ML21125A156
| ML21125A156 | |
| Person / Time | |
|---|---|
| Issue date: | 05/03/2021 |
| From: | Scott Krepel NRC/NRR/DSS/STSB |
| To: | Patton R, Andrea Russell NRC/NRR/DSS |
| Russell, A., NRR/DSS, 301-415-8553 | |
| References | |
| Download: ML21125A156 (7) | |
Text
From: Krepel, Scott To: Russell, Andrea; Patton, Rebecca Cc: Lukes, Robert
Subject:
RE: Another AP1000 STS Question: STS Bases 3.1.2 Date: Monday, May 03, 2021 2:35:26 PM There are actually two separate revisions to the TS Bases, and Becky is correct that this isnt unique to Vogtleit could apply to any PWR in the operating fleet.
The first revision updates the text to indicate that the hot excess reactivity (HEXR) is changing rather than decreasing (with the possible exception of near BOC). That is generally accurate, and I can see how the older wording may be a little misleading because core designs developed for longer cycles at EPU-type conditions in conventional PWRs can end up with high enrichment fuel and a large amount of burnable absorbers. That can cause the HEXR to increase from equilibrium-xenon BOC conditions to roughly midcycle, when the burnable absorbers are mostly depleted and then the natural reactivity reduction from U-235 depletion takes over. This is something that didnt happen decades ago when the STS for conventional PWRs were written, since the core energy requirements werent large enough to pursue these kinds of core design strategies.
The second revision seems to suggest that the basis for the boron concentration should be the boron concentration calculated using a calculational model consistent with the design analysis, using consistent core conditions, rather than directly comparing it to the predicted boron letdown curve. To understand the distinction, its helpful to understand that legacy PWR approaches in monitoring the boron letdown typically include a boron letdown curve calculated at hot full power (HFP) conditions, plus a whole slew of tables that provide reactivity adjustments for off-nominal conditions. Thus, if a plant does their monitoring when their core is not at nominal HFP conditions, they can use these adjustments to correct the critical boron concentration and use that value to compare to the predicted boron letdown curve. Today, advances in computing power mean that it is pretty easy to just directly calculate the critical boron concentration within minutes for any core condition you want. So, doing the monitoring against an updated reference calculation for the critical boron concentration makes sense. That said, I dont know the details of how the Vogtle TS requirements are written or the internal plant procedures for meeting the requirement. There is some caution advisable in the statement a calculational model consistent with the design analysis. Core monitoring models used by plants are typically built based on the design analysis models, but during core operations, the models are corrected to reflect various small deviations that may accumulate in the depletion characteristics of the core based on differences between the measured vs predicted power distributions. This is appropriate for thermal limits monitoring, since you want to ensure that your model used to verify thermal limits is the best possible fit to the actual conditions.
However, these models may not be good models to use in doing a critical boron concentration comparison because the intent of this comparison is to ensure that the core reactivity does not deviate too much from the core reactivity used in the safety analyses. Youd need to use the actual design analysis models, not corrected models, since much of the potential deviation that youre looking for may already have been eliminated from the corrected model. This is an important distinction that isnt always obvious to operators/reactor engineers at the plant.
To summary, the change seems reasonable, as long as they arent getting too loose with their definitions on how the boron concentration monitoring is done.
Scott Krepel SNSB Branch Chief OWFN 10-H12 423-331-0893 (text message)
From: Russell, Andrea <Andrea.Russell@nrc.gov>
Sent: Monday, May 03, 2021 2:05 PM To: Patton, Rebecca <Rebecca.Karas@nrc.gov>
Cc: Krepel, Scott <Scott.Krepel@nrc.gov>; Lukes, Robert <Robert.Lukes@nrc.gov>
Subject:
RE: Another AP1000 STS Question: STS Bases 3.1.2 Thanks Rebecca. I appreciate any help.
Bob - I copied you on this to bring you in on the question. I have an AP1000 STS question that I sent to Rebecca. She provided to Scott and thought maybe you may have some input. See e-mail thread below.
