ML021710108

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

ML021710108
Person / Time
Site:	LaSalle
Issue date:	06/08/2002
From:	Schiavoni M Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021710108 (8)

Text

Exelkn .

Exelon Generation Company, LLC www.exeloncorp.com Nuclear LaSalle County Station 2601 North 21"Road Marseilles, IL61341-9757 June 8, 2002 10 CFR 50.46 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

Reference:

(1) Letter from M. A. Schiavoni (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 8, 2001.

In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," Exelon Generation Company (EGC), LLC, submits the enclosed attachments to fulfill the annual reporting requirement for LaSalle County Station, Unit 1 and Unit 2. The previously calculated Peak Cladding Temperature (PCT) of 1301 degrees Fahrenheit (°F) for General Electric (GE) fuel and 1825 0 F for Framatome-ANP (FANP) fuel was reported in Reference 1. The PCT for GE fuel remains unchanged in this report, while the PCT for FANP fuel increased by 2°F to a value of 1827°F.

Both units employ a mixed core design containing co-resident GE and SPC fuel. The Loss of Coolant Accident (LOCA) analyses of record for both GE and SPC fuel are within all of the acceptance criteria set forth in 10 CFR 50.46.

Attachments 1 and 2 provide PCT information for the limiting LOCA evaluations for LaSalle County Station, Unit 1 and Unit 2, including all assessments as of June 12, 2001. The assessment notes are contained in Attachment 3 and provide a detailed description for each change or error reported.

June 8, 2002 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. Glen Kaegi, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Mark A. Schiavoni Plant Manager LaSalle County Station Attachments cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station

Attachment I LaSalle Units I and 2 10 CFR 50.46 Report (GE Fuel)

PLANT NAME: LaSalle Units 1 and 2 ECCS EVALUATION MODEL: SAFER/GESTR LOCA REPORT REVISION DATE: June 8, 2002 CURRENT OPERATING CYCLES: L1C10 and L2C9 ANALYSIS OF RECORD Evaluation Model Methodology: "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident," Volumes 1,11 and Ill, NEDE-23785-1-P-A, dated February 1985.

Calculation: "Project Task Report, LaSalle County Station, Power Uprate Evaluation, Task 407: ECCS Performance," GE report number GE-NE-Al 300384-39-01, Revision 1, dated September 1999.

Fuel: GE8x8NB (GE9)

Limiting Single Failure: HPCS Diesel Generator Limiting Break Size and 1.0 Double Ended Guillotine of Recirculation Pump Location: Suction Piping Reference PCT: 1301°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated June 12, 2000 (see Note 1) APCT = 0 OF 10 CFR 50.46 Report dated June 8, 2001 (see Note 2) APCT = 0 OF Net PCT 1301 OF B. CURRENT LOCA MODEL ASSESSMENTS None APCT = 0 OF Total PCT Change from Current Assessments ZAPCT = 0 OF Cumulative PCT Change from Current Assessments Z IAPCT I= 0 OF Net PCT 1301 °F

Attachment 2 LaSalle Units I and 2 10 CFR 50.46 Report (FANP Fuel)

PLANT NAME: LaSalle Units 1 and 2 ECCS EVALUATION MODEL: EXEM BWR Evaluation Model REPORT REVISION DATE: June 8, 2002 CURRENT OPERATING CYCLE: LIC10 and L2C9 ANALYSIS OF RECORD Evaluation Model Methodology: Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, ANF-91-048(P)(A), January 1993.

BWR Jet Pump Model Revision for RELAX, ANF-91 048(P)(A), Supplement 1 and Supplement 2, Siemens Power Corporation, October 1997.

Calculation: 1. LaSalle LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM TM-9B Fuel, EMF-2175(P), March 1999.

2. LOCA Break Spectrum Analysis for LaSalle Units 1 and 2, EMF-2174(P), March 1999.

3. LaSalle Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM TM-1 0 Fuel, EMF 2641(P), November 2001.

4. LaSalle Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM TM -10 Fuel, EMF-2639(P),

November 2001.

Fuel: ATRIUM TM-9B and ATRIUM TM-10 Limiting Fuel ATRIUM TM-9B Limiting Single Failure: HPCS Diesel Generator Limiting Break Size and 1.1 ft2 Recirculation Pump Discharge Side Line Break Location:

Reference PCT: 1807 OF MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated May 7, 1999 (See Note 3) APCT = 0 0F 10 CFR 50.46 report dated February 20, 2000 (See Note 4) APCT =18 *F 10 CFR 50.46 report dated June 12, 2000 (See Note 5) APCT = 0 *F 10 CFR 50.46 report dated June 8, 2001 (See Note 6) APCT = 0 0F Net PCT 1825 OF

Attachment 2 LaSalle Units I and 2 10 CFR 50.46 Report (FANP Fuel)

B. CURRENT LOCA MODEL ASSESSMENTS Incorrect pellet dish volume terms in RDX2LSE fuel swelling APCT = 0 °F calculation (see Note 7)

Reconciliation of RODEX2-2A numerical iteration scheme (see Note APCT = 1 OF 8)

Incorrect HUXY gadolinia conductivity model (see Note 9) APCT = -3 °F Incorrect calculation start time for the BULGEX code (see Note 10) APCT = 0 °F Incorrect constant used in the rupture temperature calculation (see APCT = 1 °F Note 11)

Incorrect Zircaloy heat of reaction (see Note 12) APCT = 3 °F Unit 1 Cycle 10 reload fuel (see Note 13) APCT = 0 °F ATRIUM-9B Exposure Extension (See Note 14) APCT = 0 °F Total PCT Change from Current Assessments ZAPCT = 2 OF Cumulative PCT Change from Current Assessments Y IAPCT = 8 OF Net PCT 1827 °F

Attachment 3 LaSalle Units 1 and 2 10 CFR 50.46 Report Assessment Notes

1. Prior LOCA model assessment for GE fuel The reference letter reported a new analysis of record for GE fuel as a result of the mid-cycle power uprate to 3489 MWt during Unit 1 Cycle 9 and Unit 2 Cycle 8.

