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SECY-14-0002 - Plan for Updating the U.S. Nuclear Regulatory Commission's Cost Benefit Guidance

POLICY ISSUE INFORMATION January 2, 2014 SECY-14-0002 FOR: The Commissioners FROM: Mark A. Satorius Executive Director for Operations SUBJECT: PLAN FOR UPDATING THE U.S. NUCLEAR REGULATORY COMMISSION’S COST-BENEFIT GUIDANCE PURPOSE: The purpose of this C...

Enclosure 1 GE Response to NRC Request for Additional Information Letter No. 3 for the ESBWR Design Certification Application PRA-RAI Numbers 19.0.0-7, 19.1.05, 19.1.0-6.

MFN 06-020 Enclosure 1 General Electric Company ENCLOSURE 1 MFN 06-020 GE Response to NRC Request for Additional Information Letter No. 3 for the ESBWR Design Certification Application – PRA – RAI Numbers 19.0.0-7, 19.1.0-5, 19.1.0-6 MFN 06-0...

Rancho Seco Nuclear Generating Station, Decommissioning Technical Basis Document.

DCGLs for RSNGS Structural Surfaces PREPARED BY: L. Brown /RA/ 8/2/04 Author Date REVIEWED BY: J. Newey /RA/ _ 5/23/05 Technical Reviewer Date ...

Schlumberger Technology Corporation - Deficiency Fax dated 10/27/2005.

TRA N S M ITTA L U.S. Nuclear Regulatory Commission Region IV 61 1 Ryan Plaza Drive, Suite 400 Arlington, Texas 7601 1 DIVISION OF NUCLEAR MATERIALS SAFETY Name: Raymond N. Dickes Licensee: Schlumberger Phone 281-285-8775 Fax 281-285-8526 From: Date: Subject : Pages: Judith Wa...

Westinghouse Electric Company, AP1000 Response to Request for Additional Information (SRP 18) in Support of the AP1000 Design Certification Amendment Application.

O WestinghouseWestinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USA412-374-6206412-374-5005.sisklrb@westinghouse.comU.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, D.C. 20555Direct tel:Direct fax:e-mai...

000-3DR-MGR0-00100-000, Rev. 007, "Project Design Criteria Document," Criteria/Basis Change Notice.

ENG.20071108.0001 BSC Criteria/Basis Change Notice Complete only applicable items. 1. QA: N/A 2. Page 1 of .3­3. Document Identifier: 000-3DR-MGRO-00100-000 6a. Title: Project Design Criteria Document 6b. Safety Classification of SSC: Non-ITS & Non-ITWI 7. Reason for Change: T...

Worchester Polytechnic Institute - Request for Additional Information.

Enclosure REQUEST FOR ADDITIONAL INFORMATION Worcester Polytechnic Institute (WPI) DOCKET No. 50-134 1. Comment: The Worcester Polytechnic Institute (WPI) Decommissioning Plan (DP) indicates in Section 1.2.2 that a historical site assessment and radiological surveys have b...

Joint Meeting of Essex & Union Counties, Renewal - Performance Evaluation Checklist dtd 12/13/2004.

APPENDJX C Performance Evaluation Checklist PERFORMANCE EVALUATION OF RENEWAL APPLICANT Official Agency Record I License or Docket No: 2? I 9 J X 8 -DJ Control No: L3FFf% I Records for the 5 years preceding this renewal application were reviewed andor appropriate staff were in...

07/16/2015, Summary of Category 3 Public Meeting to Discuss the Plan for Updating Cost-Benefit Guidance Phase 1.

U.S. Nuclear Regulatory Commission Public Meeting Summary August 11, 2015 Title: Public Meeting to Discuss the Plan for Updating Cost-Benefit Guidance Phase 1 Meeting Identifier: 20151022 Date of Meeting: Thursday, July 16, 2015 Location: U.S. Nuclear Regulator...

Affidavit of T Urbanik on Contention EPJ-1.Prof qualifications encl.

l..UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE TFE A 0MIC SAFETY AND LICENSING BOARDIn the Matter of)\CAROLINA POWEP AND LIGHT COMPANY AND ) .NORTH CAROLINA EASTERN MUNICIPAL) Docket Nos. 50-400 OLPOWER AGENCY) 50-401 OL)(Shearon Harris Fuclear Power Plant,)Uni...

Fort Calhoun, Unit 1, Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component due to Inoperable Power Source.

1Burkhardt, JanetFrom: Wilkins, LynneaSent: Tuesday, July 30, 2013 5:08 PMTo: 'HANSHER, BILL R'Cc: 'LIPPY, DONNA L'; 'EDWARDS, MICHAEL L'; Burkhardt, Janet; Sebrosky, JosephSubject: DRAFT: Fort Calhoun RAI Re: Revisions to TS 2.01 and 2.7 (MF0691)Attachments: MF0691 email RAI....

Enclosure 2: Summer Units 2 and 3 Nuclear Criticality Safety.

Enclosure 2 5.0 NUCLEAR CRITICALITY SAFETY 5.1 REGULATORY REQUIREMENTS The regulatory basis for the review of Virgil C. Summer Nuclear Station (VCSNS) nuclear criticality safety (NCS) is contained in Title 10 of the Code of Federal Regulations (10 CFR) 70.22, “Contents of Ap...

Fort Calhoun, Unit 1 - Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component due to Inoperable Power Source (TAC No. MF0691).

