: Tulon T
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-02-064, TAC MB4747
Download: ML022380190 (23)


Text

Exekrn.

Exelon Generation Company, LLC www exeloncorp corn Nuclear Ouad Cities Nuclear Power Station 22710 206th Avenue North Cordova, IL 61242-9740 August 9, 2002 SVP-02-064 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Unit 1 Facility Operating License No. DPR-29 NRC Docket Number 50-254

Subject:

Core Operating Limits Report for Quad Cities Unit 1 Cycle 17A

Reference:

Letter from USNRC to J. L. Skolds (Exelon) dated, July 29, 2002 "Quad Cities Unit 1 - Issuance of Amendment RE: Change in Minimum Critical Power Ratio Safety Limit (TAC NO. MB4747)

The referenced letter amended Quad Cities Unit 1 Minimum Critical Power Ratio Safety Limit to allow for operation to the end of cycle 17A. On January 9, 2002, Quad Cities Nuclear Power Station (QCNPS) Unit 1 was forced to shutdown (Q1 F49) as a result of a failed jet pump. During the forced shutdown QCNPS replaced a leaking fuel bundle with a bundle from the spent fuel pool, and elected to shuffle additional fuel bundles to extend full power operation for the Unit 1 core. As a result, Cycle 17A has been developed for Unit 1. This revised COLR is applicable until the end of Cycle 17A, which ends in November of 2002.

Enclosed is the revised COLR for Cycle 17A, submitted in accordance with Technical Specifications Section 5.6.5.d.

Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.

Respectfully, Timothy J.prTde Site Vice r* ent Quad Cities'Nuclear Power Station Attachment A: Core Operating Limits Report for Quad Cities Unit 1 Cycle 17A cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 4NrcoD\

Attachment A Core Operating Limits Report for Quad Cities Unit I Cycle 17A

Core Operating Limits Report For Quad Cities Unit I Cycle 17A July 2002 i

Quad Cities Unit 1 Cycle 17A July 2002

ISSUANCE OF CHANGES

SUMMARY

Affected Affected Summary of Changes Date Section Pages All All Original Issue (Cycle 17A) 1/02 iii, 3-1, and Deleted "first sequence exchange" restriction on validity of 4-1 the COLR and LHGR and MCPR limits. 4/02 iv Added control blade history analysis reference.

Special iii, 3-1, 3-2, Removed 4140 MWD/MT cycle exposure limitation on the Instructions, and 4-1 COLR, LHGR, and MCPR limits.

3.2, and 4.2 References, iv, v, 4-1, Added MCPR operating limits corresponding to 1.15 dual List of 4-2, 4-3, and loop and 1.16 single loop MCPR Safety Limit. 7/02 Tables, and 4-4 4.2 5.0 5-1 and 5-2 Add additional methodology based on Amendments 201/197 of Section 5.6.5 of the Technical Specifications.

1 Quad Cities Unit 1 Cycle 17A July 2002

TABLE OF CONTENTS SPECIAL INSTRUCTIONS ........................................................................... 111 REFERENCES ............................................................................................ iv LIST OF TABLES ........................................................................................ v 1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION ................ 1-1 1.1 TECHNICAL SPECIFICATION REFERENCE ............................... 1-1

1.2 DESCRIPTION

(TLO) ............................................................. 1-1

1.3 DESCRIPTION

(SLO) ............................................................. 1-1 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........ 2-1 2.1 TECHNICAL SPECIFICATION REFERENCE ............................... 2-1

2.2 DESCRIPTION

..................................................................... 2-1 2.3 SINGLE LOOP OPERATION MULTIPLIER ................................. 2-1 3.0 LINEAR HEAT GENERATION RATE (LHGR) ....................................... 3-1 3.1 TECHNICAL SPECIFICATION REFERENCE .............................. 3-1

3.2 DESCRIPTION

..................................................................... 3-1 4.0 MINIMUM CRITICAL POWER RATIO (MCPR) ...................................... 4-1 4.1 TECHNICAL SPECIFICATION REFERENCE ............................... 4-1

4.2 DESCRIPTION

..................................................................... 4-1 5.0 ANALYTICAL METHODS ................................................................. 5-1 Quad Cities Unit 1 Cycle 17A July 2002

SPECIAL INSTRUCTIONS This Core Operating Limits Report (COLR) contains the applicable reactor core limits and operational information mandated by Technical Specifications Section 5.6.5. When the COLR is referenced by applicable Technical Specifications or procedures for Technical Specification compliance, a controlled copy of this report shall be used as the official source of the applicable limit or requirement.

