ML16215A391
| ML16215A391 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/28/2016 |
| From: | Pickett D V Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D V, NRR/DORL/LPL1-1, 415-1364 | |
| References | |
| NRC-2504 | |
| Download: ML16215A391 (24) | |
Text
Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: 10 CFR 2.206 Petition Review Board RE Union of Concerned Scientists Docket Number s: Indian Point Nuclear Generating Unit Nos. 2 and 3. 50
-247 and 50
-286 Location:
teleconference
Date: Thursday, July 28, 2016 Edited by Douglas Pickett, August 2, 2016 Work Order No.:
NRC-2504 Pages 1-22 NEAL R. GROSS AND CO., INC.
Court Reporters and Transcribers 1323 Rhode Island Avenue, N.W.
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-4433 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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10 CFR 2.206 PETITION REVIEW BOARD (PRB)
CONFERENCE CALL RE UNION OF CONCERNED SCIENTIST'S PETITION DATED JUNE 30, 2016
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THURSDAY JULY 28, 2016
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The conference call was held, Eric Benner, Chairperson of the Petition Review Board, presiding.
PETITIONER: DAVID LOCHBAUM PETITION REVIEW BOARD MEMBERS ERIC BENNER, Dep uty Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation DOUGLAS PICKETT, Petition Manager for 2.206 petition RUSS ARRIGHI, Senior Enforcement Specialist,
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-4433 Office of Enforcement CHRISTOPHER HAIR, Attorney, Office of General Counsel ALLEN HISER, Senior Technical Advisor, Division of License Renewal JACK MCHALE, Branch Chief, Division of Engineering NRC HEADQUARTERS STAFF GANESH CHERUVENKI, Mechanical Engineer, Vessels and Internal Integrity Branch NIKLAS FLOYD, Acting Senior Project Engineer, Division of Reactor Projects, Region 1 MICHAEL MODES, Senior Reactor Inspector, Engineering Branch, Region 1 GARRETT NEWMAN, Resident Inspector, Indian Point SERITA SANDERS, Petition Coordinator, Office of Nuclear Reactor Regulation DIANE SCRENCI, Sr. Public Affairs Officer, Office of Public Affairs, Region 1 NEIL SHEEHAN, Public Affairs Officer, Office of Public Affairs, Region 1 TRAVIS TATE, Branch Chief, Division of Operating Reactor Licensing
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-4433 P R O C E E D I N G S 1 1:33 p.m.
2 MR. PICKETT: Good afternoon. I would like 3 to thank everybody for attending this meeting. My 4 name is Doug Pickett, and I am an Indian Point Project 5 Manager for the NRC's Office of Nuclear Reactor 6 Regulation.
7 We are here today to allow the 8 Petitioner, Mr. David Lochbaum of the Union of 9 Concerned Scientists, to address the Petition Review 10 Board, also referred to as PRB, regarding their 11 petition submitted on June 30th, 2016.
12 I am the Project Manager for this 13 petition and the PRB Chairman is Mr. Eric Benner. A s 14 part of the PRB's review of this petition, the Union 15 of Concerned Scientists requested this opportunity to 16 address the PRB.
17 This meeting is scheduled from 1:30 to 18 approximately 3:00 Eastern Time. The meeting is being 19 recorded by the NRC Operations Center and will be 20 transcribed by a court reporter. The transcript will 21 be treated as a supplement to the petition and will 22 be made publicly available.
23 I'd like to open this meeting with 24 4 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 introductions. As we go around the room please be 1 sure to clearly state your name, your position, and 2 the office that you work for within the NRC. I'll 3 start off with myself, Douglas Pickett. As previously 4 stated, I am serving as the Petition Manager.
5 MS. SANDERS: Hi, I'm Serita Sanders. I am 6 the backup f or Ms. Banic as the Petition Coordinator 7 in the Office of NRR.
8 MR. BENNER: Eric Benner. As Doug said, 9 I'm the PRB Chair, and I'm a Deputy Director in the 10 Division of Operating Reactor Licensing in the Office 11 of NRR. 12 MR. HISER: I'm Allen Hiser, Senior
-Level 13 Advisor in the Division of License Renewal, and I'm 14 a member of the PRB.
