ML20218A576
| ML20218A576 | |
| Person / Time | |
|---|---|
| Issue date: | 07/20/2020 |
| From: | Derek Widmayer Advisory Committee on Reactor Safeguards |
| To: | |
| Widmayer, D, ACRS | |
| References | |
| Download: ML20218A576 (150) | |
Text
Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION
Title:
Advisory Committee on Reactor Safeguards Future Plant Designs Subcommittee Docket Number:
(n/a)
Location:
teleconference Date:
Monday, July 20, 2020 Work Order No.:
NRC-0992 Pages 1-113 NEAL R. GROSS AND CO., INC.
Court Reporters and Transcribers 1323 Rhode Island Avenue, N.W.
Washington, D.C. 20005 (202) 234-4433
NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 1
1 2
3 DISCLAIMER 4
5 6
UNITED STATES NUCLEAR REGULATORY COMMISSIONS 7
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 8
9 10 The contents of this transcript of the 11 proceeding of the United States Nuclear Regulatory 12 Commission Advisory Committee on Reactor Safeguards, 13 as reported herein, is a record of the discussions 14 recorded at the meeting.
15 16 This transcript has not been reviewed, 17 corrected, and edited, and it may contain 18 inaccuracies.
19 20 21 22 23
1 UNITED STATES OF AMERICA 1
NUCLEAR REGULATORY COMMISSION 2
+ + + + +
3 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 4
(ACRS) 5
+ + + + +
6 FUTURE PLANT DESIGNS SUBCOMMITTEE 7
+ + + + +
8 MONDAY 9
JULY 20, 2020 10
+ + + + +
11 The Subcommittee met via Video 12 Teleconference, at 9:30 a.m. EDT, Dennis Bley, 13 Chairman, presiding.
14 COMMITTEE MEMBERS:
15 DENNIS BLEY, Chairman 16 RONALD G. BALLINGER, Member 17 CHARLES H. BROWN, JR., Member 18 VESNA B. DIMITRIJEVIC, Member 19 WALTER L. KIRCHNER, Member 20 JOSE MARCH-LEUBA, Member 21 DAVID A. PETTI, Member 22 JOY L. REMPE, Member 23 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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2 ACRS CONSULTANT:
3 DESIGNATED FEDERAL OFFICIAL:
4 DEREK WIDMAYER 5
7 ALSO PRESENT:
8 RICHARD DENNING 9
ED LYMAN, Union of Concerned Scientists 10 SCOTT MOORE, NMSS 11 WILLIAM RECKLEY, NRR 12 JOHN SEGALA, NRR 13 MARTIN STUTZKE, NRR 14 15 16 17 18 19 20 21 22 23 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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3 P R O C E E D I N G S 1
9:35 a.m.
2 CHAIR BLEY: Good morning. The meeting 3
will now come to order. This is a meeting of the 4
Advisory Committee on Reactor Safeguards, Subcommittee 5
on Future Plant Designs. I'm Dennis Bley, chairman of 6
the Subcommittee.
7 ACRS's members in attendance are Matt 8
Sunseri, Joy Rempe, Ron Ballinger, Charlie Brown, Walt 9
Kirchner, Dave Petti, Vesna Dimitrijevic and Jose 10 March-Leuba. Also in attendance is our consultant Mike 11 Corradini. Derek Widmayer, of the ACRS staff is the 12 Designated Federal Official for this meeting. And 13 Christopher Brown of the ACRS staff is the backup 14 designated federal official. This is a Skype meeting 15 and members are occasionally dropped off the web 16 connection or lose their sound, as just happened. If 17 that happens to me, Dr. Petti will seamlessly take 18 control of this meeting until I return.
19 The purpose of today's meeting is to 20 discuss the staff white paper entitled, Questions 21 Supporting ACRS and Public Interactions on Developing 22 a
Risk-Informed, Technology-Inclusive Regulatory 23 Framework for Advanced Reactors. You may have noticed 24 that our meeting was announced as 10 CFR Part 53.
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4 That remains true. The rulemaking is required by the 1
Nuclear Energy Innovation and Modernization Act, which 2
directs the NRC to complete a rulemaking to establish 3
a technology-inclusive regulatory framework for 4
optional use, commercial, advanced, nuclear reactor 5
applicants. Sorry, I lost my place.
6 This rulemaking is expected to create 10 7
CFR 53. In SECY 20-0032, the staff provided a 8
rulemaking plan to the commission that included a 9
request to eliminate the usual regulatory basis 10 document. In its stead they plan extensive public 11 outreach. The commission has not issued an SRM on the 12 rulemaking plan, so information about Commissioner 13 votes on the proposal are not yet public information.
14 This rulemaking is intimately related to 15 several technical issues that have come before our 16 committee in recent years, including NUREG-1860, which 17 was originally known as the Technology-Neutral 18 Framework. On that one, an Advanced Notice of 19 Proposed Rulemaking was developed back in 2006, but 20 was abandoned when the expected test application for 21 a pebble bed reactor design failed to materialize.
22 Also, the Next Generation Nuclear Plant White Papers, 23 the staff vision and strategy for review of non-LWR 24 applications, including implementation plans such as 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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5 Reg Guide 1.233, which endorses NEI 18-04. Functional 1
containment performance
- criteria, emergency 2
preparedness for SMRs and ONTs, population-related 3
considerations and advanced computer code evaluations.
4 We have written letter reports on all of 5
these precursor programs. The rulemaking will be the 6
culmination of all that previous work. It's come upon 7
us suddenly and I think many of us expected complete 8
trials of the OMP before there would be an actual 9
rulemaking.
Back at our October 30,
- 2018, 10 subcommittee meeting, there was spirited discussion 11 about frequency consequence curves and their use, and 12 some indication that the use and final form might 13 evolve during trials. There were other areas of 14 discussion as well, and I expect those to continue 15 today.
16 One related issue for members, in several 17 of our reports we urged the staff to develop guidance 18 on mechanistic source terms. I am pleased to tell you 19 that the staff is providing the committee with two 20 documents. Derek will be delivering them to the 21 subcommittee members later this week, and we expect to 22 have a meeting to review them at some time in the 23 future.
- Today, the subcommittee will gather 24 information, analyze relevant issues and facts, and 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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6 formulate proposed positions and actions as 1
appropriate. This matter is scheduled to be presented 2
to the ACRS full committee at the October 2020 full 3
committee meeting.
4 The ACRS was established by statute and is 5
governed by the Federal Advisory Committee Act, FACA.
6 NRC implements FACA in accordance with its regulations 7
found in Title 10 of the Code of Federal Regulations 8
Part VII. The committee can only speak through its 9
published letter reports. We hold meetings to gather 10 information and perform preparatory work that will 11 support our deliberations at full committee meetings.
12 The rules for participation in all ACRS meetings, 13 including today's, were announced in the federal 14 register on June 13, 2019.
15 The ACRS section of the US NRC public 16 website provides our charter, bylaws, agendas, letter 17 reports and full transcripts of all full and 18 subcommittee meetings, including the slides presented 19 there. The meeting notice and agenda for this meeting 20 were posted. As stated in the federal register notice 21 and the public meeting notice posted to the website, 22 members of the public who desire to provide written or 23 oral input to the subcommittee may do so, and should 24 contact the designated federal official five days 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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7 prior to the meeting as practicable.
1 Today's meeting is open to the public 2
attendance and we have received no written statements 3
or requests to make an oral argument. We have also 4
set aside ten minutes in the agenda for spontaneous 5
comments from members of the public attending or 6
listening to our meetings.
7 During the COVID pandemic today's meeting 8
is being held over Skype for ACRS and NRC staff 9
attendees. There is also a telephone bridge line 10 allowing public participation over the phone.
11 A transcript of today's meeting is being 12 kept, therefore, we request that meeting participants 13 on the bridge line identify themselves when they are 14 asked to speak, and to speak with sufficient clarity 15 and volume so that they can be readily heard. At this 16 time I ask attendees on Skype and on the bridge lines 17 to keep their devices on mute to minimize disruptions, 18 and unmute only when speaking.
19 We will now proceed with the meeting and 20 I call upon Joe Segala, Chief of the Advanced Reactor 21 Policy Branch of NRR, to make introductory remarks.
22 Joe.
23 MEMBER SEGALA: Thank you, and good 24 morning. I think a lot of my opening remarks you had 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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8 already gone over so I'll try to go quickly. We're 1
here today to brief the ACRS on our plans to develop 2
a new technology-inclusive, risk-informed performance-3 based regulation for advanced reactors, which we are 4
calling 10 CFR Part 53, and to obtain insights and 5
feedback from the ACRS subcommittee at the very early 6
stages of developing this new framework. Although we 7
are expecting to leverage our ongoing readiness 8
activities for this new rule, we are starting with a 9
clean slate in looking for new and innovative ways to 10 regulate advanced reactors.
11 As background, back in 2017, we developed 12 NRC's vision and strategy document and implementation 13 action plans or IAPs for enhancing our readiness to 14 effectively and efficiently review and regulate 15 advanced reactors. The IAPs include near-term, mid-16 term and long-term activities.
17 The near-term IAP activities are divided 18 into six strategies. Strategy one on training, two on 19 computer codes, three on developing guidance, four on 20 industry consensus codes and standards, five policy 21 issues, and six, communications. The ACRS recommended 22 at that time that NRC focus its near-term IAP 23 activities on strategies three and five, which we have 24 been doing. The mid and long-term IAPs included a new 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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9 activity to assess whether a new regulatory framework 1
should be developed for advanced reactors. However, 2
in January of 2019, the Nuclear Energy Innovation and 3
Modernization Act, or NEIMA, was signed into law and 4
required the NRC complete a technology-inclusive, 5
risk-informed, performance-based regulation for 6
advanced reactors by no later than the end of 2027.
7 As Dennis indicated, on April 2020, we 8
issued the rulemaking plan in SECY 20-032, which is 9
currently with the Commission. On July 13, we issued 10 a draft white paper with questions to help facilitate 11 discussions today with the ACRS on Part 53. We are 12 planning for this meeting to be the first of many 13 interactions with the ACRS on Part 53. In addition to 14 discussing Part 53, we will also be briefing the ACRS 15 today on Regulatory Guide 1.233, which was issued in 16 June of 2020 and endorses the licensing modernization 17 project or LMP methodology described in NEI 18-04, as 18 one acceptable methodology for non-light water reactor 19 designers to use to establish key parts of the 20 licensing basis and content of applications. LMP 21 focuses on identifying Licensing Basis Events, 22 classifying structure systems and components, and 23 ensuring adequate defense in depth. This briefing 24 will include a discussion on how we disposition the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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10 public comment received on the associated draft guide 1
1353.
2 As a follow-up to LMP we have started to 3
engage during several public meetings with the 4
southern led, NEI-coordinated and DOE-cost-shared, 5
Technology-Inclusive Content of Application Project or 6
TICAP. The purpose of TICAP is to provide guidance 7
for developing the content of the specific portions of 8
an application that are within the scope of the 9
licensing modernization project.
10 Similar to what was done for LMP, five 11 developers, General Electric, Hitachi, Westinghouse, 12 Kairos, TerraPower and X-energy, have expressed 13 interest in piloting TICAP starting in August of 2020.
14 In addition, the NRC is leading the Advanced Reactor 15 Content of Application Project, or ARCAP, which will 16 provide technology-inclusive, risk-informed and 17 performance-based application content guidance. ARCAP 18 is broader and encompasses the industry-led TICAP 19 project. ARCAP includes those portions of an 20 application outside the scope of the licensing 21 modernization project. We are planning to brief the 22 ACRS on TICAP and ARCAP in the future, and will be 23 working with the ACRS staff to schedule these 24 meetings.
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11 As Dennis also mentioned, we recently 1
published two mechanistic source term reports: One 2
from Sandia National Labs in January, and the other 3
from Idaho National Labs on June 30th on our public 4
website. They provide guidance for determining 5
technology-inclusive mechanistic source term for 6
offsite dose assessments for advanced reactors. These 7
reports were developed in response to letters from the 8
ACRS sent to the commission in 2018 and 2019 on the 9
licensing modernization project and our emergency 10 preparedness for SMRs and other new technologies 11 rulemaking where the ACRS expressed the importance of 12 the staff developing guidance on how source terms 13 should be developed.
14 And so we are prepared to support future 15 briefings on these reports of the ACRS. We are 16 looking forward to hearing from the ACRS today on Part 17 53, and any insights and feedback you all may have.
18 We expect that these activities will result in 19 additional interactions with the subcommittee over the 20 next year or so. This completes my opening remarks.
21 Thank you.
22 CHAIR BLEY: Thanks, John. I'm sorry I 23 misstated your name, to begin with. I guess we're now 24 going to Bill Reckley, is that right?
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12 MR. RECKLEY: Yes, Dennis. This is Bill.
1 CHAIR BLEY: All right, go ahead.
2 MR. RECKLEY: Okay, as Dr. Bley and John 3
mentioned, before we get into the discussions of our 4
development of Part 53, we wanted to provide an update 5
on our issuance of Reg Guide 1.233. Going to slide 6
two, as was mentioned, our first detailed interactions 7
with the ACRS, it actually started before September 8
2018, but in September 2018, we developed kind of the 9
complete package to bring before the ACRS and 10 subsequently the Commission and the public, with a 11 coordinated effort that involved issuance of what was 12 then draft revision N of NEI 18-04, the industry 13 guidance document. The staff had prepared Draft 14 Regulatory Guide 1353 and we also presented to the 15 ACRS a draft commission paper because we thought some 16 of the matters that were involved in this methodology 17 warranted Commission consideration.
18 Ultimately, we had a subcommittee meeting 19 in October and that was followed by the full committee 20 meeting in February 2019, and ACRS issued its letter 21 generally supportive of the methodology in March 2019.
22 Going on to slide three.
23 CHAIR BLEY: Bill?
24 MR. RECKLEY: Yes, sir.
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13 CHAIR BLEY: Just a quick comment for you 1
guys. As we move from testing an approach to an 2
actual rulemaking, I think we need to look for gaps, 3
and some areas have come up in our discussions about 4
recent submittals on particular projects, that 5
reminded us that especially when you have new designs 6
and designs that might have multiple hazards and 7
things for which we don't have 50 years of history to 8
help us out, when one looks for initiating events in 9
the scenarios that follow them, you need something 10 very creative, and you have to start kind of from a 11 blank sheet of paper, and some kind of systematic ways 12 to look.
13 That idea, isn't really laid out in your 14 SECYs or the Reg Guide, or in the NEI document.
15 They're hinted at as the main PRA standard. I'm not 16 certain where the non-LWR standard actually stands 17 right now, or I don't remember the details there. So 18 I'm not sure that area is well covered and we're going 19 to be pushing on that a little bit as we go forward.
20 So go ahead.
21 MR. RECKLEY: Okay, thank you. And I 22 think that would be fully appropriate. So with that 23 background, moving on then to slide three, and 24 catching up on what happened after our interactions 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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14 with the ACRS. So the ACRS letter was in March of 1
2019. We issued DG-1353 for public comment in April.
2 We did receive one public comment from Drs. Denning 3
and Mubayi, and we'll talk about that comment in the 4
next couple slides.
5 For various reasons, NEI went ahead and 6
issued Revision 1 in August of 2019. After some 7
internal delays we ultimately issued SECY-19-0117 in 8
December of 2019, to get the issues before the 9
commission. The commission's Staff Requirements 10 Memorandum was issued in May of 2020, and that, again, 11 was generally supportive of proceeding down the path 12 we had recommended. And we issued Reg Guide 1.233 in 13 June of this year, June 2020. Based on the 14 discussions that there were minimal changes to NEI 18-15 04 and minimal changes to Reg Guide 1.233 from the 16 drafts, we requested, and ACRS agreed not to do 17 further review.
18 Onto slide four, on the public comment, I 19 view the comment to kind of be in two different, but, 20 closely related issues. The first is on the actual 21 frequency consequence curve, Dr. Denning observed that 22 the use of a complementary cumulative distribution 23 function would enable applicants, designers, and the 24 staff, to see the contributions of event sequences to 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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15 the integral risk since the CCDF, the complementary 1
cumulative distribution function is a way to look at 2
the integration of the risks.
3 The other part of the concern, again 4
somewhat related, is that looking as licensing 5
modernization project does in the NEI-18-04 and Reg 6
Guide 1.233, at individual event sequences and making 7
judgments on individual event sequences, that process 8
might introduce variability and flexibility to 9
analysts that would change where the event sequence 10 was plotted in terms of frequency, and that might 11 bring up an issue of, again, variability between 12 analysts, or even the ability to continually subdivide 13 event sequences in order to try to reduce the estimate 14 of the event frequency. So we looked at that comment.
15 MEMBER KIRCHNER: I'm sorry, John. Bill?
16 I'm sorry, John, 17 CHAIR BLEY: Mr. Kirchner?
18 MEMBER KIRCHNER: Yes, sorry, Dennis, this 19 is Walt Kirchner. May I ask a question of Bill?
20 CHAIR BLEY: Sure.
21 MEMBER KIRCHNER: Bill, just for the 22 record, would you - I think I get it, but would you 23 define what a complementary cumulative distribution 24 function is in this situation?
