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Category:Legal-Exhibit
MONTHYEARIR 05000413/20083012009-02-0505 February 2009
Official Exhibit - CCS-118-00-BD01 - Catawba Nuclear Station NRC Operator License Examination Report 05000413-08-301 and 05000414-08-301
ML0513600792005-02-17017 February 2005
Security Exhibit List for Hearing Held from January 11 to January 14, 2005
ML0506702592005-01-13013 January 2005
Catawba Hearing - Staff Exhibit (SEC-28), Attachment 1. Resumes of Sherri L. Cross, Albert G. Garrett, Michael R. Burrell, R. John Vanden Berghe, John Brian Mckirgan, and William Troskoski
ML0506702552005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 8 (SEC-13), IAEA Safeguards Glossary 2001 Edition. International Nuclear Verification Series No.3
ML0506702152005-01-13013 January 2005
Catawba Hearing - Staff Exhibit 8 (SEC-24), the Physical Protection of Nuclear Material and Nuclear Facilities
ML0506701562005-01-13013 January 2005
Catawba Hearing - Staff Exhibit 7 (SEC-23), Technical Reports Series No.415, Status and Advances in MOX Fuel Technology
ML0506701442005-01-13013 January 2005
Catawba Hearing - Intervener Exhibit 14 (SEC-19), Doe'S Involvement in Negotiations on the Question of Whether to Revise the Convention on Physical Protection of Nuclear Material
ML0506701062005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 5 (SEC-10), NUREG/CR-1378, Rev 1, Hardening Existing Strategic Special Nuclear Material Storage Facilities
ML0506701042005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 1 (SEC-9), Curriculum Vitae of Edwin Stuart Lyman
ML0506700932005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 4 (SEC-4), Resume of Howard B. Williams
ML0506700862005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 1 (SEC-1), Steven P. Nesbit Statement of Professional Qualifications - Rec'D 01/11/05
ML0506700892005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 2 (SEC-2), Resume of Glenn A. (Skip) Copp, III
ML0506700902005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 3 (SEC-3), Resume of William Thomas Byers, III
ML0506700982005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 5 (SEC-5), Resume of Rita A. Edwards
ML0506701012005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 14 (SEC-7), Diagram of FS-65 Transportation Package, Cross-Section
ML0506701132005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 15 (SEC-8), Duke Energy Corp. Administrative Change to Facility Operating Licenses in Conjunction with the Commission Order EA-03-088 Re Revised Design Basis Threat and Revisions to Safeguards.
ML0506702622005-01-0909 January 2005
Catawba Hearing - Intervenor Exhibit 22 (SEC-A), the Big Gun, Broadcast on CBS Tv Show 60 Minutes
ML0503801632004-12-31031 December 2004
R. Nevin Staff Exhibit 6, Nirs/Pc EC-7: Duke Power, About Us Nuclear Power Plants, 2004, Available at Http://Www,Dukepower.Com/Aboutus/Plants/Nuclear
ML0422603132004-07-16016 July 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 52, Y. Yan, Et Al., LOCA Results for Advanced-Alloy and High-Burnup Zircaloy Cladding - Rec'D 07/15/04
ML0422603652004-07-15015 July 2004
Catawba Hearing 07/15/04 - Applicant Exhibit D, E. H. Karb, Et Al., Results of the FR2 In-Pile Tests on LWR Fuel Rod Behavior - Identified 07/15/04
ML0422603062004-07-15015 July 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 51, J. Papin, Et Al., Synthesis of CABRI-RIA Tests Interpretation - Rec'D 07/15/04
ML0422600822004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 19 - Figure 14, Figure M5 Rupture Strain Versus Rupture Temperature Slow Ramp Rate - Rec'D 07/14/04
ML0422602282004-07-14014 July 2004
Catawba Hearing 07/14/04 - Staff Exhibit 3 (Official Exhibit #40), Excerpt from Y. Yan, Et Al. Slide Presentation of LOCA Test Results for High-Burnup BWR Fuel and Cladding - Rec'D 07/14/04
ML0422602212004-07-14014 July 2004
Catawba Hearing 07/14/04 - Staff Exhibit (Official Exhibit #37), Professional Qualifications Statements of Undine Shoop, Ralph R. Landry, and Ralph O. Meyer - Rec'D 07/14/04
ML0422600432004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 10 - Figure 5, Thermal Conductivity Comparison for MOX and Leu Fuel (Fuel Porosity of 0.0479) (Figure Q21-1) - Rec'D 07/14/04
ML0422602122004-07-14014 July 2004
Catawba Hearing 07/14/04 - Intervenor Exhibit H (Official Exhibit #32), NUREG/CR-6744, Phenomenon Identification and Ranking Tables (Pirts) for Loss-of-Coolant Accidents in Pressurized and Boiling Water Reactors... - Rec'D 07/14/04
ML0422600742004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 16 - Figure 11, FR2 Test E4 for High Exposure Fuel (Relocation) - Rec'D 07/14/04