15 MR. CHERUVENKI: Ganesh Cheruvenki, 16 Materials Engineer, Vessels and Integrity Branch, 17 NRR. 18 MR. McHALE: I'm Jack McHale. I'm a Branch 19 Chief in NRR, Division of Engineering, and I'm a P RB 20 member. 21 MR. TATE: I'm Travis Tate. I'm a Branch 22 Chief in the Division of Operator Reactor Licensing 23 in NRR. 24 MR. HAIR: Hi, this is Chris Hair. I'm an 25 5 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 attorney with the Office of the General Counsel.
1 MR. PICKETT: We've completed 2 introductions at NRC Headquarters in this room. At 3 this time, are there any NRC participants elsewhere 4 on the phone?
5 MR. MODES: Michael Modes, Senior Reactor 6 Inspector, Region I.
7 MR. PICKETT: That was Michael Modes, and 8 I think Russ?
9 MR. ARRIGHI: Yes, Russ Arrighi, Senior 10 Enforcement Specialist, Office of Enforcement. I'm a 11 PRB member.
12 MR. PICKETT: Are there any 13 representatives for the licensee on the phone?
14 MR. WALPOLE: Yes, Doug. It's Bob Walpole 15 and Dave Mannai, both from Entergy.
16 MR. PICKETT: Okay. Would the 17 representatives of the Union of Concerned Scientists 18 please introduce yourselves along with anyone else 19 assisting you for the record.
20 MR. LOCHBAUM: David Lochbaum, Director of 21 the Nuclear Safety Project from Union of Concerned 22 Scientists, and it's jus t me. 23 MR. PICKETT: All right. It is not 24 required for members of the public to introduce 25 6 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 themselves for this call; however, if there are any 1 members of the public on the phone that wish to do so 2 at this time, please state your name for the record.
3 Hearing nothing, is there anyone else on the phone 4 that we missed?
5 MS. SCRENCI: Doug, it's Diane Screnci in 6 Region I, Public Affairs.
7 MR. PICKETT: Okay.
8 MR. NEWMAN: Garrett Newman, Resident 9 Inspector.
10 MR. PICKETT: So we have the Resident 11 Inspector here?
12 MR. NEWMAN: Correct.
13 MR. PICKETT: Who was it?
14 MR. NEWMAN: Garrett Newman.
15 MR. PICKETT: Okay. Garrett Newman, 16 Resident Inspector, Office of
-- somebody else spoke 17 at the same time?
18 MR. SHEEHAN: Neil Sheehan, Region I, 19 Public Affairs.
20 MR. PICKETT: Okay. Is there anybody else 21 on the phone with us?
22 MR. FLOYD: Lastly, this is Niklas Floyd, 23 Acting Senior Project Engineer, Division of Reactor 24 Projects, Region I.
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-4433 MR. PICKETT: Okay. I'd like to emphasize 1 that we each need t o speak clearly and loudly to make 2 sure that the court reporter can accurately 3 transcribe this meeting. If you do have something 4 that you would like to say, please state your name 5 first. For those dialing into the meeting, please 6 remember to mute your phones to minimize any 7 background noise or distractions. If you do not have 8 a mute button, this can be done by pressing *6 key; 9 to unmute press *6 key again.
10 At this time, I'll turn it over to the 11 PRB Chairman, Eric Benner.
12 MR. BENNER: Thank you, Doug, and th ank 13 you, Dave for scheduling this with us.
14 So good afternoon, welcome to the meeting 15 regarding the petition submitted by the Union of 16 Concerned Scientists. I'd like to first share some 17 background information on our process.
18 Section 2.206 of Title 10 of th e Code of 19 Federal Regulations describes the petition process, 20 the primary mechanism for the public to request 21 enforcement action by the NRC in a public process.
22 This process permits anyone to petition the NRC to 23 take enforcement
-type action related to NRC licensees 24 or licensed activities.
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-4433 Depending on the results of this 1 evaluation the NRC could modify, suspend, or revoke 2 an NRC-issued license, or take any other appropriate 3 enforcement action to resolve a problem. The NRC 4 Staff Guid ance for the disposition of 2.206 petition 5 requests is in Management Directive 8.11 which is 6 publicly available.