Any help with this would be appreciated.
From: Patton, Rebecca <Rebecca.Karas@nrc.gov>
Sent: Monday, May 03, 2021 1:57 PM To: Russell, Andrea <Andrea.Russell@nrc.gov>
Cc: Krepel, Scott <Scott.Krepel@nrc.gov>
Subject:
RE: Another AP1000 STS Question: STS Bases 3.1.2 So, just on a quick read - the new language is probably more accurate. Theres nothing unique about AP1000 with respect to this, though. They are probably using changing instead of decreasing because its more accurate. Its not always decreasing. I would actually suggest this should maybe be looked at by someone in another branch, as whatever we do here should probably be done for the op fleet also. Ccing Scott for suggestions - or maybe Bobs branch?
From: Russell, Andrea <Andrea.Russell@nrc.gov>
Sent: Monday, May 03, 2021 1:12 PM To: Patton, Rebecca <Rebecca.Karas@nrc.gov>
Subject:
Another AP1000 STS Question: STS Bases 3.1.2 Rebecca I have another AP1000 STS question. Not sure who on your staff would be able to assist, but here goes TS 3.1.2 for the Vogtle TS Bases was revised in Revision 48. I could not find any LAR associated with the changes so have no information regarding the justification for the changes. Craig asked that I determine the validity of the changes and whether those changes should be incorporated into the STS. I have looked in the UFSAR for Vogtle and the Westinghouse STS and have not been able to determine whether the language in the Vogtle bases should be adopted into the standard and the justification for that language.
The third and fourth columns below are Craigs comments to me and my response. Below this e-mail is my initial e-mail to Craig and his response (for background).
Heres the generic CAC if needed: A11008/ /L-2018-PSS-0000
Any help would be appreciated in determining whether the Vogtle language should be adopted into the STS and if you know of the reasoning behind the changes.
VEGP TS Bases up to AP1000 STS Bases Differences Disposition /
Rev 59 draft Rev. 1 Action Bases Subsection B 3.1.2 Rev. 48 Background paragraph 4 Background paragraph 4 Need to verify that VEGP Unit When the core is producing When the core is producing 3 FSAR THERMAL POWER, the fuel THERMAL POWER, the fuel supports and burnable absorbers are and burnable absorbers are differences in being depleted and excess being depleted and excess PTS Bases reactivity reactivity (except possibly introduced by is changing. As the fuel and near beginning of cycle Rev. 48, and burnable absorbers deplete, (BOC)) is decreasing. As the which, if any, the RCS boron fuel and burnable absorber LAR was concentration is periodically deplete, the RCS boron associated with adjusted to compensate for concentration is adjusted to Rev. 48 the net core reactivity compensate for the net core changes.
change reactivity change while maintaining constant Response (apr):
THERMAL POWER. The Could not find boron letdown curve is any LAR based on steady state associated with and to reposition the operation at RTP. Rev. 48 Control Banks within the changes. I limits defined in LCO 3.1.6, have looked at Control Bank Insertion the UFSAR and Limits. A predicted RCS while I find boron concentration can be some determined for any core Therefore, deviations from information condition using a the predicted boron regarding the calculational model letdown curve may indicate changes in the consistent with the design deficiencies in the design PTS in Chapter analysis. analysis, deficiencies in the 4 and Chapter Therefore, deviations from calculational models, or 15, I do not the predicted RCS boron abnormal core conditions, know enough Action (apr):
concentration with and must be evaluated. about this Determine otherwise consistent core system to validity of PTS conditions may indicate determine Bases changes in deficiencies in the design whether the Rev. 48 and analysis, deficiencies in the text should be whether the
calculational models, or incorporated revised text abnormal core conditions, into the STS. I should be and must be evaluated. could not find incorporated in any written STS Bases.
justification for Ensure written the changes.
justification for changes is W-STS Bases included in new says this:
GTST for When the core Subsection 3.1.2, is producing if PTS text is THERMAL adopted.
