Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Agenda - ACRS Joint Fukushima and Reliability & PRA Subcommittee Meeting, August 22, 2014.pdf

1 Advisory Committee on Reactor Safeguards Joint Fukushima and Reliability and PRA Subcommittee Meeting Rockville, MD T2-B1 Friday, August 22, 2014 Filtering Strategies Rulemaking Proposed Agenda (Rev 1) Cognizant Staff Engineer: Weidong Wang(301) 415-6279 mailto:weidon...

H. B. Robinson, Unit 2, Response to IE Bulletins 77-05 and 05A.

Carolina Power & Light Company December 7, 1977 FILE: NG-3513 (R) SERIAL: NG-77-1377 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II, Suite 1217 230 Peachtree Street, N.W. Atlanta, GA 30303 H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 DOCKET NO...

Requests 30-day extension of submittal date for initial leak rate test results,per NUREG-0737,TMI Action Item III.D.1.1 & SSER 5.Leakage data currently being gathered.

. - _*-uU- 600818L30- 87(01-27 )-L1A.120ILLIN018 POWER COMPANYCLINToN POWER STATION. P.o. Box 678. CLINTON. ILLINOIS 61727aJanuary 27, 1987Docket No. 50-461Director of Nuclear Reactor RegulationAttention: Dr. W. R. Butler, Director-BWR Project Directorate No. 4Division of BWR ...

RO:on 890902,radiation monitor inoperable for period exceeding 7 days.Caused by installation of nonfuse dependent isolation devices in communication loops of radiation data mgt sys & need for relocation of monitor due to new design.

_ _ _ _ _ _ ,'i _ gi &e: . . 96 ,' .: New. Hampshire -YankeetNYN- 89118September 25, 1989'.- United States Nuclear Regulatory ComraissionWashington, DC 20555Attention: .' Document Control Desk.1References: Facility Operating License NPF-67. Docket No. 50-443Subject:Inoperabili...

PNO-V-86-009:on 860227,unusual event declared when small leak from pressurizer instrument top weld discovered. Borating began to achieve necessary shutdown margin.Cooldown & leak repair planned.

-[gt[CL_.PRELIMINARY NOTIFICATION OF EVT.NT OR l'> USUAL OCCirdRENCE--PNO-V-86-09 Date: 02/27/86This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or publicintcrest significance. The information presented is as initially received without verifi...

H B Robinson - LICENSEE TECHNICAL SPECIFICATION AMENDMENT REQUEST TO INCREASE ULTIMATE HEAT SINK TEMPERATURE FROM 950F to 970F - SUBMITTAL VIA E-MAIL DATED MARCH 13,2000

// March 27, 2000 MEMORANDUM TO: File FROM: Ram Subbaratnam, Project Manager, Section 2 /RA/ Project Directorate II Division of Licensing Project Management SUBJECT: LICENSEE TECHNICAL SPECIFICATION AMENDMENT REQUEST TO INCREASE ULTIMATE HEAT SINK TEMPERATURE FROM 950F to 970F...

Press Release-IV-97-042 NRC TO MEET WITH ENTERGY TO DISCUSS APPARENT VIOLATIONS AT WATERFORD 3 NUCLEAR POWER PLANT

UNITED STATES NUCLEAR REGULATORY COMMISSIONOFFICE OF PUBLIC AFFAIRS, REGION IV611 Ryan Plaza Drive - Suite 400Arlington, Texas 76011-8064RIV: 97-42 FOR IMMEDIATE RELEASECONTACT: Breck Henderson July 25, 1997OFFICE: 817/860-8128PAGER: (800) 443-7243 (065477)E-MAIL: bwh@nrc.govN...

Bellefonte Units 3 & 4 COLA (Environmental Report), Rev. 0 - Chapter 02 Figure 2.1-1

SILT FENCEBRUSHSILT FENCESWAMPSWAMPEL.594.5'EL.603.9'63064064565065566066567067568068569069570070571071572075074574073063064062563564063062562061563561572071571070570069569068568067567066566065565064564063062562061561060560061561060560061062062562561061561061060560061560060561...

Monticello - Tech Specs - Issuance of Amendment RE: Two Inoperable Control Room Ventilation Subsystems Per TSTF-447.

Control Room Ventilation System3.7.53.7 PLANT SYSTEMS3.7.5 Control Room Ventilation SystemLCO 3.7.5APPLICABILITY:Two control room ventilation subsystems shall be OPERABLE.MODES 1, 2, and 3,During movement of recently irradiated fuel assemblies in the secondarycontainment,Durin...

Notice of Administrative Closure.

OFFICE OF NUCLEAR REACTOR REGULATION Petition for Rulemaking to be Considered in the Rulemaking Process On March 12, 2012, the Executive Director for Operations is expected to sign a notice stating that the NRC will consider the petition for rulemaking (PRM) submitted ...

Press Release-13-048: NRC Issues Enhanced Requirements For Post-Fukushima Venting Systems at Many U.S. Reactors.

No: 13-048 June 6, 2013 CONTACT: Scott Burnell, 301-415-8200 NRC Issues Enhanced Requirements For Post‐Fukushima Venting Systems at Many U.S. Reactors  The Nuclear Regulatory Commission has directed 31 U.S. reactors to further improve their systems for safely venting pressure...

Dresden, Units 2 and 3 - Special Report No. 33, Final Flood Protection Measures.

·-·: ~~llh.. ,_!3-eg'~latory . file Cy. CommonweaAEdison One First NationaWza. Chicago. Illinois Address Reply to: PoStOfficeBox 767 Chicago, Illinois 60690 Mr. D. L. Ziemann, Chief Operating Reactors - Branch 2 .Directorate of Licensing Off ice of Regulation U.S. Atomic Energ...