7 The purpose of today's meeting is to 8 provide the Petitioner an opportunity to provide any 9 additional explanation or support for the petition 10 before the PRB's initial consideration and 11 recommendation. The meeting is not a hearing, nor is 12 it an opportunity for the Petitioner to question or 13 examine the PRB on the merits or issues presented in 14 the petition request. No decisions regarding the 15 merits of this petition will be made at this meeting.
16 And following this meeting, the PRB will conduct its 17 internal deliberations. The outcome of this internal 18 meeting will be discussed with the Petitioner, 19 though. 20 The PRB typically consists of a Chairman, 21 usually a Manager at the Senior Executive Service 22 Level at the NRC, which I do fulfill that; a 23 Petitioner Manager, who is Doug Pickett, and a PRB 24 Coordinator, normally Lee Banic but for today it's 25 9 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 Serita Sanders. We are not
-- a number of members of 1 the Board here are basically based on their technical 2 and regulatory expertise to help, you know, derive an 3 effective evaluation of the petition.
4 As described in our process, the NRC 5 Staff may ask clarifying questions in order to better 6 understand the Petitioner's presentation and to reach 7 a reasoned decision whether to accept or reject the 8 Petitioner's request for review under the 2.206 9 process. 10 I'd like to summarize the scope of the 11 petition as we understand it under consideration and 12 the NRC activities to date. On June 30th, 2016, 13 sighting discovery of an unexpected degradation of 14 the baffle
-former bolts at the Indian Point Nuclear 15 Generating Station Unit 2, the Union of Concerned 16 Scientists submitted a petition pursuant to 10 CFR 17 2.206 reques ting the following enforcement actions.
18 One, NRC should issue an order requiring the Indian 19 Point licensee to inspect the baffle bolts and to 20 install the downflow to upflow modifications on Unit 21 2 during its refueling outage.
22 Two, NRC should issue a deman d for 23 information requiring the Indian Point licensee to 24 submit an operability determination to the Agency 25 10 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 regarding continued operation of Unit 3 until its 1 baffle bolts can be inspected per the Materials 2 Reliability Project, 227A.
3 And lastly, three, NRC issue a demand for 4 information requiring the Indian Point licensee to 5 submit an evaluation of the performance goal and 6 operating experience of the Metal Impact Monitoring 7 System detecting and responding to indications of 8 loose parts such as broken baffle bolts within the 9 reactor coolant system.
10 On July 7, 2016, the NRC Staff contacted 11 the Petitioner by email to offer him the opportunity 12 to make a presentation before the PRB, and the 13 Petitioner was also reminded that the 2.206 proces s 14 is a public process. On July 12th the Petitioner and 15 the NRC Staff reached agreement to schedule the PRB 16 presentation for today.
17 As a reminder to the phone participants, 18 please identify yourself if you make any remarks as 19 this will help us in the preparation of the meeting 20 transcript that will be made publicly available.
21 Thank you.
22 At this point, I'll turn it over to Mr.
23 Lochbaum of UCS to provide any information he 24 believes the PRB should consider as part of this 25 11 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 petition.
1 MR. LOCHBAUM: Thank you. This i s Dave 2 Lochbaum with the Union of Concerned Scientists.
3 Thank you, Doug and Eric for that tee up, for setting 4 it up. 5 As indicated, the reason UCS requested 6 this opportunity to present to the PRB was to 7 basically highlight or summar ize the request made in 8 our petition, and also to answer any clarifying 9 questions the PRB members or Staff may have for us.
10 With that, I'd like to start by pointing 11 out that by letter dated May 18th, 2016, which is in 12 ADAMS under ML16144A789, E PRI submitted to the NRC 13 summaries of the reactor vessel internals inspections 14 conducted at nine reactors during 2014 and 2015 under 15 MRP-227-A, the same procedure that identified the 16 degraded baffle bolts at Indian Point Unit 2. These 17 reactors had operated for 26.1 to 35.5 effective full 18 power years at the time these inspections were 19 conducted, with most having more operating time than 20 Indian Point Unit 2 did at the time of its discovery.
21 According to Table 4
-2 in another E PRI 22 report, MRP
-191 dated November 2006, which is in 23 ADAMS under ML12335A503, five of these reactors, or 24 five of these inspections were at reactors having the 25 12 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 downflow configuration that Entergy identified as 1 contributing to the degradation at Indian Point Unit 2 2. 3 All things being equal then it would be, 4 therefore, expected that these reactors would have 5 more extensive baffle bolt degradation than was 6 experienced at Indian Point Unit 2, but that was from 7 the case and things are far from being equal. Only 8 one of the 864 bolts e xamined at Palisades had 9 indications. Only one of the 864 baffle
-former bolts 10 examined at Oconee Unit 3 had an indication. Only 40 11 of 688 baffle
-former bolts examined at Prairie Island 12 Unit 1 had indications. Only 15 of the 727 baffle 13 bolts examined at Point Beach Unit 2 had indications.
14 None of the 305 baffle bolts examined at Turkey Point 15 Unit 3 had indications. There were more degraded 16 baffle bolts identified at Indian Point Unit 2 than 17 at these five as old or older reactors combined. For 18 reasons not yet identified and confirmed, the baffle 19 bolts at Indian Point Unit 2 experienced more 20 degradation than the bolts at reactors with more 21 operating time.
22 Because of this unexplained 23 vulnerability, UCS requested in our petition that the 24 NRC order Entergy to take two corrective actions the 25 13 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 company committed to take in its licensee event 1 report dated May 31st, 2016, which is in ADAMS under 2 ML 16159A219; namely, to reinspect the bolts and to 3 install the downflow to upflow conversion during the 4 next Unit 2 refueling outage. We explained in our 5 petition why commitments alone aren't sufficient.
6 Between now and the next scheduled Unit 7 2 refueling outage, Indian Point Unit 3 is scheduled 8 to have its next refueling outage. Entergy separately 9 has committed to volumetrically inspecting the baffle 10 bolts on Unit 3 for the first time during that outage.
11 Consider for a moment the possible 12 outcomes from the Unit 3 bolt inspections. Few 13 indications of degradation could be found comparable 14 to the results from inspections at other reactors 15 during 2014 and 2015. That outcome would make Indian 16 Point Unit 2 an even more unexplainable outlier.
17 Alternatively, the Unit 3 bolt 18 inspections could reveal degradation approaching or 19 even surpassing that found on Unit 2.
That outcome 20 would not help answer the question of why degradation 21 is so extensive on Unit 2, but it would reinforce the 22 need for the baffle bolts on Unit 2 to be reinspected 23 at the next convenient opportunity.
24 Our petition did not request that the NRC 25 14 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 issue an order compelling Entergy to conduct the 1 inspections of the baffle bolts on Unit 3 during the 2 refueling outage planned during 2017. Our request in 3 the petition to back commitments for the bolt issues 4 on Unit 2 with an order seems contradictory to our 5 request not seeking an order to back a commitment for 6 bolt issues on Unit 3, but that's only because it is 7 contradictory. Let me attempt to explain this 8 contradiction.
9 Our petition requested that the NRC issue 10 a Demand for Information requiring Entergy to conduct 11 an operability determination for Unit 3 continuing to 12 safely operate until the bolt inspections are 13 performed. We also requested that Entergy make its 14 operability determination publicly available by 15 placing it on the docke
- t. 16 From our perspective, this operability 17 determination would answer the timing of the initial 18 inspection question. It is highly likely that an 19 operability determination would rely in part on time 20 until the bolt inspections are performed. In other 21 words, the operability determination would very 22 likely articulate reasons why it's acceptable to 23 safely operate Unit 3 until some future refueling 24 outage when the inspections of baffle bolts will be 25 15 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 performed. Such an operability determination would 1 establish bou ndaries and conditions for continued 2 safe reactor operation like an order would do.
3 The UCS feels the operability 4 determination to be the more appropriate vehicle in 5 the case of Unit 3, much more applicable or 6 appropriate than an order.
7 There is ample evidence indicating that 8 the baffle bolts are needed to affirm the 9 degradation; thus, Entergy's plan to reinspect the 10 bolts and implement the downflow to upflow conversion 11 during the next refueling outage on Unit 2 i s sound, 12 so sound safety
-wise that backing up that great 13 intention with a regulatory requirement is most 14 prudent. But there is enough evidence indicating that 15 the baffle bolts on Unit 3 are a lso degraded. Maybe 16 they are as degraded as the bolts on Unit 2, or maybe 17 they have little to no degradation like the bolts 18 inspected at several other reactors in 2014 and 2015.
