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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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General Electric BWR/4 Plants, Rev 3.0 Vol 2 STS Plus Incorporated Travelers

Standard Technical Specifications General Electric Plants, BWR/4 Bases This electronic text represents the Commission’s current Standard Technical Specifications. This document is updated periodically to incorporate NRC approved generic changes to the Standar...

IR 05000282/2006003, 05000306/2006003; 4/01/06 - 6/30/06; Prairie Island Nuclear Generating Plant, Units 1 and 2; Inservice Inspection Activities, Reactor Vessel Head Replacement, Radiation Protection, and other activities.

August 14, 2006Mr. T. PalmisanoSite Vice PresidentPrairie Island Nuclear Generating PlantNuclear Management Company, LLC1717 Wakonade Drive EastWelch, MN 55089SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2NRC INTEGRATED INSPECTION REPORT 05000282/2006003;05000...

539th Meeting of the Advisory Committee on Reactor Safeguards, Minutes.

ML070871206 iCERTIFIED Date Issued: 03/29/07Date Certified: 03/29/07TABLE OF CONTENTSMINUTES OF THE 539th ACRS MEETINGFebruary 1 - 3, 2007 I. Opening Remarks by the ACRS Chairman (Open)II. Final Review of the Power Uprate Application for the Browns Ferry Nuclear Plant,Unit ...

A Literature Review of Structural Integrity of Existing Analog Canisters, Chapters 6 through End.

6-16 STRUCTURAL EVALUATION OF A MULTI-CANISTER OVERPACKMulti-canister overpacks were developed as part of the Hanford Spent Nuclear Fuel Project. The multi-canister overpacks facilitate the removal, processing, and storage of deterioratingspent nuclear fuel currently stored i...

12/02/05 - Ltr R Nelson to H Shamkhani (Duratek, Inc.) Authorization for Shipment in the Model No. UX-30 Package.

December 2, 2005Mr. Hisham ShamkhaniVice President, Logistics EngineeringDuratek, Inc.140 Stoneridge DriveColumbia, SC 29210SUBJECT: AUTHORIZATION FOR SHIPMENT IN THE MODEL NO. UX-30 PACKAGEDear Mr. Shamkhani:As requested by your application dated April 7, 2005, as supplemente...

Examination Outline Submittal for the Point Beach Nuclear Plant Initial Examination July 2007.

EXAMINATION OUTLINE SUBMITTAL FOR THE POINT BEACH NUCLEAR PLANT INITIAL EXAMINATION JULY 2007 Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC Committed io Nuclear Exca//ence April 10, 2007 NRC 2007-0016 Mr. Hironori Peterson, Chief Operations Branch U. S....

South Texas Project Unit 2, Request for Enforcement Discretion for Technical Specification 3.5.2 and 3.6.2.1.

Nuclear Operating CompanySouth Tetas Project Ektinc Generaftin Station PO. Box 289 Wadswortho Texas 77483 ***.December 4, 2006NOC-AE-060020901OCFR50.36STI: 32095724U. S. Nuclear Regulatory CommissionAttention: Document Control DeskOne White Flint North11555 Rockville PikeRock...

2003/03/14-Safety Light Corporation, Ltr. dtd 03/14/2003 Enclosing Response Action Work Plan (RAP).

AUXIER & ASSOCIATES. INC.9821 COGDILL ROAD, SUITE 1KNOXVILLE, TENNESSEE 37932PHONE: (865) 675-3669FAX (865) 675-3677INTERNET: www.auxier.comE-MAIL: info(auxier.comA O H S ADT7 -S , ,, e*RADIOLOGICAL HEALTH, SAFETY, AND ENVIRONMENTAL CONSULTING -iMarch 14, 2003VIA FEDERAL EXPRE...

Appendix B to ECCS Suctions DPV, NRC Bulletin 96-03: Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors. - (Records Already Publicly Available).

APPENDIX B (RECORDS ALREADY PUBLICLY AVAILABLE)ACCESSION NUMBER 9605020119DESCRIPTION/(PAGE COUNT) NRC Bulletin 96-03: Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors (10 pages)NO. DATE1. 5/6/96OMB No. 3150-0011 NRCB 96-03 UNI...