iii Quad Cities Unit 1 Cycle 17A July 2002

REFERENCES

1. Exelon Generation Company, LLC and MidAmerican Energy Company Docket No. 50-254, Quad Cities Nuclear Power Station, Unit I Facility Operating License, License No. DPR-29.
2. Letter from D.M. Crutchfield to All Power Reactor Licenses and Applicants, Generic Letter 88 16; Removal of Cycle-Specific Parameter Limits from Technical Specifications, 10/3/1998.
3. "Quad Cities Unit I Cycle 17 Neutronics Licensing Report (NLR)", Document ID # DGOO 001158, TODI NFM0000100, Sequence 0.
4. Quad Cities Nuclear Power Station, Units I and 2, SAFER/GESTR - LOCA Loss-of-Coolant Accident Analysis, NEDC-31345P, Revision 2, Class 111, July 1989 (as amended).
5. EMF-96-037(P), Rev. 1, "Quad Cities Extended Operating Domain (EOD) and Equipment Out Of Service (EOOS) Safety Analysis for ATRIUM-9B Fuel", September 1996, NFS NDIT # 9600134 Seq 02.
6. EMF-2415, "Quad Cities Unit I Cycle 17 Plant Transient Analysis", Rev. 0, August 2000.
7. EMF-2416, "Quad Cities Unit I Cycle 17 Reload Analysis", Rev. 0, August 2000.
8. EMF-2348(P), Revision 0, "Quad Cities LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 9B Fuel", February 2000.
9. DEG:98:177, "Permission to Send the NRC Nonproprietary Transient Analysis and Reload Analysis Reports", D.E. Garber to R.J. Chin, June 1, 1998.
10. GE DRF C51-00217-01, "Instrument Setpoint Calculation Nuclear Instrumentation, Rod Block Monitor, Quad Cites I & 2", December 14, 1999.
11. EMF-2706(P) Revision 0, "Quad Cities Unit I Cycle 17A Neutronic and Safety Analyses,"

January 2002.

12. JI 1-03692-LHGR, Revision 1, Class 3, February 2000, "CoinEd GE9/GEIO LHGR Improvement Program", NDIT NFM0000067, Sequence 0.
13. DEG:01:077, "Quad Cities Unit I Cycle 17 Evaluation of Fuel Thermal Conductivity (Non Proprietary Version for Exelon)," David Garber to Dr. R. J. Chin, May 14, 2001.
14. DEG:02:063, "Control Blade History Evaluation for Quad Cities Unit I Cycle 17A," D. E. Garber to F. W. Trikur, April 1, 2002.
15. EMF-2743, "Quad Cities Unit I Cycle 17A Plant Transient Analysis," Revision 0, May 2002 (TODI NFM0200101 Rev. 0).
16. EMF-2735. "Quad Cities Unit 1 Cycle 17A Reload Analysis," Revision 0, May 2002 (TODl NFM0200100 Rev. 0).

iv Quad Cities Unit I Cycle 17A July 2002

LIST OF TABLES Table Title Page 2-1 MAPLHGR vs. Average Planar Exposure for GE1O-P8HXB311-8GZ-100M-145- 2-2 CECO 2-2 MAPLHGR vs. Average Planar Exposure for GE1O-P8HXB312-7GZ-100M-145- 2-3 CECO 2-3 MAPLHGR vs. Average Planar Exposure for GEI0-P8HXB332-8G5.0-100M- 2-4 145-CECO 2-4 MAPLHGR vs. Average Planar Exposure for GE10-P8HXB333-4G5.0/6G4.0- 2-5 1OOM-145-CECO 2-5 MAPLHGR vs. Average Planar Exposure for SPCA9-3.4 8B- 11G6.5-ADV, 2-6 SPCA9-3.60B- 1 G6.5-ADV, SPCA9-383B- 11 GZH-ADV and SPCA9-382B 12GZL-ADV 3-1 LHGR vs Average Planar Exposure for ATRIUM-9B Steady State 3-2 3-2 LHGR vs Average Planar Exposure for ATRIUM-9B Transient 3-2 4-1 QIC17A Base Operating Limit MCPRs 4-2 4-2a Q1C17A Operating Limit MCPRs for Manual Flow Control - Dual Loop 4-2 Operation 4-2b QIC17A Operating Limit MCPRs for Manual Flow Control - Single Loop 4-2 Operation 4-3a Q1C17A Operating Limit MCPRs for Automatic Flow Control - Dual Loop 4-3 Operation (Normal Operation or 1 Bypass Valve OOS) 4-3b QIC17A Operating Limit MCPRs for Automatic Flow Control - Single Loop 4-3 Operation (Normal Operation or 1 Bypass Valve OOS) 4-4a QlC17A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS - 4-3 Dual Loop Operation 4-4b QIC17A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS - 4-3 Single Loop Operation 4-5a Q1C17A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves 4-4 OOS - Dual Loop Operation 4-5b Q1C17A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves 4-4 OOS - Single Loop Operation v

