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120 discussions

MC&A Program Reports
by Fago, Carl D 17 Jun '08

17 Jun '08

I'm looking for examples of reports made to the NRC under 10CFR 70.32(c)(2) for changes in your MC&A program. What level of detail did you include? Also, did you make a report for any change in either your SNM inventory procedure or directive, no matter how minor? At Duke, the RxE Supervisors own the MC&A program so I'd thought I'd start with this esteemed crew. Thanks in advance! Carl Carl D. Fago Reactor Engineering Supervisor Oconee Nuclear Station Duke Energy 864-885-3047 cdfago(a)duke-energy.com

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Re: [Respvr] Temperature Coastdown
by William.Stanley＠exeloncorp.com 07 May '08

07 May '08

Answers to STP questions: 1. What type of temperature coast do you use (Tavg, Treference, others)? Why? TMI-1 is a Babcock & Wilcox-designed plant, which runs at constant Tavg of 579 F when above ~20% power (when the once-through steam generator level rises above the low level limit setpoint). Tavg is one of the controlled parameters during normal operations. Therefore the TMI-1 temperature coastdown is a Tavg coastdown. The analysis for cycle stretch by Tavg reduction allows operators to reduce Tavg by up to 7 F. The procedural limit is a bit less than that. 2. What instrument recalibrations are usually necessary? Power range nuclear instruments require more frequent recalibration. As Tavg is reduced, Tcold goes down, downcomer density increases, and thus fewer neutrons escape to be read by the out-of-core neutron detectors. This drives the NIs in a non-conservative direction. 3. When do you reach valves wide open on the turbine? They never go wide open. TMI-1 turbine is designed to operate w/ the control valves nearly full open. We have found that they don't control well when open more than 85%. As Tavg decreases, the turbine control valves will tend open up. To preserve some "bite" on the control valves, we will reduce power during the Tavg reduction to keep the turbine control valves less than 85% open. 4. How does the secondary side efficiency drop with steam pressure? We maintain steam pressure. During normal operation, the once-through steam generators (OTSGs) provide about 50 F of superheat. As Tavg decreases, the amount of superheat in the steam to the turbine drops slightly. Another phenomenon is that OTSG operating range "level" (more like OTSG delta-P) increases as Tavg decreases. This is one result of slightly colder/higher flow of feedwater entering the OTSG. Carnot implies that as Tavg drops (with attendant drops in Thot and Tsteam), plant efficiency declines. However, there are some compensations. For example, the heat losses are slightly lower due to reduced temperatures and flow losses through the turbine control valves are lower because they are open a bit more. Bottom line: we did not observe any change in plant efficiency during the Tavg reduction at the end of the last cycle. 5. What operational issues/lessons learned would you care to pass along? As implied above, stay on top of NI calibrations and turbine control valve position. Bill Stanley TMI-1 Reactor Engineering (717) 948 8695 -----Original Message----- From: Crawford, Howard C. Sent: Tuesday, 06 May 2008 12:12 To: Stanley, William S (TMI) Subject: FW: [Respvr] Temperature Coastdown Please respond to this request for TMI. Thanks -----Original Message----- From: Buckley, Fred Sent: Tuesday, May 06, 2008 8:13 AM To: Crawford, Howard C.; Tsai, Robert W. Subject: FW: [Respvr] Temperature Coastdown Thought you might be interested in this question. -----Original Message----- From: respvr(a)retaqs.com [mailto:respvr@retaqs.com]On Behalf Of Gore, Duane Sent: Tuesday, May 06, 2008 8:02 AM To: respvr(a)keffective.com Subject: [Respvr] Temperature Coastdown STP currently performs a Power Coastdown at the end of each cycle. I have been tasked with exploring performing a Temperature Coast (on Tavg) to the lower Safety Analysis limit, followed by a Power Coast. We reach Valves Wide Open on the turbine in about 4 days (2F drop in Tavg). After that, the efficiency of the secondary side drops. For those who perform a temperature coast, I would like to know: 1. What type of temperature coast do you use (Tavg, Treference, others)? Why? 2. What instrument recalibrations are usually necessary? 3. When do you reach valves wide open on the turbine? 4. How does the secondary side efficiency drop with steam pressure? 5. What operational issues/lessons learned would you care to pass along? Thanks in advance. Duane Gore Supervisor, Reactor Engineering STPNOC (361) 972-8909 ----------------------------------------- ************************************************** 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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Temperature Coastdown
by Gore, Duane 07 May '08

07 May '08

STP currently performs a Power Coastdown at the end of each cycle. I have been tasked with exploring performing a Temperature Coast (on Tavg) to the lower Safety Analysis limit, followed by a Power Coast. We reach Valves Wide Open on the turbine in about 4 days (2F drop in Tavg). After that, the efficiency of the secondary side drops. For those who perform a temperature coast, I would like to know: 1. What type of temperature coast do you use (Tavg, Treference, others)? Why? 2. What instrument recalibrations are usually necessary? 3. When do you reach valves wide open on the turbine? 4. How does the secondary side efficiency drop with steam pressure? 5. What operational issues/lessons learned would you care to pass along? Thanks in advance. Duane Gore Supervisor, Reactor Engineering STPNOC (361) 972-8909

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Re: [Respvr] Ramp Rates for Normal Operations
by paul_gurney＠fpl.com 21 Feb '08

