PWRRM

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244 discussions

Negative Margin to FqN transient Limit.
by Adina K Lafrance 15 Jan '10

15 Jan '10

Our Fleet RM Team would like to know how other sites would classify/grade the following event: During the initial power escalation following a refueling outage, QPTR alarms required a flux map to verify quadrant power tilt and allow for new currents to be installed to clear the alarm. Originally, the hot channel factors surveillance was to be performed at 73% (the next scheduled flux map) but was performed at ~50%. If the 50% map had passed all acceptance criteria, the 73% map would not have been required and all restrictions based on hot channel factors would have been removed all the way to full power; other hold points would have still been required. The power ascension procedure states that the acceptance criteria for the Intermediate Power (40% to 75%) map to be the technical specification on hot channel factors, which references the COLR limit: "Once after each refueling prior to exceeding 75% RATED POWER and every 31 effective full power days thereafter" the FQN transient needs to be confirmed within limits. During the power ascension, it was decided to confirm the FQN transient using the 50% map to allow for power to be increased >75%. FQN transient was determined to be outside the COLR limits, which caused the entry into the TS action statement. The calculated margin was -1.701% based on a measured value with uncertainties of 5.085 compared to the limit of 5.00. As a result, the following actions were required: -Reduce the AFD limits greater than or equal to 1% for each 1% that the FqN transient exceeds its limits within 4 hours after this determination has been made. -Similarly reduce the Power Range Neutron Flux-High Trip Setpoints and Overpower delta-T Trip Setpoints within 72 hours by greater than or equal to 1% that maximum allowable power of the axial flux difference limits is reduced. A WO was made for I&C to make adjustments to the Power Range Neutron Flux-High Trip Setpoints and OPDT Trip Setpoints as specified above. Prior to completing the WO, the flux map at 73% power determined that there was no need to Reduce Overpower Delta T trip setpoints and the WO was canceled. It was noted that the ~50% map was not originally planned and would not have been performed except for the QPTR alarms-instead the 73% would have been performed. 1) How would your site classify the above event in reactivity management space (precursor, incident, event...)? 2) What is the justification for the grading (the example or statement from your procedure with your grading requirements)? Thank you in advance. Adina LaFrance The significant problems we face cannot be solved at the same level of thinking we were at when we created them. -Albert Einstein Nuclear Analysis & Fuel Reactor Engineer Surry Power Station Email: Adina.K.LaFrance(a)Dom.com<mailto: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.

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Fw: Electronic Benchmarking - Fuel Handling Issues
by ddgoff＠aep.com 14 Jan '10

14 Jan '10

1. Do your stations fuel handling machines require fall protection? One side of the manipulator crane requires fall protection prior to flood up of the refueling cavity. After flood up, a life vest is acceptable. a. If yes, what measures are taken? Netting, harnesses, etc. b. If using netting, where is it attached? c. If using fall protection, where are the tie-offs? There is a cable running the width of the bridge. 2. What are you requirements for fuel movement in the Spent Fuel Pool? Continuous communication capability between the control room and the spent fuel pool bridge, spent fuel pool area supervisor, and fuel transfer system operator. d. Continuous communications with Control Room? If yes, SRO, RO., Other. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)? Spent Fuel Pool Area Supervisor. f. Is your procedure Continuous Use, Information Use or Reference Use? The core shuffle physics data sheet is continuous. The rest is reference. g. Do you utilize Vendors? Yes. If so, what additional oversight is required? SRO in containment, Spent Fuel Pool Area Supervisor (reporting to the SRO) at the pool 3. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? ROS h. Style: drop light or mounted Mounted i. Vendor: ROS j. How many: 9 k. Spacing: about 25 feet max. l. Ballasts: above water or submerged? submerged 4. What type of underwater lights do you use for normal Reactor Cavity Lighting? m. Style: drop light or mounted Mounted n. Vendor: Hydro Vision o. How many: 6 p. Spacing: varies q. Ballasts: above water or submerged? N/A 5. What type of underwater lights do you use for supplemental lighting? If Necessary. r. If so what would require the additional lighting? s. Style: drop light or mounted Drop Lights t. Vendor: Master-Lee u. How many: As required v. Spacing: As required w. Ballasts: above water or submerged? N/A Jim Greendonner Refueling Project Manager Cook Nuclear Plant American Electric Power Nuclear Generation Group 269-466-2684

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Re: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues
by Jeffrey A Camp 14 Jan '10

