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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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U,& iJCLfA REGULJY COMIUWON Citizens Exhibits 53 =4uq CC). lc Docet No. LIU O)-- C-ificial ExhbtW NO.CY-ý-5 e
5I/1 70 OFFERED by: Applicant/Lireflý
Intere*nor IDENTIFIED on .**VOiMMISSIr';fl ___
UNITED STATES Action Taken: "ADMITTED R *j.T6)WITHDRAWN WASHINGTON. 0I. C. 20555 eo rlar- .--
November 19, 1991 DOCKETED USNRC Docket No. 50-219 October 1, 2007 (10:45am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Mr. John 3. Barton, Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey' 08731
Dear Mr. Barton:
SUBJECT:
CLARIFICATION OF STAFF POSITION ON EVALUATION OF STRUCTURAL INTEGRITY OF A DEGRADED STEEL CONTAINMENT (TAC N0A79166)
References:
- 1. Letter to J. J. Barton from A. W. Dromerick providing the subject staff's position dated September 3, 1991.
- 2. Letter'to NRC from GPU Nuclear Corporation providing the-response to staff's position dated October 9, 1991.
In a letter of October 9, 1991 (Reference 2), GPU Nuclear Corporation (GPUM) provided responses to the staff position on the evaluation *of the structural integrity of a degraded steel containment. It appears from the responses that GPUN differs with the staff's position, specifically on the application of ASME subsection NE-3213.10. Enclosed is the staff's reviei of GPUN's response. It clarifies the staff's position and requ-ires GPUN to provide additional information to aid in a final resolution of staff's concerns.
We request that the information be provided within 30 days of receipt of this letter. If you have any questions regarding this request, please contact me.
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Mr. John J. Barton The requirements of this letter affect fewer than 10 respondents, and therefore, are not subject to Office of Management review under P.L.97-511, Sincerely, Is/
Alexander W. Dromerick, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects - I/1I Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page Distribution:
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NOT716
REVIEW OF GPUN'S RESPONSE OF OCTOBER 9, 1991 RELATED TO THE STAFF',S POSITION ON EVALUATION OF DEGRADED STEEL CONTAINMENT AT OYSTER CREEK The staff has reviewed GPU Nuclear Corporation's (GPUN) response of October 9, 1991 to the staff's position on the evaluation of the structural integrity of.
a degraded steel containment.. It is to be noted that this staff position is to be applied generically in the'evaluation of steel containments which are degraded, not specifically to the Oyster Creek steel drywell. The staff's position is based on technical criteria that conform to the spi.rit and intent of ASME subsection NE-3213.10. NE is. the design part of the ASME code and cannot be directly applied to the situation of inservice degradation without the exercise of engineering judgment. By considering the corroded area as equivalent to a-discontinuity as indicated in ME-3212.10, great caution must be exercised. It should be understood that the discontinuity as created by corrosion is not the same as the "designed" discontinuity such as a change.
in shell thicknesses, the presence of a bracket or a penetration as envisioned in the code. The basic characteristic of the discontinuity due to corrosion is irregularity, e.g. variation in thickness and extent of.corroded areas..,..
In view o~f the above observation, the ME 3312.10 stipulation cannot be applied
- indiscriminately to a corroded steel, containment. NE-3312.1O..:.specifies the limit of the discontinuity region in which the stresses can b-.greater than. 1.1 Smc. The code does not specify the outside limit of the region which is contiguous to and supports the discontinuity and in which the stresses vary from 1.1 Smc to 1.0 Smc. This -should be expected because this outside limit varies with the configuration of the discontinuity and the loading. Therefore, the lack of specific stipulation in the code in this respect should be understood and should notlbe construed to allow the stress limit of 1.1 Smc to be applied universally throughout the containment shell. The staff position is not, in any way, more restrictive than the stipulation in the ASME Code.
The staff is well aware of the extensive examinations and analysis performed on the Oyster Creek drywell as reported by GPUN. GPUN has repeatedly claimed that the Oyster Creek drywell has been examined thoroughly and the condition of the drywell is fully understood with a 95% confidence level. On the basis of this claim, the staff has requested OPUN to determine the extent of each corroded area. The staff is not requesting any additional physical examination.
However, on the basis of the information available, GPU.N should present in a figure the known areas of corrosion with the critical stresses (general primary membrane stress or local primary membrane stress) identified. The purpose of such an action is to determine the behavior of the drywell especially at and around the corroded areas. By comparing the calculated stresses of the drywell shell at and around corroded areas with the code allowables the staff can reasonably determine the adequacy of the licensee's proposed actions.
S.