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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.S. NUCLEA REGULATORY COMMISS"O Citizens Exhibits 54 Do" No' OLILMC Exhibftýo C RAS P-L53/ September 2, 1993 ,,RERE by: APVIicant/LicensLea Ir>
NRP staff Other IDUTIED on l~ itfOss/pajelC Docket No. 50-219 Di stri buti or iAc~on TahwnmR -3 WýhD, Docket File NRC & Local Mr. John J. Barton -PD.I-4 Plant JI Vice President and Director *SVarga (14E4) DOCKETED GPU Nuclear Corporation JCalvo (14A2) USNRC Oyster Creek Nuclear Generating Station SNorris October 1,2007 (10:45am)
Post Office Box 388 ADromerick Forked River, New Jersey 08731 OGC (15B18) OFFICE OF SECRETARY EJordan (MNBB 3701) RULEMAKINGS AND
Dear Mr. Barton:
ADJUDICATIONS STAFF
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - ENVIRONMENTAL ASSESSMENT (TAC NO. M81093)
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact which relates to your submittal dated July 22, 1991, as supplemented February 14, 1992, August 19, 1992, and July 12, 1993, requesting a license amendment to revise Technical Specification 5.2.A to change the current containment drywell pressure of 62 psig to the new design pressure of 44 psig and the current containment drywell temperatures of 175 'F to the new design temperature of 292 7F Related changes to Technical Specification Bases are also proposed. Unrelated editorial changes to the Bases of Technical Specification 3.4 and 3.5 are also proposed.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, Original signed by:
Alexander W. Dromerick, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page J*
OFFICE LA:PDI-4 PM:PDI-# D:P-44,/A OGC NI DATE E1/ (193 193 ' -3 /1/ 91 93 /'
I Document Name: G:\DROMERIC\N81093.EA
- 110,11 4'ý 1 22120 C.68 7-plafevt ýe*cy- oae sec~v-o g-
{-n UNITED STATES X NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 2, 1993 Docket No. 50-219 Mr. John J. 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:
OYSTER CREEK NUCLEAR GENERATING STATION - ENVIRONMENTAL ASSESSMENT (TAC NO. M81093)
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact which relates to your submittal dated July 22, 1991, as supplemented February- 14, 1992, August 19, 1992, and July 12, 1993, requesting a license amendment to revise Technical Specification 5.2.A to change the current containment drywell pressure of 62 psig to the new design pressure of 44 psig and the current containment drywell temperatures of 175 'F to the new design temperature of 292 *F. Related changes to Technical Specification Bases are also proposed. Unrelated editorial changes to the Bases of Technical Specification 3.4 and 3.5 are also proposed.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, Alexan er W. Dromerick, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page MiC HECETI COP
Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station cc:
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts & Trowbridge c/o U.S. Nuclear Regulatory Cohmission 2300 N Street, NW. Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission .New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering CN 415 BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION GPU NUCLEAR CORPORATION JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-16 issued to GPU Nuclear Corporation, et al. (the licensee), for operation of the Oyster Creek Nuclear Generating Station, located in Ocean County, New Jersey.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed amendment would revise Technical Specification 5.2.A to change the current containment drywell pressure of 62 psig to the new design pressure of 44 psig and the current containment drywell temperatures of 175 'F to the new design temperature of 292 *F. Related changes to Technical Specification Bases are also proposed. Unrelated editorial changes to the bases of Technical Specification 3.4 and 3.5 are also proposed.
The proposed amendment is in accordance with GPU Nuclear Corporation's application dated July 22, 1991, as supplemented February 14, 1992, August 19, 1992, and July 12, 1993.
Need for the Proposed Action:
The proposed changes to the Facility Operating License are needed because it is a part of GPU Nuclear Corporation's comprehensive program to address the corrosion of the Oyster Creek drywell.
Environmental Impacts of the Proposed Action:
The Commission has completed its evaluation of the licensee's proposal to change the current containment drywell pressure of 62 psig to the new design pressure of 44 psig and the current containment drywell temperatures of 175 *F to the new design temperature of 292 'F. The licensee also proposes to change the related Technical Specification Bases.
Based on its review of the licensee's analyses and the licensee's statement that the analyses have been performed in accordance with the Standard Review Plan, the staff finds that the licensee's proposed change to reduce the current containment drywell pressure of 62 psig to the new design pressure of 44 psig and the current containment drywell temperatures of 175 °F to the new design temperature of 292 °F is acceptable. The Commission has datorminarl thnt thA nrnnncad rhanap dn nnt alter anv initial conditions