1Burkhardt, JanetFrom: Wilkins, LynneaSent: Thursday, August 22, 2013 2:21 PMTo: 'HANSHER, BILL R'Cc: 'EDWARDS, MICHAEL L'; Burkhardt, Janet; Sebrosky, JosephSubject: Fort Calhoun RAI Re: Revisions to TS 2.01 and 2.7 (MF0691)Bill, By letter dated February 18, 2013 (Agencywide...

OFFICIAL EXHIBIT - NYS000523-00-BD01 - NRC, Draft Reg. Guide DG-1309 (Proposed Revision 1 of Reg. Guide 1.207, dated March 2007), Guidelines for Evaluating the Effects of Light-Water Reactor Coolant Environments in Fatigue Analyses of Metal Components.

U.S. NUCLEAR REGULATORY COMMISSION November 2014OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1DRAFT REGULATORY GUIDE Technical Lead Gary L. Stevens This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regula...

Graded Approach - Potential Criteria for Improving Certificate of Compliance and Technical Specification.

1Donald ChungUS Nuclear Regulatory CommissionOffice of Nuclear Material Safety and SafeguardsREC CONDecember 7, 2016Graded Approach - Potential Criteria forImproving Certificate of Compliance and Technical Specification2Spent Fuel Dry Storage System Safety FunctionsSafetyFunct...

12/13/2017 Meeting Presentation, Time of Detection Should be Zero for Manual Non-Suppression Likelihoods.

Time of Detection Should be Zero for Manual Non-Suppression Likelihoods Rob Cavedo Potential Realism Improvement Time of Detection should be Zero for Manual Non-Suppression Likelihoods 1 The guidance in NUREG/CR-6850 Appendix P implicitly and through example directs that the d...

08/29/05 - Monticello Nuclear Generating Plant License Renewal RAIs and Audit Questions (Audit Question No.: 2.1.1-01.

Monticello Nuclear Generating Plant License Renewal RAIs and Audit QuestionsTotal Items: 18SSR AuditMonticello Nuclear Generating PlantLicense Renewal Audit Questions Sorted by Status, NRC Reviewer/Auditor, and RAI/Question Number Assoc LRA Section - 2.1.1According to Secti...

2009/03/12 PINGP LR - PINGP Letter Providing Supplemental Information for contentions 6 and 11

1PrairieIslandNPEm ResourceFrom: Vincent, Robert [Robert.Vincent@xenuclear.com]Sent: Thursday, March 12, 2009 1:26 PMTo: Richard Plasse; Nathan Goodman; Stuart SheldonCc: Eckholt, Gene F.Subject: PINGP Letter Providing Supplemental Information for contentions 6 and 11Attachmen...

Englnspec Corp., Telephone Conversation Record dtd 6/5/2007, Subj: VOID - Insufficient Information.

Page 1 Rev. 05/02/06Document Name:C:\FileNet\ML071560209.wpdU.S. NUCLEAR REGULATORY COMMISSIONTELEPHONE CONVERSATION RECORDDate: June 5, 2007Time: 9:00 a.m.Mail Controlor Report No(s).140326 License No(s). 52-31233-01 Docket No(s). 030-37439Name of Licensee: Enginspec CorpNa...

Proposed Recommendations for Generic Issue (GI)-186, "Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants".

November 12, 2003MEMORANDUM TO: J. E. Dyer, DirectorOffice of Nuclear Reactor RegulationFROM: Ashok C. Thadani, Director /RA/ by Ashok ThadaniOffice of Nuclear Regulatory ResearchSUBJECT: PROPOSED RECOMMENDATIONS FOR GENERIC ISSUE (GI)-186,“POTENTIAL RISK AND CONSEQUENCES OF ...

Appendix D - References (1).wpd - Safety Evaluation Report With Open Items Related to the License Renewal of the R.E. Ginna Nuclear Power Plant.

D-1APPENDIX DREFERENCESThis appendix contains a listing of references used in the preparation of the Safety EvaluationReport prepared during the review of the license renewal application for Ginna, DocketNumber 50-244.American Society of Mechanical Engineers (ASME)ASME Boiler ...

Department of Health & Human Services, Request for Additional Information Concerning Application for Renewal of License, Control No. 138288.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I475 ALLENDALE ROADKING OF PRUSSIA, PENNSYLVANIA 19406-1415 April 12, 2006Docket No. 03004675 License No. 20-08361-01Control No. 138288Edmond J. BarattaRadiation Safety OfficerDepartment of Health & Human ServicesPublic H...

2010/12/07 Victoria ESP - Response Requested: Draft RAIs for Victoria County Station ESP Application

1PMVictoriaESPPEm ResourceFrom: Jessie, JanelleSent: Tuesday, December 07, 2010 10:04 AMTo: david.distel@exeloncorp.comCc: Hale, Jerry; VictoriaESP ResourceSubject: Response Requested: Draft RAIs for Victoria County Station ESP Application Attachments: DRAFT RAIs- 2.3.3-2.3.5...

E-mail from J Schaperow to R Palla regarding MACCS Results vs Decay Time

"J asonScha erow - MACCS Results vs. Decay Time,,,-_-, From: Jason Schaperow /3 7To: Robert Palla Date: Tue, Sep 19, 2000 4:50 PM Subject: MACCS Results vs. Decay Time Attached are the results you requested. CC: Charles Tinkler, John FlackJao3cha~perow -MACCS Results for Bob ...