ML110690028
| ML110690028 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 03/04/2011 |
| From: | Swift P Constellation Energy Group, EDF Group, Ginna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML110690028 (11) | |
Text
Paul Swift Manager, Nuclear Engineering Services R.E. Ginna Nuclear Power Plant, LLC CENG a joint venture of 1503 Lake Road Ontario, New York 14519-9364 585-771-5208 585-771-3392 Fax Const*iea Enww *tion 10% eDF Paul.Swift(fcenqllc.com March 4, 2011 U.S. Nuclear Regulatory Commission 11 Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
R.E. Ginna Nuclear Power Plant Docket No. 50-244 10 CFR 50.46 Annual ECCS Report
References:
(a) Westinghouse Letter LTR-LIS-1 1-56,
Subject:
10 CFR 50.46 Annual Notification and Reporting for 2010, dated January 24, 2011 In accordance with the requirements in 10 CFR 50.46 paragraph (a) (3) (ii), this annual Emergency Core Cooling System (ECCS) report is hereby submitted by R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC). Westinghouse, the provider of Loss of Coolant Accident (LOCA) analysis services for the R.E. Ginna Nuclear Power Plant, has provided an update to peak cladding temperature (PCT) margin in Reference (a).
Enclosed please find Attachment 1, "Westinghouse LOCA Evaluation Model Changes," which is the 2010 annual report of corrections to the R.E. Ginna Nuclear Power Plant ECCS Evaluation Models. This report summarizes changes made to both the large break LOCA (LBLOCA) and small break LOCA (SBLOCA) analyses. The "LBLOCA and SBLOCA Peak Clad Temperature Assessment Sheets" areenclosed as Attachment 2.
Should you have any questions regarding the information in this letter, please contact Mr.
Thomas Harding at (585) 771-5219.
Very truly yours, Paul Swift e09o Uy9Lk) C./O~
Document Control Desk March 4, 2011 Page 2 Attachments: (1) Westinghouse LOCA Evaluation Model Changes (2) LBLOCA and SBLOCA Peak Clad Temperature Assessment Sheets CC: W. M. Dean, NRC D.V. Pickett, NRC Resident Inspector, NRC (Ginna)
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes R.E. Ginna Nuclear Power Plant, LLC March 4, 2011
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes URANIA-GADOLINIA PELLET THERMAL CONDUCTIVITY CALCULATION (Non-Discretionary Change)
Background
Two errors were discovered in the pellet thermal conductivity calculation for urania-gadolinia pellets in the SBLOCTA code. First, the calculation did not include the terms required to adjust for pellet densities other than 95% of the theoretical density. Second, the conversion from Fahrenheit to Rankine used an adder of 459 instead of 459.67. These errors have been corrected and evaluated for impact on existing Small Break LOCA analysis results. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.
Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect SBLOCTA sensitivity calculations led to an estimated PCT effect of 0°F for existing Small Break LOCA analysis results.
I
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes PELLET CRACK AND DISH VOLUME CALCULATION (Non-Discretionary Change)
Background
Two errors were discovered in the calculation of the normalized pellet crack and dish volumes in the SBLOCTA code. First, an incorrect operator was used to select between two tables of normalized volume vs. linear heat generation rate. Second, the normalized volume at 18 kW/ft was incorrectly programmed in one of the tables as 1.58 instead of 1.59. These errors have been corrected in the SBLOCTA code and will be corrected (where applicable) in future versions of the BASH and LOCBART codes. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.
Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP 1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effect A combination of SBLOCTA sensitivity calculations and engineering judgment led to an estimated PCT effect of 0°F for existing Large and Small Break LOCA analysis results.
2
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes TREATMENT OF VESSEL AVERAGE TEMPERATURE UNCERTAINTY (Non-Discretionary Change)
Background
Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only "-" instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature. This uncertainty was then applied as a "+/-" uncertainty in some LOCA analyses, rather than using specific "+" and "-" uncertainties. This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results, and its resolution represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP 1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model 1999 Westinghouse Best Estimate Large Break LOCA Evaluation Model, Application to PWRs with Upper Plenum Injection 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect This issue was judged to have a negligible impact on existing Large and Small Break LOCA analysis results, leading to an estimated PCT impact of 00 F.
