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Advisory Committee on Reactor Safeguards Minutes of ACRS Subcommittee Meeting on Plant License Renewal Turkey point Units 3 & 4, March 13, 2002 Florida City, Florida.

Issued: 3/18/2002 Certified: 4/12/2002 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MINUTES OF ACRS SUBCOMMITIEE MEETING ON PLANT LICENSE RENEWAL TURKEY POINT UNITS 3 AND 4 MARCH 13, 2002 FLORIDA CITY. FLORIDA The ACRS Subcommittee on Plant License Renewal held a meeting on ...

RO/SRO Written Exam & Key Answers 2008.

DC Cook ILT NRC Exam 2008 1. 001 002/RO/OK/DIRECT/NRC EXAM 2004-033-2/00WE12 EK1.2/3.5/3.8/H/3Operators are performing 2-OHP-4023-ECA-2.1, Uncontrolled Depressurization of AllSteam Generators due to a steam leak inside containment along with failure of all SGstop valves to ...

Indian Point Nuclear Generating Unit Nos. 2 and 3 - Closeout of Responses to Generic Letter 96-06 (Tac Nos. M96822 and M96823).

August 25, 2003Mr. Michael R. Kansler, PresidentEntergy Nuclear Operations, Inc. 440 Hamilton AvenueWhite Plains, NY 10601SUBJECT: CLOSEOUT OF RESPONSES TO GENERIC LETTER 96-06, INDIAN POINTNUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. M96822 ANDM96823)Dear Mr. Kansler:On Se...

LER 06-002-00 Nine Mile Point, Unit 2 regarding RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition.

0 Constellation Energy*Nine Mile Point Nuclear StationP.O. Box 63Lycoming, NY 13093July 25, 2006U. S. Nuclear Regulatory CommissionWashington, DC 20555-0001ATTENTION:SUBJECT:Document Control DeskNine Mile Point Nuclear StationUnit No. 2; Docket No. 50-410Licensee Event Report ...

Proposed tech specs 3.4.1, "Leakage Rate" & associated bases,reducing allowable reactor bldg leakage rate from 2,000 cfm to 1,600 cfm.

ATTACHMENTANIAGARAMOHAWKPOWER CORPORATIONLICENSE NO. DPR-63DOCKET NO. 50-220Pro osed Chan es to Technical S ecification and Ba esReplace existing pages165 and 167 with the attached revised pages. These pageshave beenretyped in their entirety with marginal markings to indicate ...

LER 89-008-00:on 890910 & 11,drywell purge air supply outboard isolation valve HV-25723 automatically closed. Caused by blown fuse.Administrative controls in place to ensure that valve reworked & operable.W/891006 ltr.

gccELERA TED DlMBUTlONDEMONSTRATIONSYFl'EM.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR„8910160319 DOC.DATE: 89/10/06 NOTARIZED: NO DOCKET ¹FACIL:50-388 Susquehanna Steam Electric Station, Unit 2, Pennsy1va 05000388AUTH.NAME AUTHOR AFFILIATIONRUSANOWSKY,P.P. ...

Diablo Canyon Power Plant, Units 1 and 2 - Correction Letter Regarding Amendment Nos. 230 and 232 to Adopt Alternative Source Term (CAC Nos. MF6399 and MF6400).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Edward D. Halpin Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 May 16, 2017 S...

Forwards status rept re implementation of TMI action plan items at plant.

,ACCELERATEDDI~BUTION DEMONS~TION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8904260357 DOC.DATE: 89/04/18 NOTARIZED- NO DOCKETFACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1,Arizona Publi . 05000528STN-50-529 Palo Verde Nuclear Station, Unit 2,Ar...