14 Jan '10

From: Rob McAndrew (Generation - 3) Sent: Wednesday, January 13, 2010 10:25 AM To: Jeffrey A Camp (Generation - 3) Subject: FW: Electronic Benchmarking - Fuel Handling Issues From: pwrrm(a)retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 13, 2010 9:29 AM To: pwrrm(a)retaqs.com Cc: BUSSEY, TIMOTHY J Subject: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1. Do your stations fuel handling machines require fall protection? Only when walking out to the bridge if it isn't parked in it's normal loading location. You put on a life jacket or clip onto the railing wire. The life jacket comes off when you reach the bridge. a. If yes, what measures are taken? Netting, harnesses, etc. b. If using netting, where is it attached? c. If using fall protection, where are the tie-offs? 1. What are you requirements for fuel movement in the Spent Fuel Pool? No continuous communications, various Tech Spec must be verified for ventilation and heavy loads, crane checks, most procedures are continuous use with a peer checker. It depends somewhat on what the evolution is. Vendors are rarely used and only for special ops like reconstitution, not routine fuel movement. d. Continuous communications with Control Room? If yes, SRO, RO., Other. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)? f. Is your procedure Continuous Use, Information Use or Reference Use? g. Do you utilize Vendors? If so, what additional oversight is required? 1. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? Wall and drop lights. Don't know the type or vendor. h. Style: drop light or mounted i. Vendor: j. How many: k. Spacing: l. Ballasts: above water or submerged? 1. What type of underwater lights do you use for normal Reactor Cavity Lighting? Wall and drop lights. Plus temporary fixed lights on the flange. m. Style: drop light or mounted n. Vendor: o. How many: p. Spacing: q. Ballasts: above water or submerged? 1. What type of underwater lights do you use for supplemental lighting? If Necessary. Don't know. r. If so what would require the additional lighting? s. Style: drop light or mounted t. Vendor: u. How many: v. Spacing: w. Ballasts: above water or submerged? 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, nor 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. 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: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues
by William.Stanley＠exeloncorp.com 13 Jan '10

13 Jan '10

Answers interleaved below. Bill Stanley TMI Reactor Engineering 717 948 8695 -----Original Message----- From: Mahgerefteh, Moussa:(GenCo-Nuc) Sent: 13 January 2010 13:59 To: Stanley, William S (TMI):(GenCo-Nuc) Subject: FW: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues Mr. Stanley, Do you mind answering these questions. Moussa _____ From: pwrrm(a)retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 13, 2010 9:29 AM To: pwrrm(a)retaqs.com Cc: BUSSEY, TIMOTHY J Subject: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1. Do your stations fuel handling machines require fall protection? [Stanley, William S (TMI)] Yes, while getting on or off the bridge. Don't need fall protection once actually on the bridge, unless there is a need to climb off the normal walking paths (to check brakes and cables, for example). a. If yes, what measures are taken? Netting, harnesses, etc.[Stanley, William S (TMI)] Life vests or climbing harnesses may be used to get to the bridge. No nets b. If using netting, where is it attached?[Stanley, William S (TMI)] N/A c. If using fall protection, where are the tie-offs?[Stanley, William S (TMI)] Tie-off for the climbing harness is a cable along the walkway to the bridge. When climbing on the bridge, tie-off is to bridge structure. 2. What are you requirements for fuel movement in the Spent Fuel Pool? d. Continuous communications with Control Room? If yes, SRO, RO., Other.[Stanley, William S (TMI)] Fuel movement in SFP requires initial approval by the Control Room, but NOT continuous communication during movement. During refueling (offload/reload), the SF bridge crew is in continuous communication w/ the FH SRO, who is stationed in the Reactor Building on the Main Fuel Handling Bridge, and the Control Room (RO) who is directing the move sequence. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)?[Stanley, William S (TMI)] For "isolated" SFP operations, SRO supervises movements. f. Is your procedure Continuous Use, Information Use or Reference Use?[Stanley, William S (TMI)] Continuous use. g. Do you utilize Vendors? If so, what additional oversight is required?[Stanley, William S (TMI)] During refueling outages, bridges are operated by mix of vendor and company personnel (company personnel are part of the Reactor Services group, who travel from plant to plant for outages). Company personnel provide oversight. 3. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? h. Style: drop light or mounted[Stanley, William S (TMI)] Mounted on the wall i. Vendor:[Stanley, William S (TMI)] ROS j. How many:[Stanley, William S (TMI)] Enough to see all fuel assemblies in the SFP k. Spacing:[Stanley, William S (TMI)] about 25 feet apart l. Ballasts: above water or submerged?[Stanley, William S (TMI)] Submerged 4. What type of underwater lights do you use for normal Reactor Cavity Lighting? m. Style: drop light or mounted[Stanley, William S (TMI)] Temporary mounted lights above core, drop lights at the bottom of the core resting on the core plate. n. Vendor:[Stanley, William S (TMI)] Unknown o. How many:[Stanley, William S (TMI)] Two mounted above, one or two in the bottom p. Spacing:[Stanley, William S (TMI)] Mounted lights above core are 180 deg apart q. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. 5. What type of underwater lights do you use for supplemental lighting? If Necessary. r. If so what would require the additional lighting? s. Style: drop light or mounted[Stanley, William S (TMI)] on underwater camera poles t. Vendor:[Stanley, William S (TMI)] (camera) u. How many:[Stanley, William S (TMI)] typically dual light v. Spacing: w. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)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, nor 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. ----------------------------------------- ************************************************** 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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William V Ferguson is out of the office.
by wvferguson＠aep.com 13 Jan '10

13 Jan '10

I will be out of the office starting 01/08/2010 and will not return until 01/18/2010. I will respond to your message when I return.