3
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes GENERAL CODE MAINTENANCE (Discretionary Change)
Background
Various changes have been made to enhance the usability of the codes and to help preclude errors in analyses. This includes items such as modifying input variable definitions, units, and defaults; improving the input diagnostic checks; enhancing the code output; optimizing active coding; and, eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-1 3451.
Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated PCT impact of 0°F.
4
ATTACHMENT (1)
Westinghouse LOCA Evaluation Model Changes TREATMENT OF INTERFACIAL DRAG MULTIPLIERS IN UPPER PLENUM INJECTION PLANTS (Non-Discretionary Change)
Background
For Upper Plenum Injection (UPI) plants, condensation and interfacial drag multipliers which affect the simulated draining of the upper plenum are modeled within WCOBRA/ITRAC. The interfacial drag multipliers are applied in the upper plenum and the Counter-Current Flow Limitation (CCFL) region of the vessel. For some licensing-basis analyses, these multipliers were not ranged as intended. This discrepancy has been evaluated for impact on existing licensing-basis analysis results, and its resolution represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
Affected Evaluation Model(s) 1999 Westinghouse Best Estimate Large Break LOCA Evaluation Model, Application to PWRs with Upper Plenum Injection 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect This issue was judged to have a negligible impact on existing Large Break LOCA analysis results, leading to an estimated PCT impact of 0°F.
5
ATTACHMENT (2)
LBLOCA and SBLOCA Peak Clad Temperature Assessment Sheets R.E. Ginna Nuclear Power Plant, LLC March 4, 2011
ATTACHMENT (2)
LBLOCA and SBLOCA Peak Clad Temperature Assessment Sheets Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: R. E. Ginna Utility Name: Constellation Generation Group Revision Date: 1/14/11 Analysis Information EM: ASTRUM (2004) Analysis Date: 3/18/05 Limiting Break Size: Split FQ: 2.6 FdH: 1.72 Fuel: 422 Vantage + SGTP (%): 10 Notes: Uprate to 1811 MWt (inclusive of calorimetric uncertainty) Effective beginning Cycle 33, Mixed Core OFA &422 V+
Clad Temp (OF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1870 I (a)
A. PRIOR ECCS MODEL ASSESSMENTS 1 . HOTSPOT Fuel Relocation Error 37 2 B. PLANNED PLANT MODIFICATION EVALUATIONS 1 . None 0 C. 2010 ECCS MODEL ASSESSMENTS 1 . None 0 D. OTHER*
1 . None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1907
- It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.
References:
1 . RGE-05-32, "Transmittal of Input to Boron Concentration Increase and LOCA Methodology Change Tech Spec Amendment Submittal," April 2005
- 2. LTR-LIS-07-388, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for R. E. Ginna," June 2007.
Notes:
(a) Transition cycles containing OFA fuel are bounded by the analysis for 422 V+ fuel.
I
ATTACHMENT (2)
LBLOCA and SBLOCA Peak Clad Temperature Assessment Sheets Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: R. E. Ginna Utility Name: Constellation Generation Group Revision Date: 1/14/11 Analysis Information EM: NOTRUMP Analysis Date: 4/21/05 Limiting Break Size: 2 inch, Hi Tavg FQ: 2.6 FdH: 1.72 Fuel: 422 Vantage + SGTP(%): 10 Notes: Uprate to 1811 MWt (inclusive of calorimetric uncertainty), Effective beginning Cycle 33, Mixed Core OFA & 422 V+
Clad Temp (OF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1167 1 (a)
A. PRIOR ECCS MODEL ASSESSMENTS 1, None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. None 0 C. 2010 ECCS MODEL ASSESSMENTS
- 1. None 0 D. OTHER*
- It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.
References:
1 . RGE-05-32, "Transmittal of Input to Boron Concentration Increase and LOCA Methodology Change Tech Spec Amendment Submittal," April 2005 Notes:
(a) Transition cycles containing OFA fuel are bounded by the analysis for 422 V+ fuel.
2