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?
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)
3) Does your anomaly procedure have a threshold (such as +/-500 pcm) at which the anomaly would be documented in the corrective action system?
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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From Oconee...
1. N/A for AREVA B11 or HTP fuel. 2. Non-corrected value. Though we use the B-10 sample results to assist in monitoring the anomaly. 3. Yes. Our procedure has a review criteria of ~350 pcm and an acceptance criteria of ~500 pcm (the procedure uses ppmB to measure the anomaly so that's why the "~"). We're expected to enter results not meeting review or acceptance criteria into our corrective action program. The CAP response would be commensurate with the failure (trending, apparent cause, root cause, etc.)
Carl
Carl D. Fago Reactor Engineering Supervisor Oconee Nuclear Station Duke Energy Carolinas Phone: (864) 885-3047 Fax: (864) 885-3374 Email: cdfago@duke-energy.commailto:cdfago@duke-energy.com
________________________________ From: pwrrm@retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of Adina.K.Lafrance@dom.com Sent: Friday, January 16, 2009 7:51 AM To: pwrrm@retaqs.com Subject: [Pwrrm] Reactivity anomaly calculation
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?
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)
3) Does your anomaly procedure have a threshold (such as +/-500 pcm) at which the anomaly would be documented in the corrective action system?
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
CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and/or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.
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
CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and/or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you._______________________________________________ PWRRM mailing list PWRRM@retaqs.com http://www.keffective.com/mailman/listinfo/pwrrm
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aburger＠firstenergycorp.com -
Adina.K.Lafrance＠dom.com -
Fago, Carl D