Beaver Valley Power Station responses
Note that BV utilizes Westinghouse to perform core design analysis, however our fleet core design group utilizes CASMO/SIMULATE as an independent check/monitor of the core design process. I have provided two answers to questin 1 related to the comparison to the Westinghouse ANC model and the FENOC CASMO/SIMULATE model. A contact for the FENOC core design group would be Mark Rupp - 330-384-2528.
Anthony (A.R.) Burger Supervisor, Reactor Engineering FENOC - Beaver Valley Power Station Phone: (724) 682-4108 Cell: (724) 601-3224 FAX: (724) 682-4250 Email: aburger@firstenergycorp.com
Adina.K.Lafrance@ dom.com Sent by: To pwrrm@retaqs.com pwrrm@retaqs.com cc
01/16/2009 07:51 Subject AM [Pwrrm] Reactivity anomaly calculation
Please respond to PWR Reactivity Management <pwrrm@retaqs.com >
1) Surry uses IFBA fuel. Core modeling is performed using the CASMO-4/SIMULATE-3 computer codes. In making comparisons between measured and predicted boron concentrations (corrected for B-10, power, xenon, rod position, and RCS temperature), we notice a tendency to for the core models to underpredict the measured critical boron between 2 and 4 GWD/MTU by 10-20 ppm (about 80-160 pcm) more than at other times in life (such as at BOC equilibrium xenon or between MOC and EOC). Have you observed this tendency at your plant? RESPONSE: a. Westinghouse ANC Model - We have not observed any unusual deviations in the 2-4 GWD/MTU portion compared to the rest of the cycle. b. FENOC CASMO/SIMULATE Model - This was provided from the core design group at FENOC - The answer to 1) is Yes, we also under predict the measured B10 by 12-25 ppm (BV1) for that exposure interval. A contact for this response is: Mark S. Rupp Staff Nuclear Engineer Core Design & Physics Support Nuclear Fuel Department 330-384-2528
2) For the monthly reactivity anomaly calculation, is a B-10 corrected value used to meet Tech Spec requirements, or is the non-corrected value used? (Surry uses the non-corrected value) RESPONSE: The corrected B-10 values is used for Tech Spec requirements.
3) Does your anomaly procedure have a threshold (such as +/-500 pcm) at which the anomaly would be documented in the corrective action system? RESPONSE: A Condition Report would be issued for deviations that exceed +/- 500 pcm based on our reactor trend program.
Adina LaFrance
It's a healthy thing now and then to hang a question mark on the things you have long taken for granted. -Betrand Russell
Nuclear Analysis & Fuel Reactor Engineer Surry Power Station Email: Adina.K.LaFrance@Dom.com Phone: 757-365-2658 Pager #: 4290
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