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Issuance of the COLR
by Gore, Duane 07 Jan '10

07 Jan '10

We have been questioned by our Resident as to the timeliness of issuing the Core Operating Limits Report (COLR). We issue it after we approve our Reload Safety Evaluation report. Sometimes this is done before the refueling outage starts, other times it is just prior to core reload. Other than having it in place when the new core is loaded, we do not have any requirements on a lead-time. When we issue the COLR to the Plant we also issue it to Licensing and they do the formal transmittal to the NRC. 1. When does your organization issue the COLR to the Plant (e.g., as needed, before the start of the outage, 3 months prior to the outage) ? 2. How long after issuance to the Plant is the COLR sent to the NRC? 3. What organization prepares and issues the COLR (e.g. core design, safety analysis, licensing, etc.)? Thank you in advance for your responses. Duane Gore Supervisor, Reactor Engineering STPNOC (361) 972-8909

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RM grading: exceeding DNB
by Adina K Lafrance 15 Dec '09

15 Dec '09

I am wondering: how other sites would have classified exceeding DNB margin in reactivity management space.? Details: The plant had tripped with the TCBs closed when the cold leg temperature was exceeded. The temperature was exceeded for less than 10 seconds. The Technical Specification action statement was met in the specified time. The event was originally graded as an incident. Also, does your site consider the Tech Spec on DNB a reactivity management TS? Thank you in advance! Adina LaFrance The significant problems we face cannot be solved at the same level of thinking we were at when we created them. -Albert Einstein Nuclear Analysis & Fuel Reactor Engineer Surry Power Station Email: Adina.K.LaFrance(a)Dom.com<mailto: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.

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Fw: SNM Inventories
by gmbradham＠aep.com 05 Nov '09

05 Nov '09

DC Cook does not allow Fuel Handleers/Reactor Services to perform SNM inventories. We aren't casking yet, but I believe the same answer will apply when we get there. Glen M Bradham, 269-465-5901 X1538 ----- Forwarded by Glen M Bradham/BC1/AEPIN on 11/05/2009 10:13 AM ----- David D Goff/BC2/AEPIN 11/04/2009 03:07 PM To Glen M Bradham/BC1/AEPIN@AEPIN cc Subject Fw: [Pwrrm] SNM Inventories David Goff Reactor Engineer Donald C. Cook Nuclear Plant 269-465-5901 x1465 ----- Forwarded by David D Goff/BC2/AEPIN on 11/04/2009 03:07 PM ----- <Rosanne.Carmean(a)exeloncorp.com> Sent by: pwrrm(a)retaqs.com 11/04/2009 02:53 PM Please respond to PWR Reactivity Management <pwrrm(a)retaqs.com> To <pwrrm(a)retaqs.com> cc Subject [Pwrrm] SNM Inventories Do any of you allow the Fuel Handlers/Reactor Services to perform the annual SNM physical inventory? Are they allowed to perform the cask serial number loading inventory? If yes, do they have to have specific qualifications, and if so what are they? Rosanne Carmean Exelon Nuclear Spent Fuel and Decommissioning Phone: (630) 657-2166 Fax: (630) 657- 4331 <mailto:Rosanne.Carmean@exeloncorp.com> ---------------------------------------------------------------- This e-mail message and all attachments transmitted with it from the Nuclear Generation Group of American Electric Power are for the sole use of the intended recipient(s) and may contain confidential and privileged information. Any unauthorized review, use, disclosure or distribution is prohibited. If you are not the intended recipient, please contact the sender by reply e-mail and destroy all copies of the original message.

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SNM Inventories
by Rosanne.Carmean＠exeloncorp.com 04 Nov '09

04 Nov '09

Do any of you allow the Fuel Handlers/Reactor Services to perform the annual SNM physical inventory? Are they allowed to perform the cask serial number loading inventory? If yes, do they have to have specific qualifications, and if so what are they? Rosanne Carmean Exelon Nuclear Spent Fuel and Decommissioning Phone: (630) 657-2166 Fax: (630) 657- 4331 <mailto:Rosanne.Carmean@exeloncorp.com> ----------------------------------------- ************************************************** 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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[RCRC] TracWorks Fuel Movement Sheet Preparation
by Rosanne.Carmean＠exeloncorp.com 27 Oct '09

27 Oct '09

At Exelon, most sites use ShuffleWorks/Crystal Reports to create fuel movement sheets, however, two of our sites use TrackWorks for move sheet generation. During TracWorks training, it was noted that there currently is no procedure governing the use of TracWorks for the development of move sheets. 1. Do you use TracWorks to create move sheets? 2. If yes... a. do you have a governing procedure? b. how do you control that the move sheets are verified? c. would you be willing to share the procedure? Thank you for your time and responses. Rosanne Carmean Exelon Nuclear Spent Fuel and Decommissioning Phone: (630) 657-2166 Fax: (630) 657- 4331 <mailto:Rosanne.Carmean@exeloncorp.com> ************************************************** 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. ************************************************** ----------------------------------------- ************************************************** 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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