SVP-02-008, Core Operating Limits Report for Cycle 17A

Core Operating Limits Report for Cycle 17A

ML020500315
Person / Time
Site:	Quad Cities
Issue date:	02/01/2002
From:	Tulon T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-02-008
Download: ML020500315 (20)

Text

Exelkn.

Exelon Generation www.exeloncorp.com Nuclear Quad Cities Generating Station 22710 206th Avenue North Cordova, IL61242-9740 Tel 309-654-2241 February 01, 2002 SVP-02-008 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 In accordance with Technical Specifications Section 5.6.5.d, enclosed is the Core Operating Limits Report (COLR) for Quad Cities Unit 1 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. The enclosed COLR is applicable until the first sequence exchange of Cycle 17A or 4140 MWD/MT cycle exposure, whichever occurs first in the cycle.

Analyses for the remainder of Cycle 17A are in progress and any necessary revision to the enclosed COLR will be 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, lothy J. Tulon Site Vice President 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

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

Core Operating Limits Report For Quad Cities Unit 1 Cycle 17A January 2002 i

Quad Cities Unit I Cycle 17A January 2002

ISSUANCE OF CHANGES

SUMMARY

Affected Summary of Changes Date Affected Section Pages I All Original Issue (Cycle 17A) 1/02 All i

Quad Cities Unit I Cycle 17A January 2002

TABLE OF CONTENTS SPECIAL INSTRUCTIONS ........................................................................... nti R EFEREN C ES ......................................................................................... iv LIST OF TABLES .................................................................................... v 1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION ................ -1 1.1 TECHNICAL SPECIFICATION REFERENCE ............................... 1-1

1.2 DESCRIPTION

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

1.3 DESCRIPTION

(SLO) ............................................................. 1-1 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........ 2-i 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-I 5.0 ANALYTICAL METHODS ................................................................. 5-1 Quad Cities Unit I Cycle 17A January 2002

SPECIAL INSTRUCTIONS

1. 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.

2. This COLR and all limits contained within are applicable until the first sequence exchange of Cycle 17A. Additional analyses by Framatome-ANP are required prior to Cycle 17A operation beyond the first sequence exchange of the cycle or 4140 MWD/MTU cycle exposure, whichever occurs first in the cycle.

iii Quad Cities Unit I Cycle 17A January 2002

REFERENCES I. 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 1 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 I11,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. J l 1-03692-LHGR, Revision 1, Class 3, February 2000, "ComEd GE9/GEI0 LHGR Improvement Program", NDIT NFMO000067, 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.

iv Quad Cities Unit I Cycle 17A January 2002

LIST OF TABLES Table Title Page 2-2 2-1 MAPLHGR vs. Average Planar Exposure for GE0O-P8HXB311-8GZ-IOOM-145 CECO 2-3 2-2 MAPLHGR vs. Average Planar Exposure for GEIO-P8HXB3I2-7GZ-IOOM-145 CECO 2-4 2-3 MAPLHGR vs. Average Planar Exposure for GEI0-P8HXB332-8G5.0-100M 145-CECO 2-5 2-4 MAPLHGR vs. Average Planar Exposure for GEl0-P8HXB333-4G5.0/6G4.0 1OOM-145-CECO 2-6 2-5 MAPLHGR vs. Average Planar Exposure for SPCA9-3.48B- 11G6.5-ADV, SPCA9-3.60B- 11 G6.5-ADV, SPCA9-383B-1 IGZH-ADV and SPCA9-382B 12GZL-ADV 3-2 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 4-2 4-1 QI CI 7A Operating Limit MCPRs based on 1.11 SLMCPR 4-2 4-2 QICI7A Operating Limit MCPRs for Manual Flow Control 4-2 4-3 QICI7A Operating Limit MCPRs for Automatic Flow Control (Normal Operation or I Bypass Valve OOS) 4-2 4-4 QICI7A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS 4-2 4-5 QICI7A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves OOS v

Quad Cities Unit I Cycle 17A January 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).

I-I Quad Cities Unit I Cycle 17A January 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 GEI 0-P8HXB3 II-8GZ-1 OM-145-CECO is determined from Table 2-1.

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

Average Planar Exposure for GEI 0-P8HXB312-7GZ- IOOM- 145-CECO is determined from Table 2-2.