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16 MR. RECKLEY: I'll give it an attempt and 1
then Marty Stutzke, if you're on the line, please come 2
to my rescue through the phone-a-friend option here.
3 But I think the public comment included this figure, 4
which I think is a good way to consider how that would 5
be used. Now this is plotting two different licensing 6
basis event plots. One in red, and I'm on slide 11 as 7
a backup slide. One in red for the first event, and 8
one in blue for the second event, and you can see the 9
contributions of the uncertainties as you plot that 10 over both frequency and consequence. The licensing 11 modernization project, NEI 18-04 methodology would 12 look - if those events were not part of the same 13 family, might look at those two events separately for 14 comparison to the frequency consequence target.
15 The complementary cumulative distribution 16 function would also look at them individually, but 17 also integrate those two events and all of the other 18 licensing basis events to give you the black line 19 which would give you the integrated risk for all the 20 LBEs. Marty, if you're on, can you maybe go a little 21 deeper?
22 MR. STUTSKE: Yeah, Bill, this is Marty.
23 Can you hear me?
24 MR. RECKLEY: Yes, thank you.
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17 MR. STUTSKE: Yeah, this is Marty Stutske, 1
I'm the senior technical advisor for PRA in NRR DANU.
2 The frequency consequence target used in the LMP is 3
nothing more than a scatterplot of PRA results where 4
the x-axis being the consequence, and the y-axis being 5
the frequency. So it's true, you're comparing 6
individual sequences against the limit line up there.
7 In contrast, a complementary cumulative 8
distribution
- function, the y-axis becomes an 9
exceedance frequency. So what you do then, is you 10 pick a consequence and you say what is the frequency 11 of the sum of the frequencies of all of the sequences 12 that have a consequence greater than or equal to your 13 x-axis value.
14 MR. CORRADINI: Marty? Marty?
15 MR. STUTSKE: Yes.
16 MR. CORRADINI: So I guess, I think I 17 understood why the y-axis is different. This is 18 Corradini. But I'm confused as to why there is a 19 series of points for any one LBE. I thought, unless 20 this is a uncertainty example for the red and the blue 21 line, but isn't there for a given LBE, an estimate of 22 a frequency and an estimate of a consequence? Or why 23 is it a family of points?
24 MR. STUTSKE: Okay, yeah, let me be clear.
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18 You're right. There should be one dot for each event 1
sequence family.
2 MR. CORRADINI: Okay.
3 MR. STUTSKE: With a consequence and a 4
frequency. So when you take the entire PRA results, 5
it's however many event sequence families you have is 6
the number of dots on the graph.
7 MR. CORRADINI: So why are the red and the 8
blue showing six dots for every LBE? That's what I 9
didn't understand with this.
10 MEMBER KIRCHNER: I think, Mike, it's 11 multiple, within a family of events that are similar, 12 it's multiple events. That was my takeaway from this.
13 MR. STUTSKE: Oh, so this is not one LBE, 14 this is a family of sequences.
15 MEMBER KIRCHNER: That's what I think. I 16 don't know what poly means on the graph, but that was 17 my sense. You got one set of events that are similar 18 and you look at them and you get a curve from each 19 individual event.
20 MR. CORRADINI: Okay.
21 MEMBER REMPE: So when we, like, this --
22 CHAIR BLEY: Richard Denning is on the 23 line, he can clarify it.
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19 okay if I clarify? So if you interpret the former 1
curve there as a limit on the complementary cumulative 2
distribution function, it limits risk. That is, if 3
you integrate the curve against the y-axis, it 4
identically tells you what the total risk is. In the 5
interpretation that is in NEI 18-04, you don't limit 6
risk. You could, for example, have at one rem, you 7
could have a thousand sequences that each individually 8
satisfied the one rem, and would clearly have an 9
unacceptable risk. Okay?
10 Whereas, if you interpret it on the 11 complementary cumulative distribution function, you 12 actually limit the risk. Okay, you don't have this 13 ambiguity of where you could look at it, at a LOCA, 14 for example, and divide it if you wanted it to, into 15 five different kinds of LOCAs. If you've got to 16 consider a single point you also must consider, as is 17 done in NEI 18-04, you also have to consider some 18 uncertainty about that, right? Because we don't know, 19 in any event, you have to consider what's the 20 variability or uncertainty, and we will get into that 21 in detail.
22 So what's done here with a complementary 23 cumulative distribution function is you consider an 24 uncertain distribution around a particular kind of 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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20 event like LOCAs, okay, and then you also, in order to 1
satisfy a level of risk, you then develop the 2
complementary cumulative distribution functions for 3
the total. And that's what that dashed black line is.
4 So you know that you have limited the risk of all of 5
the LBEs by taking into account the complementary 6
cumulative distribution function.
7 MR. MOORE: Excuse me, excuse me. I think 8
Member Rempe has been trying to say something.
9 MEMBER REMPE: Well, thank you, Scott.
10 When we discussed this with Karl Fleming, my 11 understanding is that if you had two sequences that 12 are 10 rem, or a 10 rem and a 12 rem in the group, the 13 analyst is obligated to pick the 12 rem, and then 14 multiply the frequency by two, so you eliminate the 15 gaming that could be performed by the analyst.
16 This has been discussed in some of our 17 prior meetings, and you are supposed to consider 18 uncertainty distributions in the consequences, as well 19 as the frequency, if you're going to accurately apply 20 this. And Dennis, maybe you can speak up too, but we 21 have mentioned this concern about gaming in the prior 22 discussions. Now, what I don't remember, and maybe 23 Bill Reckley or Marty Stutzke can tell me too is, did 24 that concern get put into the final documentation?
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21 Because this is not a new problem.
1 MR. RECKLEY: There's not a specific 2
mention except for referencing the ASME/ANS non-Light 3
Water Reactor PRA standard that talks about the 4
processes to be used. You're right in that this 5
particular issue has been talked about as part of 6
NGNP, and even before that, as part of the 7
methodology. The other thing that, going back to 8
slide six, no, slide five, in our disposition, is that 9
we don't want to come across the staking issue with 10 the proposal in the public comment. The use of 11 complementary cumulative distribution functions is a 12 good idea, it's actually mentioned in the non-Light 13 Water Reactor PRA standard as a methodology to look at 14 cumulative risks and to make sure that, as Dr. Denning 15 mentioned, you don't focus singly on specific event 16 sequences, but you're also looking at the aggregate or 17 total risk. That's handled within NEI 18-04, and the 18 Reg Guide by including separate aggregate or 19 cumulative risk measures against the NRC safety goals.
20 For example, that's the primary one.
21 That's a way to do it to also make sure 22 that you don't forget about the total risk. So there 23 would be advantages to using the CCDF. We looked for, 24 going on to slide six, one has to consider what the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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22 methodology was actually developed to do. In the 1
context of the Reg Guide we try to make clear that, 2
actually, even the target figure, the frequency 3
consequence target doesn't correspond to regulatory 4
limits. It is instead a tool that would help us do 5
the primary objectives of this methodology, which is 6
to identify the event sequences. This may go a little 7
bit to what you were mentioning earlier, Dr. Bley, of 8
whether there's enough guidance on how you identify, 9
and especially how you look at various, you know, 10 internal and external hazards. But we can have that 11 discussion as we go forward.
12 The methodology also, by looking at the 13 margins, and the impact of assuming various failures, 14 supports looking at the safety classification and the 15 performance criteria that would be set up for both 16 safety-related and non-safety related with special 17 treatment structure systems and components. And then 18 it supports a general evaluation of defense in depth.
19 Getting to Dr. Rempke's issue about 20 looking at event sequences and trying to make sure 21 that one would not game the system, if you will, we do 22 look, you have to look at the methodology and how it's 23 used. It has an emphasis on function and system level 24 evaluation. So that provides a certain degree of 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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23 comfort. You also have the various reviews that would 1
be done as part of the PRA standard. The reviews of 2
the applicant and the designers themselves and then 3
the reviews by the NRC.
4 For those reasons, the staff continues to 5
think that the methodology described in 1353 and 6
subsequently the Reg Guide, is one acceptable way.
7 Going to the back of --
8 CHAIR BLEY: Bill? Bill? This is Dennis.
9 Let me jump in a second. I'd like to summarize a 10 couple things if I can, and then have you go ahead.
11 Kind of everybody who's spoken is right, and I want to 12 thank our former member, Rich Denning, for coming in 13 on the meeting today, I appreciate it. And I 14 mentioned that the coauthor of his comments, Vinod 15 Mubayi, was one of the primary authors of this area in 16 NUREG-1860, so well qualified. I think most PRA 17 practitioners, you know, they're generating a CCDF at 18 the end which is, as Marty well-described, an 19 exceedance plot which summarizes the overall results, 20 and, of course, that's a good measure.
21 I was reasonably comfortable with what was 22 proposed in the NEI document and that the staff has 23 supported because it does have this fallback of an 24 integrated risk measure included. So the idea is 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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24 covered, and back to Joy and her discussion of Karl 1
Fleming's area. I think this is an area where if this 2
is going to become a rule then the guidance probably 3
needs to be clarified a little better on this idea of 4
families to avoid the problem. That's a problem 5
that's kind of everywhere, and looking at PRA results, 6
one has to be careful to understand how those 7
scenarios have been broken down. But maybe the 8
guidance there could be cleaned up a little bit. I 9
think at this point, Bill, go ahead. You've got your 10 actual target curve up here.
11 MR. RECKLEY: Well, and we can use it for 12 questions. I was just going to make one last comment 13 on the concern about frequencies and being able to 14 potentially, continually try to subdivide in order to 15 lower a frequency. And this is a practical 16 observation. It's not really built in, necessarily to 17 the process as a counter to that but just for the 18 committee members to be aware, our expectation is that 19 most designers are going to adopt a design objective 20 of making sure that all the design basis events and 21 beyond design basis events, don't exceed one rem or 22 some other measure in order to take advantage of 23 things like the Emergency Planning Zone Rule or the 24 siting, the population-related siting paper that we 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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25 brought to the committee a little while ago.
1 And so as you as make that line a straight 2
line at one rem, or again, some other measure if we 3
pick it up, but it also is kind of a guard against 4
just trying to lower the thresholds. Again, it's not 5
a perfect system, but it is just a practical limit 6
that you don't gain very much by lowering your 7
frequency of all of the frequencies from 10 to the 8
minus 2 all the way down to the lower threshold is 9
using the same consequence measure of one rem. I just 10 want to make that observation.
11 So again, we did appreciate the comment 12 and again, from the staff's viewpoint we were 13 presented with a methodology and asked to make a 14 determination of whether that methodology was good 15 enough. It wasn't a decision as to whether there 16 could have been things that could be added. My own 17 observation is that if we were to pick up CCDF, again, 18 it would be most likely in addition to the 19 methodology, and as we said, it might be a very good 20 addition. It's already mentioned in the PRA standard 21 as a way to look at the cumulative risk.
22 But in order to do the other objectives of 23 identifying the events and safety classification, you 24 would probably also be looking at individual events 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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26 using the same curve or a different curve. If we went 1
down this route we would have to make all of those 2
decisions, but the decision we were asked to make was 3
whether what was proposed in NEI 18-04 was a workable 4
methodology, and we think that it is, and that's what 5
we reflected in our disposition of the comment.
6 Just in terms of updating, the last slide 7
here is just the Commission SRM on SECY-19-0117.
8 We'll get into this discussion also a little bit in 9
the Part 53 topic we're about to pick up, but the 10 commission generally endorsed this, and then also 11 reminded us in that last paragraph that the safety 12 goals and other established commission policies and 13 regulations related to safety and risk metrics are 14 applicable to advanced reactor in general, and then 15 how we would build that into the framework.
16 CHAIR BLEY: Thanks, Bill. This is Dennis 17 again. Two things, one I got knocked off the Skype 18 meeting for about a minute, which is okay, Dave 19 probably didn't even notice that happened. I 20 appreciate we've had a good discussion on this, and I 21 wanted to let that go as much as we could. At the end 22 of this meeting I'm going to ask the members to 23 consider whether we want to or need to have that 24 October full committee meeting. And I think the real 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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27 key to that is if we want to write a letter since all 1
but one of us is attending today. So keep that in 2
your minds for the end of your meeting. There are a 3
few of these issues that we might want to give a 4
heads-up early on, and that would be the only point, 5
and to let the commission know we're following this.
6 Please continue. Thanks.
7 MR. RECKLEY: Okay. So kind of along that 8
path, and switching topics a little bit, using slide 9
eight, just to talk about some of the future 10 interactions and getting to what Dennis was 11 mentioning. There's a fair number of topics on here, 12 so we will have to coordinate our interactions with 13 the ACRS and then when ACRS responds via letter, would 14 be appropriate. And when we get into Part 53, I think 15 we have some flexibility, but whatever would be the 16 most useful we can decide during that discussion.
17 So just going quickly, you're aware there 18 are design-specific applications that the ACRS will 19 need to weigh in on, and some others that they'll be 20 given the option to weigh in on, things like topical 21 reports. The remaining discussions today will be on 22 Part 53. As Dr. Bley mentioned, we did commission a 23 couple reports on mechanistic source term, and once 24 you have an opportunity to read those we can decide 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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28 what interactions would be requested.
1 I'll give you a warning ahead of time, 2
these are fairly high level discussions. Although 3
they might include examples of technologies, the two 4
reports we provided were not aimed at how do you 5
develop a mechanistic source term for a reactor 6
technology of x, y, or z. It was a kind of high-level 7
process for what needs to go into developing source 8
terms.
9 CHAIR BLEY: Bill? Excuse me. The last 10 indication we had was that you are also developing a 11 Reg Guide related to this. Is that still true?
12 MR. RECKLEY: I'll let John weigh in. At 13 this point we may as we go further down and see what 14 the reaction is to these reports and whether it 15 warrants going to the next step of issuing an actual 16 Regulatory Guide, or if we start to look at individual 17 technologies, whether it makes more sense to have a 18 Regulatory Guide that would follow up.
19 We also have some technology-specific 20 reports. Oak Ridge is doing some work, Molten Salts, 21 Argonne and Idaho on fast reactors and gas-cooled 22 reactors. So one of the discussions maybe we could 23 have during a committee meeting is where would 24 regulatory guidance in the form of a Reg Guide 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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29 actually be the most useful.
1 CHAIR BLEY: Okay, thanks, yeah, we'll 2
look forward to pursuing that with you. Go ahead.
3 Well, before you go to your next bullet, John 4
introduced the next bullet, and if you can say a 5
little more about what you're talking about here with 6
this TICAP thing, I'd appreciate it.
7 MR. RECKLEY: Sure. Okay, so we mentioned 8
in Reg Guide 1.233, kind of as a predictor, that we 9
will need additional guidance. At this point we have 10 two Reg Guides specifically for advanced reactors, and 11 one of the ones that we thought would be useful is to 12 go into more detail on actually what goes into an 13 application.
14 So that is the content of applications 15 discussion. We've broken that into two parts. The 16 first part is the unplanned event portion of an 17 application. So if you think traditionally, this 18 would be FSAR Chapters 15, the safety analysis.
19 Chapter 19, the PRA assessments, as well as the 20 discussions of individual systems and their roles in 21 addressing those unplanned events. Also some of the 22 work in the early FSAR chapters on hazards, external 23 hazard assessments, for example.
24 So the unplanned event portions of an 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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30 application is what is included in TICAP, and it's a 1
significant part of a safety analysis report. We are 2
working with kind of a coordinated effort that's 3
similar to licensing modernization, as John mentioned.
4 There's a DOE-cost-shared initiative with industry, 5
and we expect to get a guidance document from NEI that 6
would take and build upon NEI 18-04 to say, from that 7
methodology, this is how you transfer it into a FSAR.
8 One example would be a safety-related system would get 9
this amount of detail in a discussion. This is what 10 would need to be described for a non-safety-related 11 with special treatment kind of SSC. This is how the 12 performance criteria would be established and 13 monitored, for example. So that's the TICAP portion.
14 MEMBER REMPE: Bill, this is Joy. Can I 15 interrupt you?
16 MR. RECKLEY: Sure.
17 MEMBER REMPE: I was planning to bring 18 this up in the next part of the discussion, but I 19 can't resist here. When we first started doing this, 20 most of us, as I had envisioned, you'd have reactor 21 where you put fuel in it at the site, and then you 22 take the fuel out and you, at some day dispose of the 23 vessel or whatever. Nowadays we're talking about 24 bringing a loaded core to the site, and maybe you do 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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31 a few things once you get there, but then after you 1
run the reactor you take the loaded core someplace 2
else.
3 Is your vision considering this not only 4
for how you're going to select the licensing basis 5
events, but also the content of the application?
6 Because you might have more risk with this 7
transportation issue than you do with the actual 8
operation of a small modular reactor.
