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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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IR-00-005, Calvert Cliffs, DRS Report

June 30, 2000Mr.CharlesH.CruseVice President - Nuclear EnergyBaltimore Gas and Electric CompanyCalvert Cliffs Nuclear Power Plant1650 Calvert Cliffs ParkwayLusby, MD 20657-4702SUBJECT: CALVERT CLIFFS NUCLEAR POWER PLANT - NRC INSPECTION REPORTNOS. 05000317/2000-005 AND 0500031...

Monticello, Issuance of Amendment No. 136, Deleting TS 6.8.C, Thereby Eliminates the Requirements for Post Accident Sampling System.

June 17, 2003Mr. David L. WilsonSite Vice PresidentMonticello Nuclear Generating PlantNuclear Management Company, LLC2807 West County Road 75Monticello, MN 55362-9637SUBJECT: MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENTRE: ELIMINATION OF REQUIREMENTS FOR POST A...

November 2002 Davis-Besse Reactor Vessel Head Damage, NRC Update.

November 2002This is the third periodic update on the NRC response to the reactor vessel head damage at the Davis-BesseNuclear Power Station. The updates will be available at public meetings of the NRC Davis-Besse OversightPanel which is coordinating the agency’s activities r...

Arkansas Nuclear One, Units 1 and 2, License Amendment revising the TS to require verification of leak rate testing of the purge valves.

Docket Nos. 59-313 and 50-368 Mr. John Griffin Vice President, Nuclear Operations Arkansas Power t Liqht Comnany P. 0. Box 551 Little Rock, Arkansas 72203Distribution Docket File NRC PDR Local PDR SECY NSIC ORB#3 Reading DEi senhut OELD LJHa rmon W~ones TBarnhardt (8) GVissing...

SER of individual plant examination of external events submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff notes that licensee IPEEE complete with regard to info requested by Suppl 4 to GL 88-20.

g 4*.fs naop4 UNITED STATESijNUCLEAR REGULATORY COMMISSION$'t WASHINGTON, D.C. 205',H001%...../STAFF EVALUATION REPORT OF INDIVIDUAL PLANT EXAMINATIONOF EXTERNAL EVENTS (IPEEE) SUBMITTALON SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2.1.0 INTRODUCTIONOn June 28,1991, the NR...

Susquehanna, Unit 1, Technical Requirements Manual

MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2020-16626 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#:028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 10/13/2020 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-...

COMPILATION OF CONTRACT RESEARCH FOR THE CHEMICAL ENGINEERING BRANCH,DIVISION OF ENGINEERING TECHNOLOGY.Annual Report For FY 1985.

c._ _NUREG-1215_Compilation ofContractResearch for theChemicalEngineeringBranch,Divisionof Engineering TechnologyAnnual Repon for FY 1985_U.S. Nuclear RegulatoryCommissionOffice of Nuclear Regulatory Researchfr arcoy2-e,j'BR7"A8#n "' 7 .1215 RPDR'_ _ _ _ _ _ _ - . . . . _. . -...

Nonproprietary TR, "Mark-BW Fuel Assembly Application for Sequoyah Nuclear Units 1 & 2."

. _ ~ . ~ ~ - . - ~ _ . ~ . . . . .-=.. _ _ _ . _ _ _ _ _ - . _ - .. _ - ~ - -.._ .. .._. .. _ . . .. . . . _ _ . .Non ProprietaryBAW-10220NP Rev. O'Topical ReportMarch 1996MARK-BW FUEL ASSEMBLY APPLICATIONFORSEQUOYAH NUCLEAR UNITS 1 AND 2. . . . . . .......5.9-24 CCI.Line Bre...

"Connecticut Yankee Structural Reevaluation of Plant Structures to Address SEP Topic III-7.B Load Combinations Code Changes."