2016/01/19 APR1400 DCD RAI - APR1400 Design Certification Application RAI 368-8470 (14.03.08 - Radiation Protection Inspections, Tests, Analyses, and Acceptance Criteria)

1KHNPDCDRAIsPEm ResourceFrom: Ciocco, JeffSent: Tuesday, January 19, 2016 1:12 PMTo: apr1400rai@khnp.co.kr; KHNPDCDRAIsPEm Resource; Harry (Hyun Seung) Chang; Andy Jiyong Oh; Steven MannonCc: Stutzcage, Edward; McCoppin, Michael; Burkhart, Lawrence; Vera, John; Lee, SamuelSubj...

Attachment - Vogtle Electric Generating Plant Unit 4 LAR 17-040.

ATTACHMENT TO LICENSE AMENDMENT NO. 127 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO. 52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain mar...

2015 Monticello Nuclear Generating Plant Initial License Examination Form ES-201-3.

i QF-1071 -0·1 'JV. 2 (FP-T-SAT-71) j fl Xcel Energy- \ MASTER SECURITY AGREEMENT Pa~t. l:'Pf 2 ---= ~--i ·- ·---- ·--------~J The Master Security Agreement is used for those personnel having both knowledge of Exam Sensitive Material and unrestricted access to Primary and Seco...

LER 2017-004-01 for Cooper, Torus to Drywall Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function.

Nebraska Public Power District Always there when you need us NLS2019007 January 24, 2019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555.:.000l Subject: Licensee Event Report No. 2017-004-01 Cooper Nuclear Station, Docket No. 50-298, ...

AREVA Design Control Document Rev. 4 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.3.3 Severe Accident Heat Removal System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 4 Page 2.3-142.3.3 Severe Accident Heat Removal SystemDesign Description1.0 System DescriptionThe severe accident heat removal system (SAHRS) is a dedicated cooling water system for the primary containment to support miti...

OFFICIAL EXHIBIT - ENT000082-00-BD01 - NL-08-004, Letter from Fred R. Dacimo, Entergy, to NRC, •Reply to Request for Additional Information Regarding License Renewal Application - (Steam Generator Tube Integrity and Chemistry)."

ENT000082 Submitted: March 28, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Iden...

11/15/2012 Meeting Summary with Omaha Public Power District to Discuss update of issues and oversight activities at Fort Calhoun Station.

December 3, 2012 LICENSEE: Omaha Public Power District (OPPD) FACILITY: Fort Calhoun Station SUBJECT: SUMMARY OF NOVEMBER 15, 2012, MEETING WITH OMAHA PUBLIC POWER DISTRICT On November 15, 2012, a Category 1 meeting was held between the U.S. Nuclear Reg...

Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, "Generic Letter 2008-01, Managing Gas Accumulation."

11921 Rockville Pike, Suite 100, Rockville, MD 20852 Phone: 301-984-4400, Fax: 301-984-7600 Administration by EXCEL Services Corporation TECHNICAL SPECIFICATIONS TASK FORCEA JOINT OWNERS GROUP ACTIVITYTSTF August 30, 2012 TSTF-12-15 PROJ0753 Attn: Document Control Desk ...

Safety Evaluation Report with Open Items Related to the License Renewal of Seabrook Station.

Safety Evaluation Report With Open Items Related to the License Renewal of Seabrook Station Docket Number 50-443 NextEra Energy Seabook, LLC U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation June 2012 iii ABSTRACT This safety ...

Forwards response to NRC 800306 questions re 800226 transient at Crystal River Unit 3.Reviews occurrence of power supply failure affecting non-nuclear instrumentation/ integrated control sys & susceptibility to similar event.

'.TOLEDO%mm EDISONR o.an P Cra.seDocket No. 50-346..n.mLicense No. NPF-3"*'* 25S422'Serial No. 596March 12, 1980Director of Nuclear Reactor RegulationUnited States Nuclear Regulatory CommissionWashington, D.C. 20555Attention: Mr. Robert N. Reid, ChiefOperating Reactors Branch ...