9 MR. RECKLEY: Yeah. And the next-to-the-10 last bullet on microreactor issues, for example, one 11 of the things we'll have to do, and we'll have to work 12 with industry on what is the content of their guidance 13 under TICAP, and how far are they going to take it to 14 address the issues that you just mentioned. If that's 15 not picked up as part of that effort, we could pick it 16 up in the subsequent discussion, which is things that 17 we're putting under advanced reactor content to 18 application, or issues that are not picked up with the 19 unplanned event.
20 I don't believe that TICAP would probably 21 pick up transportation, for example. So maybe we need 22 to pick that up in advance reactor constant to 23 applications. We may be able to take large advantage 24 of existing guidance on transportation containers and 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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32 guidance and requirements, but we will have to make 1
that assessment.
2 So this has a lot of moving parts, as 3
you're hinting at, and exactly where any particular 4
issue lands, we are still kind of working out and 5
coordinating. But we do have them all on the radar 6
screen.
7 MEMBER REMPE: Yeah, because even, you 8
know, licensing basis event may not just be when the 9
reactor is sitting there running, and so yeah, I think 10 we need to broaden our perspective. And I'm glad to 11 hear that the staff is thinking about it even if we 12 don't have an answer yet.
13 MR. RECKLEY: Okay, thank you. And Walt?
14 I think somebody?
15 MEMBER KIRCHNER: Yes, Bill, this is Walt.
16 It would seem to me, Bill, one area that would in your 17 guidance -- I'm seeking some clarity in the use of 18 terminology. Let's start with safety-related versus 19 non-safety-related or whatever, or not safety-related.
20 For example, often we are presented in presentations 21 from the staff, we have safety-related, not safety-22 related, and then important to safety, not important 23 to safety. So sometimes that framework is used, and 24 then sometimes what we hear is it's safety-related or 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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33 not safety-related, risk-significant, not risk-1 significant, and so on.
2 So given that this is more of a risk-3 informed approach, it seems to me some clarity is 4
needed in terminology and definition so that when it 5
comes time to break down, not the contents of the 6
application, but the contents of the reactor design 7
itself, and classify SSCs, I think this is going to be 8
a real challenge for you going forward.
9 MR. RECKLEY: We agree. Actually, when we 10 get into the Part 53 questions, one of them goes 11 exactly to terminology because as you mention, within 12 the existing Part 50 and 52, there are definitions.
13 And those were clarified in various papers regarding 14 important to safety, they were also then further 15 enhanced under the passive
- reactors, and the 16 introduction of RTNSS, Regulatory Treatment of Non-17 Safety Systems. And then 50.69 has its own categories 18 that you mentioned that are based on risk 19 significance. And you have all of that history under 20 Part 50, and then what we ultimately did under Reg 21 Guide 1.233 was introduce yet another set of 22 terminology.
23 MEMBER KIRCHNER: I know. That's my 24 concern.
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34 MR. RECKLEY: Yes.
1 MEMBER KIRCHNER: I think clarity here is 2
needed.
3 MR. RECKLEY: Right, and I think we've 4
talked about this in our past interactions, was that 5
that is a challenge. We're expecting under Reg Guide 6
1.233 that anybody that uses the methodology adopts 7
the terminology out of NEI 18-04, but we do realize 8
that sets up a different definition and a different 9
discussion than maybe a similar design that would pick 10 it up under Part 50. And we've tried, and I don't --
11 any suggestions would be appreciated.
12 CHAIR BLEY: This is Dennis again.
13 Thinking about this TICAP and about Part 53 as well, 14 Mike Corradini often says, you know, work the problem 15 backwards. What's, you know, kind of to the old 16 style, what's the worst thing that could happen to 17 this? And you've got some documents that hinted that 18 it would seem that the content of applications and the 19 depth of applications ought to be linked to the worst 20
-- kind of the worst things that could happen, 21 especially when we start thinking about some of the 22 microreactors, which I assume would be under this same 23 umbrella, so there needs to be some kind of scaling 24 that's built in based on the kind of maximum source 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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35 term one would be dealing with. Is that part of what 1
you're planning?
2 MR. RECKLEY: Yes, in that Reg Guide 1.233 3
mentions that people might want to take an approach 4
like a maximum hypothetical accident approach. We 5
have had some discussions with individual designers 6
that are using or contemplating using that kind of 7
approach. One of the things, and it's all related, as 8
you mention, but maybe when you look at the 9
mechanistic source term documents that if an applicant 10 is able, or a designer is able to show that hazard 11 just is not able to put the radionuclides on a path 12 for release because they're retained within the fuel, 13 or maybe the first and second barriers, we've said 14 we're amenable to looking at those kind of approaches 15 if they can demonstrate them. It might be a big if, 16 but that's from a process-wise, we'd be open to it if 17 they can show it. And that kind of approach is used, 18 for example, in some of the research and test 19 reactors.
20 MEMBER KIRCHNER: Bill, this Walt Kirchner 21 again. On this topic, this is another area where I 22 find some clarity is needed. Source term has 23 different meanings for different people or applicants, 24 I would guess as well.
25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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36 The traditional source term if you're 1
going through the 10 CFR 50 and 52 process, is to 2
hypothesize a maximum creditable accident no matter 3
what, and then use that as the quote-unquote "source 4
term." Now any reactor that's operated by definition 5
is going to have fission product inventory buildup.
6 Depending on the fuel type used, that may be a hazard 7
in and of itself without operation, et cetera.
8 So there is always, with any advanced 9
reactor, or any micro-reactor, or any large reactor, 10 there always is a hazard. There seems to be -- I 11 think you're going to be presented with arguments that 12 we don't have a source term. And when people say that 13 they're thinking of 10 CFR 50 and 52. But clearly, 14 any reactor that's operated, builds up fission 15 products and hence presents a hazard, and that's what 16 the NRC has to assure, the adequate protection of the 17 public. So that it seems to me that you're going to 18 run into a lot of arguments about source term.
19 MR. RECKLEY: Yes. And it's sometimes, as 20 you mentioned, a terminology issue. They have an 21 inventory, obviously, and I think maybe when you look 22 through mechanistic source term papers you can see 23 we're trying to get the discussion about where are the 24 inventories and how are you controlling them or 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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37 inhibiting their release as being the topic, as 1
opposed to, as we have for Light Water Reactor saying 2
the source term is what is put into the containment 3
and then model the containment for what is the public 4
dose. So I think we'll continue to have some 5
terminology challenge as we go through.
6 In general, for non-Lights, the source 7
term as we're using it is actually what leaves the 8
last physical barrier. In other words, if you're an 9
analyst, what would you input into your atmospheric 10 dispersion code? But again, that's different because 11 we're now saying it's on the other side of the last 12 wall, if you will.
13 MR. CORRADINI: Bill, is that any 14 different than TID 18.444 and the original approach to 15 Part 100? It's essentially the same thing.
16 MR. RECKLEY: Well, it's somewhat the 17 same. It's just, again, it's largely in my view a 18 terminology issue. The source term as it was defined 19 in TID and NUREG-1465 is the radionuclides that are 20 put into the containment, and that's what's called 21 source term. And then you model it for what gets out 22 of containment, and then you model it for how it's 23 dispersed.
24 Since the role of a physical containment 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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38 structure might vary and as the discussion went, as 1
Dr. Bley mentioned, one of the first papers we did was 2
the functional containment paper, the source term as 3
we use that term, is now the radionuclides that are 4
past the last physical barrier.
5 MR. CORRADINI: Okay, good point. I'm 6
sorry, you said it much more clearly.
7 MEMBER PETTI: So Bill, this is Dave 8
Petti. It just seems that with all, even just the 9
discussion among the committee here, that some sort of 10 a document from NRC, some sort of guidance is 11 necessary to help people understand what the rules of 12 the road are. My view is there may be more than one 13 way to get to a source term, to lay out, sort of, some 14 options, but at least try to remove some of the 15 confusion that could exist, but out of such guidance.
16 I think there will always be questions, but I think 17 without guidance you'll have even more and it will 18 just take longer to, you know, to get everybody 19 through the process.
20 MR. RECKLEY: Okay, thanks, Dave. And 21 we'll finish this up and then move into Part 53, which 22 will be another opportunity for us to try to clarify 23 all of this. The other thing, and this is just an 24 additional complication, is it will also matter what 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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39 you're doing that assessment for. And we may approach 1
in the future where, from a licensing standpoint, you 2
can do as Dennis mentioned, and have some very - try 3
to avoid the term - but very conservative assumptions 4
that would go in and basically say for licensing 5
purposes we're taking a simplified approach because we 6
think we can maintain the inventory or prevent the 7
inventory from release, whereas if you're doing a more 8
best estimate, an actual analysis, you may have to go 9
into more detail.
10 And a designer might need to do that for 11 other reasons, like occupational dose or economic 12 reasons, to do more detailed assessments of where the 13 radioactive material might end up or might present a 14 challenge, even if you can show with high confidence 15 that it's not going to get out of the facility. So 16 this is all, you know, it's all a complicated endeavor 17 on the part of both the designers and us to try to 18 navigate.
19 MEMBER KIRCHNER: Bill, this is Walt 20 Kirchner. Sorry for the frequent interruptions. No, 21 I'm not sorry; I apologize. The one thing that was on 22 one of your earlier view graphs and also you had 23 presented in past meetings, I don't think on the 24 tabletop exercises conducted today, people went 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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40 completely through the defense in depth part of the 1
exercise. And I'm wondering what guidance you're 2
going to provide to get out of one person's judgement 3
versus another on what is sufficient defense and 4
depth.
5 How are you going to generally kind of 6
wrap that part of this up in terms of guidance? When 7
is enough, enough? When is, for example, just no 8
matter what, you know, we had a former member who 9
would say I just want an essentially leak-tight 10 containment, period. And that's, of course, also 11 subject to definition, but you get my point that, you 12 know, in the final analysis, you've done all this and 13 so on, but defense in depth, when is enough, enough, 14 and how do you decide that?
15 MR. RECKLEY: Right, and other than trying 16 to follow through with the process that was laid out 17 in NEI 18-04 and the Reg Guide, that's currently where 18 we are. There is, as you mentioned, a certain 19 subjective element to that, engineering judgment 20 element to that, that will maintain.
21 How we decide when is enough, enough gets 22 complicated because going back to the backup slide on 23 slide ten, what we expect is that designers are going 24 to come in and try to utilize the margins that are 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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41 available to them through the designs in order to get 1
flexibility somewhere else, like emergency planning 2
zones is the common example, or population related 3
siting considerations we talked about a couple months 4
ago. Or there will be something else.
5 The last bullet on future interactions is 6
staffing.
7 CHAIR BLEY: If I might interrupt yet 8
again. I think, Bill, the most challenging area where 9
a designer will want to use margin is cutting down on 10 the number of systems that are safety-related because 11 there's an economic cost associated with that.
12 MR. RECKLEY: And we -- yes.
13 CHAIR BLEY: That's where I think you'll 14 run into the problem, yes, on emergency planning and 15 so on, but that one probably becomes where the 16 designer first tries to use the margin that he or she 17 believes they have versus the consequence curve, the 18 frequency consequence curve.
19 MR. RECKLEY: Right. Yeah, and a lot of 20 that will be -- within this methodology I think it 21 provides the opportunity to hopefully give the 22 designer the ability to come in and say, We're gonna 23 add this system for defense and depth. The 24 methodology as it stands would generally allow that to 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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42 be done without making it safety related. Go ahead, 1
Dennis.
2 CHAIR BLEY: This is for Walt and others.
3 This is a place where I felt NEI 18-04 made a good 4
step beyond what was in 1860 15 years ago. They 5
really laid out a structured approach for looking at 6
the defense in depth issue and considering various 7
different approaches to that. It's one area where, at 8
least the last time we talked, the tabletops hadn't 9
fully exercised this methodology, and I guess I'd sure 10 like to see that at some point. This is an area we 11 might dig into in a future meeting somehow.
12 MR. RECKLEY: Right, okay. The other part 13 of it is we will see as it gets exercised, and that 14 will be where we need to remain agile enough to see 15 that some of this work that's going on in parallel, if 16 you keep track of it and incorporate any lessons, both 17 from the application of this in designs like Kairos, 18 and you guys were looking at some of those topical 19 reports, or a different committee is, we're going to 20 be watching how it's applied to the versatile test 21 reactor. They're going to use this kind of 22 methodology. So we will keep an eye on it.
23 Trying to finish this up, and all of this 24 is a great discussion, and it feeds right into Part 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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43 53, that we're going to get into next so I don't think 1
that we're really getting behind because a lot of this 2
is the same discussion.
3 So I tried to explain what TICAP was, 4
that's the unplanned events portions of a safety 5
analysis report. There would be other guidance on 6
other things outside of the final safety analysis 7
report, sections on unplanned events, the normal 8
effluents, for example, technical specifications.
9 There's some interest in additional 10 guidance on what goes into a construction permit under 11 Part 50 because it's been a long time since we've 12 looked at a Part 50 construction permit, especially 13 for a reactor design that's significantly different 14 than large light waters. The next to the last bullet 15 I mentioned.
16 There is a
pending SECY paper on 17 microreactor issues, and then out of that paper the 18 gist is an information paper that identifies various 19 issues, including the fact that micros might be 20 deployed differently and might bring up issues like 21 transportation and manufacturing even more so than 22 what we've dealt with to date.
23 Out of that paper we expect other policy 24 papers, and one that we're just beginning the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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44 discussions internally, is on staffing, and questions 1
like if a reactor can show inherent features, can 2
those features negate the need for licensed operators.
3 Would it be possible to go to autonomous operations 4
either through digital systems or inherent mechanical, 5
physical attributes, remote operations.
6 So all of these questions, we're just 7
beginning to discuss what would go into a future paper 8
on staffing, and it may be one or more of these 9
issues, depending on the timing and the applications 10 that we get in and the feedback we get from industry.
11 So I guess all of this --
12 MEMBER REMPE: Bill, this is Joy.
13 MR. RECKLEY: Yeah?
14 MEMBER REMPE: And I didn't interrupt you 15 when I wanted to about the construction permit 16 application, and what's required. You do have an 17 ongoing effort with the SHINE Medical Isotopes effort, 18 and there's a lot of coordination going on in the 19 staff because I think that's a good example that could 20 shed some light.
21 MR. RECKLEY: There is, and I'm sorry I 22 should have mentioned that. Yeah, we're looking very 23 closely at what was done to issue that construction 24 permit and then as they enter the next phase, how you 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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45 go from the construction permit review, over to the 1
operating license review. So thank you. Yes?
2 MEMBER REMPE: Thanks.
3 MR. RECKLEY: So the Part 53 discussions 4
in a different slide presentation, Dennis, are we 5
ready to jump into that one?
6 CHAIR BLEY: It's not. I'm going to call 7
a break at this point, and I think you're right. I 8
think we've made a lot of progress through some of 9
the, at least background material, and even some of 10 the questions in the Part 53 discussion. Maybe when 11 we start there you can go through the first few slides 12 pretty quickly because I think you already talked 13 about many of them.
14 Let's take a break. It's ten 'til. Let's 15 come back at ten after. What will that be back east?
16 That will be ten after 9:00 here. Ten after 11:00 17 east coast time. And we'll go right through, and if 18 we need it, we might take after an hour, we might take 19 a short five or ten minute break then before we finish 20 up.
21 So at this point we'll take a break. When 22 we come back we'll be on the next slide set. If we 23 can get those set up ahead of time. I'll see you back 24 here at ten after.
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46 (Whereupon, the above-entitled matter went 1
off the record at 10:49 a.m. and resumed at 11:10 2
a.m.)
3 CHAIR BLEY: Okay. It's 10 minutes after, 4
we're ready to start again. Bill, will you be going 5
ahead or will it be by Bill?
6 MR. RECKLEY: This is Bill Reckley. I'll 7
continue.
8 CHAIR BLEY: Okay. You're up.
9 MR. RECKLEY: Okay. Thank you. So as we 10 mentioned, some of this I can go through relatively 11 quickly because we talked about it in the last part, 12 including the background. We have considered 13 rulemakings in the past as has been mentioned, the 14 Nuclear Energy Innovation and Modernization Act 15 directed us to do a rulemaking and to have it 16 completed no later than December 2027.
17 To schedule, as Dennis mentioned in the 18 introduction, we don't have a Staff Requirements 19 Memorandum yet. We are aware, and the interaction 20 with Senator Barrasso is a public record that at least 21 a number of senators expressed a desire for us to 22 speed it up. And the Commission in the response said 23 they would give direction to the NRC staff on a 24 schedule. So 2027 is the latest schedule. One should 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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47 not be surprised if we get some encouragement to go 1
quicker.
2 I'll go into that, as Dennis mentioned, 3
maybe with ACRS interactions in a couple slides. One 4
of the things we maybe didn't talk about under NEIMA 5
is their definitions, so on Slide 3, these have come 6
out of the act. Advanced reactors means a nuclear 7
vision or fusion reactor, including a prototype plant 8
that has significant improvements. And then the act 9
lists those in terms of proliferation-resistance, 10 risk, economics, fuel, and a number of attributes that 11 would be an improvement over existing plants, or 12 plants that were under construction.