POWER, the fuel is being Disposition:
depleted and excess Action (BNL):
reactivity is Implement decreasing. As disposition in the fuel new GTST for depletes, the Subsection 3.1.2 RCS boron concentration is reduced to decrease negative reactivity and maintain constant THERMAL POWER. The boron letdown curve is based on steady state operation at RTP. Therefore, deviations from the predicted boron letdown curve may indicate deficiencies in the design analysis, deficiencies in the
calculational models, or abnormal core conditions, and must be evaluated.
From: Harbuck, Craig <Craig.Harbuck@nrc.gov>
Sent: Monday, May 03, 2021 10:38 AM To: Russell, Andrea <Andrea.Russell@nrc.gov>
Subject:
RE: STS Bases 3.1.2 I suggest looking at W-STS 3.1.2 Bases Background section corresponding paragraph(s)
Also, suggest asking for opinion of reactor systems branch reviewer who helped us before.
From: Russell, Andrea <Andrea.Russell@nrc.gov>
Sent: Monday, May 03, 2021 8:27 AM To: Harbuck, Craig <Craig.Harbuck@nrc.gov>
Subject:
STS Bases 3.1.2 Craig I have looked at the FSAR for Vogtle and do not know enough about this system to make the finding that the PTS bases language should be adopted. I found some supporting information in Chapter 4 and 15 of their FSAR, but it is like finding a needle in a haystack and following bread crumbs for me to try and determine whether their language is supported by what is in their FSAR. Below is what I provided in the comparison document for you to look at and let me know how you want me to proceed.
3.1.2 Background Paragraph 4 VEGP TS Bases AP1000 STS Bases Differences Disposition /
up to Rev 59 draft Rev. 1 Action Bases Subsection B 3.1.2 Rev. 48 Background Background paragraph 4 paragraph 4 When the core is When the core is producing producing THERMAL THERMAL POWER, the fuel and POWER, the fuel burnable absorbers are and burnable being depleted and absorbers are excess reactivity being depleted (except possibly near
and excess beginning of cycle reactivity (BOC)) is decreasing.
is changing. As As the fuel and the fuel and burnable absorber burnable deplete, the RCS absorbers boron concentration is deplete, the RCS adjusted to boron compensate for the net Need to verify that concentration is core reactivity change VEGP Unit 3 FSAR Action (apr):
periodically while maintaining supports differences in Determine adjusted to constant THERMAL PTS Bases introduced validity of PTS compensate for POWER. The boron by Rev. 48, and which, Bases changes the net core letdown curve is based if any, LAR was in Rev. 48 and reactivity change on steady state associated with Rev. whether the operation at RTP.
48 changes. revised text should be Response (apr): Could incorporated in not find any LAR STS Bases.
and to reposition associated with Rev. Ensure written the Control Banks 48 changes. I have justification for within the limits Therefore, deviations looked at the UFSAR changes is defined in LCO from the predicted and while I find some included in new 3.1.6, Control boron information regarding GTST for Bank Insertion letdown curve the changes in the Subsection 3.1.2, Limits. A may indicate PTS bases language if PTS text is predicted RCS deficiencies in the in Chapter 4 and adopted.
boron design analysis, Chapter 15, I do not concentration can deficiencies in the know enough about Disposition:
be determined for calculational models, this system to any core condition or abnormal core determine whether the Action (BNL):
using a conditions, and must text should be Implement calculational be evaluated.
incorporated into the disposition in model consistent STS. I could not find new GTST for with the design any written justification Subsection 3.1.2 analysis.
for the changes.
Therefore, deviations from the predicted RCS boron concentration with otherwise consistent core conditions may indicate deficiencies in the design analysis, deficiencies in the calculational models, or abnormal core
conditions, and must be evaluated.
Andrea Russell Safety and Plant Systems Engineer Nuclear Regulatory Commission NRR/DSS/STSB 301-415-8553