19 Absent more compelling evidence, UCS does 20 not feel that requesting that the NRC issue an order 21 for baffle bolt inspections on Unit 3 or for le tting 22 Entergy implement the downflow to upflow conversion 23 during its next refueling outage was justified.
24 UCS does feel that Entergy should be 25 16 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 required to assemble and evaluate the scant evidence 1 that is available, and justify operating Unit 3 until 2 some future date when the bolt inspections are 3 performed.
4 Operability determinations for 5 situations like this one are standard industry 6 practice and are entirely consistent with the NRC's 7 longstanding expectations. Thus, in operability 8 determinations, the tried and true way to handle 9 situations like on Unit 3 at the moment.
10 Our third and final request in the 11 petition was for the NRC to issue a Demand for 12 Information to Entergy regarding the performance of 13 the Metal Impact Monitoring System at Indian Point.
14 There is no evidence publicly available indicating or 15 even suggesting that this system detected the loose 16 parts from the degraded and broken bolts on Unit 2.
17 That's the sole purpose of this system and yet it 18 seems to have utterly failed to perform this role.
19 This system, if it functions as intended, 20 could from part of the safety net for continued safe 21 operation of Unit 2 until someone figures out why its 22 bolts are so prone to degradation, and for the 23 continued safe operation of Unit 3 until someone 24 figures out whether its bolts are Unit 2
-like, or 25 17 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 more like bolts elsewhere in the industry. But this 1 safety system seems to be nothing but a hunk of junk 2 occupying space without any redeeming value 3 whatsoever. Consequently, UCS feels that Entergy 4 should evaluate this system that's described in the 5 FSAR to determine whether it should play or can play 6 a useful role in proactively detecting baffle bolt 7 degradation.
8 Thank you for your consideration of our 9 issues, and I'll be glad to answer any questions from 10 the NRC Staff.
11 MR. BENNER: Okay, thank you, Dave.
12 I'm going to offer the opportunity for 13 the Staff here at Headquarters to ask any questions 14 of the Petitioner. I have some questions, but I'll 15 hold mine until everyone else speaks. So I'll start 16 here with the Staff in the room; do any of the Sta ff 17 in the room have questions for Dave?
18 MR. HISER: This is Allen Hiser of License 19 Renewal. Page 5 of your petition cites the Unit 3 20 UFSAR description of the loose parts monitoring. Is 21 that -- are similar provisions in the Unit 2 FSAR?
22 It's curious to me th at you're citing Unit 3 but yet 23 you're concern was with the function of Unit 2.
24 MR. LOCHBAUM: This is Dave Lochbaum. For 25 18 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 the past decade, the NRC has been blanket withholding 1 FSAR updates, and only recently restarted putting 2 UFSAR updates in the public domain, so it's been very 3 challenging for the public to obtain access to FSAR 4 information. I assume that similar to Unit 2, but the 5 limited access that the NRC has afforded the public 6 to these documents makes me uncertain. So I chose t he 7 documents I could find, and those that the NRC chose 8 to make available.
9 MR. HISER: Thank you.
10 MR. McHALE: This is Jack McHale from the 11 Division of Engineering. Just have a minor question; 12 on the petition on the top of page 4 it makes a 13 reference to Ma nual Chapter 0305 which is the 14 Operating Reactor Assessment Program. Is that a
-- I 15 know there's an earlier reference to 0326 for 16 Operability. Does the 0305 come into play here, or is 17 that just a typo?
18 MR. LOCHBAUM: That's a typo; my mistake.
19 Yes, it went back to the middle
-- the previous page 20 where I cited some criteria, and I just noticed it on 21 the next page.
22 MR. McHALE: Okay, so we're still talking 23 about the same areas. Okay, thank you.
24 MR. LOCHBAUM: That was the intention, but 25 19 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 it was mistake to get th e number wrong.
1 MR. BENNER: Questions for Dave? Okay, it 2 seems we have no other questions in the room, so are 3 there any other questions from the Headquarters folks 4 on the phone? Hearing none, I'll turn it over to are there any q uestions from our Regional 6 participants? Does the licensee have any questions or 7 comments?
8 MR. WALPOLE: This is Bob Walpole; no 9 comments, no questions.
10 MR. BENNER: Okay. Thank you, Bob.
11 So, Dave, my
-- this is Eric Benner 12 again. Mine are less questions t hat just sort of 13 confirm kind of where
-- our understanding of your 14 request. So for your
-- so your request regarding the 15 order for Unit 2, is it safe to conclude that you 16 essentially find the Corrective Actions that have 17 been proposed by the licensee to appear to be 18 sufficient. What you're looking for is a stronger 19 regulatory footprint by the NRC to insure those 20 corrective actions actually get implemented.
21 MR. LOCHBAUM: That is correct. This is 22 Dave Lochbaum. That is correct. As we espoused in the 23 petition, we're a little concerned that that's
-- the 24 current MRP 227
-A guidance would allow that to be 25 20 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 deferred for up to 10 years.
1 MR. BENNER: Okay.
2 MR. LOCHBAUM: We think, as I said, the 3 corrective actions that Entergy provided a good
--- 4 MR. BENNER: Okay. And then regarding your 5 request for the Demand for Information on Unit 3, 6 your logic there is, you know, in the absence of some 7 sort of publicly available information on the 8 applicability of this degradation mecha nism to Unit 9 3, you don't feel you have enough information to 10 warrant, you know, proposing to the NRC anything that 11 would fall within the 2.206 process like, you know, 12 ordering inspections or ordering some other activity.
13 MR. LOCHBAUM: That's correct. We think 14 the operability determination when it can be done 15 would answer those kind of questions and would show 16 why waiting until the next refueling outage is a good 17 thing. 18 MR. BENNER: Okay.
19 MR. LOCHBAUM: What we've heard today is 20 that the reason Unit 3 is okay is because it doesn't 21 have as much operating time as Unit 2 did and, 22 therefore, it's less
-- is likely to have experienced 23 less bolt degradation. That's why the information I 24 provided e arlier in this call with even older 25 21 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 reactors with more operating time having less bolt 1 degradation seems to suggest that operating time is 2 not the primary factor in determining extended bolt 3 degradation. Where the operability determination once 4 performed would more fully address issues like that 5 and explain why Unit 2 is different.
6 MR. BENNER: But for me these two parts to 7 this, because typically we would
-- the NRC would 8 look at operability determinations and the inspection 9 realm and, you know, as you well know, you know, the 10 inspection report when issued, you know, may not have 11 a sufficient level of detail that would allow you to 12 feel you could, you know, render judgments over the 13 underlying technical issues. So part of the issue 14 here is you're looking for a level of, you know, 15 public availability of this information.
16 MR. LOCHBAUM: That's a good point. It is 17 that second aspect, because this issue has attracted 18 so much attention, making an operability 19 determination is atypical but i t seems appropriate 20 given the environment or the context that it's in.
21 MR. BENNER: Okay. Those were the only two 22 clarifications I had, so with that, before I conclude 23 the meeting, no members of the public identified 24 themselves, but members of the public may provide 25 22 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 comments regarding the petition and ask questions 1 about the 2.206 petition process. However, as stated 2 in the opening, the purpose of this meeting is not to 3 provide an opportunity for the Petitioner and the 4 public to question or examine the PRB regarding the 5 merits of the petition request, so you certainly can 6 provide any comments, as desired.
7 Hearing none, I'd like to thank Mr.
8 Lochbaum for taking the time to provide the NRC Staff 9 with clarifying information on the petit ion you 10 submitted. And before we close does the court 11 reporter need any additional information for the 12 meeting transcript?
13 COURT REPORTER: Hi, this is the court 14 reporter. If I could get the representatives of the 15 licensee to please state their names for me, that 16 would be great.
17 MR. WALPOLE: Sure, I'll speak. My name is 18 Bob Walpole, W
-A-L-P-O-L-E, and I'm the Regulatory 19 Assurance Manager for Entergy. And the other person 20 that was listening in on the call, his name is David 21 Mannai, M
-A-N-N-A-I, and he also
-- he's a Senior 22 Manager of Regulatory Assurance for Entergy.
23 COURT REPORTER: Okay. Thank you very 24 much. 25 23 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
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-4433 MR. BENNER: And with that this meeting is 1 concluded, and we'll be terminating the phone 2 connection. Thank you very much, all.
3 MR. LOCHBAUM: Thank you.
4 (Whereupon, the proceedings went off the 5 record at 1:59 p.m.)
6 7 8