Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Options | Search Clear all entries |

Condition

Printout selection

Options

Parameters [+]

limit:

The maximum number of results to return

offset:

The offset of the first result

link:

Show values as links

headers:

Display the headers/property names

mainlabel:

The label to give to the main page name

intro:

The text to display before the query results, if there are any

outro:

The text to display after the query results, if there are any

searchlabel:

Text for continuing the search

default:

The text to display if there are no query results

class:

An additional CSS class to set for the table

transpose:

Display table headers vertically and results horizontally

sep:

The separator between results

prefix:

Control display of namespace in printouts

Sort options

Delete

Add sorting condition

ResultCodeDebugExtra

To embed this query inline into a wiki page use the code below.

{{#ask: [[Topic::Design basis earthquake]] [[Site::Millstone]]
 |?Issue date
 |?Title
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=Millstone
}}

Results 1 – 50 previous 50 20 50 100 250 500 next 50

JSON CSV RSS RDF

Query log

{
    "query_string": "[[Topic::Design basis earthquake]] [[Site::Millstone]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.1154",
    "from_cache": false
}

	Issue date	Title
A03831, Forwards Addl Info Re IE Bulletin 80-11, Masonry Wall Design, in Response to NRC 840224 Request.Final Response to Question 4 Will Be Provided by 850103	2 November 1984	Forwards Addl Info Re IE Bulletin 80-11, Masonry Wall Design, in Response to NRC 840224 Request.Final Response to Question 4 Will Be Provided by 850103
A04832, Forwards Response to IE Bulletin 80-11 Re Masonry Wall Design.Three Walls Qualified Using Energy Balance Techniques.All Three Walls Reanalyzed Using Linear Elastic Working Stress Method	28 October 1985	Forwards Response to IE Bulletin 80-11 Re Masonry Wall Design.Three Walls Qualified Using Energy Balance Techniques.All Three Walls Reanalyzed Using Linear Elastic Working Stress Method
B10885, Final Deficiency Rept SD-36 Re Design & Const of Main Control Board Welds.Initially Reported on 830513.Welds Repaired & Approved by S&W & Reliance.Welds Analyzed by Reliance & Approved by S&W	8 September 1983	Final Deficiency Rept SD-36 Re Design & Const of Main Control Board Welds.Initially Reported on 830513.Welds Repaired & Approved by S&W & Reliance.Welds Analyzed by Reliance & Approved by S&W
B11368, Forwards Changes to FSAR & Description of Design Basis for Mod to Solid State Protection Sys to Be Configured for 3-loop Operation.Requests Approval to Operate Unit W/Three Active Coolant Loops in Event of Equipment Failure in Loop	20 November 1984	Forwards Changes to FSAR & Description of Design Basis for Mod to Solid State Protection Sys to Be Configured for 3-loop Operation.Requests Approval to Operate Unit W/Three Active Coolant Loops in Event of Equipment Failure in Loop
B11611, Forwards Responses to Questions Re Equipment Raised During Sqrt Audit on 850304-08.Questions Raised During Pump & Valve Operability Review Team Audit on 850304-08 Successfully Resolved	6 August 1985	Forwards Responses to Questions Re Equipment Raised During Sqrt Audit on 850304-08.Questions Raised During Pump & Valve Operability Review Team Audit on 850304-08 Successfully Resolved
B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A	23 October 1985	Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A
B11880, Forwards Info Requested in 851112 Telcon Re Engineering Assurance Audit Items.Package Includes Updated Corrective Action Status Rept,Fsar Changes & Project Change Notice on Leakage Detection	18 November 1985	Forwards Info Requested in 851112 Telcon Re Engineering Assurance Audit Items.Package Includes Updated Corrective Action Status Rept,Fsar Changes & Project Change Notice on Leakage Detection
B13668, Provides Addl Info Re Util Plans for Addressing High Energy Line Breaks Outside Containment in Auxiliary Steam Sys	16 November 1990	Provides Addl Info Re Util Plans for Addressing High Energy Line Breaks Outside Containment in Auxiliary Steam Sys
B13727, Forwards Guidelines Re Seismic Evaluations to Support 910327 Application for Amend to License DPR-65,changing Tech Specs Re Seismic Restraints Other than Snubbers,Per NRC Request	6 August 1991	Forwards Guidelines Re Seismic Evaluations to Support 910327 Application for Amend to License DPR-65,changing Tech Specs Re Seismic Restraints Other than Snubbers,Per NRC Request
B16531, Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair	3 July 1997	Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair
B17296, Requests NRC Review of plant-specific Leak Before Break Revised Evaluation Rept of Unit 2 Main Coolant Loop Cold Leg Pipe.Rev 0 to Rept N-PENG-ER-007,encl	25 June 1998	Requests NRC Review of plant-specific Leak Before Break Revised Evaluation Rept of Unit 2 Main Coolant Loop Cold Leg Pipe.Rev 0 to Rept N-PENG-ER-007,encl
