PWRRM

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244 discussions

Re: [Pwrrm] final approach to critical, boron dilute or pull rods?
by David D Goff 17 Nov '16

17 Nov '16

At D. C. Cook, we will dilute to ARO BOC critical unless we have performed a Subcritical Physics Testing endpoint. In those cases, we have pulled to critical targeting CD at 135 steps. For mid-cycle startups, we pull to critical targeting CD at 135 steps. From: PWRRM [mailto:pwrrm-bounces@retaqs.com] On Behalf Of Kenneth Pike Sent: Wednesday, November 16, 2016 3:08 PM To: pwrrm(a)retaqs.com Subject: [EXTERNAL] [Pwrrm] final approach to critical, boron dilute or pull rods? 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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Count Rate Doubling vs. 1/M plots
by Kenneth Pike 05 Oct '16

05 Oct '16

Does anyone use count rate doublings to monitor approach to critical or just use 1/M plots or do both?

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Newer STS Shutdown Margin Definition
by Kenneth Pike 31 Aug '16

31 Aug '16

Anyone have the following newer SDM definition in their TS? "SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. However, with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck RCCA in the SDM calculation. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM, and b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level." If you have implemented this in your procedures what "two independent means" do you use after a trip to verify all rods have inserted? In this SDM definition it seems the "Stuck RCCA" is used interchangably with the "single RCCA of highest reactivity worth, which is assumed to be fully withdrawn". I would read this as meaning the calculation if being performed after a trip and verifying all rods inserted would no longer have to include the single RCCA of highest reactivity worth. Any thoughts? Thanks Ken Pike (610) 277-8991 x 253

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RETAQS Online Initial PWR RE Training
by Kenneth Pike 15 Jun '16

15 Jun '16

RETAQS is looking to offer an ONLINE Initial PWR RE Training course. This would consist of about 30 narrated Video modules covering all the usual RE tasks/duties as well as some fundamentals like Reactor Physics, Reactor Components, Applied Thermo, Nuclear Instrumentation Systems etc. Online Quizzes and a final cumulative Exam would be provided to document successful completion of the training. This email is to ascertain if there is anyone interested in this type of training and if they would be willing to participate in its development. A discount would be offered to a participant providing module reviews/comments and supplying current procedures /documents to be used in the modules development. Time frame is to have it in place and available by the end of this year. Presentations for many of the topics already exist as Refreshers I have taught or Continuing Training Modules I developed so this will not require the development of every topic from a blank page, but rather a updating and rework of the many existing modules for its intended purpose. Thanks Ken Pike (610) 277-8991 x 253

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Test 1
by Carlos Vidal 17 May '16

17 May '16

Testing list, please disregard. Carlos Vidal K Effective LLC

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Plant RE contact
by Kenneth Pike 07 Dec '15

07 Dec '15

RETAQS will be mailing out our 2016 Reactor Engineering Calendars soon. I am looking for a PWROG or other similar contact list to ensure the Calendars get shipped to a current RE Plant contacts. Any info is appreciated. Thanks Ken Pike (610) 277-8991 x 253

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SNM self assessment
by David D Goff 29 Sep '15

29 Sep '15

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 269-465-5901 x1465

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NIS Negative Rate Reactor Trip
by Kenneth Pike 05 Feb '15

05 Feb '15

Does anyone still have this NIS Reactor Protection Trip enabled? I know some plants removed years ago. Run Silent, Run Deep Ken Pike (610) 277-8991 x 253

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Industry Benchmark for Tracking Low-Level Reactivity Management Issues
by Tim Siefer 26 Nov '14

26 Nov '14

A recent Quick-Hit Self-Assessment of the Reactivity Management Program at D. C. Cook revealed a shortcoming in the way we track low-level reactivity management issues and drive them to resolution. Low-level reactivity management issues (i.e. blowdown, thermal power calculation, and main feedpump D/P) are carried in the Reactivity Management Oversight Committee (RMOC) meeting minutes, however there is no formal tracking method for issues identified in RMOC meetings and providing traceability for issues forward to the Plant Health Committee. The reason for this communication is to benchmark the industry in an effort to develop a formal method for tracking these issues. What is the process or mechanism your organization uses to track low-level reactivity management issues and drive them to resolution? Thank you for your time. Tim Siefer Senior Reactor Operator Unit Supervisor Donald C. Cook Nuclear Plant tcsiefer(a)aep.com

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Re: [Pwrrm] retaqs
by Kenneth Pike 25 Nov '14

25 Nov '14

RCRC(a)retaqs.com pwrrm(a)retaqs.com From: David D Goff [mailto:ddgoff@aep.com] Sent: Tuesday, November 25, 2014 11:30 AM To: Kenneth Pike (krpike(a)retaqs.com) Subject: retaqs Hi again, Ken. I've misplaced the reactivity management mail list address. Could you help me out? David

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