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TECHNICAL SPECIFICATIONS FOR BRAIDWOOD STATION,UNITS 1 AND 2.Docket Nos. 50-456 And 50-457.(Commonwealth Edison Company)

. _NUREG-1223OTechnical Specifications.Braidwood StationUnit Nos.1 and 2Docket Nos. STN 50-456 and.STN 50-457Appendix "A" toLicense No. NPF-59OIssued by theU.S. Nuclear Regulatory,CommissioniOffice of Nuclear Reactor RegulationOctober 1986pm,,!.....O8A' 288u 8ea88136P PDR_ -- ...

Proposed Tech Specs,incorporating Tech Spec Change Request 147 to increase high drywell pressure limit to 3.5 psig & bypass isolation condenser high flow trip function upon initiation of alternate shutdown panel.

4OYSTER CREEK NUCLEAR GENERATING STATIONPROVISIONAL OPERATING LICENSE N0. DPR-16DOCKET N0. 50-219TECHNICAL SPECIFICATION CHANGE REQUEST NO. 147Applicant herehy requests the Commission to change Appendix A to the abovecaptioned license as below and, pursuant to 10CFR50.91, an a...

Safety Insp Rept 50-483/86-03 on 860211-0414.No violation or deviation noted.Major areas inspected:TMI action plan requirements,surveillance,maint,operational safety & Cycle 1 refueling outage.

.-.U.S. NUCLEAR REGULATORY COMMISSIONREGION IIIReport No. 50-483/86003(DRP)Docket No. 50-483 License No. NPF-30Licensee: Union Electric CompanyPost Office Box 149 - Mail Code 400St. Louis, MO 63166Facility Name: Callaway Plant, Unit 1Inspection At: Callaway Site, Steedman, M0I...

VERIFICATION TEST CALCULATIONS FOR THE SOURCE TERM CODE PACKAGE.

__ .. . .. ..._g.-..._NUREG/CR-4656BMI-2140,Verification TestCalculationsfor the Source Term Code Package.Prepared by R. S. Denning, R. O. Wooton, C. A. Alexander, L. A. Curtis,P. Cybulskis, J. A. Gieseke, H. Jordan, K. W. Lee, S. L. NicolosiBattelle's Columbus DivisionPrepare...

Forwards objectives,limitations & extent of play,scenario time line & scenario summary for plant radiological emergency plan 1987 annual exercise,for review.

__ . _ _ _1 4),nennt. see!|E ortlandGeneralElechicCervanyP-David W. Cockfield Vice President, NuclearJuly 31,'1987Trojan Nuclear PlantDocket 50-344License NPF-1U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington DC 20555Dear Mr. Martin:Trojan Radiological E...

S"S Northeast Rope Ferry Rd. (Route 156), Waterford, CT 06385 WN Nuclear ]Energy Milstnet Nuclear Power Station Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 I- I Ž A _4I- The Northeast Utilities System rl)-T27/// Doc...

NuScale Power, LLC - Response to NRC Request for Additional Information No. 397 (eRAI No. 9238) on the NuScale Design Certification Application.

RAIO-0518-60098NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comMay 21, 2018 Docket No. 52-048U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville P...

Forwards list of proposed addl changes to TS amend,related administrative controls & schedule for submitting TS change requests.

L Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DEC 12191) LR-N96411 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 CHANGES TO TECHNICAL SPECIFICATIONS SALEM GENERATING ...

NuScale Power, LLC - Submittal of Technical Report TR-0916-51502, "NuScale Power Module Seismic Analysis," Revision 2.

LO-0319-64834 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com Docket No. 52-048 April 03, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North...

NuScale Power, LLC Response to NRC Request for Additional Information No. 508 (eRAI No. 9621) on the NuScale Design Certification Application.

December 17, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 RAIO-1218-63854 Docket No. 52-048 SUBJECT: NuScale Power, LLC Response to NRC Request for Additional Information No. 508 (eRAI N...

Requests addl info within 30 days re response to Generic Ltr 83-28,Item 1.2.Parameters necessary to perform post-trip review & info re time history equipment incomplete.Draft technical evaluation rept,based on initial response encl.

.Docket No.: 50-483NOV 07 385Mr. D. F. SchnellVice President - NuclearUnion Electric CompanyPost Office Box 149St. Louis, Missouri S3166Dear Mr. Schnell:Subject: Request for Additional Information Regarding Generic Letter 83-28Item 1.2 for Callaway, Unit 1The NRC staff is cont...

Insp rept 50-482/96-21 on 961007-11 & 21-25.Violations noted.Major areas inspected:effectiveness of sys & design engineering organizations,performance of safety & operability evaluations & self-assessment activities.

..ENCLOSURE 2U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDocket No.: 50-48.2License No.: NPF-42Report No.:50-482/96-21Licensee: Wolf Creek Nuclear Operating CorporationFacility: Wolf Creek Generating StationLocation: 1550 Oxen Lane, NEBurlington, KansasDates: October 7-11 and 2...

January 15, 1997 SECY 97-011For: The CommissionersFrom: James L. Blaha, Assistant for Operations, Office of the EDOSubject: WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 10,1997Contents EnclosureNuclear Reactor Regulation ...

Final Topical Report Safety Evaluation for rhe US-APWR Topical Report MUAP-07010-P (R4), "Non-LOCA Methodology.