Quad Cities Unit 1 Cycle 17A July 2002

1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 1.1 TECHNICAL SPECIFICATION

REFERENCE:

TS 3.3.2.1, Table 3.3.2.1-1 (COLR 1.2) and TS 3.4.1 (COLR 1.3)

1.2 DESCRIPTION

(TLO):

The Rod Withdrawal Block Monitor Upscale Instrumentation Allowable Value for two recirculation loop operation is determined from the following relationship:

< (0.65)Wd + 56.1% **

1.3 DESCRIPTION

(SLO):

The Rod Withdrawal Block Monitor Upscale Instrumentation Allowable Value for Single Loop Operation (SLO) is determined from the following relationship:

< (0.65)Wd + 51.4% **

    • Clamped with an allowable value not to exceed the allowable value for recirculation loop drive flow (Wd) of 100%

Wd is the percent of drive flow required to produce a rated core flow of 98 million lb/hr. Trip level setting is in percent of rated power (2511 MWth).

1-1 Quad Cities Unit 1 Cycle 17A July 2002

2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 2.1 TECHNICAL SPECIFICATION

REFERENCE:

TS 3.2.1 (COLR 2.2) and TS 3.4.1 (COLR 2.3)

2.2 DESCRIPTION

The base MAPLHGR limits are determined as follows:

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) vs.

Average Planar Exposure for GElO-P8HXB311-8GZ-100M-145-CECO is determined from Table 2-1.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) vs.

Average Planar Exposure for GE1O-P8HXB312-7GZ-1OOM-145-CECO is determined from Table 2-2.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) vs.

Average Planar Exposure for GE1O-P8HXB332-8G5.0-100M-145-CECO is determined from Table 2-3.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) vs.

Average Planar Exposure for GE10-P8HXB333-4G5.0/6G4.0-100M-145-CECO is determined from Table 2-4.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) vs.

Average Planar Exposure for SPCA9-3.48B-1 1G6.5-ADV, SPCA9-3.60B-1 1G6.5 ADV, SPCA9-383B-11GZH-ADV, and SPCA9-382B-12GZL-ADV is determined from Table 2-5.

2.3 SINGLE LOOP OPERATION MULTIPLIER:

The tabulated values are multiplied by 0.85 for GE fuel and 0.90 for SPC fuel whenever Quad Cities enters Single Loop Operation.