_ _ .. . _.I:I'l|| CONNECTICUT YANKEE:ESTRUCTURAL REEVALUATIONOF PLANT STRUCTURES:TO ADDRESS SEP TOPIC III-7.B;LOAD COMBINATIONS|4;CODE CHANCES'jReport No. 9203-01::;;..Submitted toNortheast Utilities Service CompanyP.O. Box 270Hartford, Connecticut 06101Prepared byHARSTEAD EN...

Requests schedular exemption from requirements of 10CFR50, App J,Sections III.D.2(a) & III.D.3,providing temporary relief from two-yr schedular requirement associated w/Type B & C periodic LLRTs.

--'fNortheast1 7 sciam strun sula cm037j@a Utilities Systemsonne.. utsue se,*, comp.oy,*P.O. Box 270!!.rtford, CT 06141-0270,(203) 665-5000September 26, 1994Docket No. 50-336B14993Re: 10CFR50.1210CFR50, Appendix JU.S. Nuclear Regulatory CommissionAttention: Document Control De...

Forwards supplemental info re potentially invalid leak detection tests used as alternative for required ASME, Section XI hydrostatic tests.Sys operability assessment for Unit 1 component cooling subsystems also encl.

__.o4,gg g g gev%wsenI,$Norefquvt. PA 1!477 (XX4April 19, 1991IN1s$$m.,am me -U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Subject: Beaver Valley Power Station, Unit No. 1 and No. 2BV-1 Docket No. 50-334, License No. DPR-66BV-2 Docket No. 5...

LER 90-012-00:on 900829,valve stem clamp setscrew & trim failures occurred due to vendor design deficiencies.W/901207 ltr.

_ _ . _ _ _ _ . _ _'*gCOOPC H NUCLE AR 51 ATION.Nebraska Public Power District"" " * "ds>?%"~??MS.^?i" ^ " " ', _ --..=_-m__ m -CNSS903986December 7, 1990U.S, Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Dear Sir:Cooper Nuclear Station Licensee Event...

08/25/2003 - SER-Cover Page, H. B. Robinson.

Safety Evaluation ReportRelated to the License Renewal of theH. B. Robinson Steam Electric Plant, Unit 2 Docket No. 50-261Carolina Power & Light CompanyU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationAugust 2003iiABSTRACTThis safety evaluation report (SE...

Oconee Nuclear Station, Units 1, 2, and 3, License Amendment Request for New Reactor Building Auxiliary Cooler Isolation Circuitry System Technical Specification (TSC 2003-06).

Duke Duke PowerOconee Nuclear StationWt ower. 7800 Rochester HighwayADOS E-V Gt"y ,Seneca, SC 29672(864) 885-3000 OFFICEAugust 26, 2004U. S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555Subject: Duke Energy CorporationOconee Nuclear Station, Units 1, 2...

Refers to mgt meeting conducted in Mishicot,WI,on 970626 to discuss status of facility performance improvement initiatives.Agenda & handout encl.

-- .. . _ . - . - _- - . - . -.July 17, 1997,Mr. S. A. Patuiski, Site Vice PresidentPoint Beach Nuclear Plant6610 Nuclear RoadTwo Rivers, Wisconsin 54241SUBJECT: POINT BEACH MANAGEMENT MEETINGDear Mr. Patuiski:This refers to the management meeting conducted at Fox Hills, Mishi...

"Conformance to Reg Guide 1.97,Zion Nuclear Station,Units 1 & 2," technical evaluation rept.

94_ _. -** * t,EGG-NTA-7368."Il!.TECHNICAL EVALUATION REPORTCONFORMANCE TO REGULATORY GUIDE 1.97 -ZION NUCLEAR POWER STATION, UNIT NOS. 1 AND 2.iDocket Nos. 50-295 and 50-304J. W. StoffelPublished January 19871Idaho National EntMneering LaboratoryEG&G Ida.o. Inc.Idaho Falls, I...

Application for amend to license NPF-43,adding Special Test Exception to allow unit to remain in Operational Condition 4 w/reactor coolant temps greater than 200 F,but less than 212 F,when performing inservice leak & hydrostatic testing.