Special rept:on 840808 & 1012,area radiation monitors 2RI-7856 & 2RI-7857,respectively,declared inoperable when found out of calibr.Caused by instrument drift during 31-day surveillance.Alternate method of monitoring initiated.

, _ _tGCEIVEDF'NECSouthern California Edison CompanyWO~W OCT 29 M ||: I6-S AN ONOFRE NUCLE AR GENER A TING ST ATIO*4P.O. BO X 12 8SAN CLEMENTE. C ALIFORNI A 92672 157J. G. H A Y N ESTELeewont' STQTsON M ANAGt4(7143492-7700October 26, 1984.U.S. Nuclear Regulatory Commission:0ff...

RO 269/77-12:on 770326,penetration room valve PR-2 found inoperable during performance of functional test on reactor bldg isolation channel 6.Caused by ruptured diaphragm in air supply exhauster resulting in insufficient air pressure.

I*..D'JKI POWER COMPANY.. -*OCONIE UNIT 1i.~ Report No.:RO-269/77-12trEeport Date: April 21, 1977Occurrence Date: March 26, 1977,Pacility: Oconee Unit 1, Seneca, South CarolinaIdentification of Occurrence: Penetration room valve PR-2 discoveredinoperableConditions Prior to Occ...

Notifies NRC that facility will complete inner personnel air lock door equalizing valve mod by 920601.

.. ,_. _. . _ _ _ . _ . . - _ . _. - . _ . . . _ _ . _ _. ~ ._ -*oOmaha Public Power District444 South 16th Street MallMarch 13 1992Omaha, Nebraska t>8102-2247LIC-92-009R402/636-2000U. S. Nuclear Regulatory CommissionATIN: Document Control DeskMail Station P1 137Washington, DC...

Revised Tech Specs incorporating STS definition of hot shutdown condition into limiting condition for operation action statement.

1O,3.5-3aIf the differential pressure of Specification 3.5.A.9a cannot be maintained,and the differential pressure cannot be restored within the subsequent 6 hourperiod, an orderly shutdown shall be initiated and the reactor shall be in theshutdown condition within the next 6 ...

Forwards slides & transparencies of photos of 1/8 scale steel model.List describing each photo included.W/o encl.

gy.. ..Sandia National Laboratories.' AlbuQueraue. New Mexico 87185.August 20,1984,Mr. Denwood F. Ross, Deputy DirectorOffice of Nuclear Regulatory ResearchMall Stop 1130 SSU. S. Nuclear Regulatory CommissionWashington, DC 20555Dear Mr. Ross:On your recent tour of our containm...

Email from Masters, Anthony to Thomas, George; FW: CR3 Status.

Masters, AnthonyFrom: Masters, AnthonySent: Wednesday, November 04, 2009 10:39 AMTo: Thomas, GeorgeSubject: FW: CR3 StatusFYIFrom: Carrion, Robert , ,-t?Sent: Wednesday, November 04, 2009 10:15 AMTo: Christensen, Harold; Iouis.lake@nrc.comCc: Masters, AnthonySubject: CR3 Statu...

Email - Subject: Emailing: Request 29 Question 23 Response (3).docx Attachments: Request 29 Question 23 Response (3).docx.

Lake, LouisFrom: Lake, LouisSent: Thursday, December 10, 2009 2:49 PMTo: Thomas, GeorgeSubject: Emailing: Request 29 Question 23 Response (3).docxAttachments: Request 29 Question 23 Response (3).docxHere is the latest response to Question #29 for your review.LouThe message is ...

Bellefonte Units 3 & 4 COLA (FSAR), Rev. 1 - FSAR Chapter 02 Figure 2.4.2-202

6306406456506556606656706756806856906957007057107507457407357306456406306356256206206156306406256356406306256206156356157207157107057006956906856806756706656606556506456406306256206156106056006106056106206256256106156106106056006156006056106156106056206156106256206206156106056...

Palisades, ES-301-2 SRO R1, Control Room/In-Plant Systems Outline.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Palisades Date of Examination: July 2008 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title...

Responds to IE Bulletin 80-05, "Vacuum Condition Resulting in Damage to Chemical Vol Control Sys (CVCS) Holdup Tanks." Review of sys demonstrated that adequate protection is included in design.Table of sys reviewed encl.

WISCONSIN PUBLIC SERVICE CORPORATION P.O. Box 1200, Green Bay, Wisconsin 54305 June 9, 1980 Mr. James G. Keppler, Director Office of Inspection & Enforcement Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Dear Mr. Keppler: Docket 50-305 ...

E-mail from L. Gibney of USNRC to N. McNamara of USNRC Regarding TMI Write Up

McNa~mara, Nancy ARFrom: Gibney, LisaSent: Tuesday, December 01, 2009 2:27 PMTo: McNamara, NancySubject: RE: TMI write upthis will be perfect. THANK YOUHappy Holidays!From: McNamara, NancySent: Tuesday, December 01, 2009 2:02 PMTo: Gibney, LisaSubject: RE: TMI write upI only h...

Responds to violations noted in insp repts 50-313/98-01 & 50-368/98-01.Corrective actions:plant Maint Rule Program was revised,conducted assessment of past availability performance & established unavailability criteria.

- _ - - - - - _ _ - - . _ _ _ _ _ _ _ - . - _ _ - _ - _ - - _ _ _ - _ _ _ _ . _ - . - - - - _ - _ _ _ _ _ _ _ _ - _ . - _ _ _ _ - - _ _ _ - _l,,*'_y Entergy Operations,Inc.,-1448 S.R. 333|~RusseMe, AR 72801|Tel 501858-5000,,10CFR2.2011June 22,1998'OCAN069801U. S. Nuclear Regul...