2-1 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 2-1 MAPLHGR vs. Average Planar Exposure for GE10-P8HXB311-8GZ-100M-145-CECO LATHCE 1807: P8HXL071-8GE-100M-T LATTICE 1806: P8HXL335-8G3.0-100M-T LATTICE 1805: P8HXL353-2G4.0/6G3.0-100M-T LATTICE 1804: P8HXL335-4G4.014G3.0-100M-T LATTICE 1054: P8HXL071-NOG-100M-T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPOSURE 1054 1806 1805 1804 1807 (GWD/ST) 0.0 11.85 12.06 11.10 12.02 11.85 0.2 11.78 12.12 11.14 12.08 11.78 1.0 11.59 12.28 11.27 12.22 11.59 2.0 11.57 12.48 11.51 12.40 11.57 3.0 11.61 12.68 11.81 12.57 11.61 4.0 11.68 12.89 12.14 12.76 11.68 5.0 11.75 13.11 12.50 12.94 11.75 6.0 11.81 13.29 12.88 13.12 11.81 7.0 11.86 13.41 13.19 13.28 11.86 8.0 11.91 13.47 13.28 13.40 11.91 9.0 11.94 13.48 13.34 13.46 11.94 10.0 11.97 13.46 13.39 13.49 11.97 12.5 11.75 13.34 13.44 13.33 11.75 15.0 11.38 12.96 13.09 12.95 11.38 20.0 10.59 12.22 12.40 12.22 10.59 25.0 9.81 11.51 11.73 11.50 9.81 27.22 12.314 12.314 12.314 12.314 12.314 48.08 10.800 10.800 10.800 10.800 10.800 58.97 6.000 6.000 6.000 6.000 6.000 2-2 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 2-2 MAPLHGR vs. Average Planar Exposure for GE1O-P8HXB312-7GZ-100M-145-CECO LATTICE 1811: P8HXL071-7GE-100M-T LATTICE 1810: P8HXL336-7G3.0-100M-T LATTICE 1809: P8HXL354-1G4.0/6G3.0-100M-T LATTICE 1808: P8HXL336-3G4.0/4G3.0-100M-T LATTICE 1054: P8HXL071-NOG-100M-T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPOSURE 1054 1810 1809 1808 1811 (GWD/ST) 0.0 11.85 12.04 11.27 12.01 11.85 0.2 11.78 12.11 11.31 12.08 11.78 1.0 11.59 12.27 11.42 12.23 11.59 2.0 11.57 12.49 11.65 12.43 11.57 3.0 11.61 12.72 11.93 12.65 11.61 4.0 11.68 12.96 12.24 12.88 11.68 5.0 11.75 13.15 12.58 13.09 11.75 6.0 11.81 13.30 12.94 13.22 11.81 7.0 11.86 13.41 13.15 13.32 11.86 8.0 11.91 13.46 13.32 13A0 11.91 9.0 11.94 13.47 13.43 13.45 11.94 10.0 11.97 13.45 13.50 13.47 11.97 12.5 11.75 13.35 13.45 13.35 11.75 15.0 11.38 12.97 13.10 12.97 11.38 20.0 10.59 12.24 12.41 12.23 10.59 25.0 9.81 11.52 11.74 11.51 9.81 27.22 12.314 12.314 12.314 12.314 12.314 48.08 10.800 10.800 10.800 10.800 10.800 58.97 6.000 6.000 6.000 6.000 6.000 2-3 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 2-3 MAPLHGR vs. Average Planar Exposure for GE10-P8HXB332-8G5.0-100M-145-CECO LATTICE 1054: P8HXL071-NOG- 100T-T LATTICE 2080: P8HXL358-8G5.0-100T-T LATTICE 2081: P8HXL377-8G5.0-100T-T LATMICE 2082: P8HXL071-8GE-i 00T-T AVERAGE MAPLHGR LIMITS (KWIFT)

PLANAR EXPOSURE 1054 2080 2081 2082 (GWD/ST) 0.0 11.85 11.98 11.55 11.85 0.2 11.78 12.05 11.58 11.78 1.0 11.59 12.18 11.65 11.59 2.0 11.57 12.33 11.80 11.57 3.0 11.61 12.48 11.97 11.61 4.0 11.68 12.57 12.11 11.68 5.0 11.75 12.67 12.25 11.75 6.0 11.81 12.77 12.38 11.81 7.0 11.86 12.88 12.47 11.86 8.0 11.91 12.85 12.57 11.91 9.0 11.94 12.83 12.67 11.94 10.0 11.97 12.84 12.77 11.97 12.5 11.75 13.05 12.92 11.75 15.0 11.38 12.89 12.77 11.38 20.0 10.59 12.17 12.24 10.59 25.0 9.81 11.46 11.50 9.81 27.22 12.314 12.314 12.314 12.314 48.08 10.800 10.800 10.800 10.800 58.97 6.0000 6.000 6.000 6.000 2-4 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 2-4 MAPLHGR vs. Average Planar Exposure for GE10.P8HXB333°4G5.0/6G4.0-100M-145-CECO LATTICE 1054: P8HXL071-NOG-100T-T LATIHCE 2077: P8HXL358-4G5.0/6G4.0-L00T-T LATrICE 2078: P8HXL377-4G5.0/6G4.0-100T-T LAMTCE 2079: P8HXL071-10GE-100T-T AVERAGE MAPLHGR LIMITS (KWIFT)