..._.' ,.~Dehog 3,,,,,n -y,sEdisonlEEF" c=-iSeptember 5,1997{NRC-97-0107U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555-0001References:1)Fermi 2NRC Docket No. 50 34iNRC License No. NPF-432)NUREG-1433, " Standard Technical Specifications, G...

Forwards util update of status of Generic Ltr 89-10 MOV test program at station.

ACCELERANT+DOCVMENT DISTRVTIONSYSTEMREGULATORY INFORMATION DXSTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:9406060016 DOC.DATE: 94/05/24 NOTARIZED: NOFACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester GAUTH.NAME AUTHOR AFFILIATIONMECREDY,R.C. Rochester Gas & Electric Cor...

Rev 0 to EMF-98-013, "Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events."

• ATTACHMENT NO. 1 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 Siemens Power Corporation Report EMF-98-013 Palisades Cycle 14: Disposition and Analysis of Standard Review Plan Chapter 15 Events May, 1998 ----- -- ---9012000079 981202 i,, ,' PDR ADOCK 05000255: p PDR...

"Dresden 2 & 3 & Quad Cities 1 & 2 Nuclear Power Plant Drywell Temp Analysis."

·, ( 8302010434 830125 I PDR ADOCK 05000237 p PDR DRESDEN 2 & 3 AND QUAD CITIES 1 & 2 NUCLEAR POWER PLANTS DRYWELL TEMPERATURE ANALYSIS ~ I I ·:__I I J NOVEMBER 1982 NSE0-52-0682 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY This report was prepared ...

Forwards addl info re Insp Rept 50-397/86-12 concerning equipment qualification of Limitorque motor operators toward resolution of remaining open item on subj audit.Grease relief valve test data & T-drain technical analysis encl.

A.C CELE P ~" i"»"--=180'fr';*lP9080706050tJLJ40~™3020100'l~ ~80»20j.Condensati.on,Heat. Transfer..Region..;...,:....r J...'.... Tr.aIIs i.ti.'on..'Rqgi.IIn....;....;Latent..Heat..of...Evaporati;on.,:..".;..";Balances. Radar ati;ve. and:""":"Convecti:'.ve" Heat".Transfer:" "::...

Attachment to License Amendment No. 108 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 3.

ATTACHMENT TO LICENSE AMENDMENT NO. 108 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain mar...

Rev 5 to 30DP-9MT01, "Assessment of Risk When Performing Maint."

NUCLEAR ADMINISTRATIVE AND TECHNICALMANUAL Page 1 of 29~ ASSESSMENT OF RISKWHEN PERFORMINGMAINTENANCE30DP-9MTOlRevision5PROCEDURE INTENTProvide guidance in meeting the requirements of 10CFR50.65 a(3) in assessing riskduring the scheduling and performance ofmaintenance on-line ...

Ack receipt of IE Insp Repts 50-250/81-07 & 50-251/81-07 on 810226-0325.No proprietary info.Corrective actions: Operating Procedure 5120 will be followed for transfer of liquid from laundry tank to other tanks.

V',k„'!, BGi( 529100 vllAiv'll,FL,331 "2I1. I I'",I'~(27"040~AaVCw4J/'49yC5 0 '(3f > c~ I'ted@ llYNay 22, 1981L-81-220Mr. James P. O'Reilly, Director, Region IIOffice of Inspection and EnforcementU. S. Nuclear Regulatory Commission101 Marietta Street, Suite 3100Atlanta, Ga. 30...

Forwards licensee 980807 written RO/SRO license exam, supporting documentation & comments IAW requirements of NUREG-1021, "Operator Licensing Exam Stds."

L-98-214Mr. Luis A. ReyesRegional Administrator, Region IIAttn: Thomas A. PeeblesU. S. Nuclear Regulatory CommissionAtlanta Federal Center61 Forsyth Street, S. W., Suite 23T85Atlanta, GA 30303Dear Mr. Reyes:Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251/In accorda...