[

Reference:

Letter from C. G. Pardee (CoinEd) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 12, 2000.]

2. Prior LOCA model assessment for GE fuel The reference letter assessed impact of Unit 2 LPCS riser leakage and errors in GE LOCA analysis model.

[

Reference:

Letter from M. A Schiavoni (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 8, 2001.]

3. Prior LOCA Model Assessment for FANP fuel The May 1999 LOCA model assessment was a new analysis of record for Framatome (Formerly Siemens) due to the introduction of ATRIUM-9B fuel into the Unit 2 Cycle 8 core. Therefore, there is no PCT change. Analysis was performed for a core power of 3722 MWt that bounds the current uprated power of 3489 MWt.

[

Reference:

Letter from J. A. Benjamin (ComEd) to U.S. NRC, "Report of Significant Change in Calculated Peak Cladding Temperature (PCT) - 10CFR 50.46 Report,"

dated May 7,1999.]

4. Prior LOCA Model Assessment for FANP fuel The February 2000 50.46 report assessed the impact of errors in the LOCA evaluation model.

[

Reference:

Letter from J. A. Benjamin (ComEd) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10CFR 50.46 Report," dated February 9, 2000.]

5. Prior LOCA Model Assessment for FANP fuel The June 2000 10 CFR 50.46 report does not have any PCT assessment for ATRIUM-9B fuel.

[

Reference:

Letter from C. G. Pardee (ComEd) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 12, 2000.]

6. Prior LOCA model assessment for FANP fuel The reference letter assessed impact of Unit 2 LPCS riser leakage, errors in FANP LOCA analysis model and Unit 2 Cycle 9 reload fuel.

[

Reference:

Letter from M. A Schiavoni (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 8, 2001.]

Attachment 3 LaSalle Units I and 2 10 CFR 50.46 Report Assessment Notes

7. Incorrect pellet dish volume terms in RDX2LSE fuel swelling calculation The equation used in RDX2LSE to calculate the dish volume for swelling accommodation has an error resulting in the underestimation of the dish volume. The underestimation could affect predicted temperatures and gap conductances at moderate to high burnups.

[

References:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156," DEG:01:108, dated July 17, 2001.

Letter from D. Garber (Siemens) to R. J. Chin (CornEd), "Transmittal of Condition Report 8266 and Associated Part 21 Evaluation Report," DEG:00:029, dated January 27, 2000.

8. Reconciliation of RODEX2-2A numerical iteration scheme FANP created a new RODEX2-2A code by merging the RODEX2-2A code for rod mechanical design analyses and the RDX2LSE code for safety analyses. The previous codes used the same NRC approved models and they are equivalent but contained some differences in iteration schemes. The new code has reconciled the differences in iteration schemes.

[

Reference:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156,"

DEG:01:108, dated July 17, 2001.

9. Incorrect HUXY gadolinia conductivity model In 1998, Framatome discovered that the NRC approved gadolinia model was not incorporated into the RDX2LSE code. Additional investigation for the condition report revealed that the HUXY code contained the same error.

[

References:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156," DEG:01:108, dated July 17, 2001.

Letter from D. Garber (Siemens) to R. J. Chin (ComEd), "Transmittal of Condition Report 6419 with Part 21 Evaluation Report," DEG:98:024, dated January 26, 1998.

10. Incorrect calculation start time for the BULGEX code During the evaluation of a new version of the HUXY code to correct a user message, it was discovered that the BULGEX subroutine needed to be initiated at a much earlier time.

Attachment 3 LaSalle Units I and 2 10 CFR 50.46 Report Assessment Notes

[

Reference:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156,"

DEG:01:108, dated July 17, 2001.

11. Incorrect constant used in the rupture temperature calculation The rupture temperature calculation over 950 °C in BULGEX incorrectly and non conservatively rounds a constant parameter term.

[

Reference:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156,"

DEG:01:108, dated July 17, 2001.

12. Incorrect Zircaloy heat of reaction The heat of reaction for zircaloy in the HUXY code is incorrect. The heat of reaction as a function of temperature does not account for the variation of the zircaloy heat capacity in the alpha-beta transformation temperature range.

[

References:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156," DEG:01:108, dated July 17, 2001.

Letter from D. Garber (Siemens) to R. J. Chin (CoinEd), "Transmittal of Condition Report 8168 R/1, with Part 21 Evaluation Report," DEG:99:349, dated December 22, 1999.

13. Unit 1 Cycle 10 reload fuel LOCA analysis for the new fuel type (ATRIUM-1 0) shows its PCT to be less than the PCT of the limiting fuel type (ATRIUM-9B). Therefore, the PCT change is reported as 0 OF.

[

Reference:

"LaSalle Unit 1 Cycle 10 Reload Analysis," EMF-2690, Revision 0, Framatome ANP, January 2002.]

14. ATRIUM-9B Exposure Extension LOCA analysis results show that the PCT for ATRIUM-9B fuel at the extended exposure of 64.3 GWd/MTU is non-limiting. Therefore, the PCT change is reported as 0 OF.

[

Reference:

Letter from D. Garber (FANP) to F. W. Trikur (Exelon), "ATRIUM-9B Exposure Extension MAPLHGR Analysis Results for LaSalle Units 1 and 2,"

DEG:02:024, January 22, 2002.]