SVP-03-063, Transmittal of 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report for Quad Cities Nuclear Power Station, Units 1 & 2

Transmittal of 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report for Quad Cities Nuclear Power Station, Units 1 & 2

ML031410086
Person / Time
Site:	Quad Cities
Issue date:	05/08/2003
From:	Tulon T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-03-063
Download: ML031410086 (4)

Text

/ Exekan Exelon Generation Company, LLC www.extXnQ0l.com Nuclear Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, IL 61242-9740 May 8, 2003 SVP-03-063 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Transmittal of 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light water nuclear power reactors," Annual Report for Quad Cities Nuclear Power Station, Units 1 and 2

Reference:

Letter from T. J. Tulon (Exelon Generation Company, LLC) to U. S. NRC, "Transmittal of 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, Annual Report for Quad Cities Units 1 and 2," dated May 9, 2002 The purpose of this letter is to provide the annual report required by 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," for Quad Cities Nuclear Power Station, Units 1 and 2.

The attachments describe the changes in accumulated Peak Cladding Temperature (PCT) since the previous annual submittal (Reference).

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

Respectfully, Ti hy J. Tulon Si e Vice President Quad Cities Nuclear Power Station Attachments:

Attachment A: Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report Attachment B: Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report Attachment C: Quad Cities Nuclear Power Station Units 1 and 2,10 CFR 50.46 Report Assessment Notes cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 1o0

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Attachment A Quad Cities Nuclear Power Station Unit 1 10 CFR 50.46 Report PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 5/08/03 CURRENT OPERATING CYCLE: 18 ANALYSIS OF RECORD Evaluation Model:

The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Methodology, NEDE-23785-1 -PA, General Electric Company, Revision 1, October 1984.

Calculations:

"SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2," NEDC-32990P, Revision 1, GE Nuclear Energy, September 2001.

Fuel Analyzed in Calculation: GE9/10, ATRIUM-9B and GE14 Limiting Fuel Type: GE14 Limiting Single Failure: Diesel Generator Limiting Break Size and Location: 1.0 Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT) PCT = 2110°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated December 6, 2002 (2) l APCT = 0F Net PCT 1 2110 OFl B. CURRENT LOCA MODEL ASSESSMENTS None APCT = 0F Total PCT change from current assessments -APCT = 0°F Cumulative PCT change from current assessments E I APCT I = F Net PCT 2110 OF

Attachment B Quad Citi@ Nuclear Power Station Unit 2 10 CFR 50.46 Report PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 5/08/03 CURRENT OPERATING CYCLE: 17 ANALYSIS OF RECORD Evaluation Model:

The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume Ill, SAFER/GESTR Application Methodology, NEDE-23785-1 -PA, General Electric Company, Revision 1, October 1984.

Calculations:

"SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2," NEDC-32990P, Revision 1, GE Nuclear Energy, September 2001.

Fuel Analyzed in Calculation: GE9/10, ATRIUM-9B and GE14 Limiting Fuel Type: GE14 Limiting Single Failure: Diesel Generator Limiting Break Size and Location: 1.0 Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT) PCT=2110°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated March 28, 2002 APCT = 0F 10 CFR 50.46 Report dated May 9, 2002 APCT = 0F Net PCT 2110°F B. CURRENT LOCA MODEL ASSESSMENTS WEVOL Si Volume Error (1) APCT = 0F Change in DG start time requirement (3) APCT =0°F Total PCT change from current assessments ZAPCT = 0°F Cumulative PCT change from current assessments E IAPCT I = 0°F Net PCT 2110°F

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Attachment C Quad Cities Nuclear Power Station Units 1 and 2 10 CFR 50.46 Report Assessment Notes

1. Current LOCA Assessment for GE Fuel GE reported that an error was found in the WEVOL code, which affects the calculated vessel volume in the downcomer region. The free volume in the region of the shroud head is calculated incorrectly. The code did not properly account for the volume of the standpipes inside the shroud head thickness.

This resulted in the value for the free volume in the downcomer being too small by 4-10 ft3. GE determined that the PCT impact of this error to be negligible.

[

Reference:

10 CFR 50.46 Notification Letter, 2002-05, August 26, 2002.]

2. Prior LOCA Assessment A new LOCA analysis was performed to support Extended Power Uprate (EPU) and transition to GE14 fuel for Quad Cities Unit 1. In the referenced letter, the impact of Core Spray (CS) and Low Pressure Coolant Injection (LPCI) leakage, GE LOCA error and change in Diesel Generator (DG) start time requirement were reported. There is no current assessment penalty.

[

Reference:

Letter from Timothy J. Tulon (Exelon) to U.S. NRC, "10 CFR 50.46, 30-Day Report for Quad Cities Nuclear Power Station, Unit 1," SVP-02-104, dated December 6, 2002.]

3. Current LOCA Assessment for GE Fuel The emergency DG start time was changed from a 10 second requirement in ITS to 13 seconds. The LOCA analysis sequence of events was examined and determined that the results and thus PCT were not affected by this change in DG start time. The change was submitted to the NRC with the TS amendment for this change approved on July 17, 2002.

[

Reference:

Quad Cities LOCA Diesel Generator and ECCS Sequencing, Calculation No. QDC-6600-N-1218, February 5,2002.]