Answers below
Barton P. Schawe, P.E. Principal Reactor Engineer Omaha Public Power District Tel: 402-533-7211 email: bschawe@oppd.commailto:bschawe@oppd.com
________________________________ From: pwrrm@retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of Charlene.N.Chotalal@dom.com Sent: Thursday, January 22, 2009 8:11 AM To: pwrrm@retaqs.com Subject: [Pwrrm] PWRRM Request for B-10 Information(in preparation for INPO)
Greetings,
INPO will be coming to Surry Power Station in a week and I would like to ask two questions to the group. In your response, you do not need to reply to everyone. I will be gathering the information and putting it into one excel file. If you would like a copy, please let me know.
1) This question has been asked already, but we did not get many responses. Core modeling is performed using the CASMO-4/SIMULATE-3 computer codes. Our most recent Reactivity Anomaly calculation(the comparison between measured and predicted boron concentrations) gave us an uncorrected value of about 750pcm. This is quite close to our tech spec limit of 1000pcm. If we corrected for B-10, the anomaly value would be closer to 300pcm. Currently we use the uncorrected value in our comparison to the predicted model. What is your typical maximum offset between your measured and predicted Reactivity Anomaly? Is this with or without B-10 depletion? Do you use your B-10 depletion value for the tech spec surveillance?
Response: FCS may be odd in that about 15 years ago, we developed a HFP and HZP K-Effective bias (i.e. k-effective versus burnup) that is used in our reload analysis and in the generation of our reactivity data in the plant data book. This bias is validated (or changed) each cycle. Therefore, our predicted data includes the effects of B-10 depletion. Our uncorrected measurement is then compared ot the predicted model. We are generally within 200 pcm for the Reactivity Anomaly.
2) This question is regarding Estimated critical conditions/position. What is the pcm delta typically observed at your plant between the predicted critical conditions and the actual conditions? If a delta is observed, does the predicted critical calculation account for B-10 depletion? At what point (i.e. >100 pcm delta) would Operations or Reactor Engineering write a condition report?
Response: We are generally within 200 pcm for an ECC. Our ECC process accounts for B-10 depletion. We would write a CR at > 300 pcm for trending, although not required until > 500 pcm.
Charlene Chotalal Lead Reactor Engineer Surry Power Station Work: (757)-365-2819
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