ML0422600182004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 08 - Figure 3, Mox/Leu Decay Heat Ratio - Rec'D 07/14/04
ML0422601132004-07-14014 July 2004
Catawba Hearing 07/14/04 - Intervenor Exhibit a (Official Exhibit #25), Edwin Stuart Lyman Curriculum Vitae - Rec'D 07/14/04
ML0422601082004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 18 - Figure 13, Figure M5 Rupture Temperature Correlation - Rec'D 07/14/04
ML0422601052004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 24 - Figure 19, Accumulated Cycle Irradiation in Effective Full Power Days - Rec'D 07/14/04
ML0422600952004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 23 - Figure 18, Fuel Exposure, Gwd/T - Rec'D 07/14/04
ML0422600912004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 22 - Figure 17, Micrograph of Irradiated MOX Pellet (Rg) - Rec'D 07/14/04
ML0422600862004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 21 - Figure 16, Micrograph of Irradiated Leu Fuel Pellet with Transverse Crack - Rec'D 07/14/04
ML0422600852004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 20 - Figure 15, Micrograph of Irradiated Leu Pellet with Typical Cracking - Rec'D 07/14/04
ML0422600312004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 14 - Figure 9, Previously Irradiated Rod 12, 74% Total Circumferential Elongation, 1066 K Estimated Burst Temperature - Rec'D 07/14/04
ML0422600762004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 17 - Figure 12, MOX Fuel and Cladding Temperature During LOCA Compared to Severe Accident Fuel Melt Temperatures - Rec'D 07/14/04
ML0422600172004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 07 - Figure 2 - Rec'D 07/14/04
ML0422602952004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 47, Professional Qualifications Statement of Steven P. Nesbit - Rec'D 07/14/04
ML0422602982004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 48, Professional Qualifications Statement of Robert C. Harvey - Rec'D 07/14/04
ML0422600302004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 13 - Figure 8 - Rec'D 07/14/04
ML0422600732004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 15 - Figure 10, FR2 Test B3.1 for Low Exposure Fuel (No Relocation) - Rec'D 07/14/04
ML0422600262004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 12 - Figure 7, Pin Power Peaking Factor, Fq, Cycle Exposure, EFPD - Rec'D 07/14/04
ML0422602992004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 49, Professional Qualifications Statement of Bert M. Dunn - Rec'D 07/14/04
ML0422603052004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 50, Professional Qualifications Statement of J. Kevin Mccoy - Rec'D 07/14/04
ML0422600222004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 11 - Figure 6, Pellet Radial Power Profiles 0.5 Gwd/T (Figure Q7-1) - Rec'D 07/14/04
ML0422600202004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 09 - Figure 4, MOX and Leu Fuel Pin Temperature Profile Comparison at Loss of Coolant Accident Initiation - Rec'D 07/14/04
ML0422600142004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 06 - Figure 1, Catawba MOX LOCA Temperatures - Rec'D 07/14/04
ML0422602742004-06-14014 June 2004
Catawba Hearing 07/14/04 - Staff Exhibit a (Official Exhibit #43), E-mail from Wolfgang Wiesenack to Miroslav Hrehor Re Statement in One of Segfsm Reports - Rec'D 07/14/04
ML0422603172004-06-0707 June 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 53, E-mail from Robert C. Harvey to Steven P. Nesbit Re Oecd/Nea/Csni Special Experts Topical Meeting on LOCA Fuel Safety Criteria, Cadarache France, March 22-23, 2001 - Rec'D 07/15/04
2009-02-05
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i DOCKETED Robert C Harvey To: Steven P NesbPWGen/DukePower@ DukePower USNRC C.cc 06/07/WO2004 04:25 PM sbet ae
Subject:
Paper 5 August 9,2004 (11:45AM)
OFFICE OF SECRETARY Forwarded by Robert C Harvey/GenlDukePower on 06/07/2004 04:25 PM RULEMAKINGS AND ADJUDICATIONS STAFF s iNssley,'Mitchen E.* To: "Robert C Harvey' <rcharvey~duke-energy.com>
- D nIssleme~westingho cc: Kobelak, Jeffrey R." <KobelaJR,1westinghouse.comr use.com>
Subject:
Paper 06/07/2004 03:34 PM qj2.pdfi>
This is from the Proceedings of the OECD/NEAICSNI Special Experts Topical Meeting on LOCA Fuel Safety Criteria, Cadarache France, March 22-23,2001. The paperwas actuaffy distributed ealier, as part of the NRC-sponsored High Bumup PIRT program. I commented on the expected significance of relocation In the following email:
<<RE: Apparent Contradiction>> 12.pdf
- Message from uNissley. Mitchell E." <nlsslemeGwestinghouse.corn> on Thu, 19 Oct 2000 12:28:22
