SVPLTR 06-0054, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

ML063200145
Person / Time
Site:	Dresden
Issue date:	11/09/2006
From:	Bost D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #06-0054
Download: ML063200145 (5)

Text

Exelon Genera tion Company, LLC ExekrnD Dresden Nuclear Power Station www.exelonICOTp.COMr Nuclear 65oo North Dresden Road Morris, IL 60450-9765 10 CFR 50.46(a)(3)(ii)

November 9, 2006 SVPLTR: #06-0054 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249

Subject:

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

Reference:

Letter from D. Bost (Exelon Generation Company, LLC) to U. S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated November 16, 2005 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Exelon Generation Company LLC, is submitting this letter and its attachment to meet the annual reporting requirements.

Dresden Nuclear Power Station (DNPS) has maintained the same emergency core cooling (ECCS) model as reported in the referenced letter. One vendor 10 CFR 50.46 LOCA model change/error notification was received since the last annual report. The vendor has implemented a change in performing analysis of small break LOCA cases, which requires considering both mid-peaked as well as top-peaked power shapes. The effect of this change was evaluated for DNPS LOCA analyses and it was determined that the impact on the licensing basis Peak Cladding Temperature (POT) is zero. The attachment provides the POT value for each unit and the "rack-up" sheets for the LOCA analyses, along with assessment note summaries.

If there are any questions concerning this letter, please contact Mr. James Ellis at (815) 416-2800.

Respectf ully, DannyB Site Vi e~ President Dresden Nuclear Power Station Attachmen t: Dresden Nuclear Power Station Units 2 and 3 - 10 CER 50.46 Report cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station 74 ow

Attachment Dresden Nuclear Power Station Units 2 and 3 1OC FR5O.46 Report PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL: SAFE R/G ESTR-LOCA REPORT REVISION DATE: 10/20/2006 CURRENT OPERATING CYCLE: 20 ANALYSIS OF RECORD Evaluation Model: The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume 111,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 2, GE Nuclear Energy, September 2003.

Fuel: 9x9-2, ATRIUM-9B3 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 = 21100'F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated December 6, 2001 (See Note 1) APCT = 00 F 10 CFR 50.46 report dated November 25, 2002 (See Note 2) APCT = 00 F 10 CFR 50.46 report dated November 25, 2003 (See Note 3) APCT = 00 F 10 CFR 50.46 report dated November 24, 2004 (See Note 4) APCT = 0OF 10 CFR 50.46 report dated November 16, 2005 (See Note 5) APCT = 00 F Net PCT 2110 OF B. CURRENT LOCA MODEL ASSESSMENTS GE Reload (Note 6) APCT = 00 F Additional Core Spray Line Leakage (Note 7) APCT = 00F Axial Power Shape Impact on Small Break LOCA (Note 8) APCT = 00F Total PCT change from current assessments Z-APCT =0 OF Cumulative PCT change from current assessments YZI APCT I 0-F Net PCT 2110 OF

Attachment Dresden Nuclear Power Station Units 2 and 3 10CFR5O.46 Report PLANT NAME: Dresden Nuclear Power Station, Unit 3 ECCS EVALUATION MODEL: SAFE R/G ESTR- LOCA REPORT REVISION DATE: 10/20/2006 CURRENT OPERATING CYCLE: 19 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 2, GE Nuclear Energy, September 2003.

Fuel: 9x9-2, ATRIUM-9B3 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 = 21100'F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated November 25, 2002 (See Note 2) APCT = 0F 10 CFR 50.46 report dated November 25, 2003 (See Note 3) APCT = 0F 10 CFR 50.46 report dated November 24, 2004 (See Note 4) APCT = 0F 10 CFR 50.46 report dated November 16, 2005 (See Note 5) APCT = 0F Net PCT 2110 OF B. CURRENT LOCA MODEL ASSESSMENTS Axial Power Shape Impact on Small Break LOCA (Note 8) APOT = 0 0 F Total PCT change from current assessments I ZAPCT = 00F Cumulative PCT change from current assessments Y_IAPCT I=OOF Net PCT 2110 OF

Attachment Dresden Nuclear Power Station Units 2 and 3 10CFR5O.46 Report Notes:

1. Prior LOCA Model Assessment The 50.46 letter dated December 6, 2001 reported a new LOCA analysis to support extended power uprate (EPU) and transition to GE14 fuel for Dresden Unit 2 Cycle

18. The same report assessed impact of errors in Framatome ANP LOCA analysis model for Dresden Unit 3 Cycle 17 at pre-EPU power level.