13 So our working scope with this then is 14 light water small modular reactors, non light water 15 reactors, and fusion reactors.
16 MEMBER PETTI: So Bill, can I ask you a 17 question? What are you going to do about fusion?
18 MR. RECKLEY: There's two thoughts 19 currently. And it's as good a place as any to talk 20 about it because I don't talk about fusion too much 21 throughout the presentation. The first thought would 22 be if you have a risk framework, can fusion actually 23 just be treated like any other reactor?
24 Our initial thoughts are that because the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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48 Atomic Energy Act spells out for production and 1
utilization facilities and their use of special 2
nuclear material, the Atomic Energy Act itself sets 3
out a number of requirements that we would have to 4
fulfill for fusion. And they may not all be needed.
5 We're still assessing, but it may be that although 6
fusion would be addressed through this rulemaking, 7
that there is a distinction made between fusion 8
reactors and those using special nuclear material with 9
a thought that the fusion reactors, if it pans out, 10 might be handled more like -- I won't say exactly 11 like, but more like a materials licensee facilities 12 like accelerators.
13 So we're still just thinking about that.
14 We had planned a workshop with the Office of Science, 15 Fusion Energy Sciences within DOE in March. And 16 unfortunately, that was delayed because of the COVID.
17 We're looking now to have a workshop or a public forum 18 again with the Fusion Industry Association, DOE, other 19 stakeholders in the September, October timeframe.
20 We'll be talking about specifically developing a 21 regulatory framework for fusion within this activity.
22 MEMBER PETTI: So Bill, back in the 90s I 23 authored a DOE safety standard on fusion, and that DOE 24 standard got -- you have to Google it, Safety of 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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49 Magnetic Fusion and Facilities or something.
1 MR. RECKLEY: Yeah.
2 MEMBER PETTI: I want to say DOE 6005.
3 MR. RECKLEY: Right.
4 MEMBER PETTI: The framework is very 5
similar to LMP. We borrow it heavily from, at the 6
time, it was through GA framework. The difference is 7
in the details, right? The nature of the radioactive 8
materials. It's a much more distributed system in 9
terms of hazards because you're pumping tritium all 10 over the place. So there are differences in terms of 11 the details, but I think you probably can fit it in at 12 the high level. You know, they had a frequency-13 consequence curve.
14 MR. RECKLEY: Right.
15 MEMBER PETTI: All of that sort of stuff.
16 So it's just that when you, you know, the devil's in 17 the details. It has to look at it in a different way.
18 But I think there could be a lot of overlap in --
19 MR. RECKLEY: Yeah, I've looked at those 20 and I think you're right. And the part of the 21 discussion might be whether, again going back to the 22 Atomic Energy Act and all it requires for facilities 23 using special nuclear material, whether we would want 24 to encumber fusion with all of those. It may be that 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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50 that's the easiest way to go. We haven't decided yet.
1 And then the other thing within fusion, I 2
think most people are familiar with facilities like 3
ITER, the big facility under construction in France, 4
but we'll have to decide. Fusion has as many 5
approaches because of the isotopes you're able to work 6
with, and the size of the reactor that you might be 7
working with. They are just as varied or maybe even 8
more varied than fission reactors. And so if we're 9
going to try to address all of those, it would be 10 amenable to a risk informed approach like you're 11 mentioning.
12 Then the other definition within NEIMA is 13 for the regulatory framework and the technology-14 inclusive framework. Going down specifically to the 15 rulemaking plan that we submitted to the commission in 16 April, SECY-20-0032. And Dennis mentioned, our first 17 proposal is to develop a new part. That provides us 18 kind of an opportunity we think to as much as we can 19 start with a clean slate and try to construct 20 something that would be the best for a range of 21 technologies.
22 The next slide, I'll just go to the --
23 well the last bullet on this slide is we're expecting 24 extensive interactions with external stakeholders and 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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51 the advisory committee. And so as we get into this, 1
and then hopefully at the end I'll try to go through 2
this all relatively quickly.
Most of this 3
presentation is a list of 14 questions. I don't plan 4
to spend a lot of time on each question.
5 We can go through them and maybe pick 6
which ones might be of most interest. But I think the 7
biggest thing to keep in mind is that this is one of 8
those rare opportunities where we're starting 9
relatively with a clean slate, and we're at the 10 beginning of the process. So how we interact would be 11 important.
12 When the ACRS would decide to send us 13 recommendations, again, we can work that out. I would 14 imagine you would especially want to do that if you 15 thought we were going down the wrong path. So 16 although the 14 questions read as if we are totally 17 from a blank slate, we have given it a little thought.
18 And we use this slide in public meetings to talk about 19 how we thought part 53 might look. And the first part 20 was kind of a decision, and we talk about this within 21 the rulemaking plan.
22 NEIMA does define the framework primarily 23 in terms of licensing. But our assessment was if we 24 overly focused on the first step in the process, we're 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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52 both going to miss an opportunity. And two, it's just 1
very difficult to talk about those first steps without 2
having a good understanding of how the whole project 3
life cycle fits together. And so the proposal in the 4
rulemaking plan is that we go beyond licensing and we 5
build a whole regulatory framework, not just a 6
licensing framework, but a regulatory framework.
7 So how would that work? One of the key 8
things would be to clearly define what are the highest 9
level safety or risk metrics. So what are the 10 fundamental safety functions, what are the metrics 11 like the 5034 criteria of 25 rem over the course of 12 the event at the low population zone. Like the NRC 13 safety goals. How they get worked in in terms of risk 14 metrics, the use of something similar to the frequency 15 consequence targets. And this might be an opportunity 16 to go to something more that would be like a limits 17 exceedance factor.
18 With the emphasis we put before, remember 19 that the frequency consequence targets, NEI 18-04, we 20 have specifically said we are not able to correlate 21 those to existing requirements because existing 22 requirements weren't defined in those terms. And that 23 turned out to be problematic throughout the Next 24 Generation Nuclear Plant project. And so early on, we 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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53 decided in NEI 18-04 that we would ask, and the 1
industry guidance document changed those from top 2
level regulatory requirements to FC targets.
3 Well we're now going to be doing a 4
rulemaking. If we were to decide to put a frequency-5 consequence figure in the rule, that could now then be 6
a regulatory requirement, and you could use something 7
like limit exceedance factors against that curve if we 8
wanted to do that.
9 Then you would also have regulatory 10 requirements just like we do now on normal l 11 effluents. Those things that are in Part 20 and also 12 for light water reactors in Appendix I to Part 50 on 13 normal effluents. And then there'll be other factors 14 that we have to define within the rules, or make sure 15 other rules are there to identify.
16 So once you're able to define those actual 17 risk metrics, safety metrics, the idea was that the 18 rule would then look and say, "What is the role of the 19 various parts of the lifecycle in meeting those 20 requirements?" So at the highest level, the 21 functional design, how are you looking at those 22 performance metrics?
23 Then down to the system level, how are you 24 making sure that individual systems are fulfilling the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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54 metrics?
How do you maintain that during 1
construction? For example, what testing you do to 2
make sure that the equipment actually has the 3
capabilities that were intended to be built in at the 4
functional or system level.
5 Then during operations, how are you doing 6
configuration control, how are you doing surveillance 7
and maintenance, how are you controlling design 8
changes. And then ultimately, what needs to be done 9
during retirement or decommissioning phase to maintain 10 those requirements?
11 So all of this is currently within our 12 framework for the operating fleet. It's just a matter 13 of again starting with a clean slate. This is an 14 opportunity to try to define the role of each one of 15 these project lifecycle parts. And maybe importantly, 16 the relationship of one part to another.
17 And those that have been around for a long 18 time, including myself, much of Part 50 was really 19 aimed at the, at least initially, at that functional 20 and system level design requirements. TMI came back 21 and reinforced some of the importance of operating, of 22 those things that you do during planned operations.
23 And then we did things like the maintenance rule and 24 other things to better define the requirements during 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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55 operation.
1 But the thought is this is an opportunity 2
to look at this as an integrated system. And in some 3
cases, you may be able to benefit by knowing what is 4
going to be required during operations in order for a 5
designer, and just as importantly for us as the staff 6
to say, "In terms of how deeply I look at a design, I 7
can build into that logic what I know will be done 8
during operations to maintain configuration to do 9
surveillance and maintenance." So again, I'm not --
10 this is done now. We're just trying to lay it out a 11 little bit from the very beginning.
12 CHAIR BLEY: Bill?
13 MR. RECKLEY: Yes, go ahead.
14 CHAIR BLEY: Two related questions. This 15 is Dennis Bley. One, your discussion sounds like you 16 already started a white paper on this. So first 17 question is is that true, are we going to see 18 something like that? And then the second question is 19 if you decide to make Part 53 whole and not relay on 20 Part 50 and Part 52, does your thinking lean toward 21 having all of the approaches in 50 and 52? And by 22 that I mean construction permits, early site permit, 23 either a design cert and Combined License or an 24 operating license. Are you thinking about including 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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56 all of those, or have you given all of that much 1
thought yet?
2 MR. RECKLEY: Our working assumption is 3
that we'll address all of those. And then it's just 4
a sentence or two within the rulemaking plan. And 5
then also see if there is something in addition that 6
we might add.
7 In other words, we would plan at this 8
point to support under Part 53 either the traditional 9
two-step CP, construction permit operating license, or 10 any of the combinations that are allowed under Part 11
- 52. And then we're also looking to see if there's 12 anything in addition that we might be able to do 13 beyond that.
14 MEMBER BROWN: Bill, this is Charlie 15 Brown. Can you hear me?
16 MR. RECKLEY: Yes, sir.
17 MEMBER BROWN:
Okay.
Just an 18 amplification of Dennis's question, or a backtrack 19 maybe, under requirements definitions -- you open with 20 that. That's how you kind of lead into this whole 21 picture. Does that mean an examination of like all the 22 general design criteria?
23 Just for information, since I'm a meaty 24 guy as opposed to commercial guy, went through and 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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57 looked at all the GDCs yesterday. And a good bit of 1
those are very, very generic. Does that mean a re-2 examination or a generation of a whole new class of 3
general design criteria?
4 MR. RECKLEY: Excuse me. the general 5
design criteria and then the advanced-reactor design 6
criteria, developed under regulatory guide 1.232, are 7
generally organized around the same fundamental safety 8
functions that we talk about elsewhere. We talk about 9
it in NEI 18-04. It's talked about in various NRC 10 documents, even IAEA documents, talk about basically 11 the fundamental safety functions as being the 12 retention of the radionuclides. That's the ultimate 13 goal.
14 And then the related safety functions such 15 as controlling power level or reactivity, and 16 controlling heat removal, sometimes also introduced as 17 things like controlling chemical attack. That might 18 be important for some design. So I think the notion 19 would be there that we would define within these 20 highest level requirements something analogous to the 21 general design criteria.
22 It may be at that higher level because 23 it's required to be technology-inclusive. So it might 24 talk about the various sections that are now included 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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58 in the GDC. Which again, align generally with those 1
three fundamental safety functions. But yes, there 2
would be something there along those lines.
3 MEMBER REMPE: Bill? Charlie, are you 4
done?
5 MEMBER BROWN: No. Can I finish the 6
question?
7 MEMBER REMPE: Oh yeah, go ahead. I'm 8
sorry. I didn't mean to interrupt.
9 MEMBER BROWN: No, that's okay. Thank 10 you, Joy. You talked about them being a technology --
11 how did you phrase that when you answered me?
12 MR. RECKLEY: Well we use the phrase 13 technology-inclusive.
14 MEMBER BROWN: Yeah. I looked at them 15 from that standpoint and most of them fundamentally 16 address the things you talk about, heat removal, 17 boundaries, radiation requirements, et cetera. So 18 they're pretty technology-inclusive as they are. And 19 it sounds like what you're telling me is that Appendix 20 A would be something all total new if you have an 21 Appendix A.
22 I mean, that's what Appendix A is, is the 23 GDCs fundamentally. So it sounds like you're thinking 24 about generating a new Appendix A with however you 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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59 want to phrase it, with one through whatever they turn 1
out to be. That's the way I got your answer. Is that 2
right or wrong?
3 MR. RECKLEY: I'd say it's kind of early.
4 But I'll just give you my thinking, was that we 5
wouldn't have Appendix A. But this would be within 6
the main body of the regulations. But again, that's 7
largely format to me. Obviously Appendix A is an 8
appendix, but it's one of the most important parts of 9
Part 50.
10 So if you had rolled the GDC into, you 11 know, and gave it a number instead of an appendix, it 12 would be largely the same. But the level of detail 13 and how far you go down in those system level 14 requirements will be one of the things that we talk 15 about. And again, we're just -- we're pretty much at 16 the outlying stage at this point.
17 And I don't even want people to over think 18 where we are right now because we're still open.
19 We've been giving it a little thought because we had 20 the time to do so. But as we'll get into the 21 questions, we're really amenable to receiving 22 suggestions that would propose something different to 23 us.
24 CHAIR BLEY: I'd remind you of something 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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60 Bill sort of reminded you of. A couple years ago, or 1
three, we went through the advanced-reactor design 2
criteria and went through those same discussions. And 3
that's probably where they're starting. I'd take one 4
second to, you know, a couple seconds to fill in a 5
little history. Because we thinking of tech specs and 6
design criteria as always being there.
7 Originally, there were no such things and 8
because people started getting construction permits 9
and then coming in with designs that didn't quite meet 10 the staff's expectations, these things developed to 11 kind of warn people where they needed to go after the 12 construction permit.
13 And then I think Joy had something she was 14 trying to get in.
15 MEMBER REMPE: Yes. I actually like this 16 figure as a layout. And I'm hoping that it's 17 preliminary, but when I looked at it, this is where I 18 wanted to bring up scope. I had already mentioned 19 about transportation to and from the site. It seems 20 like embedded in this figure is that you're only at 21 the site.
22 So maybe you can think of a way to adjust 23 it to consider that. The other thing is since you got 24 the issue of retirement, waste generation comes in.
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61 Dave mentioned fusion earlier today. My understanding 1
is you get a lot more activated materials. Even the 2
gas reactor, because of its low power density, has a 3
lot more low level waste. But maybe we ought to start 4
thinking of the whole lifecycle and what -- we might 5
end up with some different thoughts about what might 6
be of more concern with some of these designs.
7 And so have you thought about maybe 8
modifying this figure, or are you open to maybe 9
thinking about modifying it to more explicitly 10 indicate to the public that you are considering some 11 broader scope than what we have with the existing 12 fleet?
13 MR. RECKLEY: Yeah, we would be amenable.
14 And some of what you said -- again, we're kind of 15 early in the process, but some of the things like the 16 waste and the decommissioning, we currently have a 17 rule -- and I'm going to, I forget the number --
18 under Part 20, that even as you do the initial design, 19 you think through minimizing contamination to support 20 decommissioning.
21 So that would be under normal ops and 22 performance criteria or other over there in the purple 23 box that we would need to put that in as the attention 24 continues to increase on micro reactors. How this 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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62 fits in and either we incorporate things into this to 1
support things like transportation or we at least have 2
a good connection between the requirements here and 3
then the requirements on the transportation side of 4
our regulations.
5 And they would be different. Obviously 6
when you roll a new micro reactor out of the factory, 7
your concerns on the transportation will be different 8
than when you retire it and need to transport it 9
somewhere else. So yeah, we're amenable to any of 10 these discussions. And really what we'll be looking 11 for as we go through this is, in large part, make sure 12 we don't miss anything within this framework.
13 MEMBER KIRCHNER: Bill, this is Walt 14 Kirchner. I'd like to go back to Charlie's 15 observation and concur. And to just point out that 16 rather than relegate it to an appendix if it, like you 17 said, a part of it's just format. But if it's a 18 number's part of 53, probably better. But capturing 19 at least at a high level those principles, categories 20 and principles in the actual regulation I think is 21 important.
22 One of the things that the GDCs do is that 23 they -- this is going to sound a little strange, but 24 it makes the regulatory process much more predictable.
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63 By which I mean the staff uses the GDCs for their 1
determination of the performance of a system, the 2
performance of the reactor as a whole. And this 3
provides predictability in the regulatory review 4
process.
5 The expectations are clear up front and 6
the framework of the GDCs provides a structure for the 7
staff to conduct its reviews as reflected in 0800, the 8
Standard Review Plan, in great, great detail. I'm not 9
proposing 0800, but it allows them to -- you want to 10 be technology-inclusive and at the same time flexible 11 because there are such differences in the designs that 12 we expect that you will be reviewing in terms of 13 technology choices and specific issues with each of 14 those technologies. But it avoids what I'll call the 15 arbitrary and capriciousness of other reviews, like in 16 the DOE world.
17 And I won't go any further with that 18 comment on the public record than --
19 MR. RECKLEY: Okay.
20 MEMBER KIRCHNER: -- to say it provides 21 structure and expectation. So I think it's very 22 important to capture that GDC framework in the actual 23 regulation not relegated to a reg guide, although the 24 reg guide that's been developed is very nice about 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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64 adapting for specific reactor technologies. But I do 1
believe you do need something like the GDCs as a part 2
of the framework.