- 1 - FINAL SAFETY EVALUATION BY THE OFFICE OF NEW REACTORS TOPICAL REPORT MUAP-07010-P, REVISION 4 “NON-LOCA METHODOLOGY” MITSUBISHI HEAVY INDUSTRIES, Ltd DOCKET NO. 52-021 Contents 1.0 INTRODUCTION .....................................................................

Declaration of Gordon R. Thompson Addressing New and Significant Information Provided by the NRC's Near-Term Task Force Report on the Fukushima Accident.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD OR THE COMMISSION In the Matter of Docket # 50-293-LR Entergy Corporation Pilgrim Nuclear P...

Forwards application to amend License DPR-22,changing Tech Specs to add limiting conditions for operation & surveillance requirements for new RHR intertie line.

REGULATURYNFORMATION DISTRIBUTION S*TEM (RIDS)ACCESSION NbR:8406070223 DOCDATE: 84/05/29 NOTARIZED: NO FACIL:S0-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHUR AFFILIATION MUSOLFD, Northern States Power Co. RECIP.NAME RECIPIENT AFFILIATION Office of ...

Davis-Besse, Unit 1, Reply to Request for Supplemental Information for the Review of the License Renewal Application.

FENOCFirstEnergy Nuclear Operating Company5501 North State Route 2Oak Harbor Ohio 43449Bary S. AllenVice President - Nuclear419-321-7676Fax: 419-321-7582December 7, 2011L-1 1-376 10 CFR 54ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001SU...

2011/09/01 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 480 (5625, 5440,5613, 5573), FSAR Ch. 6, Supplement 3

1ArevaEPRDCPEm ResourceFrom: WILLIFORD Dennis (AREVA) [Dennis.Williford@areva.com]Sent: Thursday, September 01, 2011 7:51 AMTo: Tesfaye, GetachewCc: BENNETT Kathy (AREVA); DELANO Karen (AREVA); ROMINE Judy (AREVA); RYAN Tom (AREVA); GUCWA Len (EXTERNAL AREVA)Subject: Response ...

Proposed tech specs 3.13.1.A re limiting operation for operation.

_ _ .. ... . . - . _ - - . . . - - - . -- -- . . = . _-..**.:|,;ATTACIIMENT HZION NUCLEAR GENERATING STATIONIMARKED UP ANNOTATED COPY OF TECIINICAL SPECIFICATIONSFACILITY OPERATING LICENSESDPR-39 AND DPR-48APPENDIX A TECllNICAL SPECIFICATIONSRIIR REQUIREMENTS DURING CORE ALTER...

Proposed tech specs revising 3/4.1.2,3/4.3.1,3/4.7.6, 3/4.8.1,3/4.8.2,3/4.8.3 & 3/4.9.2 re positive reactivity insertions & reductions in RCS boron concentrations.

... .. .- . . . - - _ . . . . . ._- . - . . . . . _ . . . . . . _ , - _ _ . -*.<,,ia ,;Attachmerit II to NA 92-0122,'Page 1 of 10;iriiJ|2HARKED-1JP TECl!NICAL SPECIFICATION BASES PAGES. ;.!'fn.|-|!9212290119 921222PDR ADOCK 05000482P. PDR;;- . - - - - . _ - - - _ . , - . . -- ...

Susquehanna, Units 1 and 2 - Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (NRC Order EA-12-049).

Timothy S. Rausch President and ChiefNuclear Officer JUN 2 6 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 Timothy.Rausch@TalenEner...

Terrestrial Energy USA, Inc., Report 200608: Principal Design Criteria for IMSR Structures, Systems and Components

Abstract TERRESTRIAL ENERGY USA Principal Design Criteria for IMSR® Structures, Systems and Components TEUSA's long term licensing objective is to obtain a Standard Design Approval (SDA) for the IMSR® Core-unit. A necessary component of a 10 CFR Part 52 SDA application for the...

Provides proposed resolution for single issue of advanced reactor severe accident program Topic Paper Set 4, "Essential Equipment Performance."

c.-.,**.,> . . . . .September 9,1988LD-88-088Docket No. STN 50-470F(Project No. 675)Mr. Frank J. MiragliaAssociate Director for ProjectsOffice of Nuclear Reactor RegulationAttn: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Subject:Advanced React...

Requests review & approval of deviation from BWROG EPGs,rev 4,NEDO-31331,to permit EOPs to recognize 2/3 core height as adequate for core cooling following large break LOCA.

y--Northem States Power CompanyMorticello Nuclear Generating Plant'2007 West Hwy 75Monticetto, Minnesota $5362 9637November 18,1997US Nuclear Regulatory CommissionNUREG-0737Attn: Document Control DoskSupplement 1Washington, DC 20555MONTICELLO NUCLEAR GENERATING PLANTDockot No....

Unistar Nuclear - Nine Mile Point 3 COLA (FSAR), Rev. 0 - Chapter 3.0 Design of Structures, Components, Equipment and Systems

FSAR Chapter 3.0NMP3NPP 3–1 Rev.0© 2008 UniStar Nuclear Services, LLC. All rights reserved.COPYRIGHT PROTECTEDFSAR Chapter 3.0Table of Contents3.0 Design of Structures, Components, Equipment and Systems. . . . . . . . . . . . . . . .3–63.1 Compliance with Nuclear Regulatory Co...