LER 89-002-01:on 890125,discovered that safety classification of instrument air tubing that supplies outlet isolation valves installed as non-nuclear safety.Caused by use of weld filler matl.Tech Spec change sent.

J. ''L*-.1seRC Po,sm 386U S. NUCLE AJ4 R$1UL ATORY COMMIT $lON53s.PP20VE3 OMD NO 31660104LICENSEE EVENT REPORT (LER)'"''a''''8''"*>.iF Acittiv NAME til DOCKET NUMSEM (26FAGE Gi Waterford Steam Electric Station Unit 3015 | 0 !a | 0 | 310 |2 1|oF|0 |6| TITLt setInadequate Qualif...

Responds to 781031 & 761124 NRC ltrs requesting addl info re pump & valve testing insvc progs.W/encl oversize drawings available in Central Files only.

.*.. i...B ALTIMORE G AS AND ELECTRIC COMPANYP.O. B O X 1475B A LTIM O R E. M A R YL A N D 2120 3Antwun C. Lumovatt,Ja.''" [" * * " 'November 20, 1978 ,Office of Nuclear Reactor RegulationU.S. Nuclear Regulatory ComissionWashington, D.C.20555ATTENTION: Mr. Robert W. Reid, Chie...

Submits eleventh edition of integrated implementation schedule for Units 2 & 3.

,.. .~./.Southem Califomia Edison Company'.23 PARKER STREET,IRVINE. CALIFORNIA 92718December 29, 1994WALTER C, MARSH , , , , , . _WNAGER OF NUCL F AR R,GULATORY AFF AIR $(714)454-4403U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D. C. 20555Gent...

Updated LER 76-15/03L:on 761006,leakage of water observed from recirculation spray HX A piping.Caused by cracking in heat affected zones of several welds.Listed piping will be replaced.W/761122 ltr.

- . . . - - - -GATE REPORT - PREVIOUS REPORT D E - Navimbsr 3, 1976 USRE-S2-76-15-,W LICENSEE EVENT REPCONTROL 8 LOCK:| | | | | | |(pLEASE PRINT ALL REGUIhED INFORMATION)1 6'S'AME77p"E'LCENSE NUMBERE|V | A |S | P| S| 2| | 0| 0|-|0 | 0 | 0| 0| 0|-|0 |0 ||4|1|1|1|0| | O! 3| O17 ...

2.3-Mechanistic Source Term

MECHANISTIC SOURCE TERM erhtjhtyhyDave GrabaskasArgonne National LaboratoryMarch 27, 2019Fast Reactor Technology TrainingU.S. Nuclear Regulatory CommissionOBJECTIVES2 Understand sources of radioactivity Understand barriers to the release of radioactivity to the environment ...

Forwards response to Generic Ltr 82-05 re NUREG-0737,Items II.B.2, "Plant Shielding," II.B.3, "Post-Accident Sampling Sys" & II.F.1, "Accident Monitoring Instrumentation." Response to four other items submitted 801215.

..VIRGINIA ELECTHIC AND POWER COM1%NYllICIIMOND, VIHUINIA 2!!26ln. II.12 Anne no May 17, 1982Vu s PanasomwrNannAm oramarsomeMr. Harold R. Denton, Director Serial No. 226Office of Nuclear Reactor Regulation N0/DWL:acmAttn: Mr. Dartcll G. Eisenhut, Director Docket Nos. 50-338Div...

Suppl 1 to "Safety Review of Pilgrim Nuclear Power Station Unit 1 at Core Flow Conditions Above Rated Flow for End-of- Cycle 6."

-- ------ - - - - - - - - - - - -o#22'O* "7Ja*i'7#0#a'..SAFETY REVIEW OF PILGRIMNUCLEAR POWER STATION, UNIT NO.1AT CORE FLOW CONDITIONS ABOVERATED FLOW FOR END-OF-CYCLE 6.WRg8!!88E%gg88|ggGENER AL h ELECTRICP_ . . _ .. . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ...