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Category:Legal-Exhibit
MONTHYEARML14029A3412013-07-0101 July 2013 Official Exhibit - STP000090-00-BD01 - Safety Evaluation by NRR, Proposed Transfer of Oyster Creek Nuclear Generating Station Operating License from Jersey Central Power & Light Company and Gpu Nuclear, Inc. to Amergen Energy Company, LLC, ML0823409702008-04-0303 April 2008 2008/04/03-Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_24, NRC, Notification of Information in the Matter of Oyster Creek Nuclear Generating Station License Renewal Application (April 3, 2008) ML0728303172007-09-25025 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit a, List of Exhibits ML0728508252007-09-25025 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit a, Staff Exhibit List ML0728501192007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 63, Note: Deliberately Omitted, Provided as Amergen Exhibit 7 ML0727805772007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 E, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region ML0727805712007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 C, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region ML0727805752007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 D, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region ML0727805552007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 a, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region ML0727805642007-09-24024 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 62 B, Color Photograph of Three-Dimensional Model of Quarter Section of the Sand Bed Region ML0728400722007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 5, Exelon Nuclear, Calculation C-1302-187-E310-041 Revision 0: Statistical Analysis of Drywell Vessel Sandbed Thickness... Note: Intentionally Omitted. ML0728303182007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit D, Curriculum Vitae of Rudolf H. Hausler ML0728500642007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 51, Sketches Showing Ultrasonic and Echo to Echo Techniques, and Explanations of Sketches (OCLR00026641) ML0728410782007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 23, Amergen, Disclosed Document Relating to Drywell Leakage (Ref. # OCLR00013354) ML0728501062007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 59, Deliberately Omitted, Submitted by Amergen as Applicant Exhibit 39 ML0728303162007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 9, Schematic Drawing Showing Detail of the Reactor Cavity Section, Detail a ML0727805002007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 60, L. Bertolini, Et Al., Corrosion of Steel in Concrete - Prevention, Diagnosis, Repair, Wiley - Vch, Weinheim, Germany, 2004, Selections Describing Corrosion Rates. ML0727705942007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 7, Schematic Drawing Showing Detail of the Lower Drywell/Sand Bed Region ML0727705452007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 25, Table Showing the Location, Mean Thickness (by Date), and the 95% Confidence Interval of the Internal UT Grid Data for the Sand Bed Region, 1992, 1994, 1996, 2006. ML0728303252007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 2, Partial Cross Section of Drywell and Torus ML0727705872007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 5, Schematic Drawing of the Drywell Shell Exterior ML0727805522007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 48, ASME Code Section XI, Article IWE: Inservice Inspection, Repair, and Replacement of Class Mc Pressure-Retaining Components ML0728500402007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 37, Background and Statement of Facts ML0727805312007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 43, Figure Showing Bay 19 UT Thickness Measurements and the Significant Difference Between Two Types of Statistical Confidence Limits ML0727805282007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 44, Scaled Maps of Internal and External UT Thickness Measurements for Bays 1, 13, 17, and 19 ML0728500342007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 33, Exelon Nuclear, Calculation C-13-2=198=532-=-24 Rev/ 2 P/C/ Drywell Ext. UT Eavluation in Sand Bed - Note: Intentionally Omitted, Submitted by Amergen. ML0728304812007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit C, Hausler Rebuttal Affidavit - Corrected Numbering. No Other Changes to Document ML0728500322007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 31, Amergen, Calculation Sheet C-1302-187-5300-011, Note: Intentionally Omitted, Submitted by Amergen at Applicant Exh. 23 ML0727705802007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit a, Amergen'S List of Exhibits ML0727706222007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 11, Drawings of the 0.536 Local Buckling Acceptance Criterion Tray (Front and Isometric Views) ML0727805242007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 36, Curriculum Vitae of Dr. Har Mehta (Duplicative of Witness Curriculum Vitae That Forms Part of Exhibit D) ML0727705992007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 8, Schematic Drawing Showing Detail of the Drywell to the Reactor Cavity Seal Detail, Detail B ML0727705912007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 6, Schematic Drawing Showing Top View of the Ten Bays in the Sand Bed Region ML0728509452007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit 4, Exelon Procedure TQ-AA-122, Rev. 3; Qualification and Certification of Nondestructive (NDE) Personnel ML0727705852007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 4, Schematic Drawing of the Cross-Section of the Drywell Shell (Embedded Into a Concrete Pedestal Atop the Reactor Building Concrete Foundation) ML0728303312007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 4, Exelon Nuclear, Calculation C-1302-187-5320-024 Revision 1: O.C. Drywell Ext. UT Evaluation in Sandbed - Note: Intentionally Omitted. ML0728508272007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit D, Professional Qualifications of Staff Witnesses, This Exhibit Contains All Statements of Professional Qualifications That Are Also Included in Staff Exhibits B. ML0727805212007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 35, Devoe Coatings Data Sheets for the Epoxy Coating System Installed in the OCNGS Sand Bed Region: Devoe Pre-Prime 167 and Devran 184: 100% Solids... ML0728400762007-09-20020 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 8, Amergen, Passport 00546049 07 (AR A2152754 E09): Water Found in Drywell Trench 5 - UT Data Evaluation - Note: Intentionally Omitted. ML0726105992007-09-14014 September 2007 Oyster Creek - Staff Exhibit 4 to the NRC Staff Response to Rebuttal Presentations ML0728508262007-09-14014 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit C.1, NRC Staff Sur-Rebuttal of Hansraj G. Ashar, Dr. James Davis, Dr. Mark Hartzman, Timothy L. O'Hara, and Arthur D. Salomon ML0727706102007-09-14014 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit C.1, Sur-Rebuttal Testimony ML0728304462007-09-13013 September 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit C1, Prefiled Sur-Rebuttal Written Testimony of Dr. Rudolf H. Hausler Regarding Citizens' Drywell Contention ML0727804792007-08-28028 August 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit 54, OCNGS Work Order No. R2104033: Inspect Poly Bottles for Presence of Water, 8-28-2007 Inspection Results ML0727706092007-08-17017 August 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit C, Rebuttal Testimony ML0728509402007-08-17017 August 2007 Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit C, NRC Staff Rebuttal Testimony of Hansraj G. Ashar, Dr. James Davis, Dr. Mark Hartzman, Timothy L. O'Hara and Arthur D. Salomon and Answer to Board Questions ML0728500452007-08-16016 August 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 39, Memorandum from Dr. Rudolf Hausler, Subject: Further Discussion of the Nature of the Corroded Surfaces and the Residual Wall Thickness of the Oyster Creek Dry Well ML0728500422007-08-16016 August 2007 Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 38, Memorandum from Dr. Rudolf Hausler, Subject: Response to the Questions About Statistics ML0722003062007-07-20020 July 2007 Amergen'S Pre-filed Direct Testimony Exhibits - Volume 1 of 2: Exhibits 1 - 19 ML0727706072007-07-20020 July 2007 Oyster Creek September 2007 Evidentiary Hearing - Applicant Exhibit B, Initial Testimony 2013-07-01
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DOCKETED Transcript excerpt from: USNRC.
Official Transcript of Proceedings October 1, 2007 (10:45am)
OFFICE OF SECRETARY Nuclear Regulatory Commission RULEMAKINGS AND ADJUDICATIONS STAFF Advisory Committee on Reactor Safeguards 485th Meeting held on September 6, 2001 Exhibit 62 I of 5
UA.MAUMMMLRW4 HU U I 1101I Citizens Exhibits 62 ASsMrir'0
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,fficial Exhibit NO. 6 O'= by: Applir DR. WALLIS: So you have some sort of acceptance criterion whi --.
has to be within some limits or something, or you just guess?
MR. ULSES: Well, actually, let mejump in here. Basically, what that statement is intended to mean is that if you look at the review of the kinetics package in its entirety, including both the test problem that -- called the GE-validation against experimental data on all of the other work that we did, basically the bottoni line conclusion was that the effect of any of the -- well, I am just thinking how best to put this.
That was really intended to discuss the fact that as Ralph said, we did have some --
well, some malingering differences in the prediction of power for the sample problem..
However, the effect of those differences on the bottom line answer for AO transients, which is the effect on changes in the minimum critical power ratio, was effectively nil, and actual what I mean by nil, was that it was basically almost impossible to see the effect.
But that's the relevant output of all of these transients. We do all this stuff with all these big codes, and we get one number out of it.
DR. WALLIS: What number did you get for uncertainty?
MR. LANDRY: Well, this is just looking at this transient.
MR. ULSES: Right. This is how it is applied in actual licensing of the plants. I mean, that's what they use to set the operating limits of the plant.
DR. WALLIS: I see. Well, the criteria for accepting this code are that there is reasonable models over physics, and that is part of it. But the other part of it is that when you make a prediction, you can also predict the uncertainty.
Now, that is the requirement for the best estimate code isn't it? Now, what the staff does with that I think is still up in the air. The-useofthe code maybe able to do all the things with CSAI and predict all these uncertainties.