-0400-To: joe@anatech.com, alexandc@battelle.org, lehnuc@engr.psu.edu, nwaeckel@epri.com, bdunn,@fra rdeveney@ framatech.com, geraldpotts@gene.ge.com, jens.andersen@gene.ge.com, fmoody@gfol wolfgang.wiesenack@hrp.no, georges.hache@ipsn.frjoelle.papin@ipsn.fr, bboyack@ianl.gov, do sej @nfuel.com, hgrkO3 @nspco.com, richardj.rohrer@nspco.com, toyo@nsrr.tokai jaeri.goJp, Afl keijo.valtonen@stuk.fi, k-peddicord~tamu.edu, tulenko@ufl.edu, 'Risher, Daniel Hi" <risherdh@
<ROM@nrc.gov>
cc: Harold Scott <HHS.twf5..po.TWFN DO@nrc.gov>, Sudharnay Basu <SXB2.twf5_po.TWF )C
<nissleme@westinghouse.com>, "Ohkawa, Katsuhiro" <ohkawak@westinghouse.com>, "Ebeling-
<derek.b.ebeling-koning@us.westinghouse.com>, "Blaisdell, John A. (Notes)" <john.a.blaisdel(i@
Subject RE: Apparent Contradiction Reviewing the transcripts at page 288, the discussion had to do with the experimental simulation of fuel relocation effects on local power generation. I would agree that fuel relocation is a real phenomenon which could have a significant effect on whether or not the experiments are prototype Designing an experiment with external heating to simulate these effects would certainly be challenling. However, analyzing the effects in a reactor transient Is more straightforward, and has been dorne by1several organizations. atJ b For the purposes of the analysis group, I think the ranking of mediums is appropri for igh bumup U02 fuel. Brent Boyack provided the following IPSN paper In his email of 6127/00:
(same attachment, deleted for storage reasons)
Using a deterministic method similar to the US Appendix K approach, IPSN showed What high bumup U02 fuel with relocation had margin to the 2200F1/1200C cladding temperature limit. The residual ductile cladding thickness was also sufficient to satisfy the Chung and Kassner criteria for thermal shock 011077 qe AemJXLTAS Ie 7~,,o/afe; o.g sec 10%
INUCLEAR REGULATORY COMivji,.; .
Docket No 5 L) Official Exh. No. _ _
In the matte Of _o Staff IDENTIFIED.II Applicant RECEIVED La Intervenor _ REJECrED Cont'g Off'r Cotractor DAE Other _,_____
, .d4.
.1, I embrittlement. It was noted that more severe results would be obtained for low bumuD U02 or high burnup MOX.
Westinghouse has included fuel relocation effects on local power generation, fuel thermal conductivity, and gap conductance in its best-estimate + uncertainties large break LOCA mQdel approved by the.
USNRC. When the analysis Is done statistically, 'such that all parameters are NOT at their worst value simultaneously as done in a deterministic calculation, the burst node is typically non-limiting except in very high temperature transients. The 10 CFR 50A6 acceptance criteria are met for low bumup U02 fuel.
The above supports the conclusion that rmeediumm Is an appropriate ranking for high bumup U02 fuel. A higher ranking for MOX may be appropriate.
Mitch From: Ralph Meyer[SMTP:ROM~nrc.gov]
Sent: Friday, October 13, 200010:52 AM To: 16etanatech.com; alexandcrbattelle.org; lehnuc engr.psu.edu; 'nwaeckelbepricom; bdunn@framatech.com; rdeveney~framatech.com; gerald.potts@ gene.ge.comr; jens.andersen~gene.ge.com; fmoodyigoldrush.com; lab@grs.de; wolfgangvWiesenack~hrp.no; georges.hache~ipsn.fr joelle.papin@ ipsn.fr, bboyack@ lanL.gov, dougwpruitf@ nfuel.com; seJ @nfuel.com; hgrkO3 @nspco.com; richard.j.rohrerl nspco.com; toyo @nsrr.tokal.jaeri.gojp; ATM2@psu.edu; keijo.valtonen stuk.fi; k-peddicord~tamu.edu; tulenko~ufl.edu; Nissley, Mitchell E.; Risher, Daniel H.
Cc: Harold Scott; Sudhamay Basu
Subject:
Apparent Contradiction PIRT Participants, During the LOCA PIRT meeting, we had discussions about fuel relocation =
into the ballooned section of a fuel rod. This discussion starts on p. =
288 of the transcript.
In Category B, the experimental group ranked 'Fuel relocation, residual =
bonding andlor dispersal as 7H, OM. OL and referred to this as a =
"significant effect.'
In Category C, the analytical group ranked "Fuel relocations as OH, 5M, OL =
and said it had a "modest effect on local linear heat rate."
My guess is that all the people who are concerned about this issue were in the experimental group and that the analytical group ranked this too low. =
Ballooning strains can be 100% (twice the diameter and four times the =
area) such that relocated fuel could substantially increase the local =
linear heat rate even though the rubble density would be less than the =
original pellet density.
This is one of the issues that I am going to include in my writeup of =
011078 AIOXL7Ar 5.e&
II
- i. -. , -
Implications and actions. Maybe we should re-visit this Issue during the =
discussions at the coming PIRT meeting. Please think about it. I have =
reviewed some older information on this subject since the last PIRT =
meeting and could mention that Information in a discussion at the next =
meeting.
Ralph 011079 QUOXLA
- S%'