Final As- Administered Walkthrough JPMS For Prairie Island Initial Examination - August 2002.

FINAL AS-ADMINISTERED WALKTHROUGH JPMS FOR THE PRAIRIE ISLAND INITIAL EXAMINATION - AUGUST 2002ES-301 Control Room Systems Form ES-301-2 (R8, Si) and Facility Walk-Through Test OutlineFacility: Prairie Island Exam Level (circle one): -/ SRO(I) / SRO(U)B.1 Control Room Systems ...

Safety Evaluation Report, Model No. HI-STAR 100 Cask System Certificate of Compliance No. 9261, Revision No. 0.

ENCLOSURE 2SAFETY EVALUATION REPORT Model No. HI-STAR 100 Cask System Certificate of Compliance No. 9261 Revision No. 0 Summary By application dated October 23, 1995, as revised, Holtec International (Holtec) requested approval of the HI-STAR 100 cask system as a Type B(U)F-85...

10/22/2002 Summary of the Public Workshop on Key Issues Related to the Licensing of Future Non-Light Water Reactors.

November 13, 2002MEMORANDUM TO: Ashok C. Thadani, DirectorOffice of Nuclear Regulatory ResearchFROM: Farouk Eltawila, Director /RA/ original signed by C. TrottierDivision of Safety Analysis and Regulatory EffectivenessOffice of Nuclear Regulatory ResearchSUBJECT: SUMMARY OF TH...

Final - Section C Operating.

Scenario OutlineNine Mile Point 1 Scenario No. 1 Operating Test No. 1 Examiners: Candidates: SRO SRO-1 SRO-3 BOP RO-1 RO-2 RO-3 CSO SRO-2 SRO-4 SRO-5 Objectives: Evaluate candidates ability to perform routine operating tasks, raise and/or lower reactor power and to respond to ...

Limerick Generating Station, Units 1 & 2 Peach Bottom Atomic Power Station, Units 2 & 3 Common Nuclear Emergency Response Procedure Revision.

Exel ns. Exelon Nuclear www.exeloncorp.com N ucl e ar 200 Exelon Way Kennett Square, PA 19348 1OCFR50, Appendix E May 31, 2001 Docket Nos. 50-277 50-278 50-352 50-353 License Nos. DPR-44 DPR-56 NPF-39 NPF-85 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Wash...

Limerick, Amendment Nos. 75 & 36 to Facility Operating License Nos. NPF-39 & NPF-85 Relocating the Seismic Monitoring Instrumentation Limiting Condition for Operation, Surveillance Requirements, & Associated Tables & Bases.

August 29, 1994Docket Nos. 50-352 and 50-353 Mr. George A. Hunger, Jr. Director-Licensing, MC 52A-5 Philadelphia Electric Company Nuclear Group Headquarters Correspondence Control Desk P.O. Box No. 195 Wayne, Pennsylvania 19087-0195 Dear Mr. Hunger: SUBJECT: RELOCATION OF SEI...

Draft - Outlines (Facility Ltr dtd 12/21/00) Millstone, Unit 2.

V ''E Northeast Rope Ferry Rd. (Route 156), Waterford, CT 06385 Nuclear Energy i L Millstone Nuclear Power Station ' " I Northeast Nuclear Energy Company P.O. Box 128 Zr§ CI 26 11 9 9 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities System...

Salem, Unit 1 - Issuance of Amendment 25, deleting the Safety Technical Specifications (Appendix A) involving secondary water chemistry and inserts a new license requirement for implementing a secondary water chemistry monitoring program.

APR IL 2 2 1980 Docket No. 50-272 Mr. F. P. Librizzi, General Manager Electric Production Public Service Electric and Gas Company 80 Park Place, Room 7221 Newark* New Jersey 07101 Dear Mr. Librizzi: The Commission has issued the enclosed Amendment No.d"to Facility Operating Li...

Part 2 of 4, Limerick Generating Station, Units 1 and 2 Second Ten-Year Interval Inservice Inspection (ISI) Program, Appendix B Augmented Inspection Programs, Table of Contents.

