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244 discussions

PWR In-Core detector Physical Inventories
by Rosanne.Carmean＠exeloncorp.com 27 May '11

27 May '11

Has any one ever pursued an NRC exemption for 10CFR74.19(c) physical inventory of in-core detectors in efforts to eliminate risk of going into containment and reduce dose? Thanks in advance for responding. Rosanne Carmean Exelon Nuclear Spent Fuel and Decommissioning Phone: (630) 657-2166 Fax: (630) 657- 4331 <mailto:Rosanne.Carmean@exeloncorp.com <BLOCKED::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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values of "x" for PI
by ddgoff＠aep.com 04 Jan '11

04 Jan '11

What values of "x" are plants using for example criteria 3.9 and 4.6 in the PWR Reactivity Management Performance Indicator PI? David Goff Reactor Engineer Donald C. Cook Nuclear Plant 269-465-5901 x1465

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AUTO: Anthony R Burger/FirstEnergy is out of the office. (returning 01/03/2011)
by aburger＠firstenergycorp.com 28 Dec '10

28 Dec '10

I am out of the office until 01/03/2011. I will be out of the office on vacation starting the afternoon of 12/22/10 and will return on 1/3/2011. If you have any immediate reactor engineering related items please contact Travis Link or Tyler Dileo. Note: This is an automated response to your message "[Pwrrm] values of "x" for PI" sent on 12/28/10 14:53:01. This is the only notification you will receive while this person is away. ----------------------------------------- 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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VC Summer Survey on Rod Drop Testing
by BELL, WILLIAM H 14 Dec '10

14 Dec '10

V. C. Summer has been conducting the Shutdown and Control Rod Drop Timing Technical Specification required surveillance using the plant process computer since 1991. Prior to that a strip chart recorder (Visicorder) was used to perform this test. A condition report was recently initiated that asks whether or not this is an appropriate method of testing. The Visicorder was a calibrated field standard while the plant computer is not. We are now trying to determine how to demonstrate the timing accuracy of the plant computer for use in rod drop testing. 1. Does your plant use the plant computer or another computer for rod drop testing? If yes do you perform any type of timing accuracy test for such a computer and how do you perform such a test. 2. If you do not use a computer to perform rod drop testing what method do you use to confirm you meet the required rod drop time? Please email or call Bill Bell with your response to this survey. William H. Bell, PE Chemical Engineer Reactor Engineering V. C. Summer Station South Carolina Electric & Gas Co. 803-345-4389

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Mail Lists
by Tom Tomlinson 10 Dec '10

10 Dec '10

As many of you know, we identified a security hole in our mail lists this week. In the process of addressing that problem, some unintended messages were released to the groups which caused great confusion. I apologize for that. We now believe that the issue has been resolved. If you see any further suspicious messages, please forward them to me. The lists should now be safe to use. I wish all of you a blessed and joyous Holiday Season, Tom Tomlinson

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[retaqs.com] has Activated your New Mail Services!
by [retaqs.com] Support 09 Dec '10

09 Dec '10

Dear pwrrm(a)retaqs.com, [retaqs.com] has activated your virus and junk mail protection services. You should log in to your personal, password-protected [retaqs.com] Message Center as soon as possible. Your login address is: pwrrm(a)retaqs.com Your temporary password is: h3~Naidq (You will be asked to create a new password after first log in.) To log in to your [retaqs.com] Message Center, use this link: http://login.postini.com/exec/login?email=pwrrm@retaqs.com You may also modify your default settings or deactivate any services. Thank You! [retaqs.com]

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Accounting for SNM in containment
by Adina K Lafrance 23 Nov '10

23 Nov '10

The recent OE concerning the reactor vessel surveillance capsules, OE32026, has generated a number of additional questions here at Dominion concerning the storage of used non-fuel SNM items in our containment buildings. In particular, how are physical inventories performed when an item is relativity inaccessible during reactor operation (e.g., sub-atmospheric containments)? In the past Dominion has used administrative controls. Realizing the 2009 ANSI Standard, N15.8 "Material Control Systems-SNM Control and Accounting Systems for Nuclear Power Plants" provides some guidance in situations such as this, we are looking for some practical approaches to satisfy this guidance. 1. Do you have Non-Fuel SNM stored in containment (not installed in a system)? 2. If yes, when and how are physical inventories performed on these items, i.e. during outages or at-power entries, item count or container count if protected by tamper-indicating devices (TIDs)? 3. If TIDs are used, do you have a TID control program that follows the May 2010 Reg. Guide 5.80, "Pressure-Sensitive and Tamper-Indicating Device Seals for Material Control and Accounting of SNM"? If you do not follow Reg. Guide 5.80, where do you differ? 4. If a container that is protected by a TID is opened, what actions are taken to assure the contents of the container are properly accounted for prior to applying another TID e.g. piece count of items in the container, simultaneous verification by two individuals of the items added or removed from the container, etc? Thank you in advance for your help. Adina LaFrance Reactor Engineer Nuclear Analysis and Fuels, Surry Power Station Dominion Generation Phone: 757-365-2658; Internal: 8-798-2658 E-mail: Adina.K.LaFrance(a)dom.com 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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SNM inventory question
by WILLETT, JOSEPH E 23 Nov '10

23 Nov '10

Fort Calhoun performs two verifications first in the SFP following CEA Shuffle. Second, core verification is performed following core reload using a PTZ camera. The verification of 133 fuel assemblies takes two(2) hours, including camera setup after reload is complete. We have an RE and an STA or RE-alternate on the refueling machine. QA usually observes. Fuel assembly IDs orientation and core location are read by one person and confirmed by the other that verifies correct core location, ID and orientation. Prior to the serial number verification, FCS utilizes refueling machine mast camera to perform the alignment verification, which also takes about two(2) hours. 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.

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SNM inventory question
by ddgoff＠aep.com 23 Nov '10

23 Nov '10

DC Cook is looking at efficiencies during the outages. We are trying to minimize activities associated with reload. For those of you who do the Core SNM Inventory as you load the fuel. What is the process you use, camera check of serial number and camera check of the core when you put it in the core? How many people do the video check, one on line and one later, two online, or just one? Where do the checkers sit, in the office, in a camera room? Can you share you SNM procedure on your core Inventory? thanks Glen M Bradham, 269-465-5901 X1538

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reference bank worth by dilution during physics
by Kenneth R Pike 13 Nov '10

13 Nov '10

For those that measure reference bank worth by dilution during physics testing, how do you determine when to stop the dilution? The process for Beaver Valley is to start a dilution with ARO and the reference bank at near ARO. The dilution is compensated for by inserting the reference bank (measured with a reactimiter supplied by the vendor). The goal is terminate the dilution so that less than 75 pcm is left in the reference bank. Contingencies are built in if you "overshoot" to insert another bank then borate it back out. Contingencies are also built in if you come up short of 75 pcm to dilute the bank into less than 75 pcm. We have experienced both under and overshoots here which is fine and allowed by procedure, we are just looking to see if there is a more precise method. Travis B. Link Beaver Valley Reactor Engineering P.O. Box 4 - Mail Drop A-BV-A Shippingport, PA 15077 (724) 682-4149 (Work) (412) 667-1487 (Cell) (412) 305-3041 (Pager) (724) 682-4250 (FAX) tlink(a)firstenergycorp.com

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