Semantic search

Jump to navigation Jump to search
 Issue dateTitle
L-16-179, License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits.1 November 2016License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits.
L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR18 December 2019Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR
L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements24 September 2020Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
L-20-169, Request for Licensing Action to Revise the Technical Specifications14 December 2020Request for Licensing Action to Revise the Technical Specifications
L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position5 August 2022Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position18 October 2022Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML02093080731 March 2002March 2002, Perry Initial Operator Licensing Examination; Senior Reactor Operator Written Examination
ML0211902925 March 2002Final As-Administered Scenarios for the Perry Initial Examination - March 2002
ML0212303245 March 2002Initial Submittal of Written Examination for the Perry Initial Examination - March 2002
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0325300383 September 2003Submittal of Technical Specification Bases, Revision 4
ML0503503643 February 2005Technical Specification Pages Revision of the Minimum Critical Power Ratio Safety Limit
ML05045060230 November 2004NRC Proposed Written Exam for the Perry Initial Exam - Nov/Dec 2004
ML0504806459 December 2004Ro/Sro Nov/Dec 2004 Perry Examination
ML0520704789 December 2004Initial Written Examination (Revised to Include Hq Comments)
ML0526304919 September 2005Report of 10 CFR 50.59 Evaluations for 2003-2005
ML05299032314 October 2005Submittal of Technical Specification Bases, Revision 5
ML06053062010 February 2006License Amendment Request to Revise Required Action B.1 in the Emergency Core Cooling System Instrumentation Technical Specification to Be Consistent with the Improved Standard Technical Specifications
ML0707405248 March 2007Response to a Request for Additional Information on a License Amendment Request to Revise Required Action B.1 in Technical Specification 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation
ML0726106957 September 2007Report of Facility Changes, Tests and Experiments for 09/09/2005 to Present
ML09072095212 March 2009Er 05000440-09-301(DRS), on 1/12/2009 - 1/21/2009, First Energy Corp., Perry Station Initial License Examination Report
ML10061057112 January 2009Initial License Exam, As-Administered Scenarios
ML10217019318 July 20102010 Perry Plant Initial License Examination Proposed Written Examination
ML10217019721 June 20102010 Perry Plant Initial License Examination Administered Written Examination
ML10298044621 October 2010License Amendment Request to Modify Technical Specification 2.1.1, Reactor Core Sls, to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values
ML11077031518 April 2011License Amendment, Issuance of Amendment License Amendment to Modify Technical Specification 2.1.1, Reactor Core Sls to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values
ML13051B1446 May 2013Issuance of Amendment Regarding Adoption of TSTF-275, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-Up, and TSTF-300
ML15075A09127 March 2015Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325)
ML15075A13930 March 2015Issuance of Amendment Concerning Full Implementation of Alternative Source Term (TAC No. MF3197) (L-13-306)
ML17096A7445 April 20172017 Perry Nuclear Power Plant Initial Licensed Operator Examination Administered Written Examinations
ML17139C37219 June 2017Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179)
ML17158B4353 February 20172017 Perry Nuclear Power Plant Initial Licensed Operator Examination Written Exam Outline ES-401-1 and 3 - Updated
ML17158B4653 February 20172017 Perry Nuclear Power Plant Initial Licensed Operator Examination Written Exam Outline ES-401-1 and 3
ML17164A0633 February 20172017 Perry Nuclear Power Plant Initial Licensed Operator Examination Proposed Written Exam - RO and SRO Combined
ML18292A81612 December 2018Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control
ML20006A38419 January 1990Proposed Tech Spec 3.3.2 Re RCIC Sys Isolation Trip Function,Trip Setpoint & Response Time
ML20012C44116 March 1990Proposed Tech Specs Re RCIC Equipment Room Differential Temp Isolation Actuation Instrumentation Trip Setpoint & Allowable Value
ML20027B3848 September 1982Action Plan to Address Addl Containment Issues (Humphrey Concerns).
ML20027B57516 September 1982Answer Opposing Oh Citizens for Responsible Energy 820818 Motion for Leave to File Contentions 21-26.Adequate Basis, Specificity or Good Cause Not Demonstrated.Certificate of Svc Encl
ML20028G01926 January 1983Forwards Update of Program to Resolve Concerns Raised by J Humphrey,W/Results of Completed Action Plans,Per SER Outstanding Issue 8 on Mark III Containment Sys Issues. Schedule for Completion of Unresolved Items Noted
ML20028H75225 January 1991LER 90-041-00:between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo issued.W/910125 Ltr
ML20029C36619 March 1991Proposed Tech Spec 3.3.3 Actions,Revised to Make Actions for Various ECCS Actuation Instrumentation Consistent W/ Purpose & Logic of Instrument Involved
ML20038B14516 November 1981Part 21 Rept Re Transmitter & Trip Units for Reactor Vessel Water Level Scrams,Initially Reported 810818.No Similarly Defective Equipment Offered to Util.River Bend Should Not Have Been Included in Rept
ML20040C94420 January 1982Forwards Draft Responses Re Instrumentation & Control Sys, in Response to NRC 811117 Request.Meeting Held 811216-17 W/Members of Instrumentation & Control Branch to Discuss Concerns & Identify Action Items
ML20040E76321 January 1982Forwards Draft Responses to NRC 811120 Request for Addl Info Re Reactor Sys.Responses Will Be Incorporated in Amend to FSAR
ML20040F4193 February 1982Forwards Draft Responses to NRC 811117 Ltr Requesting Info Re Instrumentation & Control Sys.Meeting Held on 820113 & 14 to Discuss Concerns & Identify Action Items
ML20043H38418 June 1990LER 90-009-00:on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut replaced.W/900618 Ltr
ML20046B48030 July 1993Forwards Response to NRC Bulletin 93-003, Resolution of Issues Related to Rv Water Level Instrumentation in Bwrs. Info Also Responds to NRC 930520 RAI Re Proposed C/As & Implementation Schedule Required by GL 92-04
ML20050A51625 March 1982Forwards Draft Responses to Concerns Identified in Draft SER for Reactor Sys.Responses Will Be Identified in Subsequent Amend to FSAR
ML20052B43221 April 1982Forwards Response to Reactor Sys Branch SER Questions Re plant-specific ECCS Analyses & Overpressure Protection Analyses Using Odyn Code.Analyses Will Be Incorporated Into Next FSAR Amend
Retrieved from "https://kanterella.com/Special:Ask"