3 MR. RECKLEY: Okay.
4 CHAIR BLEY: Some words from the joint 5
committee and the AEC back in about 1960 --
6 MR. RECKLEY: Did Dennis drop off?
7 CHAIR BLEY: No. Did you hear me? I just 8
made a comment.
9 MR. RECKLEY: Oh, okay. As we go through 10 the interactions with you guys and stakeholders in 11 general, trying to strike that balance between 12 predictability and clarity that you get through 13 something like the GDC versus the flexibility that you 14 get through performance based approaches more like 15 that presented in NEI 18-04, trying to get the best of 16 both worlds and where that balance is, that'll be part 17 of what we're trying to do in this rule. And it goes 18 back.
19 I guess Dennis is -- well a number of 20 members might remember. But this is in some part kind 21 of related to the structuralist rationalist approach 22 that was the number of a whole bunch of ACRS meetings 23 and interactions and papers back during the 24 development of, I guess is that reg guide 1.174. Back 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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65 in that timeframe. So many of those questions remain 1
what's the right balance. You have to do both, I 2
think. You can't have it all one way or the other.
3 But trying to strike the balance is what we'll be 4
trying to do. So --
5 MEMBER BROWN: Bill? I just had -- I'm a 6
little bit parochial, I mean a little bit with this 7
particular comment. Since I do I&C stuff, protection 8
reactivity control systems, when I go back and look at 9
what it's like, GDC 20 through -- I don't know, 29 or 10 30 or something like that. Those are basically 11 performance based. I mean is the idea that I don't 12 need independence if something's performance based?
13 Or that I don't need reliability and testability?
14 MR. RECKLEY: No, no, no. Again, I --
15 MEMBER BROWN: Bill, I'm losing the bubble 16 a little. I keep hearing this performance based 17 stuff. In my mind, I know what performance based 18 means. I'm not so sure it's well defined even in the 19 way I think about it. Like protection system 20 functions to shut down the reactor. What it needs to 21 be is that's a performance based function. Like Walt 22 says, throwing the baby out with the bathwater gets a 23 little bit difficult for me --
24 MR. RECKLEY: No, no. Yeah, not --
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66 MEMBER BROWN: -- in a longer term view.
1 MR. RECKLEY: Yeah, okay. And I didn't 2
mean to imply that many of the GDC are relatively 3
flexible and performance based in terms of giving you 4
options as to how you might incorporate those things 5
into the design. So no, I didn't mean to make that 6
implication.
7 MEMBER BROWN: No, I'm not accusing you of 8
anything. That was not my intent, I'm sorry. That 9
was not my intent. It's just I get a little bit 10 concerned when people lose sight and they start 11 thinking everything in these GDCs is prescriptive, but 12 it's not. Even the coolability issues. Forget the 13 instrumentation type stuff, you go back to reactor 14 cooling. All reactors has to be cooled in some way.
15 And that particular GDC just fundamentally said you 16 got to be able to cool them under various conductions.
17 MR. RECKLEY: Right.
18 MEMBER BROWN: So I think we just have to 19 be very, very careful about thinking about doing 20 everything brand brand new, and then we lose what's 21 been learned. Like Dennis says, many of these things 22 evolved after -- the first plant shipping port didn't 23 have any of these.
24 I mean they were kind of modeled after the 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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67 way we did the Navy plants in terms of principles. So 1
I mean I just get concerned that we lose what we've 2
learned over 60 years, which has been very valuable, 3
in the process of trying to get something that's more 4
reasonably approached from a licensing and a review 5
basis.
6 MR. RECKLEY: All right.
7 MEMBER BROWN: I'll quit right there.
8 MR. RECKLEY: Okay. And again, we'll test 9
all of this out as we go forward. The only thing I'll 10 mention, as we go forward and look and different 11 technologies, the role and the importance and the 12 timing of some of these changes, and the general 13 design criteria for light water reactors were 14 developed.
15 And I
agree with
- you, they are 16 performance-based and they generally at the high 17 level. But they were developed with the notion in 18 mind that reactivity was something you had to address 19 very quickly because a mismatch between power and heat 20 removal and a light water reactor is something that is 21 a fast-acting transient.
22 When you get over into some of the other 23 non light water reactors that might have more thermal 24 margins or thermal capacities, some of the specifics 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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68 may change. And we just need to be able to look at 1
that and see where -- what would be the most 2
appropriate criterion. I mean this is getting down 3
into the details, and we're still working on the 4
framework. So going over just converting that figure 5
into what Part 53 might look like, we would think it 6
might look like this. You would have general 7
provisions.
8 All the regulations have to start off with 9
a certain amount of those provisions that tell 10 applicants and licensees and the NRC staff how the 11 process works. But then going back to the figure that 12 you would have -- for example, I'll describe these in 13 terms of subparts, just like Part 52 is divided into 14 subparts. But maybe you have subpart B, and it would 15 talk about those safety objectives.
16 What are the regulatory limits? How do 17 the safety goals figure in? And that sets out how 18 safety the facility has to be. And then you would go 19 into, again as I mentioned, what's the role of the 20 design requirements, what's the role of siting, what's 21 the role of construction and manufacturing in meeting 22 those safety goals.
23 The requirements for operation in terms of 24 programmatic controls that we talked about.
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69 Configuration control, maintenance and surveillance.
1 And then what would be the role during decommissioning 2
or retirement? And then you would have those parts of 3
Part 53, or those subparts related to licensing and 4
maintaining the licensing basis information. So this 5
is all of the -- this is basically -- Part 52 is 6
largely oriented towards the applications. Then the 7
things like 50.59 for controlling your licensing basis 8
information, 50.74 on providing updates to the FSAR 9
and then administrative requirements.
10 So this is just a general possible layout.
11 And then getting to Dennis's question on how we might 12 interact, if we were to develop a framework like is on 13 Slide 5. If we have some early discussions and 14 thinking that something like this would be the way to 15 go, then the most important thing, because everything 16 is built off of it, would be the purple box.
17 And we would want to start having 18 discussions on that, you know, as early as later this 19 year or very early next year because whatever schedule 20 gets defined for us by the Commission when we get our 21 instructions, if we keep this framework, it all builds 22 off of how do we define the purple box on Slide 5.
23 Again, in terms of timeframe, I could see 24 those interactions and discussions going or starting 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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70 as early as later this year or very early in 2021.
1 The ultimate schedule of when we would have to finish 2
those discussions, the Commission will tell us.
3 So within the whitepaper, and I heard it 4
mentioned earlier, the whitepaper by and large -- we 5
started writing an Advanced Notice of Proposed 6
Rulemaking because that's what we proposed to do in 7
the rulemaking plan. It was just a vehicle to start 8
us to engage stakeholders. What you're seeing in this 9
whitepaper is what we started as the ANPR, whether we 10 end up doing that or not.
11 The most important thing is that we start 12 to engage stakeholders, whatever vehicle that might 13 be. So one of the things that we would be looking for 14 both from the ACRS, since that's today's discussion.
15 And then we'll be having this same discussion with 16 public stakeholders. What is the interest, what do we 17 see as the major issues and challenges so we can set 18 out a schedule and a kind of a plan as to how we're 19 going to talk about the various issues.
20 MEMBER BROWN: Bill?
21 MR. RECKLEY: Yes?
22 MEMBER BROWN: When you talk about 23 stakeholder interest, didn't the -- what is it, the 24 NEI whatever it is, didn't that say do it as opposed 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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71 to asking people if they have interest in that 1
rulemaking? Don't you have to do the rule now based 2
on the rule?
3 MR. RECKLEY: Yeah, yeah. I'm sorry. We 4
have to do the rule. The question would be what are 5
the stakeholder's interests in working with us to do 6
the rule, not whether we do the rule. Do they want to 7
play, or do they just want to tell us go do it and 8
we'll see what you propose at the proposed rulemaking 9
stage, and then we'll comment.
10 We hope that's not the point. I mean the 11 outcome. We hope stakeholders agree to work with us 12 all throughout the development of the proposed rule so 13 that we don't spend however much time coming up with 14 a finished product, and then people telling us they 15 don't like it. So that's what I mean by stakeholder 16 interest.
17 MEMBER BROWN: It sounds like you would be 18 then in the mode of offering them at each stage, which 19 you have something to propose, you reach out to them.
20 MR. RECKLEY: Right. Right.
21 MEMBER BROWN: Is that what you're talking 22 about?
23 MR. RECKLEY: Yes.
24 MEMBER BROWN: Okay. All right.
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72 MR. RECKLEY: I think that's how it will 1
work by the time we're instructed. And then the other 2
part is the last bullet, preparing both the proposed 3
rule and seeing what related guidance might be 4
appropriate, and we're receptive to any aspect. The 5
next few slides we're going to start going through 6
some of the questions.
7 MEMBER BROWN: Can I interrupt you one 8
more while you're on Slide 7? When you go out for 9
comments or stakeholder interest, I went back and 10 pulled up the 2006 ANPR, whatever it is, which was 11 multiple pages and was so broad, I mean it sounded 12 like you had so much stuff, nobody would ever get 13 anything defined. Are you going to try to narrow it 14 somewhat more?
15 MR. RECKLEY: Well yes, and as an example 16 17 MEMBER BROWN: That was a disaster in my 18 own mind.
19 MR. RECKLEY: Just as one example, that 20 particular ANPR had I think 60 questions. We did look 21 through it and we tried to narrow it down to start the 22 interactions I think. I mean they did have a 23 companion document in 2006 that kind of went over the 24 framework.
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73 I think because we've been directed to do 1
a rule, we have somewhat of an advantage in -- well in 2
that we will be past the question of whether to do it, 3
and people should be providing feedback on more 4
specific things about what should be in it and how it 5
should look. But yes, we are going to try to narrow 6
it down. And it's a good teeing up, I guess, to go in 7
the next couple slides. One of the, on Slide 8 is 8
just the rulemaking objectives. I don't think this'll 9
be surprising, number one.
10 And two, it's basically to maintain the 11 same level of protections as exists for the operating 12 fleet. And then the third one is going to, again what 13 the Commission told us most recently in the Staff 14 Requirements Memorandum for SECY-19-0117. And then in 15 more description in an older SECY that goes back to 16 SECY paper 10-0121.
17 And this is where the third objective of 18 the rulemaking comes from, which is to ensure that to 19 the degree advanced reactor designers are able to 20 provide attributes that are talked about in the 21 Advanced Reactor Policy Statement, that the 22 expectations in that Advanced Reactor Policy Statement 23 is that those attributes, things like less 24 vulnerabilities to accidents, increased thermal 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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74 margins, slower responses leading to releases, those 1
kind of attributes in the Advanced Reactor Policy 2
Statement gets translated into operational 3
flexibilities.
4 And one example we've used in the past is 5
the tradeoff between those attributes and reduced 6
consequences that then enable you to do things like 7
reduce emergency planning zones, or come up with 8
different criteria for population related siting 9
considerations. And then number four and five are 10 just trying to make sure the proposed rule is 11 developed such that it's clear.
12 And this would also be an opportunity 13 during which we might have to identify and resolve 14 areas like staffing. And the time period that we have 15 to resolve issues like that might get determined by 16 the rulemaking schedule if it's not needed to be 17 resolved for some other reason, like an actual 18 application.
19 CHAIR BLEY: Bill? Two things, this is 20 Dennis. This number five is a little rule-y, I think.
21 One problem I envision is that some of these issues 22 won't be clear. Turn it around. When you see some 23 new unique facility design that mixes chemical hazards 24 and nuclear hazards in odd ways, new problems will be 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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75 identified.
1 I think somehow we need to leave a -- by 2
the time we're done, we need to leave something like 3
your number five that has to be resolved on each new 4
unique design. I don't think you can resolve all, you 5
know, identify these up at the level you'd be working 6
at for a technology-inclusive rule.
7 And the other thing is we've got an hour 8
left, so as you can comb through the questions, we can 9
go through those in about 45 minutes. That'll leave 10 us a little time at the end to get comments from the 11 public and from the members of the subcommittee.
12 MR. RECKLEY: Okay. Again, I was just 13 planning to step through the questions at the highest 14 level. Most of them, or many of them, we've talked 15 about before. This first one just have we defined the 16 right objectives. Second one, we are taking the 17 definition out of NEIMA in terms of what reactors were 18 under construction, given AP-1000 was under 19 construction at the time. Our general thought is that 20 that captures generation three and three-plus type 21 reactors as not needing to be.
22 It's not excluded, but they don't need to 23 be in the scope. And so just a general question about 24 what should be within the scope. You can tell we've 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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76 given some thought, I think, to where we envision this 1
going. But one of the simplest questions remains for 2
Part 53, do we incorporate in, as Dennis I think you 3
mentioned earlier, do you try to incorporate within it 4
the licensing processes, so they'll be sections on 5
licensing, or do you just try to define technical 6
requirements and then refer back to Parts 50 and 52 7
for the licensing part?
8 Again, there's no right or wrong to any of 9
these things. Some of it is just ease and 10 understanding and clarity as to where the rules are.
11 But a question that we have is what do stakeholders 12 think about what Part 53 should look like, whether 13 it's like we describe it or whether it's more narrow 14 to be just technical requirements.
15 A big one, again, this is within the 16 previous figure. The way we're currently thinking the 17 rule might look, this becomes kind of like the 18 foundation or the cornerstones on how the whole part 19 would work is how do you define the performance 20 criteria. And is it possible to define a single set 21 that's possible for all technologies?
22 That would look, again, at the NRC safety 23 goals at the highest level, not necessarily the 24 surrogates that were developed later for light water 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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77 reactors in specific, but going up to the higher level 1
safety goals looking at consequences in terms of off-2 site doses.
3 MEMBER KIRCHNER: Bill, this is Walt 4
Kirchner. I'm assuming, since you -- based on what 5
you just said and also the previous idea, I'm assuming 6
that you would take the same approach as 50 and 52 7
with regard to dose limits, which gets into 8
consequences of course. That you wouldn't try -- I 9
mean 10 CFR 100 is 10 CFR 100.
10 You're not going to try and change the 11 outside to 10 CFR 50, 52 part of 10 CFR. In other 12 words, I'm not saying this very well, you would take 13 things like -- and forgive me if I don't remember the 14 exact number. It's 10 CFR 52.34 which talks about 15 contents of applications and demonstrating that the 16 dose at the exclusionary or boundary is less than 17 what, 25 rem per two hours. And at the LPZ, 25 rem 18 for the entire course of the event, et cetera.
19 MR. RECKLEY: Right.
20 MEMBER KIRCHNER: I'm assuming we would 21 still use those and put them in 53.
22 MR. RECKLEY: Yeah. Our interpretation of 23 past commission decisions, including the ones I 24 mentioned, SECY-10-0121, and then even more recently 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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78 SECY-19-0117, is the Commission is telling us those 1
metrics are good enough and are to be used.
2 MEMBER KIRCHNER: Good, good. That makes 3
your job a lot simpler actually if you --
4 MR. RECKLEY: Well it does. Yes.
5 MEMBER KIRCHNER: Yeah. And it provides 6
some agreed upon basis to -- as measures for what's 7
acceptable in terms of --
8 MR. RECKLEY: Right.
9 MEMBER KIRCHNER: -- consequence to the 10 public. Okay.
11 MR. RECKLEY: And then just as we were 12 having discussions early on, on reg guide 1.233, part 13 of the what we'll need in my view to construct within 14 Part 53 though is that advanced reactors have said 15 that when they incorporate the attributes from the 16 Advanced Reactor Policy Statement, that they are able 17 to meet those criteria and then have margins that are 18 greater than what we've seen historically.
19 And then they want to use those margins to 20 do things like incorporate smaller emergency planning 21 zones, reduce staffing, or other things. And so to 22 me, the trick within Part 53 will be to have -- to use 23 those potential advanced reactor attributes and build 24 within the rule how it interplays with those other 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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79 areas to give them the operational flexibility. And 1
that's one of the reasons we built it in as an 2
objective so that we could get some comment and 3
suggestions on that.
4 CHAIR BLEY: I'd remind the members that 5
we wrote a letter not too long ago on the staff's 6
implementation action plan on population-related 7
siting considerations. And then in paper, the staff 8
was not recommending any change in the current rule 9
where Walt was, but it was recommending a change in 10 the guidance for implementing that rule, especially 11 the guidance dealing with population density 12 requirements. And probably, you'll be using these 13 implementation action plans as part of your thinking 14 going forward. I assume that's why they're there.
15 MR. RECKLEY: That's right. And we're 16 trying to tie these things together and make sure we 17 get maximum use out of things like what we just talked 18 about, the reviews that were done of NEI 18-04, and 19 the ongoing reviews of things like TICAP. We want 20 them, if at all possible, to be supportive of what 21 we're doing under Part 53.
22 Risk metrics, more specifically I guess a 23 question. It's related to the previous question on 24 setting up the performance criteria. But to what 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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80 degree do we incorporate the safety goals into the 1
regulations? That would be a change in how we've 2
historically treated that particular policy statement, 3
and the consideration of risk insights.