[

Reference:

Letter from Preston Swafford (PSLTR: #01 -0122) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," December 6, 2001.]

2. Prior LOCA Model Assessment Unit 3 implemented GE LOCA analysis and GE14 fuel with Dresden Unit 3 Cycle 18 startup on October 25, 2002. Therefore, both Dresden Units 2 and 3 are being maintained under the same LOCA analysis. In the referenced letter, the impact of GE LOCA error in the WEVOL code was reported for Dresden Units 2 and 3 and determined to be negligible.

[

Reference:

Letter from Robert J. Hovey (RHLTR: #02-0083) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 25, 2002.]

3. Prior LOCA Model Assessment The annual 50.46 report provided information on the LOCA model assessments for SAFER LevelNolume table error and Steam Separator pressure drop error. In the referenced letter, the impact of these two GE LOCA errors were reported to be negligible.

[

Reference:

Letter from Robert J. Hovey (RHLTR: #03-0077) (Exelon) to USNRC, "Plant Specific ECOS Evaluation Changes - 10 CFR 50.46, Report," November 25, 2003.]

4. Prior LOCA Model Assessment The referenced annual 50.46 report provided information on reload of GE14 fuel for Dresden Unit 2 Cycle 19 and impact of postulated hydrogen-oxygen recombination on PCT. GE determined that there is no PCT impact because of the change due to the new reload of GE14 fuel and the postulated hydrogen -oxygen recombination.

[

Reference:

Letter from Danny Bost (SVPLTR: #04-0075) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 24, 2004.]

5. Previous LOCA Model Assessment The referenced letter provided the annual 50.46 report for Units 2 and 3. The letter reported the PCT impact of reload of GE1 4 fuel for D3C1 9 starting on December 8,

Attachment Dresden Nuclear Power Station Units 2 and 3 10CFR5O.46 Report 2004. Also, the letter reported the GE LOCA evaluation for Unit 3, which implemented the lower sectional replacement and T-box clamp repairs. GE determined that there is no POT impact because of the change due to the new reload of GE1 4 fuel and the lower sectional replacement and T-box clamp repairs.

[

Reference:

Letter from Danny Bost (SVPLTR: #05-0044) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 16, 2005.]

6. Current LOCA Model Assessment Dresden Unit 2 Cycle 20 started on November 20, 2005 with a reload of GE14 fuel.

The impact of this reload was evaluated by GE and reported to be negligible. With this reload, Unit 2 core consists of all GE14 fuel type. GE determined that there is no PCT impact because of the change due to the new reload of GE14 fuel.

[

Reference:

"Supplemental Reload Licensing Report for Dresden 2 Reload 19 Cycle 20," 0000-0035-6363-SRLR, Revision 1, October 2005.]

7. Current LOCA Model Assessment During D2R19 outage, an increased leakage of less than 5 gpm at runout condition in core spray line flow due to crack growth was evaluated by GE for impact on the LOCA analysis. The analytical limit for the Core Spray flow increased by 50 gpm that offsets the increase in the leakage. The Dresden Unit 2 LOCA analysis continues to meet the 10 CFR 50.46 acceptance criteria.

[

Reference:

"Effect on Increased Leakage and CS Flow on Dresden 2 LOCA, GE-NE-0000-0047-9777-RO, 11/17/05 (transmitted via letter GE-EB2JXFGG-002, dated 11/18/05).]

8. Current LOCA Model Assessment Past GE small break analysis assumed a mid-peaked power shape consistent with the GE methodology. Recently, GE has determined that for small break cases, a top-peaked power shape can result in higher calculated PCT than a mid-peaked shape. GE has implemented a change in performing analysis of small break LOCA cases, which requires considering both mid-peaked as well as top-peaked power shapes. GE has evaluated effect of this change for Dresden LOCA analysis and determined the impact on the licensing basis PCT is zero. This is because the limiting POT is based on the DBA large break and the revised small break POT remains below the limiting large break. Therefore, the impact on the limiting large break POT and as a result licensing basis POT is reported as zero.

[

Reference:

Exelon Dresden Station (Unit 2 & 3), "10 CFR5O.46 Notification Letter 2006-1, July 28, 2006.]