PLANAR EXPOSURE 1054 2077 2078 2079 (GWD/ST) 0.0 11.85 11.81 11.22 11.85 0.2 11.78 11.86 11.26 11.78 1.0 11.59 11.95 11.36 11.59 2.0 11.57 12.11 11.52 11.57 3.0 11.61 12.25 11.69 11.61 4.0 11.68 12.40 11.88 11.68 5.0 11.75 12.56 12.08 11.75 6.0 11.81 12.72 12.29 11.81 7.0 11.86 12.85 12.46 11.86 8.0 11.91 12.89 12.61 11.91 9.0 11.94 12.94 12.76 11.94 10.0 11.97 13.00 12.90 11.97 12.5 11.75 13.14 13.02 11.75 15.0 11.38 12.90 12.79 11.38 20.0 10.59 12.17 12.24 10.59 25.0 9.81 11.46 11.50 9.81 27.22 12.314 12.314 12.314 12.314 48.08 10.800 10.800 10.800 10.800 58.97 6.0000 6.000 6.000 6.000 2-5 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 2-5 MAPLHGR vs. Average Planar Exposure for SPCA9-3.48B-11G6.5-ADV SPCA9-3.60B-11G6.5-ADV SPCA9-383B-11GZH-ADV and SPCA9-382B-12GZL-ADV AVERAGE PLANAR ATRIUM-9B MAPLHGR EXPOSURE (GWD/MTU) (KW/IFT) 0.0 13.5 20.0 13.5 60.0 8.7 61.1 8.6 2-6 Quad Cities Unit 1 Cycle 17A July 2002

3.0 LINEAR HEAT GENERATION RATE (LHGR) 3.1 TECHNICAL SPECIFICATION

REFERENCE:

TS 3.2.3 and TS 3.2.4

3.2 DESCRIPTION

A. The LHGR limit for the GE fuel types in the Q1C17A core are as follows:

GE10.P8HXB311-8GZ-100M-145-CECO NODAL EXPOSURE LHGR (KW/ft)

(GWD/MTU) 0.0 14.40 12.87 14.40 27.16 12.31 48.91 10.80 60.61 6.00 GE10.P8HXB312-7GZ-100M-145-CECO NODAL EXPOSURE LHGR (KW/ft)

(GWD/MTU) 0.0 14.40 13.00 14.40 27.27 12.31 49.01 10.80 60.70 6.00 GE1O.P8HXB332-8G5.0-10OM-145-CECO NODAL EXPOSURE LHGR (KW/ft)

(GWD/MTU) 0.0 14.40 12.75 14.40 27.25 12.31 48.97 10.8 60.62 6.00 GE10-P8HXB333-4G5.0/6G4.0-100M-145-CECO NODAL EXPOSURE LHGR (KW/ft)

(GWD/MTU) 0.0 14.40 12.69 14.40 27.11 12.31 48.87 10.80 60.54 6.00 3-1 Quad Cities Unit 1 Cycle 17A July 2002

B. The LHGR limits are provided in Table 3-1 for all of the SPC fuel types (ATRIUM-9B Offset) in the Q1C17A core.

The Protection Against Power Transient LHGR Limits for ATRIUM-9B Offset fuel are provided in Table 3-2.

TABLE 3-1 LHGR vs AVERAGE PLANAR EXPOSURE for ATRIUM-9B Steady State TABLE 3-2 LHGR vs AVERAGE PLANAR EXPOSURE for ATRIUM-9B Transient 3-2 Quad Cities Unit 1 Cycle 17A July 2002

4.0 MINIMUM CRITICAL POWER RATIO (MCPR) 4.1 TECHNICAL SPECIFICATION

REFERENCE:

TS 2.1.1.2, TS 3.2.2 and TS 3.4.1

4.2 DESCRIPTION

The following conditions are accounted for in the MCPR Operating Limits:

50% of the LPRMs out of service 40% of the TIPs out of service 2500 EFPH LPRM calibration interval No reused channels 15 psi reduction in steam dome pressure Technical Specification SCRAM speeds Increased Core Flow (ICF)

Relief Valve out-of-service (RVOOS)

The Operating Limit MCPR shall be determined as follows:

1. During steady-state operation at rated core flow, the Operating Limit MCPR shall be greater than or equal to the limits provided in Table 4-1 for the appropriate operating conditions.
2. During off-rated flow conditions in Manual Flow Control Mode, the Operating Limit MCPR for each fuel type at a specific core flow condition shall be determined from the greater of the following:
a. Table 4-2 using the appropriate flow rate and operating conditions, or
b. Table 4-1 using the appropriate operating condition.

PercentRated Core Flow based on 98 MLB/hr with 110% Maximum Flow in Manual Flow Control.

