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2007/09/28 - Indian Point 2 and 3 - FUSE Corrected Petition for Leave to Intervene, Request and Contentions; and Notice of Appearance, Exhibit L.

EXHIBIT LRCS Operational LEAKAGE3.4.133.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGELCO 3.4.13 RCS operational LEAKAGE shall be limited to:a. No pressure boundary LEAKAGE,b. 1 gpm unidentified LEAKAGE,c. 10 gpm identified LEAKAGE, andd. 150 gallons per day prim...

Watts Bar, Unit 2 - Final Safety Analysis Report (FSAR), Amendment 104, Section 3.8, Design of Category I Structures, through Figure 3.8.4-80.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-104m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...

1/12/10; R. Boyle, U.S. DOT; Consolidated Tables for NCS-45 Package.

Enclosure 2 Table of TS-R-1 2005 General Requirements for Packages Number Summary of Requirement Staff Evaluation 606 Package mass, volume and shape shall be such that it can be easily and safely transported. In addition, the package needs to be prope...

DAEC 2009 Revised Written Exam Outline (ES 401-1,3,4).

ES-401 Written Examination Outline Form ES-401-1 Facility: DAEC Date of Exam: September 2009 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1 3 4 2 4 4 3 20 5 2 7 2 1 1 2 1 1 1 7 2 1 3 1. Emer...

Mitsubishi Heavy Industries' Responses to US-APWR DCD Draft Open Items 16.4.6 and 16.4.11.

A&MITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANNovember 11, 2009Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-09518Subject: MHI's Responses to US-AP...

Requests addl info in support of review of application for CP,including reactor design,reactor vessel primary sys,ESF, seimic design & safety evaluation.Summary of PSAR deficiencies encl.

Docket No. 50-286 Consolidated Edison Company of New York, Inc. 4 Irving Place New York, New York 10003 Attention: Mr. Donham Crawford Administrative Vice President Gentlemen: We have completed our review of the information in your application for a construction permit for In...

2009/05/26-Petition by Citizen Power to Require Supplementation of the Safety Evaluation Report for Beaver Valley Power Station, Units 1 & 2.

1May 26, 2009 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION ______________________________________________________ ) In the Matter of ) ) Docket No. FirstEnergy Nuclear Operating Company ) 50-334 and (Beaver Valley Power Stati...

"Technical Evaluation of Hatch Units 1 & 2 Plant-Unique Analysis Repts."

Enclosure 3'.Technical Evaluation of the Hatch (Units 1 & 2)Plant-Unique Analy:is Reports.John D. RanletConstantino Economosi.Reactor Safety Licensing Assistance DivisionDepartment of Nuclear EnergyBrookhaven National Laboratory-4Upton, New York 11973September 1983.FIN-A-3713B...

EVALUATION OF SEVERE ACCIDENT RISKS: SURRY UNIT 1.Main Report.

- . .. . - .. . ..4.NUREG/CR-4551SAND 86-1309Vol. 3, Rev.1, Part 1,Evaluation ofSevere Accic.ent Risis:Surry Unit 1'Main Report.J l e ng, J. C liciton, W. B. Murfin, L N. SmithSandia National Laboratories-Operated bySandia CorporationPrepared for -U.S. Nuclear Regulatory Commi...

Vogtle Electric Generating Plant, Units 3 & 4, Revision 8 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Appendix 2.5A - Geotechnical Investigation and Laboratory Testing Data Report - ESP

2.5A-1 Revision1VEGP 3&4 – UFSARAppendix 2.5A—Geotechnical Investigation and Laboratory Testing Data Report – ESP(Excludes contents of report; cover page only)Prepared byMACTEC Engineering and Consulting, Inc.November 16, 20072.5B-1 Revision1VEGP 3&4 – UFSARAppendix 2.5B—High ...

Forwards June 1979 "Response to Dept of Natural Resources Specific Comments on Amends 11 & 12 Environ Rept."

.WISCONSINUTILITIESPROJECTAPPLICANTS' RESPONSETODEPARTMENT OFNATURAL RESOURCES'SPECIFIC COMMENTS ONAMENDMENTS II AND 12THE ENVIRONMENTAL REPORTHAVEN NUCLEAR PLANT.2229 303WISCONSIN ELECTRIC POWER COMPANYWISCONSlH POWER & LIGHT COMPANYWISCONSIN PUBLIC SERVICE CORPORATION;UNe i9...

Susquehanna, Unit 2, Technical Requirements Manual

• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 20:J-9-12954 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 08/23/2019 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (N...

"Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study," draft rept.

__ _ __. _ _ - _ _ - .._**~DRAFT=.Letter ReportonReview and Evaluationof theIndian Point Probabilistic Safety StudyAugust 25, 1982.Sandia National LaboratoriesAlbuquerque, New Mexico87185Prepared forReliability and Risk Assessment BranchOffice of Nuclear Reactor RegulationU. S...

OVERVIEW OF TRAC-BD1/MOD1 ASSESSMENT STUDIES.

_ _,j-"~NUREGICR4428*EGG-2422-November 1985Overview of TRAC-BD1/ MOD 1Briant L. Charboneau|Assessment Studies'-~. te.'.,F O R M A L R E P O R T EGcGw u.pWork performed underDOE Contract No DE-AC07-76|D01570forthe U.S. NuclearRegulatory CommissionAm- ."1 |i.-:,atw.a:n/,3 mfd,,x...

