PWRRM November 2011

pwrrm@retaqs.com

6 participants
3 discussions

fuel inspection
by ddgoff＠aep.com 02 Dec '11

02 Dec '11

DC Cook Reactor Engineering is looking at possible extraneous work to remove from the refueling outages. Cook is a PWR which performs a fuel core offload and reload. Currently our Quality Control department performs a 4-sided camera inspection of the assemblies as they leave containment on unload and as they enter containment on reload. We are looking at reducing the inspections to occur only on unload, eliminating the reload inspection. My Questions: What organization at your plant performs the fuel inspections? Do you perform the inspection on Unload? Do you perform the inspection on Reload? What method do you use to perform the inspection, 4 cameras, 1 camera, binoculars, eyeball, etc.? thanks Glen M Bradham, 269-465-5901 X1538 gmbradham(a)aep.com

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Reactivity Management Oversight
by WILLETT, JOSEPH E 28 Nov '11

28 Nov '11

I was asked to do a little electronic benchmarking related to your Reactivity Management Oversight Committee meetings. 1) How frequently do you meet; (What is required? Monthly? Quarterly? Semi-Annually? 2) What level of your organization is the meeting focused? Working level (Supervisors)? Middle Management (Department Heads/ Managers)? Senior Management (Division/Director)? 3) What is the required attendance? Is there a quorum? 4) What functional areas are required / represented? Operations, Engineering (Systems, Design, Programs, Reactor), Work Management, Maintenance, RP, Chemistry, Licensing? 5) What agenda items are required? Performance Indicator(s)? Corrective Action Program? Deficient Equipment? 6) Are there any specific goals for the committee? Performance improvement targets; 7) Are any of Reactivity Management goals forward looking? J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)oppd.com<mailto:jwillett@oppd.com> Omaha Public Power District Phone: (402) 533-7213 Fort Calhoun Station Pager: (402) 561-3899 9610 Power Lane FAX: (402) 533-6747 Blair, NE 68008 Mail Station: FC-1-1 Plant ---------------------------------------------------- -------- ---------------------------------------------------------------------- This e-mail contains Omaha Public Power District's confidential and proprietary information and is for use only by the intended recipient. Unless explicitly stated otherwise, this e-mail is not a contract offer, amendment, or acceptance. If you are not the intended recipient you are notified that disclosing, copying, distributing or taking any action in reliance on the contents of this information is strictly prohibited.

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Re: [Pwrrm] Feedback on quantifying SNM due to leaking fuel rod
by edward.mcvey＠exeloncorp.com 08 Nov '11

08 Nov '11

A survey from TVA. Please be sure and respond directly to Kathleen Cunningham (kacunningham(a)tva.gov). Thanks. Ed McVey ________________________________ From: Cunningham, Kathleen Anne [mailto:kacunningham@tva.gov] Sent: Tuesday, November 08, 2011 9:47 AM To: McVey, Edward A.:(GenCo-Nuc) Cc: Keck, James M; Faulkner, Craig S; Kniedler, Gregory S; Barnes, Steven A Subject: Feedback on quantifying SNM due to leaking fuel rod Hi Ed - hope you are doing well. I noticed your name as the RCRC Chairman so I was wondering if you could forward on the following request for feedback from the other BWROG members. We have a step in our corporate TVA procedure on Special Nuclear Material that requires us to quantify the amount of fuel rod pellets/fragments if fuel washout has occurred from a leaking fuel rod. We have been introduced to handbooks from Advanced Nuclear Technology who have developed PWRFUELRELEASE 1.0 and BWRFUELRELEASE 2.0, computer models to assess the amount of fissile materials and tramp uranium on core surfaces. This in turn would help us quantify the amount of SNM "displaced" from the fuel rods. We are looking to incorporate these methodologies in our procedure but I was wondering if any other utilities have done this already and if so, would be willing to share their thoughts and possibly their implementation procedures. Also, if they do not quantify the amount of SNM from a leaking fuel rod, please provide thoughts/justification for not providing this info per SNM reporting requirements. Thank you! Kathleen Cunningham Program Manager, Fuel Program Oversight and Fuel Inventory NPG, Nuclear Fuel Engineering kacunningham(a)tva.gov LP4G-C 423.751.3094 w 423.486.5911 m ----------------------------------------- ************************************************** This e-mail and any of its attachments may contain Exelon Corporation proprietary information, which is privileged, confidential, or subject to copyright belonging to the Exelon Corporation family of Companies. This e-mail is intended solely for the use of the individual or entity to which it is addressed. If you are not the intended recipient of this e-mail, you are hereby notified that any dissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is strictly prohibited and may be unlawful. If you have received this e-mail in error, please notify the sender immediately and permanently delete the original and any copy of this e-mail and any printout. Thank You. **************************************************

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PWRRM November 2011