Specification No. NE-042 Revision 3 Appendix B Page 1 of 91NPPENDIX B AUGMENTED INSPECTION PROGRAMS TABLE OF CONTENTSPROGRAM No. AUG-01 AUG-02 AUG-03 AUG-04 AUG-05 AUG-06 AUG-07 AUG-08 AUG-09 AUG-10 AUG-11 AUG-12 AUG-13 AUG-14 AUG-15 AUG-16 AUG-17 AUG-18DESCRIPTION USNRC Gene...

North Anna, Units 1 and Proposed Improved Technical Specifications Request for Additional Information ISTS 3.7.7 and ITS 3.7.9 Beyond Scope Issue.

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOlOD, VIRGINIA 23261 November 19, 2001 U.S. Nuclear Regulatory Commission Serial No.: 01- 560 Attention: Document Control Desk CM/RAB RO Washington, D.C. 20555 Docket Nos.: 50-338 50-339 License Nos.: NPF-4 NPF-7 Gentlemen: VIRGINIA ELE...

Joseph M. Farley, Units 1 and 2, Issuance of amendments 106 and 99, incorporating changes allowing longer surveillance test intervals and allowed outage times for reactor trip system and engineered safety features actuation system instrumentation into TS

¾>UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 1994 Docket Nos. 50-348 and 50-364 Mr. D. N. Morey, Vice President Southern Nuclear Operating Co., Inc. Post Office Box 1295 Birmingham, Alabama 35201-1295 Dear Mr. Morey: SUBJECT: ISSUANCE OF A...

Turkey Point, Issuance of amendments 10 and 9, incorporating in TSs revised Administrative Controls Section except for portion relating to reporting requirements which is still under review.

CHebron ACRS (14) AESteen SE.P ,JRBuchanan TBAbernathyand 5 1Florida Power and Light Company ATTN: Dr. Robert E. Uhrig Vice President P. 0. Box 013100 Miami, Florida 33101 Gentlemen:DISTRIBUTION: Docket NRC PDR Local PDR ORB-3 Reading Attorney, OELD OI&E (3) NDube BJones (w/4 ...

McGuire, Units 1 & 2, Correction to Amendments 128 & 110,

December 17,,'991Docket Nos. 50-369 and 50-370 Mr. T. C. McMeekin Vice President, McGuire Site Duke Power Company 12700 Hagers Ferry Road Huntersville, North CarolinaDISTRIBUTION SEENrY E28078-8985Dear Mr. McMeekin: SUBJECT: CORRECTION TO AMENDMENTS 128 AND 110, MCGUIRE NUCLEA...

Catawba Nuclear Station Units 1 & 2, Issuance of Amendment Nos. 81 & 75 to Facility Operating License Nos. NPF-35 & NPF-52, Relocation of Fire Protection Requirements from TSs to Final Safety Analysis Report , Chapter 16.0.

November 30, 1990Docket Nos. and50-413 50-414Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company P.O. Box 1007 Charlotte, North Carolina 28201-1007 Dear Mr. Tucker:SUBJECT: ISSUANCE OF AMENDMENT NO. 81 TO FACILITY OPERATING AND AMENDMENT NO. 75 T...

Comanche Peak Steam Electric Station (CPSES), License Amendment Request LAR 03-05, One-Time Change to Technical Specification (S) 3.7.10, Control Room Emergency Filtration/Pressurization System (CREFS) Completion Time.

* TXUTXU EnergyComanche Peak SteamElectric StationP.O. Box 1002 (EO1)Glen Rose, TX 76043Tel: 254 897 8920Fax: 254 897 6652lance.terry@txu.comC. Lance TerrySenior Vice President &Principal Nuclear OfficerRef: IOCFR5O.90CPSES-200301321Log # TXX-03096File # 00236July 10, 2003U. S...

Fermi 2, License Amendment 135, Amendment Revises Current TS 3.6.1.8 By Adding Footnote To Action B.

* Mr. Douglas R. Gipson October 19, 1999 Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166 SUBJECT: FERMI 2 - ISSUANCE OF AMENDMENT RE: ONE-TIME CHANGE TO THE REQUIREMENTS FOR PENETRATION X-26 IN THE DRYWELL AND SUPPRESS...