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

Average Planar Exposure for GEI 0-P8HXB332-8G5.0-I OOM- I45-CECO is determined from Table 2-3.

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

Average Planar Exposure for GE! 0-P8HXB333-4G5.0/6G4.0-10OM-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-l 1G6.5-ADV, SPCA9-3.60B-l IG6.5 ADV, SPCA9-383B-I GZH-ADV, and SPCA9-382B-I 2GZL-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 I Cycle 17A January 2002

TABLE 2-1 MAPLHGR vs. Average Planar Exposure for GE1O-P8HXB311-8GZ-IOOM-145-CECO LATTICE 1807: P8HXL071-8GE- I OOM-T LATTICE 1806: P8HXL335-8G3.0-1 OOM-T LATTICE 1805: P8HXL353-2G4.0/6G3.0-1 OOM-T LATTICE 1804: P8HXL335-4G4.0/4G3.0-I00M-T LATTICE 1054: P8HXL07 I-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 January 2002

TABLE 2-2 MAPLHGR vs. Average Planar Exposure for GEl 0-P8HXB312-7GZ-1OOM-145-CECO LATTICE 1811: P8HXL071-7GE-1 OOM-T LATTICE 1810: P8HXL336-7G3.0- I00M-T LATTICE 1809: P8HXL354-1G4.0/6G3.0-100M-T LATTICE 1808: P8HXL336-3G4.0/4G3.0-I00M-T LATTICE 1054: P8HXL071-NOG-I00M-T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR ... r loll EXPOSURE 1 SU9 1054 1810 1809 1808 ]oil (GWD/ST) 1 4 1204 4 11.27 t I.L.UI 1 I 1.0) ____

11.85 11.27 12.01 i I .0j 0.0 1*

1204-11 II ql 12_08 11.78 0.2 J i./O. / I .- .. . ..-

11.59 12.27 11.42 12.23 11.59 1.0 11.57 12.49 11.65 12.43 11.57 2.0 11.61 12.72 11.93 12.65 11.61 3.0 11.68 12.96 12.24 12.88 11.68 4.0 11.75 13.15 12.58 13.09 11.75 5.0 11.81 13.30 12.94 13.22 11.81 6.0 11.86 13.41 13.15 13.32 11.86 7.0 11.91 13.46 13.32 13.40 11.91 8.0 11.94 13.47 13.43 13.45 11.94 9.0 11.97 13.45 13.50 13.47 11.97 10.0 11.75 13.35 13.45 13.35 11.75 12.5 11.38 12.97 13.10 12.97 11.38 15.0 10.59 12.24 12.41 12.23 10.59 20.0 25.0 9.81 11.52 11.74 11.51 9.81 12.314 12.314 12.314 12.314 12.314 27.22 10.800 10.800 10.800 10.800 10.800 48.08 6.000 6.000 6.000 6.000 6.000 58.97 2-3 Quad Cities Unit I Cycle 17A January 2002

TABLE 2-3 MAPLHGR vs. Average Planar Exposure for GE10-P8HXB332-8G5.0-IOOM-145-CECO LATTICE 1054: P8HXL07 I-NOG- ! 00T-T LATTICE 2080: P8HXL358-8G5.0- I OOT-T LATTICE 2081: P8HXL377-8G5.0-I OOT-T LATTICE 2082: P8HXL071-8GE-100T-T AVERAGE MAPLHGR LIMITS (KW/FT)

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 I Cycle 17A January 2002

TABLE 2-4 MAPLHGR vs. Average Planar Exposure for GEl 0-P8HXB333-4G5.0/6G4.0-1OOM-145-CECO LATTICE 1054: P8HXL071-NOG-100T-T LATTICE 2077: P8HXL358-4G5.0/6G4.0-1OOT-T LATTICE 2078: PSHXL377-4G5.0/6G4.0- 100T-T LATTICE 2079: P8HXL071-10GE-100T-T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPOSURE 1054 2077 1 2078 1 2079 (GWD/ST) 1 4 11.22 t 11.85 0.0 11 R55 11.81 11.22 1 11.85 1.11..