4 So we have a question in that regard:
5 would people expect to see something like a frequency-6 consequence curve in Part 53, or would it be at a 7
higher level and simply talk about managing the risks 8
using appropriate consideration, some higher level 9
language. And then things like frequency-consequence 10 curves, or the target figure would be in guidances.
11 All of these things we'll kind of have to 12 work out and decide as we prepare the rule. And then 13 to the degree that we are already thinking that things 14 will need to go in guidance, we'll have to consider 15 whether the existing guidance is at the right level or 16 whether we need additional guidance.
17 Again, we gave some thought in the 18 rulemaking plan and we talked that we think it should 19 be addressing the whole lifecycle of the facility, not 20 just a licensing framework. But that's what our 21 thinking is. We're looking for feedback.
22 Going to what Walt was mentioning earlier, 23 there's a whole range of terminology. And we realized 24 even in SECY-19-0117, we were using different 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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81 definitions than were in Part 50 and 52. So one 1
question is just on definitions: is it okay for Part 2
53 to define a term different than it's defined in 3
Part 50, or do we need to try to make sure we avoid 4
that kind of confusion within the whole Title 10, if 5
you will?
6 Just a general question on performance-7 based regulation. The Commission, since 1990s, has 8
had a general policy of encouraging risk-informed and 9
performance-based approaches. Just a general question 10 on how we might incorporate performance-based concepts 11 such as the guidance document that was produced back 12 in that timeframe in the early 2000s, NUREG/BR-0303.
13 CHAIR BLEY: Hey, Bill? Can I back you up 14 one? On the definitions, it's not something I usually 15 get too concerned about. But I think it does create 16 difficulties with changing definitions. And I know 17 the staff has put together a glossary of definitions 18 trying to avoid this problem.
19 And, boy, it seems like it would be 20 worthwhile to try to clear that up. I know you got 21 some difficulties now with the NEI document. But 22 being consistent within the regulator offers some real 23 help to people who are trying to use it, although that 24 would require bringing other documents into agreement.
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82 MR. RECKLEY: Yeah. I don't disagree, but 1
it's a challenge. Only because --
2 CHAIR BLEY: I get it.
3 MR. RECKLEY: Yeah. Talked about this 4
one. One of the questions that we're raising is that, 5
this goes really back to the objectives, and we had 6
two levels of safety defined under the objectives.
7 One, the traditional reasonable assurance of adequate 8
protection.
9 And then the second one was the provision 10 that we typically use when we are looking at a 11 substantial increase in the overall protection, and we 12 consider costs. So in initial licensing, we don't 13 provide as much clarity on distinguishing between 14 those two criteria.
15 And so this question is just going to 16 stakeholders and say, as we develop this new part, 17 should we be looking at those two things and 18 distinguishing between the two. And even at initial 19 licensing, should we be looking at cost-effectiveness 20 when we're making licensing decisions.
21 MEMBER KIRCHNER: Bill, pragmatically, 22 since you brought that one up as a question -- this is 23 Walt Kirchner. Boy, at the initial licensing when you 24 have -- and I don't mean this in a pejorative sense 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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83 for some of these advanced reactors, a paper design.
1 2
You're really not going to have specs or 3
good cost information until you go out in the next 4
step and do the, you know, prepare procurement specs 5
and so on. So it would just pragmatically I think be 6
very difficult to -- it could be open-ended arguments 7
about cost at that phase.
8 I mean, they would be heuristic or 9
estimates maybe falling back on LWR experience and 10 pricing of equipment and such. But I just think that 11 would prove very difficult at the initial stage of a 12 specific license review.
13 MR. RECKLEY: I agree. None of these are 14 easy, and they come with challenges to implement. As 15 you just mentioned, this one would be somewhat hard to 16 say at an early stage we're already deciding there's 17 not a cost-effective -- that there is or isn't a cost-18 effective way if you try to make that decision too 19 early on.
20 The other observation though is that, as 21 we've looked at how we've done backfits on operating 22 plants and even considered putting in place 23 requirements that somebody would need -- would pick up 24 at a future time, a forward-fit requirement, that 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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84 initial licensing wasn't talked about in those 1
guidance documents, in the Management Directive 8.4, 2
that provided additional clarity on how we use those 3
provisions for initial license. So the question is 4
should we. You're exactly right, there'll be 5
challenges in trying to do it.
6 MEMBER KIRCHNER: If I'm the designer and 7
I'm submitting my advanced reactor design, you 8
basically if you think about you've got -- you're 9
looking as a designer for a sweet spot. You're 10 balancing cost, reliability, and safety. And they're 11 all interrelated.
12 I would presume that your applicants will 13 come in with their most cost-effective proposal, in 14 their estimation, as their opening gambit. So I just 15 would be concerned that it would be very difficult to 16 get into -- you mentioned backfitting where you have 17 actually a much better basis for making an estimate of 18 the actual cost of the backfit versus the increased --
19 the gain in terms of whatever the metric is, rem 20 avoided or whatever.
21 So my sense is that they will come in to 22 you with their best most cost-effective proposal, and 23 it probably will go in the other direction. I mean, 24 the arguments that will ensue I predict will be, is 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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85 this system safety-related or is it not?
1 And if it wasn't safety-related and you 2
insist and they have to change it to be safety-3 related, then it likely would cost more to first 4
order. But, you know, but I think it would be very 5
difficult to make that in the cost an initial factor 6
in your review.
7 MR. RECKLEY: Again, I agree with you to 8
it would be a challenge. You or someone else was 9
asking earlier, how do you make decisions on defense 10 in depth, and when is enough enough?
11 This question is somewhat related to that 12 which is at what point when you're deciding how much 13 additional margin to add, not only do you change the 14 classification of a system maybe from non-safety with 15 special treatment up to safety-related, but when do 16 you even need to have a backup that would even be non-17 safety-related special treatment?
18 Again, I don't have answers. One of the 19 questions is to what degree do we bring in this same 20 logic that we use in the operating fleet to try to 21 make decisions on when is enough enough?
22 This is question 10 on slide 16. Just 23 again, a more general question of how do you take an 24 integrated look and ensure that what you're doing in 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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86 terms of safety, security, how emergency preparedness 1
fits in, how do you take this integrated look and make 2
sure that Part 53 has enough? But it also provides 3
the potential for flexibility where the safety 4
features of the reactor might warrant it.
5 This is just a similar question to what we 6
talked about before. We are using, or we could use 7
within the rulemaking, things like NRC Safety Goal 8
Police Statement from 1986. We think the Commission 9
has told us to use that. But as a question to 10 stakeholders, is this an opportunity for us to 11 revisit?
12 One of the questions we put to 13 stakeholders in a public meeting is to what degree is 14 this an opportunity to align ourselves with other 15 international standards? And should the rulemaking 16 try to do that, or just recognize that as you go from 17 country to country, the methodology is generally the 18 same, but recognize that any particular point on a 19 frequency-consequence target figure or any particular 20 offsite dose criteria might change from country to 21 country.
22 Again, the methodology will generally fit, 23 but as you do your assessment, you still might need to 24 make either different arguments or even potentially 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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87 make modifications to address the differences between 1
standards. Again, it's a generally broad question of 2
whether we should maintain what we have, or use this 3
as an opportunity to look elsewhere, or look for 4
tweaking the guidance, or tweaking the requirements in 5
this case by changing what will go into Part 53.
6 Quality assurance, this was an issue 7
people mentioned back in 2006, is some of these 8
questions are basically the same questioned we asked 9
back in 2006 in that ANPR. And whether there's an 10 alternative to how we're currently doing quality 11 assurance. Not that quality assurance doesn't remain 12 fundamentally important, but is there time now that we 13 might look for different ways to do it?
14 And now that you have QA organizations 15 surrounding NQA-1. You have additional standards on 16 the international arena. You have a whole set of ISO 17 standards. So just a general question of whether we 18 could revisit how that's done. This one goes to the 19 guidance and standards area. If we're going to 20 develop a Part 53, it'll have a large -- it could 21 potentially have the need for a large number of 22 standards and guidance documents.
23 So this question is to stakeholders, are 24 we going to have either standard-development 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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88 organizations or NEI or Nuclear Industry Council or 1
some other group identify potential guidance documents 2
that we could endorse. Or to the degree there are 3
needed guidance documents will it fall on the staff to 4
try to develop those as we're doing the proposed rule?
5 And then the catch-all question 14 which 6
is just, you know, these were just some initial 7
questions. We boil down the strong events and then we 8
boil down the 60 or so that was offered in 2006 to 14 9
questions. But are there other matters that we didn't 10 identify that people want to bring up?
11 So with that, Dennis, we're open to the 12 broader discussion and then also maybe the path 13 forward in terms of starting to talk about when we 14 might come back.
15 CHAIR BLEY: Yeah. I think that's good.
16 But first, let's go to the members and see if any have 17 more questions or want to say anything about the 18 questions you folks have posed.
19 MEMBER PETTI: So, Bill, this is Dave 20 Petti. I didn't hear a lot about certification about 21 the overall approach, which is something I hear in the 22 advanced reactor community a lot. In terms of how you 23 weigh all these questions, it just seems to me that 24 simplification and the schedule is being imposed from 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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89 the outside, they answer your questions for you 1
instead of, say, the more thoughtful approach.
2 MEMBER BROWN: Dennis, I can't really hear 3
you.
4 CHAIR BLEY: That was Dave Petti.
5 MEMBER BROWN: Oh, Dave? He's speaking 6
very softly. I couldn't hear him. I didn't know if 7
it was your connection or what but I just --
8 MR. CORRADINI: I think, Charlie -- this 9
is same as Corradini. I barely hear you, Dave.
10 You're very muffled.
11 CHAIR BLEY:
- Well, he asked some 12 questions. If Bill heard him, maybe he can respond.
13 If not, maybe Dave can say them again.
14 MR. RECKLEY: Well, I'll summarize, Dave, 15 and push back if I mischaracterize it. But Dave's 16 primary point was simplification in both design and I 17 think expectations for what would be in Part 53. And 18 we hear those. The other thing I would point to in 19 Part 53 in addition to trying to make sure we're able 20 to address simpler designs, ones that are using more 21 inherent and passive features, is when you try to make 22 this rulemaking technology-inclusive, our preliminary 23 thinking is that pushes you up higher to be more 24 general, to be simpler in what the rule requires.
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90 The counter to that, as some other people 1
have raised, is you are now perhaps less clear because 2
you're now saying you're up at a functional level in 3
terms of what you're imposing in asking applicants and 4
designers to provide. So that'll be I think one of 5
the primary challenges, is to try to balance the --
6 what I'm looking at now, the Part 53 rulemaking, the 7
simplicity that we want to maintain and keeping it up 8
at a high level, and then the tradeoff with clarity 9
because the higher you get, most likely, the less 10 clear you are.
11 MEMBER KIRCHNER: Bill, this is Walt 12 Kirchner. If I might make a specific observation, and 13 also given the schedule that you're likely going to 14 have to work against, it seems to me that one would --
15 borrow is not the right word, but use what are 16 accepted metrics that are well-defined or actually, 17 how should I say it, that can be calculated by the 18 applicants.
19 And I'm referring again specifically to 20 the dose at the exclusionary boundary and the LPZ, and 21 rather than the safety goals themselves. I have the 22 safety goals right in front of me, as you were 23 speaking, and I just quickly looked at them again.
24 And I think that if you were -- just what you were 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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91 saying, if you go that high a level, you open the door 1
for endless arguments.
2 And even the safety goal statement, which 3
I have in front of me, points out that there are 4
sizeable uncertainties still present. Now this was 5
written -- and I'm talking about the quantitative 6
parts of the safety goals. When was this written? In 7
'86. I would submit there's still large uncertainties 8
in terms of the relative measures versus, you know, 9
the more qualitative goals.
10 So if you use that, I just don't see how 11 you get to closure. It seems to be a much better path 12 as to use what is accepted as a surrogate for the 13 safety goals in the case of dose there at the EAB and 14 the LPZ, and then do things like the paper Dennis 15 reminded us of your proposal on how to then take the 16 existing regulations and provide guidance in terms of 17 determining, like, LPZ.
18 And that to me would pragmatically let you 19 get to closure in a reasonable timeframe. If it gets 20 too high-level, I just don't know that you can get to 21 closure. Or you don't get to closure with the 22 applicants because of the large uncertainties in the 23 actual licensing process, if indeed they're going to 24 compare against the safety goals. You see what I'm 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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92 saying?
1 MR. RECKLEY: Yes, I do. Again, and 2
that'll be the challenge. I think our initial 3
thinking is that we would probably end up using both.
4 But both the traditional 25 rem at the low population 5
zone, or EAB. And in addition, somehow using the 6
safety goals. But how we do that, that'll be part of 7
the discussion as we try to set up what the 8
performance requirements would be.
9 MEMBER BROWN: I would just echo Walt's 10 thoughts a little bit because the lack of specificity 11 or what people term as prescriptive requirements just 12 increases uncertainty and an increase number of RAIs 13 and back-and-forths on why you're doing it this way 14 vice the other, and it becomes very difficult to close 15 those out. That's a real worry to me as well. I'm not 16 trying to argue one way or the other, I'm just saying 17 that is a problem.
18 MR. RECKLEY: And we'll be looking for 19 real smart people to help us with that, like you guys.
20 MEMBER BROWN: I'm not so sure anybody, or 21 there's enough smart people in the world to do that.
22 There's always a -- I mean, a typical example in my 23 area is control of access that we keep fighting over 24 on every design in terms of do you give people a door 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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93 that's software-controlled out to the outside world, 1
that they can come in if they want to, or do you just 2
close the door based on hardware? That's a specific 3
thing.
4 That's just my own parochial area that I 5
have to deal with. I just think you can fight about 6
that forever and say, well, gee, I can do it whatever 7
way I want. Well, no. We don't want the door open.
8 somewhere, you're the regulator and you're responsible 9
for safety. Your ultimate issue is safety. Sometime 10 you have to say, no, do it this way. I can see that 11 being we're falling away from that in some 12 circumstances. That's always the other argument that 13 seems to want to prevail. That's my thought process 14 relative to Walt's comment.
15 MR. CORRADINI: So, Bill? This is 16 Corradini.
17 MR. RECKLEY: Yes, sir.
18 MR. CORRADINI: Can you hear me?
19 MR. RECKLEY: Yes, sir. I can.
20 MR. CORRADINI: Okay. So let me ask you 21 a couple of pointed questions, and you tell me that 22 that's to be determined. So I'm thinking about this 23 relative to a research reactor as an alternative. In 24 a research reactor, whether it be one megawatt, or a 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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94 few megawatts, or a sub-megawatt in size, I don't have 1
to worry about external manmade hazards.
2 Is there a power size here that's going to 3
say that if I'm below a certain power size, I don't 4
have to worry about external manmade hazards, or must 5
I consider it regardless? And then I add to that 6
concern about multiple modules.
7 If I decide that I have a small machine 8
and meets all the new criteria of the new 10 CFR 53, 9
does that mean it's on a per-module basis, or is it a 10 population of modules on a site? Are those things 11 going to be identified in 53, or did I miss a question 12 in that area?
13 MR. RECKLEY: Well, they'll need to be 14 addressed in Part 53 in terms of the natural -- I 15 mean, manmade hazards, and to some degree even natural 16 hazards. It, on approach can be as you identify those 17 top-level criteria that I mention back in the figure, 18 the purple box, what are the dose criteria, what are 19 the risk metrics.
20 Then you can look and see in terms of 21 hazards, manmade or natural, is there a way -- I guess 22 my response would be you have to address it. But one 23 way to address it might be there's no way for a 24 manmade hazard or some other hazard to challenge those 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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95 performance metrics. And so if I look at a manmade 1
hazard related to, let's say, toxic gases, if I have 2
a plant that doesn't require people -- so I'm building 3
a house of cards here, but if I have a plant that 4
doesn't require people, then maybe my concern about 5
toxic gases is less.
6 A design feature, like putting a plant 7
underground, might be able to address something like 8
explosions from a nearby railroad line, or an aircraft 9
crash. So they will need to address all of those 10 things, but they might be able to address them by 11 having design features that show that those hazards 12 can't challenge the safety metrics that are 13 established within the part. In terms of multiplant 14 versus -- or multiunit, you know, NEI --
15 MR. CORRADINI: Bill, whatever you want to 16 call it.
17 MR. RECKLEY: Right. NEI 18-04 was set up 18 on per plant basis, which is different than Part 50.
19 One of the questions, maybe we should have added it, 20 is a question would be, should Part 53 be set up that 21 way. When we said throughout the development of the 22 Part 53 that we would build off of things like Reg 23 Guide 1.233, it does provide us a vehicle to go to 24 multimodule, and address it perhaps more clearly than 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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96 Part 50 has.
