Carl, Tom Tomlinson (RETAQS) also gave me
the same story on the Fuel Failure issue and its impact on Reactivity
Management. In this case, I do feel you could potentially bin this in
Level 2 space because of how it failed. However, that may not be
indicative of the health of your RM Program.
We agree with your issue about fuel issues
not all belonging under RM issues. BWROG RCRC is developing another PI
looking at Fuel-related issues that would not fall under reactivity management
for exactly that reason. We did get some input from PWR’s on it and
are also including INPO up-front. It will be some time before we have a
product ready for use on that.
For you final issue, on technical product,
in my opinion, it is Level 4 since it doesn’t impact operation. I
have attached a discussion on similar topics. They are examples that had
happened recently at BWR’s and we discussed them at the January RCRC
meeting. Many of them are BWR specific examples, but some would apply to
both and certainly the concepts could be applied. From the description
you’ve given below, it appears that it looks much like events described
on Slides 9, 11, 15 and 16. It would be consistent with Level 4 in all of
those examples.
Ed McVey
From: pwrrm@retaqs.com
[mailto:pwrrm@retaqs.com] On Behalf Of Fago,
Carl D
Sent: Thursday, April 08, 2010
5:44 AM
To: PWR Reactivity Management
Subject: Re: [Pwrrm] PWROG RM
Coding Questions
With regard to the delta between the
BWROG and PWROG for fuel failures, as I recall from the meeting in Pittsburgh,
the basis was that a fuel failure for PWRs is potentially significantly less RM
impact than a fuel failure for BWRs. Since PWRs don’t suppress failures,
only certain cases do failures impact RM in any way. Thus, those that do should
be treated the same as SL3 events but those that don’t are either not RM
at all (say low power grid-to-rod fretting failures) or a lower event level (L4
for fuel handling issue that results in damage).
The other issue that needs to be
discussed in Philly is that RM needs to be just that, RM. Not all fuel issues
are RM-related. There are really big deals that are not RM big deals. (ONS fuel
damage event for instance). If INPO wants to encompass all fuel issues in any
way, shape or form, within RM then INPO 06-06 and SOER 07-1 need to change to
reflect that. Currently they don’t encompass what I hear second hand that
INPO wants. My management has also pushed back on some of the PWROG
criteria based on the issue not being RM per the definition and I’ve
asked them to provide that feedback to INPO.
On a different note, another example
just to make sure we’re implementing consistently…
·
An error in the core cycle design calculations for a
current operating cycle that either does not result in any change to the COLR
or the design deliverable document used at the plant for managing the operating
core. (Say, a conservative error in the analysis for a non-limiting event
… thus the AO, rod insertion or tilt limits are not changed.)
-
SL4 as a technical error in an RM product after
implementation but no impact to operation? (it’s been implemented,
though, so the information has been “used”)
-
SL3 does not seem to apply since the error does not
impact operation.
-
Or is it even lower than SL4 since the site documents
(COLR, etc.) did not have an error … only the basis calculation did?
Thanks!
Carl
Carl D. Fago
Reactor Engineering Supervisor
Oconee Nuclear Station
Duke Energy Carolinas
Phone: (864) 873-3047
Fax: (864) 873-3374
Email: Carl.fago@duke-energy.com
From: pwrrm@retaqs.com
[mailto:pwrrm@retaqs.com] On Behalf Of edward.mcvey@exeloncorp.com
Sent: Tuesday, April 06, 2010 2:04
PM
To: pwrrm@retaqs.com
Subject: Re: [Pwrrm] PWROG RM
Coding Questions
See my responses below. Some of
these are good topics for our meeting in July in Philly.
Ed McVey
From: pwrrm@retaqs.com
[mailto:pwrrm@retaqs.com] On Behalf Of Fago,
Carl D
Sent: Tuesday, April 06, 2010
11:59 AM
To: pwrrm@retaqs.com
Subject: [Pwrrm] PWROG RM Coding
Questions
During
our transition to the use of the PWROG RM event coding, several questions arose
and we’d like to get some feedback on how others are handling similar
issues. Specifically…
1.
For multi-unit sites, if there is
an issue generic to all units (e.g., vendor core design analysis method error),
are you applying the “hit” to all applicable units equally? Most definitely.
2.
For those sites with dry storage
(or event multi-unit sites with dry storage), how are you addressing issues
with cask transport to dry storage (e.g., while transporting a cask the
trailer/transporter breaks)? Is this an issue of less than adequate fuel
handling equipment performance while handling fuel or control component (no
fuel/component damage), L5? If so, for multi-unit sites, which unit would get
the RM hit based on dry storage?
We don’t really address that very well. That may be an item for
clarification in the next revision. I would take your pick on the
unit. Probably, if only one unit’s fuel is involved, then use that
unit (like you do in 3 below). Otherwise, either would suffice.
3.
ONS has a shared fuel pool between
Unit 1 and 2. For fuel handling practices / equipment issues, we are proposing
to apply any RM hit against the unit to which the specific fuel assembly or
control component last operated. As far as we can tell, there is no
“hit” if the fuel bridge or other equipment fails when fuel is not
being handled, therefore, there will always be a unit that can be associated
with the event. That sounds
appropriate to me.
4. ONS
Fuel Damage Event (SEN-280) has been classified as L4 based on fuel handling
that results in damage to fuel assembly or control component. While the RM
level isn’t indicative of the organizational significance of the event,
this is the classification we came up with. Any comment or insights into how
others might classify this event? (While we weren’t “handling fuel”
at the time, we conservatively said it met the intent.) Note that there
was no specific RM impact in the event (again, this was a big event for ONS but
we’re specifically focusing on RM for this question.) This is definitely a weakness in the PWR RM PI.
The PWR PI puts a fuel failure at Level 4 versus the BWR PI puts it at
Level 3. Also, the BWR PI would also have gotten you to Level 3 in that
an emergency core redesign due to fuel damage, would also have gotten you to
Level 3. You could also call it a Level 2 since technically you could
argue that it failed due to “operational” issues. I can tell
you that my discussions with INPO on classification of an event like this as a
Level 4 would cause them serious heartache. That was one of the major issues
that they had with the PI, was how could fuel handling damage be considered so
low. That’s why it got elevated in the BWR PI. Not sure why
the PWR team arrived where they did on that one. I think the only
justification you have is that it does not necessarily reflect the health of
your RM program. Although, someone else might argue that could be because
you haven’t gotten the right sensitivity in the entire organization to
ensure all personnel realize their potential impacts to Reactivity Management
and Fuel Integrity. If you look at the standard philosophy of Reactivity
Management (see below for Exelon’s which was taken from other industry
documents), you are suppose to operate fuel such fuel failure does not occur.
In your event, a maintenance activity caused the fuel to fail. That
has to be more than a Level 4 event. If you can’t bin it under a
standard example, then use management discretion to elevate. The examples
that we have couldn’t think of all the possibilities of things happening,
but I’m pretty sure that had we thought your event was possible, it would
have been binned under something higher than Level 4.
“
Thanks
in advance for all the feedback!
Carl
Carl D. Fago
Reactor Engineering Supervisor
Oconee Nuclear Station
Duke Energy Carolinas
Phone: (864) 873-3047
Fax: (864) 873-3374
Email: Carl.fago@duke-energy.com
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