0.2 11 82 7R 11.86 11.26 11.78 1159 11.3 11.8 78 11.36 11.59 1.0 11.95 5

711 5 11.9.551 2.0 11 19 11 il.52 11.57 Z'7 9 11.69 11.51 3.0 11 M1 19 9*; 11.69 11.61 11 &£ Al4 11.869.b 4.0 12 Aft 11.88 11.68 1956 12.088IL.

11 7' 19 *6 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 January 2002

TABLE 2-5 MAPLHGR vs. Average Planar Exposure for SPCA9-3.48B-1 1G6.5-ADV SPCA9-3.60B-1 1G6.5-ADV SPCA9-383B-I 1GZH-ADV and SPCA9-382B-12GZL-ADV AVERAGE PLANAR ATRIUM-9B MAPLHGR EXPOSURE (GWD/MTU) (KW/FT) 0.0 13.5 20.0 13.5 60.0 8.7 61.1 8.6 2-6 Quad Cities Unit I Cycle 17A January 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. Thermal limits provided in this section are only valid until the first sequence exchange of Cycle 17A or a cycle exposure of 4140 MWD/MTU, whichever occurs first. Additional analyses by Framatome-ANP are required prior to Cycle 17A operation beyond this point.

B. The LHGR limit for the GE fuel types in the QICI7A core are as follows:

GE 10-P8HXB311-8GZ-100 M-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 GEl0-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 GEl 0-P8HXB332-8G5.0-100M-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 GE I 0-P8HXB333-4G5.0/6G4.0-1OOM-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 I Cycle 17A January 2002

C. The LHGR limits are provided in Table 3-1 for all of the SPC fuel types (ATRIUM-9B Offset) in the Q1CI7A 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 I Cycle 17A January 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

Thermal limits provided in this section are only valid until the first sequence exchange of Cycle 17A or a cycle exposure of 4140 MWD/MTU, whichever occurs first. Additional analyses by Framatome-ANP are required prior to Cycle 17A operation beyond this point.

The MCPR Operating Limits are based on the dual loop MCPR Safety Limit of 1.11. For Single Loop Operation the MCPR Safety Limit is 1.12 which increases the MCPR Operating Limit by 0.01. The MCPR Safety Limit is based on the following equipment conditions:

50% of the LPRMs out of service 40% of the TIPs out of service 2500 EFPH LPRM calibration interval Single Loop Operation No reused channels The MCPR Operating Limits are based on a 15 psi reduction in steam dome pressure and Technical Specification SCRAM speeds.

The Operating Limit MCPR shall be determined as follows:

I. 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, or

b. Table 4-1 using the appropriate operating condition.

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

(Technical Requirements Manual 2.1.a.I 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. Percent Rated Core Flow based on 98 MLB/hr with 108% Maximum Flow in Automatic Flow Control Operation (Technical Requirements Manual 2. L.a. I 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 I Cycle 17A January 2002

TABLE 4-1 QIC17A Operating Limit MCPRs based on 1.11 SLMCPR GEI0 ATRIUM-9B OLMCPR OLMCPR Normal Operation 1.51 1.47 (Supports ICF and RVOOS)

EOD/EOOS Operation 1.55 1.51 (FHOOS)

I Bypass Valve OOS 1.51 1.47 (Supports ICF and RVOOS)

All Bypass Valves OOS 1.56 1.52 (Supports ICF and RVOOS)

TABLE 4-2 Q1CI7A Operating Limit MCPRs for Manual Flow Control Total Core Flow GEI0 OLMCPR ATRIUM-9B Offset

(% of Rated) OLMCPR 110 1.11 1.11 30 2.00 2.05 0 2.56 2.59 TABLE 4-3 QlCI7A Operating Limit MCPRs for Automatic Flow Control (Normal Operation or I Bypass Valve OOS)

Total Core Flow GE 0 OLMCPR ATRIUM-9B Offset

(% of Rated) OLMCPR 108 1.51 1.47 30 2.83 2.82 0 3.73 3.68 TABLE 4-4 QICI 7A Operating Limit MCPRs for Automatic Flow Control EOD/EOOS Total Core Flow GEl0 OLMCPR ATRIUM-9B Offset

(% of Rated) OLMCPR 108 1.55 1.51 30 2.90 2.90 0 3.82 3.79 TABLE 4-5 Q1CI7A Operating Limit MCPRs for Automatic Flow Control All Bypass Valves OOS Total Core Flow GEIO OLMCPR ATRIUM-9B Offset

(% of Rated) OLMCPR 108 1.56 1.52 30 2.92 2.92 0 3.85 3.81 4-2 Quad Cities Unit I Cycle 17A January 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:

2000.