1 CHAIR BLEY: Okay. Thanks, Bill. We're 2
nearing the end, but I'm going to -- I'm sorry, we'll 3
get a chance to go around and have members make 4
comments. While Bill's still up, let's only address 5
questions to him and save comments for a couple of 6
minutes from now. Go ahead, Vesna. You had 7
something?
8 MEMBER DIMITRIJEVIC: Well, I'm going to 9
save comments when we go around.
10 CHAIR BLEY: Perfect.
11 MEMBER DIMITRIJEVIC: I don't have any 12 question, I just have a comment.
13 CHAIR BLEY: Perfect. Anybody else have 14 a question? Then at this point, I'm going to thank 15 Bill very much, and all of his staff who helped out on 16 this for giving us the status of where they are. When 17 we go around to members, I'm also going to ask you 18 about October. If we would have an October meeting, 19 I would ask the staff to have a very short 20 presentation just on Part 53.
21 And the reason we'd do that is if we want 22 to write a letter. I'm inclined that it'd be a good 23 time to send a letter to the Commission, just a short 24 one, saying we're on board, we're following this. And 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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97 we have a couple of issues, if we do, that we want to 1
make sure the staff pursues. But we'll get to that in 2
the minute.
3 Are there any members of the public either 4
on the web broadcast or on the outside line who would 5
like to make a comment? Please make sure the outside 6
line is open for us, our staff.
7 OPERATOR: The line is open for comments.
8 CHAIR BLEY: Okay. Is there anyone from 9
the public who would like to make a comment? If so, 10 give us your name and your comment.
11 MR. LYMAN: Hello. This is Ed Lyman from 12 the Union of Concerned Scientists. Can you hear me?
13 CHAIR BLEY: Yes, Ed. We can. Please go 14 ahead.
15 MR. LYMAN: Yeah, hi. Yeah, so I 16 appreciate this meeting. I'd just like to say that 17 UCS did not oppose the passage of NEIMA, and we 18 testified twice that we have a neutral position. The 19 reason why we didn't oppose it is because we believe 20 that it gave the Commission enough discretion and did 21 not micro-manage what to do vis-a-vis licensing 22 advanced reactors.
23 And so we didn't oppose it because we 24 thought the Commission, you know, with that discretion 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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98 and with the competence of the technical staff that it 1
would do the right thing. But I'm starting to regret 2
that decision. And that is because I don't believe 3
this is going in the right direction. And I do 4
appreciate some of the concerns I heard raised by 5
members about the ambiguous and the amorphous nature 6
of what's taking place here.
7 The potential for not only having 8
discretion on how standards are met, but also what the 9
standards actually are. And that seems like an 10 invitation to chaos. And I don't think the vendors, 11 if that's what they thing is going to help make their 12 lives easier in trying to license these reactors, I 13 think they have surprises ahead because I don't see 14 how this -- how weakening or making standards more 15 ambiguous is going to actually help in resolving these 16 issues, many of the difficult issues that we heard 17 with how do you license paper designs with very 18 limited operating experience, or no operating 19 experience with a very weak or sparse experimental 20 database with regard to only important factors that 21 would need to go into these determinations such as 22 mechanistic source term.
23 So I'm very concerned about this, and I do 24 hope that the committee will express it's concerns, 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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99 and hold the feet to the fire because I don't think 1
that the Commission's political leadership is actually 2
safeguarding public health and safety in this respect.
3 On that note, I can't think of any other regulator 4
that is so content with not imposing stricter safety 5
standards on future facilities.
6 So we have this whole enterprise is based 7
on this artifice that the Commission expects advanced 8
reactors to be safer, and it's building a regulatory 9
infrastructure based on that expectation. But as we 10 heard Bill Reckley say multiple times, even for 11 designs that have some inherent safety features, that 12 the vendors are going to look for ways to use that 13 margin in other ways.
14 And so without a strict or a compelling 15 mandate from the Commission that you have at the end 16 is going to be in return fleet, you're going to end up 17 with reactors, you know, possibly locking for decades 18 to come with using the additional margin up in getting 19 relief for things like EPZ security and safety already 20 in the system. So that just doesn't make sense to me 21 for a forward-thinking agency.
22 And so I would encourage everyone to think 23 about how to make plants safer in the future rather 24 than just embrace the status quo. For instance, rely 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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100 on the safety goals, which were developed decades ago 1
specifically so the parent fleet would meet them is 2
not an appropriate parameter to use if you're going to 3
use a new criteria. So that's my comment, and I 4
appreciate your time. Thank you.
5 CHAIR BLEY: Thanks very much, Ed. And we 6
have your comments on the transcript. We appreciate 7
them. Anyone --
8 MEMBER BROWN: Someone was just speaking.
9 Dennis, who was just speaking? It got garbled on my 10 end.
11 CHAIR BLEY: That was Ed Lyman from the 12 Union of Concerned Scientists.
13 MEMBER BROWN: Oh, okay. I just wanted to 14 comment I actually agree with him, a good bit of what 15 he said. So thank you, Ed.
16 CHAIR BLEY: Anyone else have a comment 17 from the public line? Okay, we're going to close the 18 public line and come back to --
19 OPERATOR: Public line is closed.
20 CHAIR BLEY: I'm sorry, who?
21 OPERATOR: Public line is now closed.
22 CHAIR BLEY: Thanks, I'm sorry. Hear 23 while I was talking. I'm now going to go around to 24 the committee members. And I think this time, I'm 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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101 going to call people by name, because I'm looking for 1
general comments and also specific thoughts if we 2
should write a letter in October to at least lay out 3
a few things that we want to bring to the staff's 4
attention, and to let the Commission know that we're 5
tracking this at this point in time. So let's go to 6
Ron Ballinger.
7 MEMBER BALLINGER: Yeah. I agree with 8
your comment related to we should meet and have a 9
letter.
I'm talking as a
metallurgist now.
10 Historically, we have had painful experience with 11 respect to things that pop up in a design as we build 12 it and over history. And they're largely related to, 13 at least on the materials side, degradation that 14 occurs that we didn't anticipate.
15 So I'm curious as to whether or not 16 consideration, since Bill says we have an option, we 17 actually have a clean sheet of paper, whether 18 something could be incorporated in the requirements to 19 take a look at what some famous government official 20 has termed unknown unknowns. And I don't know how you 21 do that, but it seems to me that there's an 22 opportunity here.
23 We have an example of an unknown unknown 24 that we're dealing with, with another plant design 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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102 right now. And so I'm just curious as to whether that 1
some consideration should be given to that. Thank 2
you.
3 CHAIR BLEY: Thanks, Ron. And maybe make 4
some notes on that to have around come October.
5 That'd be useful. Charlie?
6 MEMBER BROWN: Well, I've made most of my 7
comments.
8 CHAIR BLEY: Back to your earlier comment.
9 MEMBER BROWN: I've made most of my 10 comments earlier. But one of my general concerns I 11 would echo Lyman's comment relative to everybody's 12 assuming these advanced reactors are going to be safer 13 and have more margin, but margin tends to get used to 14 generate more power.
15 And based on the few designs, very few, 16 there's a lot of other aspects to some of these 17 designs that add other non-safe factors to how they 18 operate and their waste products. So I'm not quite as 19 confident that these new advanced reactors are all 20 safer than the pressurized waters, which had a very 21 definitive nature of unsafeness that we have to deal 22 with, and we know what it is.
23 I'm worried about so much generality in 24 the high level we'll be fighting about it, and we'll 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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103 end up not being able to get a plant defined very 1
well. And so that's my general concern, is an 2
overarching concern. So I'll be quiet now and let 3
somebody else go on.
4 CHAIR BLEY: Thank you, Charlie. Now 5
Vesna?
6 MEMBER DIMITRIJEVIC: Okay. I found the 7
button to activate my microphone. Okay. I can 8
actually -- I mean, I have too many notes actually to 9
talk about that, so I will just keep this on high 10 level. I think we definitely should write the letter 11 about that. One is to address the questions.
12 I mean, which we couldn't do in all of 13 those, my notes, if I, you know, go through them now 14 where I can talk for half-hour. So I think that 15 writing letter to address some of the questions from 16 this presentation, and maybe to talk about licenses 17 through our review of the advanced plants and some 18 things like that, how would that help in the new 19 regulation.
20 I mean, what issues did we notice that the 21 regulation has an issue with it needs some, you know, 22 exemptions and things like this. I think that can be 23 very helpful. On the high level, I just want to say 24 the following, that's it's no -- I mean, I don't think 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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104 the human race will progress if we always try to 1
address all the risk associated with different things.
2 And obviously when we are meeting with 3
some totally new designs, we will not be able to do 4
that. So we can make an honest attempt to, you know, 5
keep this as safe as our understanding in this moment, 6
but we will have to learn, you know, with every new 7
technology, new lessons.
8 So in my opinion, I think it's very good 9
to keep this as simple as possible on this level. We 10 were talking about cost-effective designs, but we also 11 should talk about cost-effective regulation because we 12 should really make this the practice going through 13 approval not to be too complex, because the complexity 14 doesn't really help in identifying important issues.
15 It often, actually buries them.
16 So in order to keep this simple enough, I 17 think it's also the selection of what is going to be 18 criteria or risk matrix or criteria to -- what to base 19 regulation on, that's very important to see how 20 complex this regulation will become, you know. So for 21 example, I'm not big fan as you know of the F-C curve.
22 And because I think it's already complex and could 23 lead to the many, you know, different combinations and 24 different answers requires the source terms for so 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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105 many, you know, sequences, groups and things like 1
that.
2 And that can be also as an option, but it 3
should be open to other approaches to the measures of 4
risk. And one other thing, which I always also think 5
is extremely important, it will be very good to run 6
some example how would that actually look in actual 7
application.
8 And since we only have example of the 9
existing plants or the advanced plants, which have the 10 PRAs which are extremely complex, and example can be 11 very complex. We can actually run it just on one 12 attendant group. So simplify just to see example how 13 would this all go through the process. That's it.
14 CHAIR BLEY: Thanks very much, Vesna. And 15 for all members, if you get a chance to summarize your 16 thoughts, then send them to me sometime over the next 17 few months, that would be very helpful. I'll probably 18 send out a reminder. Walt, let's go to you. We have 19 your comment from a few minutes ago.
20 MEMBER KIRCHNER: Yes.
21 CHAIR BLEY: Any other comments?
22 MEMBER KIRCHNER: I've made a lot of 23 comments already so I should be brief. Just yes to 24 the letter. And what was not clear to me, it doesn't 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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106 have to be answered here, but whether 10 CFR 53 would 1
be a one-or two-step process, or some hybrid. And 2
address some of what I see problems in 10 CFR 52. And 3
I'll just stop there.
4 CHAIR BLEY: Thank you. Yeah, I guess 5
that comes under a kind of a lessons learned Vesna was 6
talking about. After Walt, Jose.
7 MEMBER MARCH-LEUBA: Hello. Yeah, this is 8
Jose. I'll also be short. I think we should have a 9
letter, and I would like to schedule sometime to make 10 like the advertisers do with focus groups. Just have 11 a letter and go line-by-line changing the grammar, but 12 try to reach a consensus of the group.
13 On the advice, I'm going with the 14 following same advice that many of the members have 15 already said, but attack it from a different point.
16 My concern has always been, right, recently is the 17 NUREG-0800, the Standard Review Plan, is an excellent 18 document.
19 I mean, it's the best invention since 20 sliced bread for locating reactors because it accepts 21 all of the built-up experience, the crowd-sourcing of 22 everything that can happen to one of these reactors.
23 The tendency on new reactors is to start with that, 24 and remove the items that don't apply, instead of 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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107 trying to seek outside the box and say what is my 1
reactor applying -- that is not covered by the SRP.
2 So when one identifies the DBEs, maybe I don't think 3
it's a rule, but we need to make sure to say that the 4
SRP is not the beginning -- it's not the endpoint, 5
it's only the beginning. Look outside of it for your 6
reactor particular things. Okay. And that's it.
7 CHAIR BLEY: Thank you very much, Jose.
8 Dave Petti?
9 MEMBER PETTI: So my greatest concern is 10 how complex this could potentially be for designs that 11 will be much less mature than what historically has 12 come to the Commission. And I'm just wondering if 13 there's a way to have some pilot projects that could 14 be done that even the ACRS could participate in to 15 help us all just get a better understanding of what we 16 think the issues are or could be to help, you know, 17 get this over the finish line. That's it.
18 CHAIR BLEY: Thanks very much, Dave. Joy?
19 MEMBER REMPE: This time I'm slow on the 20 button. Yeah, I would like to see us do a letter. I 21 guess I have to quickly point out that when I became 22 a parent, I realized that I had not thought of things 23 that my kids could do to say, no, that's now what you 24 should. A new rule was imposed.
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108 And I'm looking at this figure on slide 1
five thinking about the scope, as I've mentioned 2
earlier. So I hope in our letter that we talk about 3
the need to, as other members have said, to think 4
outside the box because of new chemical issues and 5
hazards, transportation hazards. And if we're going 6
to do the whole lifecycle, we've never really thought 7
a whole lot about the waste maybe, and the way we 8
should, because we haven't as a country been able to 9
address it.
10 And maybe we should think about that too 11 in the lifecycle diagram. And so anyway, I would like 12 to see us discuss that in our own letter. And I liked 13 Jose's idea about having discussion times for the 14 points, although I know you'll probably have a draft 15 you circulate. But it might make it more effective on 16 how we generate the letter. Thank you.
17 CHAIR BLEY: Thanks, Joy. Matt?
18 MEMBER SENSERI: Thank you, Dennis. The 19 members have raised some very important points here in 20 my judgment, and I don't have anything that I'll add 21 on top of that. So I would think that the points are 22 value-added, and that we should come together as a 23 committee, get consensus, and provide our formal 24 thoughts in the form of a letter, and that's all I 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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109 have. Thank you to the staff for the good 1
presentations today.
2 CHAIR BLEY: Thank you, Matt. Now I think 3
I'll turn to our consultant, Mike Corradini. Are you 4
still there, Mike?
5 MR. CORRADINI: Yes, sir. I am. Can you 6
hear me?
7 CHAIR BLEY: Clear as a bell.
8 MR. CORRADINI: Okay. So in going through 9
all the members' comments, I think the one that I want 10 to come back to, Vesna went through a series of what 11 I'll call bullet points to kind of match exactly what 12 concerns me.
13 And I think Dave said it best, which is we 14 have to find at least a pathway through this because 15 however much we say these are new advanced reactors, 16 none of these things haven't been thought of in the 17 1950s. We might have new technologies that can be 18 applied to them, whether it be to instrumentation or 19 monitoring or materials, but these reactor concepts 20 have been around.
21 So it's not that the concepts are new, 22 it's a matter of how you essentially work with them 23 relative to a licensing framework. And since staff 24 wants to do a licensing framework that goes beyond 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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110 just licensing of a particular reactor type, I really 1
do think we've got to keep it as simple as possible.
2 Just because it's simple doesn't mean that the process 3
is going to be non-conservative.
4 Just the opposite. You can think of it by 5
keeping the same safety goals, whether it be the 6
qualitative safety goals or the quantitative safety 7
goals of CDF and large release frequency, or large 8
release, radioactivity release. And still be more 9
conservative in terms of how you estimate these 10 advanced designs and how they perform, and still do a 11 good job of it.
12 So my thought is to keep it as simple as 13 possible. And I would just simply go back to what 14 Vesna said, is she had three or four points relative 15 to that, and try to at least do this. Now my 16 recommendation would be that the ACRS get involved in 17 this early and often.
18 Without that, we're going to come back to 19 this and eventually and have all the same questions.
20 And I think this possibly may be the one good example 21 that the Commission wants ACRS input from the 22 beginning. And so to the extent that, Dennis, you 23 feel comfortable with it, I think you want to do this 24 as much as possible. That's it, thank you.
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111 CHAIR BLEY: Thanks so much, Mike. Gee, 1
I'm happily surprised by all the comments from the 2
members. I had a whole list of things I wanted to 3
talk about, and I don't think --
4 MEMBER BROWN: Dennis, Dennis?
5 CHAIR BLEY: Yeah, Charlie. Go ahead.
6 MEMBER BROWN: I forgot one point when I 7
was making mine, and it goes along with Mike's comment 8
about the -- I forgot how he phrased it, simplicity or 9
not getting too complicated. Bill's comments on their 10 slide three relative to separating the design 11 operational programmatic from existing licensing 12 processes relative to permits, Part 50 and 52.
13 And that was an interesting comment 14 because if we're going down this path, it seems to me 15 you could simply this process if you did separate 16 them. In other words, use what's out there for what 17 I call the hammer-and-tongs part of the business as 18 opposed to the more advanced thinking and advanced 19 reactor concept part, which is the first part in terms 20 of the regulations and technical standards. I meant 21 to say that in my ending comments, and I'm sorry for 22 interrupting you, so.
23 CHAIR BLEY: Thank you, Charlie. I kind 24 of got it, but we'll have it in the transcript. And 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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112 for everyone, if you made some notes and you would be 1
happy to send them to me, and I would appreciate that.
2 I do have a couple of quick things. I agree with 3
almost everything all of my colleagues have said.