But I don't think the staff has really thought through what it is going to do with these uncertainties when it gets them, and that's where I think we have also mentioned in our letters that, yes, our codes are doing all these things that we have asked them to do, and you need a measure of the predictions, and the answer, and the causes of all the answers and all of that.
But what are you going to do when you have got that? I mean, there has still got to be some relationship with these uncertainties to margins and acceptance criteria, and so on.
I am not sure that the staff really has thought that through. Do you have any comments on that?
Exhibit 62 2 of 5
MR. LANDRY: At this point, we would just have to say we are continuing to study that, and we are trying to define.
DR. WALLIS: Well, that's typical. I mean, you see, there must be a criterion, some acceptance criterion, when they want to uprate the power to some point where it is meeting some boundary.
Then how big the uncertainties are in the code are very important to know, and whether you may step over that boundary or not. So it seems to me that maybe the acceptabilities then are going to depend upon the use.
Yes, they have got a good code, and they have an assessment of uncertainty, and then look at something like power uprate, and start using this code, and then you can figure out perhaps how big the uncertainty or what is the effect of the uncertainty on your decision about whether or not they should be allowed to uprate power.
MR. CARUSO: Dr. Wallis, this is Ralph Caruso from the staff. We do actually have some criterion in this area for AOOs. For example, we set a safety limit minimum critical power ratios to ensure that 99.9 percent of the rods don't undergo boiling transition.
I think that your question is what does reasonable assurance mean, and I think that the ACRS has had this discussion with the Commission in the past about what reasonable assurance means, and I don't think there has ever been any definition that everyone has agreed to.
This is an eternal question that we try to deal with, and it comes out ofjudgment to a large extent at this point. When we can quantify it, for example, and say setting safety limit MICPRs, we try to do that.
We are trying to do our regulation in a more risk-informed manner, and that is another attempt to do it in a more quantifiable way. But right now these are the words that the law requires us to use to make a finding.
So those are, unfortunately, the words that we use and they are not well defined.
DR. WALLIS: But the law requires you to make a finding with 95 percent confidence.
MR. CARUSO: No, the law requires us to make a reasonable assurance finding.
DR. WALLIS: If your criterion is 95 percent confidence, then the fact that they have evaluated these uncertainties enables you to make that assessment.
MR. CARUSO: We could say that a 95 percent confidence does define reasonable assurance, but --
Exhibit 62 3 of 5
DR. WALLIS: That is the thing that I think is not being worked out yet. I mean, you have got the tools to do it, but if someone comes around like tomorrow and says reasonable assurance is 99 percent, then you have still got the tools to do it, but where you come out on allowing some change in the plant may be different.
MR. CARUSO: I really hate to pass the buck on this, but I do believe that this has been the subject of some extensive discussions with the Commission about the definition of reasonable assurance, and I don't believe that anyone has come up with an acceptable definition for all the parties involved.
DR. WALLIS: So maybe my --
MR. CARUSO: This is a little bit beyond my pay grade as they say.
DR. WALLIS: -- saying that you have got a good tool is, but the staff isn't quite sure how to use it, is a true statement.
MR. CARUSO: I can't explain why. I don't want to get into philosophy on this particular issue.
DR. WALLIS: It is not philosophy. It is really very real.
DR. KRESS: Yes, and in a number of our letters, we have commented that the staff needs to get more into formal decision criteria, and this is exactly what we mean by formal decision criteria.
How do you use these uncertainties to make our decision.
And you would come up with some sort of a technical definition of reasonable assurance that way, and we said that in a number of letters. And I think it could be repeated over and over. I think it is needed.
DR. WALLIS: And the reasonable assurance probably should be risk-informed. If it is not important to risk, then you can do it with less assurance perhaps.
MR. CARUSO: And there is a lot of effort going on in that area for a formal decision.
DR. KRESS: And that would be part of the formal decision process.
DR. WALLIS: That is part of a broader picture. So, maybe we should move on.
DR. KRESS: But I don't think that is these guys'job. They just have to be sure that the code can
-- well, I agree with you that if there is reasonable assurance that it does the uncertainty correct, then they have got a basis for saying its okay for this.
MR. CARUSO: As a lower level engineer, I would be thrilled if someone could define the term for me, but I have not seen it defined yet.
MR. LANDRY: Okay. Moving on to experience...
Exhibit 62 4 of 5
Official Transcript of Proceedings, Nuclear Regulatory Commission - Advisory Committee on Reactor Safeguards, http ://www.nrc.gov/reading-rm/doc-collections/acrs/tr/fullcommittee/2001/ac010906.html (last visited Sept. 13, 2007) (transcript excerpt from the 485th Meeting held on September 6, 2001).
Exhibit 62 5 of 5