1. NEDE-2401 I-P-A-14, "General Electric Standard Application for Reactor Fuel," June Methods." Revision 0. November

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

Design Methods - Quad

3. Commonwealth Edison Topical Report NFSR-0085, Supplement I, "Benchmark of BWR Nuclear Cities Gamma Scan Comparisons," Revision 0, April 1991.

Design Methods - Neutronic

4. Commonwealth Edison Topical Report NFSR-0085, Supplement 2, "Benchmark of BWR Nuclear Licensing Analyses," Revision 0, April 1991.

5. Advanced Nuclear Fuels Methodology for Boiling Water Reactors: Benchmark Results for CASMO-3G/MICROBURN-B 4,

Calculation Methodology, XN-NF-80-19 (P)(A), Volume I, Supplement 3, Supplement 3 Appendix F. and Supplement Advanced Nuclear Fuels Corporation, November 1990.

to BWR Reloads. XN-NF-80-19

6. Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology (P)(A), Volume 4, Revision 1, Exxon Nuclear Company, June 1986.

Summary Description, XN

7. Exxon Nuclear Methodology for Boiling Water Reactors THERMEX: Thermal Limits Methodology NF-80-19 (P)(A), Volume 3, Revision 2, Exxon Nuclear Company, January 1987.

XN-NF-80-19 (P)(A),

8. Exxon Nuclear Methodology for Boiling Water Reactors- Neutronic Methods for Design and Analysis, Volume I and Supplements I and 2, Exxon Nuclear Company, March 1983.

1, Exxon Nuclear

9. Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, XN-NF-85-67 (P)(A), Revision Company, September 1986.

of ENC 9x9 BWR

10. Qualification of Exxon Nuclear Fuel for Extended Bumup, Supplement I: Extended Bumup Qualification Fuel, XN-NF-82-06 (P)(A), Supplement I. Revision 2, Advanced Nuclear Fuels Corporation, May 1988.

9x9-1X and 9x9-9X 1I. Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation October (P)(A), Revision I, and Supplements I and 2. Advanced Nuclear Fuels Corporation, BWR Reload Fuel, ANF-89-014 1991.

I Supplement 1,

12. Generic Mechanical Design Criteria for BWR Fuel Designs, ANF-89-98 (P)(A), Revision I, and Revision Advanced Nuclear Fuels Corporation, May 1995.

2 Supplements 1.2

13. Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors, XN-NF-79-71 (P)(A), Revision and 3, Exxon Nuclear Company, March 1986.

April

14. ANFB Critical Power Correlation, ANF-1 125 (P)(A) and Supplements I and 2, Advanced Nuclear Fuels Corporation, 1990.

Fuels

15. Advanced Nuclear Fuels Corporation Critical Power Methodology For Boiling Water Reactors/Advanced Nuclear Channel Bowing Corporation Critical Power Methodology for Boiling Water Reactors: Methodology for Analysis of Assembly Nuclear Fuels Effects/NRC Correspondence, ANF-524 (P)(A), Revision 2, Supplement I Revision 2, Supplement 2, Advanced Corporation, November 1990.

Revision I and

16. COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analyses, ANF-913 (P)(A) Volume I Volume I Supplements 2, 3, and 4, Advanced Nuclear Fuels Corporation, August 1990.

ANF-91-048

17. Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, (P)(A), Advanced Nuclear Fuels Corporation, January 1993.

Methods,"

18. Commonwealth Edison Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design 0, Supplements I and 2, December 1991, March 1992, and May 1992, respectively; SER letter dated March 22. 1993.

Revision

19. ANFB Critical Power Correlation Application for Coresident Fuel, EMF-l 125 (P)(A), Supplement I, Appendix C, Siemens Power Corporation, August 1997.

125 (P)(A),

20. ANFB Critical Power Correlation Detemiination of ATRIUM-9B Additive Constant Uncertainties, ANF-l Supplement 1, Appendix E, Siemens Power Corporation, September 1998.

5-1 Quad Cities Unit 1 Cycle 17A January 2002