IR 05000245/1987033	11 February 1988	Insp Repts 50-245/87-33 & 50-336/87-29 on 871201-31. Violations Noted.Major Areas Inspected:Action on Previous Insp Findings,Physical Security,Plant Operations,Lers, Surveillance Testing & Implementation of License Amends
IR 05000245/1998208	12 August 1998	Insp Repts 50-245/98-208,50-336/98-208 & 50-423/98-208 on 980428-0629.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support
IR 05000245/2011009	13 May 2011	IR 05000245/2011009, 05000336/2011009, and 05000423/2011009; 04/01/2011 - 04/29/2011; Millstone Power Station, Units 1, 2 and 3; Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event
IR 05000336/2009006	31 March 2009	IR 05000336-09-006, 05000423-09-006; on 01/12/2009 - 03/06/2009; Millstone Power Station; Component Design Bases Inspection
IR 05000336/2023003	6 November 2023	Integrated Inspection Report 05000336/2023003 and 05000423/2023003
ML021420114	13 May 2002	Response to Request for Additional Information Technical Specifications Change Request 3-2-00 Emergency Diesel Generator Allowed Outage Time
ML062480263	1 September 2006	Request for Amendment, Proposed Surveillance Requirement Changes: Use of Generic Terminology for Emergency Core Cooling Systems Containment Sump Strainers (LBDCR 06-MP2-031 & 06-MP3-029)
ML072040069	13 July 2007	Request for Proprietary Review of Draft Corrective Actions Audit Report for Generic Safety Issue - 191 Related to Generic Letter 2004-02
ML072290550	30 August 2007	GSI-191, Generic Letter 2004-02 Corrective Actions Audit Report
ML080650561	29 February 2008	Submittal of Supplemental Information of Corrective Actions, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
ML081140083	17 April 2008	WCAP-16896-NP, Rev. 1, Millstone, Unit 2, RCS Surge, Spray, Shutdown Cooling, Safety Injection, Charging Inlet, and Letdown/Drain Nozzles Structural Weld Overlay Qualification.
ML092090216	30 June 2009	WCAP-16896-NP, Rev 2, Millstone Unit 2 RCS Surge, Spray, Shutdown Cooling, Safety Injection, Charging Inlet, and Letdown/Drain Nozzles Structural Weld Overlay Qualification.
ML12353A242	27 November 2012	Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3
ML14002A397	30 January 2014	Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14013A271	30 January 2014	Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14092A417	31 March 2014	Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1
ML17123A378	27 April 2016	Reevaluated Seismic Hazard Mitigating Strategies Assessment Report
ML17212A041	29 June 2017	Final Safety Analysis Report, Rev. 35, Frontmatter
ML17212A042	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 1, Introduction and Summary
ML17212A044	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 3, Reactor
ML17212A045	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 4, Reactor Coolant System
ML17212A047	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 6, Engineered Safety Features Systems
ML17212A049	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 8, Electrical Systems
ML17212A050	29 June 2017	Final Safety Analysis Report, Rev. 35, Chapter 9, Auxiliary Systems
ML18102A533	16 March 2018	Revision 56 to Emergency Plan, MP-26-EPI-EPMP
ML18241A091	3 August 2018	Emergency Plan
ML18247A221	18 June 2018	Revision 36 to Final Safety Analysis Report, Frontmatter
ML18247A222	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 1, Introduction and Summary.(Redacted)
ML18247A223	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 2, Site and Environment
ML18247A227	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features Systems
ML18247A231	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 7, Instrumentation and Control
ML18247A232	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 8, Electrical Systems
ML18247A233	18 June 2018	Revision 36 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems
ML18295A114	29 June 2017	Redacted - Millstone Power Station, Unit 2, Updated Final Safety Analysis Report, Chapter 2, Revision 35
ML19064A590	28 February 2019	Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service
ML19249B772	29 August 2019	Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated)
ML19330C205	16 July 1980	Responds to IE Bulletins 79-14 & 79-02 Re Accuracy of Input Info for Seismic Analysis of safety-related Piping & Pipe Support Base Plate Designs W/Concrete Expansion Anchor Bolts on Category I Sys,Respectively.Updates Project Work
ML19345C707	4 November 1980	Responds to IE Bulletin 80-11, Masonry Wall Design. Re-evaluation of Concrete Masonry Walls & Any Resulting Mods Will Be Completed by 810501
ML20070Q456	31 January 1989	Nuclear Power Plant Sys Sourcebook,Millstone 2

Semantic search

Query log

Navigation menu

Search