Forwards Tech Spec improvement program discussed in 850409 meeting.Program attempts to make Tech Specs more useful document for control room operators.

_ _%'.MIMay 29, 1985SBN-806Pub 5c Service of New Hampshire T.F. B7.1.1New Hampshire Yankee DivisionUnited States Nuclear Regulatory CommissionWashington, DC 20555Attention: Mr. George W. Knighton, ChiefLicensing Branch No. 3Division of LicensingReference: (a) Construction Perm...

Susquehanna Steam Electric Station Unit 2 - Rev. 2 to Technical Requirements Manual.

• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2020-4683 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 03/18/2020 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCS...

Proposed tech specs,consisting of change requests 226 & 98, revising Table 3.3-3 functional Unit 4.c & Spec 3/4.5.5 & associated Bases Section for Unit 1 & 3/4.5.4 for Unit 2.

- . . . - . . . _ - . . . _. . - - - _. - _ _ . - -!(!! .jATTACHMENT A-1 !-,4\Beaver Valley Power Station, Unit No. 1l 1|Proposed Technical Specification Change No. 226lIi.Il|The following is a list of the affected pages:i|Affected Pages:3/4 3-18i3/4 5-8! B 3/4 5-3:B 3/4 5-5i!...

Forwards Rev 6 to response to NUREG-0588,incorporating final resolution of all environ qualification audit items,updated info for main steam line break in doghouse & equipment addition & deletions.Attachment 5 not revised.

._________ _ ____ijDUKE POWER GOMPANYP.O. BOX 33180CIEARLOTTE. N.C. 28242HAL B. TUCKERTELEPHONEV908 PRESIDENT(ros) ara-seApril 1, 1985 = == ri--.Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attentio...

Summary of ACRS Advanced Reactors Design Subcommittee 880803 meeting in Washington,DC re review of NRC draft SER for modular high temp gas-cooled reactor & remaining safety- related issues from 880622 meeting.

'OMS -as99- -..CERT 1FH~-.DATE ISSUED: 8/15/88ACRS Meeting Minutes /Sumary of theAdvanced Reactors Designs SubcomitteeAugust 3, 1988Washington, D.C.PurposeThe purpose of the meeting was to continue the review of the NRC staff'sdraft safety evaluation report (SER) for the modul...

BEHAVIOR OF A CORIUM JET IN HIGH PRESSURE MELT EJECTION FROM A REACTOR PRESSURE VESSEL.

. _ . - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ __ _ - _ _ - __ - __- - - - ____ _ ___'*.,NUREG/CR-4508SAND 85-1726R1,R3,R5Printed April 19881Behavior of a Corium Jet in High;I Pressure Melt Ejection From aReactor Pressure Vessel'| |,,| |lWiktor FridvPrepared bySandia Nation...

Requests that concerns to adopt new set of Tech Specs for facility be fully investigated to ensure that public health & safety not in jeopardy.Certificate of Svc encl.Related correspondence.

_ _ _ _ _ . ___ __ _ _.. _ _ _ ._. _ _ _ __ _ ._' 0 L 55i;_ 3. RELATED CORRESPONDENCE j.,NUCLEAR ENERGY ACCOUNTABILITY Prob|,33468 0129 (407) 7b-0% gg P3;p ,%Post Office Box 129 Jupiter, FloridaEnvironmental Protection . Involvement . Litigation . Infortnationv'sm. , ,:*1 OlWr...

"Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,NY."

c. .i s. ., .CONFIRMATORY SURVEY.-OF THE REACTOR BUILDING 1AND' PHASE 4 SYSTEMSSHOREHAM NUCLEAR POWER STATION'.BROOKHAVEN, NEW YORK--[ DOCKET No. 50-322]T.J. VITKUSPrepared for the[Division of Waste ManagementHeadquarters OfficeU.S. Nuclear Regulatory Commisiond _f'-,w ~%, 2,*...

Application for amend to License DPR-46,consisting of Proposed Change 96 to Tech Specs re verification of equipment operability by exam of appropriate plant records.

*: ..h94hg,, ,m_4 GENERAL OHICEP O DOX 4P9 COLUMDUS. NE DRA5KA(McM499Nebraska Public Power District "TA3522"ca m a rm= m :c . m == = = = xn --- ...w= - -NLS9100363June 7, 1991Attention: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555Gentlemen:Subjec...

2020/03/23 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information RE: Measurement Uncertainty Recapture Power Uprate (EPID L-2019-LLS-0002)

From: Williams, Shawn Sent: Monday, March 23, 2020 3:25 PM To: Coleman, Jamie Marquess Cc: Sparkman, Wesley A.; Bates, Ernest F. Subject: Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information RE: Measurement Uncertainty Recapture Power Uprate (EPI...

Insp rept 50-285/98-09 on 980412-0523.Violations noted:Major areas inspected:operations,maint,engineering & plant support.

..ENCLOSURE 2U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDocket No.: 50-285.License No.: DPR-40Report No.: 50-285/98-09Licensee: Omaha Public Power DistrictFacility: Fort Calhoun StationLocation: Fort Calhoun Station FC-2-4 Adm.P.O. Box 399, Hwy. 75 - North of Fort CalhounFort ...