21 Feb '08

For Seabrook 10% per hour from 20% to 90% 3% per hour above 90% No restrictions below 20% Paul Gurney RE Supv aburger@firstener gycorp.com To: respvr(a)retaqs.com Sent by: cc: respvr-bounces@re Subject: [Respvr] Ramp Rates for Normal Operations taqs.com 02/20/2008 09:35 AM Please respond to "RE Supervisors" What restrictions do PWRs place on ramp rates for normal operations (fuel already conditioned to 100% power)? This would include extended reduced power operation considerations, i.e. reduced power for X number of days would require further ramp rate restrictions compared to a weekend load swing. 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(a)firstenergycorp.com ----------------------------------------- The information contained in this message is intended only for the personal and confidential use of the recipient(s) named above. If the reader of this message is not the intended recipient or an agent responsible for delivering it to the intended recipient, you are hereby notified that you have received this document in error and that any review, dissemination, distribution, or copying of this message is strictly prohibited. If you have received this communication in error, please notify us immediately, and delete the original message. _______________________________________________ Respvr mailing list Respvr(a)retaqs.com http://www.keffective.com/mailman/listinfo/respvr

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Ramp Rates for Normal Operations
by aburger＠firstenergycorp.com 21 Feb '08

21 Feb '08

What restrictions do PWRs place on ramp rates for normal operations (fuel already conditioned to 100% power)? This would include extended reduced power operation considerations, i.e. reduced power for X number of days would require further ramp rate restrictions compared to a weekend load swing. 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(a)firstenergycorp.com ----------------------------------------- The information contained in this message is intended only for the personal and confidential use of the recipient(s) named above. If the reader of this message is not the intended recipient or an agent responsible for delivering it to the intended recipient, you are hereby notified that you have received this document in error and that any review, dissemination, distribution, or copying of this message is strictly prohibited. If you have received this communication in error, please notify us immediately, and delete the original message.

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Hugh E McKenney is out of the office.
by Hugh.E.McKenney＠dom.com 20 Feb '08

20 Feb '08

I will be out of the office starting 02/15/2008 and will not return until 02/25/2008. I will respond to your message when I return. ----------------------------------------- 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.

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Re: [Respvr] PWR Core Reload Question
by ALDAY, CLINT L 11 Dec '07

11 Dec '07

Yes 1. 144 hours (best ever is 128, best ever for offload-CEA shuffle-reload is 144) 2. 217, 89 CEAs 3. 217 + 92 = 319 fuel, 89 CEA 4. Yes, we have a dual masted refuel machine - one for CEAs and one for fuel (including a fuel assembly with a CEA in it) Clint Alday Waterford 3 -----Original Message----- From: respvr-bounces(a)retaqs.com [mailto:respvr-bounces@retaqs.com] On Behalf Of Fago, Carl D Sent: Friday, December 07, 2007 8:37 PM To: respvr(a)retaqs.com Subject: [Respvr] PWR Core Reload Question Some questions for the PWR folks: Do you perform in-core shuffle for reloads? If yes ... 1. How much time is normally scheduled for in-core shuffle? 2. How many FA in your core? How many components (burnable poisons, control rods, sources, thimbles, etc.)? 3. Roughly, how many individual assembly or component moves is your normal reload? 4. Do you have an installed mast for components (I've heard that some use a temporary component mast installed each outage)? Thanks! Carl Carl D. Fago Reactor Engineering Supervisor Oconee Nuclear Station Duke Energy 864-885-3047 cdfago(a)duke-energy.com

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PWR Core Reload Question
by Fago, Carl D 10 Dec '07

10 Dec '07

Some questions for the PWR folks: Do you perform in-core shuffle for reloads? If yes ... 1. How much time is normally scheduled for in-core shuffle? 2. How many FA in your core? How many components (burnable poisons, control rods, sources, thimbles, etc.)? 3. Roughly, how many individual assembly or component moves is your normal reload? 4. Do you have an installed mast for components (I've heard that some use a temporary component mast installed each outage)? Thanks! Carl Carl D. Fago Reactor Engineering Supervisor Oconee Nuclear Station Duke Energy 864-885-3047 cdfago(a)duke-energy.com

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Question on SOER 07-01 Reactivity Management
by Fago, Carl D 04 Oct '07

04 Oct '07

I'm looking for some info on how everyone else is addressing the simulator training recommendation in the subject SOER. Specifically, the bullet in the recommendation says: Reactor Engineers participate in simulator training with shift operating crews at least once per refueling cycle or at least once every two years. Will your site credit Just In Time Training (JITT) opportunities to meet this or just simulator scenarios as part of the Operator Training program? I'll compile individual results and send it out for everyone. Thanks, Carl Carl D. Fago Reactor Engineering Supervisor Oconee Nuclear Station Duke Energy 864-885-3047 cdfago(a)duke-energy.com

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RIS 2007-021 Compliance
by Michael.Fanguy＠dom.com 02 Oct '07

02 Oct '07

Question to Reactor Engineering Supervisors with respect to RIS 2007-021. What type of time averaged values are used in your calorimetric program (e.g. 1 minute average, 5 minute average, etc)? What type of time averaging is used for either feed flow or steam flow which feeds your calorimetric program? Which of the time average calorimetric values are used to ensure compliance with your licensed thermal power limitations and the intent of RIS 2007-021? Have you made changes to your calorimetric procedures or methods as a result of the RIS? Is "Steady State" in reference to licensed thermal power defined at your plant? Michael J. Fanguy Nuclear Analysis & Fuel Lead Reactor Engineer Surry Power Station Email: Michael.Fanguy(a)Dom.com Phone: 757-365-2155 Pager #: 3453 ----------------------------------------- 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.

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