(Technical Requirements Manual 2.1.a.1 and Bases of TS 3.2.2)

3. During off-rated flow conditions in Automatic Flow Control Mode, the Operating Limit MCPR for each fuel type at a specific core flow condition shall be determined from Table 4-3, Table 4-4, or Table 4-5 using the appropriate operating conditions. PercentRated Core Flow based on 98 MLB/hr with 108% Maximum Flow in Automatic Flow Control Operation(Technical Requirements Manual 2.l.a.1 and Bases of TS 3.2.2).
4. During PLU Out of Service Conditions a 0.980 MFLCPR Administrative Limit shall be used.

4-1 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 4-1 Q1C17A Base Operating Limit MCPRs Cycle Exposures Cycle Exposures

< 4000 MWD/MT >= 4000 MWD/MT*

GEl0 ATRIUM-9B GE 10 ATRIUM-9B OLMCPR OLMCPR OLMCPR OLMCPR Normal Operation - Dual Loop 1.51 1.47 1.50 1.50 Single Loop Operation 1.52 1.48 1.51 1.51 EOD/EOOS Operation - Dual Loop 1.55 1.51 1.56 1.51 (FHOOS/FFrR and/or coastdown)

EOD/EOOS Operation - Single Loop 1.56 1.52 1.57 1.52 (FHOOS/FFrR and/or coastdown) 1 Bypass Valve OOS- Dual Loop 1.51 1.47 1.50 1.50 1 Bypass Valve OOS -Single Loop 1.52 1.48 1.51 1.51 All Bypass Valves OOS - Dual Loop 1.56 1.52 1.50 1.50 All Bypass Valves OOS - Single Loop 1.57 1.53 1.51 1.51 TABLE 4-2a QIC17A Operating Limit MCPRs for Manual Flow Control - Dual Loop Operation Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 110 1.11 1.11 1.15 1.15 30 2.00 2.05 2.07 2.12 0 2.56 2.59 2.64 2.67 TABLE 4-2b Q1C17A Operating Limit MCPRs for Manual Flow Control - Single Loop Operation Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 110 1.12 1.12 1.16 1.16 30 2.01 2.06 2.08 2.13 0 2.57 2.60 2.65 2.68

  • Based on Framatome methodology, these limits can be applied at all cycle 17A exposures (this includes exposures prior to 4000 MWD/MT).

4-2 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 4-3a Q1C17A Operating Limit MCPRs for Automatic Flow Control - Dual Loop Operation (Normal Operation or 1 Bypass Valve OOS)

Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.51 1.47 1.50 1.50 30 2.83 2.82 2.81 2.88 0 3.73 3.68 3.71 3.76 TABLE 4-3b Q1C17A Operating Limit MCPRs for Automatic Flow Control - Single Loop Operation (Normal Operation or 1 Bypass Valve OOS)

Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.52 1.48 1.51 1.51 30 2.84 2.83 2.82 2.89 0 3.74 3.69 3.72 3.77 TABLE 4-4a Q1C17A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS - Dual Loop Operation Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.55 1.51 1.56 1.51 30 2.90 2.90 2.92 2.90 0 3.82 3.79 3.85 3.79 TABLE 4-4b Q1C17A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS - Single Loop Operation Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.56 1.52 1.57 1.52 30 2.91 2.91 2.93 2.91 0 3.83 3.80 3.86 3.80

  • Based on Framatome methodology, these limits can be applied at all cycle 17A exposures (this includes exposures prior to 4000 MWD/MT).

4-3 Quad Cities Unit 1 Cycle 17A July 2002

TABLE 4-5a Q1C17A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves OOS - Dual Loop Operation Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.56 1.52 1.50 1.50 2.92 2.92 2.81 2.88 30 3.85 3.81 3.71 3.76 0

TABLE 4-5b Loop Operation QIC17A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves OOS - Single Cycle Exposures < 4000 MWD/MT Cycle Exposures >= 4000 MWD/MT*

Total Core Flow GEl0 ATRIUM-9B GEl0 ATRIUM-9B

(% of Rated) OLMCPR OLMCPR OLMCPR OLMCPR 108 1.57 1.53 1.51 1.51 30 2.93 2.93 2.82 2.89 0 3.86 3.82 3.72 3.77

  • Based on Framatome methodology, these limits can be applied at all cycle 17A exposures (this includes exposures prior to 4000 MWD/MT).

4-4 Quad Cities Unit 1 Cycle 17A July 2002

5.0 ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

June 2000.

1. NEDE-24011-P-A-14, "General Electric Standard Application for Reactor Fuel,"

Methods," Revision 0, November

2. Commonwealth Edison Topical Report NFSR-0085, "Benchmark of BWR Nuclear Design 1990.

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