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Issue date | Title | |
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ML22299A056 | 1 November 2022 | Integrated Inspection Report 05000445/2022003 and 05000446/2022003 and Notice of Violation |
IR 05000445/2022003 | 1 November 2022 | Integrated Inspection Report 05000445/2022003 and 05000446/2022003 and Notice of Violation |
ML21285A038 | 23 September 2021 | CP-2021-08-FINAL Written Exam |
ML21299A022 | 23 September 2021 | CP-2021-08-DRAFT Written Exam |
CP-202000311, Notification of Deviation from Electric Power Research Institute MRP 2018-027, NEI 03-08 Needed Inspection Guidance for PWR CRDM Thermal Sleeve Wear, Superseded by PWROG-16003-P, Evaluation of . | 11 May 2020 | Notification of Deviation from Electric Power Research Institute MRP 2018-027, NEI 03-08 Needed Inspection Guidance for PWR CRDM Thermal Sleeve Wear, Superseded by PWROG-16003-P, Evaluation of . |
IR 05000445/2017004 | 9 February 2018 | NRC Integrated Inspection Report 05000445/2017004 and 05000446/2017004 |
05000445/LER-2016-002 | 22 February 2017 | Unanalyzed Condition Involving Potential Moderate Energy Line Break LER 16-002-01 for Comanche Peak Nuclear Power Plant, Units 1 & 2 Regarding Unanalyzed Condition Involving Potential Moderate Energy Line Break |
IR 05000445/2016002 | 11 August 2016 | NRC Integrated Inspection Report 05000445/2016002 and 05000446/2016002 |
CP-201600048, Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels | 27 January 2016 | Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels |
ML15320A100 | 13 November 2015 | IR 05000445/2015008 and 05000446/2015008, on 08/31/2015 - 10/01/2015, Comanche Peak Nuclear Power Plant, NRC Problem Identification and Resolution and Notice of Violation |
ML15191A163 | 24 June 2015 | EPP-201, Emergency Action Level Technical Bases Document(Clean Version) |
ML15191A164 | 24 June 2015 | Emergency Action Level Technical Bases (Redline and Strikeout Version) |
IR 05000445/2011004 | 27 October 2011 | IR 05000445-11-004, 05000446-11-004, on 6/19/2011 - 9/17/2011, Comanche Peak Nuclear Power Plant, Units 1 and 2, Integrated Resident and Regional Report, Licensed Operator Requalification Program; Refueling and Other Outage Activities |
ML112710033 | 28 September 2011 | ROP Tabletop Examples and Results |
ML101241015 | 29 March 2010 | 2010-04-Final Operating Test |
ML092950551 | 26 February 2010 | Issuance of Amendment Nos. 150 and 150, Administrative Revision to the Operating License to Change Plant Name, Reissue Technical Specifications to Remove Ts/Tables No Longer Applicable to Operation |
CP-200900262, License Amendment Request (LAR) 09-001, Administrative Revision to Operating Licenses and Technical Specifications | 11 February 2009 | License Amendment Request (LAR) 09-001, Administrative Revision to Operating Licenses and Technical Specifications |
CPSES-200600635, License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls. | 31 March 2006 | License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls. |
CPSES-200401863, License Amendment Request LAR 04-05 Change to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System | 5 August 2004 | License Amendment Request LAR 04-05 Change to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System |
ML040770122 | 3 February 2004 | Draft Information Inputs Corrected TS Pages 3.0-2 Attachment 1 |
ML040360223 | 23 January 2004 | Tech Spec Pages for Amendment Nos. 109 and 109, Increasing Flexibility in Mode Restraints |
ML040860300 | 23 January 2004 | Technical Specification Pages for Amendments 109 to Licenses NPF-87 & NPF-89 |
CPSES-200301485, License Amendment Request (LAR) 03-06 Revision to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | 18 July 2003 | License Amendment Request (LAR) 03-06 Revision to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process |
ML020560470 | 22 February 2002 | Technical Specification Page for Amendment No 92 & 92 |
ML023570388 | 4 January 2002 | CP - Init Exam -11/2002 - Draft Exam |
IR 05000445/1999015 | 20 October 1999 | Insp Repts 50-445/99-15 & 50-446/99-15 on 990822-1002. Non-cited Violations.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support |
ML20206G711 | 4 May 1999 | Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections |
ML20141C927 | 15 May 1997 | Application for Amends to Licenses NPF-87 & NPF-89,adding License Conditions to Address SRs Not Previously Performed by Existing Requirements or Tests.Attachments 1-20 Encl |
Information Notice 1996-44, Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly | 5 August 1996 | Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly |
ML20058K561 | 8 December 1993 | Forwards Tia:Interpretation of Reporting Requirements, 93TIA006.Guidance Provided in Response to Region 5 Request for Interpretation of Reporting Requirements for safety- Related Components |
ML20086J820 | 6 December 1991 | Part 21 Rept P21R-91-001 Re Defective Cylinder Head in Delaval Emergency Diesel Generator.Initially Reported on 911108.Defective Head Replaced in Train a EDG & Successful Engine Run Performed |
ML20011E279 | 8 February 1990 | Advises That Util Ready for Issuance of OL Authorizing Fuel Load & Operation Up to 5% Rated Power for Unit 1.Design, Const & Preoperation Testing of Unit Complete in Accordance W/Fsar |
ML20244B712 | 22 May 1989 | Forwards Addl Info,Requested in NRC Ltr from CE Rossi to RA Newton,To Support NRC Review of Merits Tech Specs & Bases (WCAP-12159) |
ML20236X250 | 2 December 1987 | Affidavit of Dn Chapman.* Discusses Mgt Analysis Co Audit Rept |
TXX-6396, Responds to NRC Re Violations & Deviations Noted in Insp Repts 50-445/86-22 & 50-446/86-20.Corrective Actions:Required Certification for Valve Bonnet Received from Vendor & Placed in Appropriate Receipt Insp Package | 27 April 1987 | Responds to NRC Re Violations & Deviations Noted in Insp Repts 50-445/86-22 & 50-446/86-20.Corrective Actions:Required Certification for Valve Bonnet Received from Vendor & Placed in Appropriate Receipt Insp Package |
ML20205D213 | 16 March 1987 | Insp Repts 50-445/86-22 & 50-446/86-20 on 860701-0831. Violations & Deviations Noted:Stainless Steel & Carbon Steel Stored in Outside Areas W/Improper Protective End Coverings & Records of Heat Treatment Not Available for Disc Inserts |
IR 05000445/1986022 | 10 February 1987 | Confirms That Review of Encl Insp Repts 50-445/86-22 & 50-446/86-20 Completed,Per Jm Taylor 860626 Memo.Concurrence in Rept Provided on 870210 |
ML20210Q004 | 21 March 1986 | Forwards Memorandum & Order CLI-86-04 Re Matters Raised by Case Concerning Extension of CPPR-126.Requests for Halt to Facility Const Denied |
ML20154N135 | 13 March 1986 | Memorandum & Order CLI-86-04 Denying Case 860131 Request for Stay of Extension of CPPR-126 & Halt to Const Activities. Served on 860313 |
ML19254F218 | 24 October 1979 | Response by Public Utils Board of City of Brownsville,Tx in Opposition to Central & South West Corp,Et Al 791016 Motion for Protective Order.Submits Motion for Modified Order Limiting Scope of Confidentiality.Certificate of Svc Encl |