PWRRM

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244 discussions

Mail List For PWR REs
by Tom Tomlinson 11 Apr '22

11 Apr '22

I have received questions about this email list server so I am sending this message to the group. This email is available so that all enrolled PWR REs can communicate with each other. The BWR community has a similar list that is used often. They use it to share OE, ask questions of each other, and coordinate industry responses. I encourage the PWR community to use this tool as well. If you have questions about this mail list, please let me know. If others in your group want to be added to the list, have them send me an email to tom(a)retaqs.com <mailto:tom@retaqs.com> and I will add them to the group. Tom Tomlinson RETAQS, Inc. 610 277-8991 (Work) 610 659-5342 (Cell) 102 Muirfield Dr Blue Bell PA 19422

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SNM request
by David D Goff 17 Jan '22

17 Jan '22

D. C. Cook has an NRC Special Nuclear Material accountability audit approaching. We are requesting any input on a suggested strategy for a self-assessment prior to the audit, including your own self-assessment experiences. Thanks, David Goff Reactor Engineer

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industry SNM query
by David D Goff 01 Dec '21

01 Dec '21

I'm seeking a short description of how you perform the SNM inventory in the SFP including any challenges you may need to grapple with. For example, at D. C. Cook: Our procedure provides for a piece count done visually. This involves standing at the edge of the pool (with FME controls and a life vest - no railing is installed) with a powerful flashlight and looking into the racks. We check each rack location as empty or containing fuel or containing a non-fuel item (e.g., a trash can), and we then compare the actual configuration to SNM records. It's not unusual to have visual challenges near the SFP cooling discharge due to air entrainment in the flow.

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Incore Thermocouple exclusion
by David D Goff 17 Jun '20

17 Jun '20

Greetings, all, At D. C. Cook, we have an old discrete subcooling margin monitor in addition to that function being handled by the plant computer. We exclude thermocouples in the outer two pitches nearest the core edge when considering which ones to wire into the subcooling margin monitor. This is based on recommendation from Westinghouse regarding steam generator refluxing following an accident, where steam condenses in the hot leg and drains back into the reactor vessel as relatively cool water. Does your station exclude the outer two pitches? Do you have a basis for this? Thanks, David Goff Reactor Engineer, D. C. Cook

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SNM self assessment
by David D Goff 03 Sep '19

03 Sep '19

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PWROG RMPI Guideline most current Revision Green Performance Goal %
by Kenneth Pike 19 May '17

19 May '17

I am looking for the most recent PWROG RMPI Green Goal, greater than or equal to X %. It used to be 95%, but not sure that is still true in the latest revision. Thanks Ken Pike

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question on fuel assembly bottom nozzle observation
by Hulvey, Kimberly Dawn 30 Mar '17

30 Mar '17

During our refueling outage fuel assembly inspections, we noticed something unusual in a number of periphery fuel assemblies removed from the core. We initially thought it was some type of debris and were going to attempt removal. Upon further inspection, the 'marking' is only seen at certain angles of viewing - it looks like a haze. Since we have seen this on more than one assembly, we don't think it is camera distortion or camera focusing issues. When we zoon in and look at the flow holes better, we do not see any obstruction so we are currently planning to reuse these assemblies. Just curious if anyone had ever seen anything similar. Pictures are attached. Thank you in advance for your response and help. Kim Hulvey WBN Reactor Engineering Manager 423-365-7720 (office) 931-581-5423 (cell)

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Part power extended operation
by Kenneth Pike 19 Jan '17

19 Jan '17

Anyone have experience with extended part power operation during a cycle with AREVA W17 HTP fuel? Thanks Ken Pike (610) 277-8991 x 253

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Re: [Pwrrm] PWRRM Digest, Vol 83, Issue 2 - Methods to going critical
by Gore, Duane 21 Nov '16

21 Nov '16

STP dilutes to critical (ARO) after a refueling outage. Subsequent startups are pull-to-critical. Duane Gore, P.E. Supervisor, Reactor Analysis Nuclear Fuel & Analysis STPNOC degore(a)stpegs.com (361) 972-8909 (w) (979) 318-6314 (c) (361-972-8081 (fax) -----Original Message----- From: PWRRM [mailto:pwrrm-bounces@retaqs.com] On Behalf Of pwrrm-request(a)retaqs.com Sent: Thursday, November 17, 2016 10:02 AM To: pwrrm(a)retaqs.com Subject: PWRRM Digest, Vol 83, Issue 2 **THIS EMAIL IS FROM AN EXTERNAL SENDER OUTSIDE OF THE STPNOC NETWORK. BE CAUTIOUS ABOUT CLICKING LINKS OR OPENING ATTACHMENTS FROM UNKNOWN SOURCES. DO NOT PROVIDE PERSONAL INFORMATION SUCH AS SS#, USER ID/PASSWORD, ETC.** Send PWRRM mailing list submissions to pwrrm(a)retaqs.com To subscribe or unsubscribe via the World Wide Web, visit http://www.keffective.com/mailman/listinfo/pwrrm or, via email, send a message with subject or body 'help' to pwrrm-request(a)retaqs.com You can reach the person managing the list at pwrrm-owner(a)retaqs.com When replying, please edit your Subject line so it is more specific than "Re: Contents of PWRRM digest..."

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final approach to critical, boron dilute or pull rods?
by Kenneth Pike 17 Nov '16

17 Nov '16

Do you still position rods and dilute to critical during initial startup after a refueling? On a mid cycle startup do you dilute to critical boron then pull rods to critical or position control rod at estimated critical position and dilute to critical? TVA is interested in what method other plants are using to achieve criticality. Thanks Ken Pike (610) 277-8991 x 253

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