4 I would like to talk some time in the next 5
couple weeks with Derek, and maybe you can set this up 6
Derek, but also Larry and Scott, for how we can 7
legitimately do something like the focus group that 8
was suggested by Jose. We talked about doing 9
something like this in the past, and we've never 10 really implemented it.
11 But given this is going to take a few 12 years, and it's of lasting importance, I think it 13 would be good for us to really hash out among 14 ourselves our thoughts before we engage further with 15 everyone. Bill, you're probably surprised that we 16 need a letter, but we leaned so far that way that I 17 think we should count on having a meeting in October, 18 and a letter.
19 And I will ask, and we'll work through 20 Derek on this, but we just have a presentation on Part 21
- 53. Somebody turn off their microphone. On Part 53 22 and fairly short because all but one of us was here at 23 this meeting. I got involved in something, it took me 24 back through the history a lot in recent months. And 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433 WASHINGTON, D.C. 20005-3701 (202) 234-4433
113 there's an interesting history on the tech specs and 1
the design criteria and how they came about.
2 But also our committee was pretty much 3
opposed to the design criteria as being nothing more 4
than sort of mom and apple pie. But after several 5
years, both the Commission and the vendors and the 6
staff convinced the committee that the value of all 7
these things were all clear to the folks at the time 8
they needed to be considered.
9 The value was it made it clear to people 10 submitting applications what they need to consider.
11 And that issue of taking out some of the variability 12 in the licensing process was a key part of that. At 13 this point, we'll be going forward. I don't think we 14 have any more time.
15 And I guess there's another meeting coming 16 up in about an hour. Thanks to everyone to today and 17 especially further discussions from the staff. And I 18 thank our former member, Rich Denning, for coming in 19 to explain his comments. At this point, the meeting 20 is adjourned.
21 (Whereupon, the above-entitled matter 22 went off the record at 1:02 p.m.)
23 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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July 20, 2020 1
ACRS Future Plants Subcommittee Regulatory Guide 1.233 Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors
2 NEI 18-04, Risk-Informed Performance-Based Technology Inclusive Guidance for Non-Light Water Reactor Licensing Basis Development (Draft Revision N, September 2018)
Draft Regulatory Guide (DG) -1353 (September 2018)
Draft SECY Paper (September 2018)
ACRS Subcommittee and Full Committee (February 2019)
Meetings ACRS Letter Dated March 19, 2019 ACRS Interactions
3 Post-ACRS Activities Issuance of DG-1353 for public comment (April 2019)
- One public comment received (R. Denning & V. Mubayi)
NEI 18-04, Revision 1 (August 2019)
(no significant changes from Draft Revision N)
Issuance of SECY-19-0117 (December 2019)
Commissions Staff Requirements Memorandum (SRM) related to SECY-19-0117 (May 26, 2020)
Issuance of RG-1.233 (June 2020)
(minimal changes from DG-1353)
4 The development and interpretation of the frequency-consequence curve proposed to be endorsed in DG-1353 does not have a strong technical basis. An underlying weakness of the proposed logic of assessing each candidate licensing basis event is that results could be influenced by the way an analyst chooses to define and group event scenarios. A better approach would be to consider a frequency-consequence curve as not only a tool for assessing individual licensing basis events but also as a bound on the complementary cumulative distribution function (CCDF) of accident sequences.
(ADAMS Accession No. ML19158A457)
Public Comment
5 Disposition of Public Comment (ADAMS Accession No. ML20091L696)
The staff agrees that the approach described by the commenters may be a viable alternative to the methodology described in DG-1353 and NEI 18-04.
Suggested approach (complementary cumulative distribution function) offers some advantages in terms of supporting the assessment of cumulative risk and the contributions from various licensing basis events.
The methodology in DG-1353 and NEI 18-04 includes assessments of cumulative risks (e.g., a comparison to the NRCs safety goals)
6 Disposition of Public Comment NEI 18-04 methodology supports the established objectives o
Identification and assessment of licensing basis events; o
Establishing safety classifications and performance criteria for plant features; and o
supporting evaluations of defense in depth
- Issues related to defining event sequences are expected to be addressed by the implementation of consensus standards, integrated decisionmaking processes, peer reviews of probabilistic risk assessments, and the reviews performed by the NRC staff.
- For these reasons, the staff has determined that the methodology described in DG-1353 remains one acceptable approach for informing the licensing basis for advanced reactors and decided not to alter the guidance documents as requested.
7 SRM dated May 26, 2020 (ADAMS Accession No. ML20147A504)
The Commission has approved the use of the technology-inclusive, risk-informed, and performance-based methodology described in this paper as a reasonable approach for establishing key parts of the licensing basis and content of applications for licenses, certifications, and approvals for non-light-water reactors.
The staff should remain open to continuous, critical examination of its thinking regarding approaches and metrics for the licensing of this coming class of advanced reactors.
In its work on the regulatory framework for advanced reactors, the staff should continue to recognize that the Commissions established policy on the application of the safety goals and safety performance expectations provides an acceptable minimum safety standard for new reactors while taking into account the need to adapt the aspects of our current regulatory framework for reactors that provide operational flexibility based on risk assessment, such as the more than minimal increases in risk test in Section 50.59, the Maintenance Rule of Section 50.65, and the quality assurance criteria of Appendix B to reflect the significantly lower risks inherent in the design of advanced reactors.
8 Possible Future Interactions Design-specific applications 10 CFR Part 53, Licensing and Regulation of Advanced Nuclear Reactors Mechanistic Source Term INL/EXT-20-58717, Revision 0, Technology-Inclusive Determination of Mechanistic Source Terms for Offsite Dose-Related Assessments for Advanced Nuclear Reactor Facilities, June 2020 Draft Regulatory Guide - Technology-Inclusive Content of Applications (TICAP)
Regulatory Guidance - Advanced Reactor Content of Applications (ARCAP)
Content beyond TICAP/Licensing Modernization Project Construction Permit Applications Microreactor issues (pending information SECY paper)
SECY Paper - Staffing Issues (Licensed Operators, Autonomous Operations, Remote Operations)
9 Questions/Discussion
10 Backup: Event Selection & Analysis
11 Backup: Public Comment Example - complementary cumulative distribution function (CCDF)
See public comment, ADAMS Accession No. ML19158A457
12 Backup: Risk-Significant SSCs A prevention or mitigation function of the SSC is necessary to meet the design objective of keeping all LBEs within the F-C target.
The LBE is considered within the F-C target when a point defined by the upper 95%-tile uncertainty of the LBE frequency and dose estimates are within the F-C target.
The SSC makes a significant contribution to one of the cumulative risk metrics used for evaluating the risk significance of LBEs.
A significant contribution to each cumulative risk metric limit is satisfied when total frequency of all LBEs with failure of the SSC exceeds 1% of the cumulative risk metric limit. The cumulative risk metrics and limits include:
- The total frequency of exceeding of a site boundary dose of 100 mrem <1/plant-year (10 CFR 20)
- The average individual risk of early fatality within 1 mile of the Exclusion Area Boundary (EAB) < 5x10 -7/ plant-year (QHO)
- The average individual risk of latent cancer fatalities within 10 miles of the EAB shall not exceed 2x10-6/plant-year (QHO)
13 Backup: Safety-Significant SSCs All Plant SSCs PRA Modeled SSCs Safety-Significant SSCs Risk-Significant SSCs Safety-Related SSCs An SSC that performs a function whose performance is necessary to achieve adequate defense-in-depth or is classified as Risk-Significant (see Risk-Significant SSC).
Summary
July 20, 2020 1
ACRS Future Plants Subcommittee 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors
2 Background
Advance Notice of Proposed Rulemaking, Approaches to Risk-Informed and Performance-Based Requirements for Nuclear Power Reactors, dated May 4, 2006 (71 FR 26267)
NRCs Vision and Strategy report (12/16) for non-light-water reactors and related implementation action plans identified a potential rulemaking to establish a regulatory framework Nuclear Energy Innovation and Modernization Act (NEIMA; Public Law 115-439) signed into law in January 2019 requires the NRC to complete a rulemaking to establish a technology-inclusive, regulatory framework for optional use for commercial advanced nuclear reactors no later than December 2027
3 Background - NEIMA (1) ADVANCED NUCLEAR REACTORThe term advanced nuclear reactor means a nuclear fission or fusion reactor, including a prototype plant with significant improvements compared to commercial nuclear reactors under construction as of the date of enactment of this Act, (9) REGULATORY FRAMEWORKThe term regulatory framework means the framework for reviewing requests for certifications, permits, approvals, and licenses for nuclear reactors.
(14) TECHNOLOGY-INCLUSIVE REGULATORY FRAMEWORKThe term technology-inclusive regulatory framework means a regulatory framework developed using methods of evaluation that are flexible and practicable for application to a variety of reactor technologies, including, where appropriate, the use of risk-informed and performance-based techniques and other tools and methods.
4 SECY-20-0032, Rulemaking Plan SECY-20-0032, Rulemaking Plan on Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors, dated April 13, 2020 Proposing a new 10 CFR part that could address performance requirements, design features, and programmatic controls for a wide variety of advanced nuclear reactors throughout the life of a facility.
Focus the rulemaking on risk-informed functional requirements, building on existing NRC requirements, Commission policy statements, and recent activities (e.g.,
Expect extensive interactions with external stakeholders and the Advisory Committee on Reactor Safeguards (ACRS) on the content of the rule.
5 Retirement Design Changes Configuration Control Surveillance Maintenance Operation Testing Construction System Design Functional Design Analyses (Prevention, Mitigation, Compare to Criteria)
LB Documents (Applications, SAR, TS, etc.)
Plant/Site (Design, Construction, Configuration Control)
Requirements Definition Fundamental Safety Functions Prevention, Mitigation, Performance Criteria (e.g., F-C Targets)
Normal Operations (e.g., effluents)
Other Technology Inclusive Regulatory Framework Project Life Cycle Clarify Controls and Distinctions Between Plant Documents (Systems, Procedures, etc.)
6 Example - Possible Layout General Provisions Technology-Inclusive Safety Objectives o Regulatory limits, safety goals Design Requirements Siting Construction and Manufacturing Requirements Requirements for Operation Decommissioning Requirements Applications for Licenses, Certifications and Approvals Maintaining and Revising Licensing Basis Information Reporting and Administrative Requirements
7 NRC Staff White Paper The NRC staff developed a white paper (ADAMS ML20195A270) to support discussions with ACRS and other stakeholders Soliciting information that:
1)
Defines the scope of stakeholder interest in a rulemaking to develop a technology inclusive framework for advanced nuclear reactors, 2)
Identifies major issues and challenges related to technology-inclusive approaches to licensing and regulating a wide variety of advanced nuclear reactor designs, 3)
Supports prioritizing and developing plans to resolve identified issues within the rulemaking for the wide variety of advanced nuclear reactor designs, and 4)
Supports the development of the proposed rule and related guidance.
Staff receptive to feedback on any aspect of developing a technology-inclusive regulatory framework to support the regulatory objective, whether or not in response to a question listed in this white paper or future solicitations.
8 Part 53 Rulemaking Objectives 1)
Provide reasonable assurance of adequate protection of the public health and safety and common defense and security at reactor sites at which advanced nuclear reactor designs are deployed, to at least the same degree of protection as required for current-generation light water reactors; 2)
Protect health and minimize danger to life or property to at least the same degree of protection as required for current-generation light water reactors; 3)
Provide greater operational flexibilities where supported by enhanced margins of safety that may be provided in advanced nuclear reactor designs; 4)
Ensure that the requirements for licensing and regulating advanced nuclear reactors are clear and appropriate; and 5)
Identify, define, and resolve additional areas of concern related to the licensing and regulation of advanced nuclear reactors.
9 Questions for Public Feedback 1.
Regulatory Objectives: Are the regulatory objectives, as articulated above, understandable and achievable? If not, why not? Should there be additional objectives? If so, please describe the additional objectives and explain the reasons for including them.
2.
Scope and Types of Advanced Nuclear Reactors: Should the scope of the rulemaking be limited to advanced nuclear reactors as defined in NEIMA or should the scope include all future applications for licenses, certifications, or approvals for commercial nuclear reactors regardless of design?
10 Questions for Public Feedback 3.
Technical Requirements versus Licensing Process: Should the framework focus only on those regulations related to technical standards (i.e., design, operational and programmatic requirements) and rely on the existing licensing processes in Parts 50 (e.g., construction permit and operating license) and 52 (e.g., early site permit, combined license, etc.) or should the framework develop a new alternative licensing process that looks different than the existing processes? If the latter, what should this new licensing process look like? Should this new process be self-contained, such that it would provide its own licensing, procedural, administrative, and reporting requirements?
11 Questions for Public Feedback 4.
Performance Criteria: NEIMA calls for a technology-inclusive framework for advanced nuclear reactors, which encompasses a wide range of reactor technologies and power levels. To what extent should the NRC try to define a single set of performance criteria for all technologies and sizes (e.g., estimated offsite doses from postulated events),
versus developing specific regulatory approaches for different categories of advanced nuclear reactors such as microreactors and fusion reactors?
12 Questions for Public Feedback 5.
Risk Metrics: In a risk-informed performance-based regulatory regime, should risk metrics be included in the regulations? Possible examples of risk metrics include the quantitative health objectives described in the NRCs Safety Goals for the Operation of Nuclear Power Plants Policy Statement (51 FR 28004, Aug. 4, 1986, as corrected and republished, 51 FR 30028, Aug. 21, 1986) and the frequency-consequence targets described in SECY 0117, Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors.
13 Questions for Public Feedback 6.
Facility Life Cycle: How could the new Part 53 licensing and regulatory framework align with the design, construction, operation, and decommissioning phases of an advanced nuclear reactor facilitys life cycle?
7.
Definitions: Should terms in the new Part 53 have identical definitions to terms in Parts 50 and 52? For example, SECY-19-0117 proposes to accept definitions for terms such as safety related and design basis event for non-light water reactors applications that differ from the definitions provided in 10 CFR Part 50. If possible, please provide alternative terminology for non LWR technologies.
14 Questions for Public Feedback 8.
Performance-Based Regulation: How should the requirements developed for this alternative regulatory framework incorporate performance-based concepts such as those described in NUREG/BR-0303, Guidance for Performance-Based Regulation?
15 Questions for Public Feedback 9.
Identifying Levels of Protection: Regulatory requirements in Parts 50 and 52 have been imposed as either needed to:
- 1) ensure a facility provides adequate protection to the health and safety of the public and is in accord with the common defense and security; or 2) provide a substantial increase in the overall protection of the public health and safety or the common defense in security when the costs of implementation are justified in view of the increased protection. Should specific requirements developed in this Part 53 rulemaking be identified as either needed to provide reasonable assurance of adequate protection or justified as cost-effective safety improvements?
16 Questions for Public Feedback
- 10. Integrated Approach to Rulemaking: In developing the requirements for this alternative regulatory framework, how can an integrated approach be developed to address areas such as safety, security, emergency preparedness, and other means to prevent or mitigate the potential release of radionuclides from an advanced nuclear reactor?
17 Questions for Public Feedback
- 11. Consistency with Historical Standards: SECY-19-0117 describes a methodology that is meant to support the licensing process through identifying key safety functions, events that might challenge those functions, performance criteria for equipment and related programmatic controls, and defense in depth. The methodology uses risk-informed and performance-based criteria that are derived from existing regulations related to potential offsite doses and from the NRCs Safety Goal Policy Statement (51 FR 30028; dated August 21, 1986). Should this rulemaking use these existing criteria or should this opportunity be used to adopt or develop alternative criteria? If so, please describe possible alternatives and explain the reasons for using them within the regulatory framework being developed for advanced nuclear reactors.
18 Questions for Public Feedback
- 12. Quality Assurance: Should quality assurance, as it is currently defined in Appendix B to Part 50, be a requirement in the new risk-informed, performance-based regulatory framework?
Alternatively, should NRC regulations defer to internationally recognized, independent certification schemes for assessing quality processes at commercial nuclear facilities and at suppliers of equipment and services?
19 Questions for Public Feedback
- 13. Stakeholder Documents, Standards, Guidance: The NRC encourages active stakeholder participation through development of proposed supporting documents, standards, and guidance. In such a process, the proposed documents, standards, and guidance would be submitted to and reviewed by NRC staff, and the NRC staff could endorse them, if appropriate. Is there any interest by stakeholders to develop proposed supporting documents, standards, or guidance?
20 Questions for Public Feedback
- 14. Other Issues: Are there significant issues, possible approaches, or other topics related to the initial crafting of a regulatory framework for advanced nuclear reactors that are not addressed in the above questions? If so, please identify the subject areas and, if possible, provide a suggestion on how the new framework could resolve the issue or incorporate a proposed approach.
21 Part 53 Rulemaking
22 Consequence Based Security (SECY-18-0076)
EP for SMRs and ONTs (SECY-18-0103)
Functional Containment (SECY-18-0096)
Insurance and Liability Siting near densely populated areas Environmental Reviews Licensing Modernization Project Backup Slide - Integrated Approach