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: [[Category:Letter type:NL]] [[Site::Hatch||Vogtle||07200036||07201039||Holtec]]
 |?Issue date
 |?Title
 |?Topic
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=[Table view]
}}

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

JSON CSV RSS RDF

Query log

{
    "query_string": "[[Category:Letter type:NL]] [[Site::Hatch||Vogtle||07200036||07201039||Holtec]]",
    "query_source": "SMWSQLStore",
    "query_time": "2.8791",
    "from_cache": false
}

	Issue date	Title	Topic
NL-03-0086, December 2002 Monthly Operating Report for Edwin I. Hatch Nuclear Plant	7 January 2003	December 2002 Monthly Operating Report for Edwin I. Hatch Nuclear Plant
NL-03-0088, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response, Request for Additional Information	17 January 2003	Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response, Request for Additional Information	Boric Acid VT-2 Pressure Boundary Leakage
NL-03-0120, Inservice Inspection Summary Report	4 February 2003	Inservice Inspection Summary Report
NL-03-0157, Response to Request for Additional Information	17 January 2003	Response to Request for Additional Information
NL-03-0168, Southern Nuclear Operating Company, Inc., Answer to the Order for Compensatory Measures Related to Access Authorization	27 January 2003	Southern Nuclear Operating Company, Inc., Answer to the Order for Compensatory Measures Related to Access Authorization	Incorporated by reference
NL-03-0169, Licensee Response to Order for Compensatory Measures Related to Access Authorization	27 January 2003	Licensee Response to Order for Compensatory Measures Related to Access Authorization	Incorporated by reference
NL-03-0200, Response to Request for Additional Information, Steam Generator Tube Inspections	12 February 2003	Response to Request for Additional Information, Steam Generator Tube Inspections
NL-03-0257, Technical Specification Revision Request, Integrated Leakage Rate Testing Interval Extension	26 February 2003	Technical Specification Revision Request, Integrated Leakage Rate Testing Interval Extension	High winds Mission time Probabilistic Risk Assessment Coatings Large early release frequency
NL-03-0322, Emergency Implementing Procedure Revisions	4 February 2003	Emergency Implementing Procedure Revisions	Health Physics Network Met Tower
NL-03-0346, National Pollutant Discharge Elimination System Permit Renewal	6 February 2003	National Pollutant Discharge Elimination System Permit Renewal	Grab sample Biofouling
NL-03-0369, Occupational Radiation Exposure Reports	19 March 2003	Occupational Radiation Exposure Reports
NL-03-0390, Licensee'S Answer to February 11, 2003 Commission Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors at Joseph M. Farley Nuclear Plant & Vogtle Electric Generating Plant	3 March 2003	Licensee'S Answer to February 11, 2003 Commission Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors at Joseph M. Farley Nuclear Plant & Vogtle Electric Generating Plant	Boric Acid Pressure Boundary Leakage
NL-03-0438, Property Insurance Coverage as of 04/01/2003	3 March 2003	Property Insurance Coverage as of 04/01/2003
NL-03-0457, Transmittal of Edwin I. Hatch Nuclear Plant Physical Security Plan Revision	28 February 2003	Transmittal of Edwin I. Hatch Nuclear Plant Physical Security Plan Revision
NL-03-0472, Edwin I Hatch - Nuclear Security Training & Qualification Plan	28 February 2003	Edwin I Hatch - Nuclear Security Training & Qualification Plan
NL-03-0488, 10 CFR 50.59 Changes to the Technical Specification Bases	28 February 2003	10 CFR 50.59 Changes to the Technical Specification Bases	Test box
NL-03-0538, February 2003 Monthly Operating Report for Edwin I. Hatch Nuclear Plant	5 March 2003	February 2003 Monthly Operating Report for Edwin I. Hatch Nuclear Plant
NL-03-0584, February 2003 Monthly Operating Report for Vogtle	13 March 2003	February 2003 Monthly Operating Report for Vogtle
NL-03-0596, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant, Response to RIS 2003-01 and Request for Technical Alternative to ASME Section Xl, Appendix Viii, Supplement 10	14 May 2003	Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant, Response to RIS 2003-01 and Request for Technical Alternative to ASME Section Xl, Appendix Viii, Supplement 10	Dissimilar Metal Weld
NL-03-0620, Additional Information Concerning GL 96-06, Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions	14 November 2003	Additional Information Concerning GL 96-06, Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions	Anchor Darling
NL-03-0636, Physical Security & Contingency Plan Revision	24 March 2003	Physical Security & Contingency Plan Revision
NL-03-0656, Joseph M. Farley Nuclear Plant and Vogtle Electric Generating Plant - Request for Technical Alternative to ASME Section XI, IWA-4120(a) and IWA-4310	7 May 2003	Joseph M. Farley Nuclear Plant and Vogtle Electric Generating Plant - Request for Technical Alternative to ASME Section XI, IWA-4120(a) and IWA-4310	Weld Overlay Hydrostatic Coatings Liquid penetrant
NL-03-0693, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))	26 March 2003	Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))	Decommissioning Funding Plan
NL-03-0694, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))	28 March 2003	Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))	Incorporated by reference Decommissioning Funding Plan
NL-03-0696, Technical Specifications Revision to DC Electrical System Requirements	20 July 2004	Technical Specifications Revision to DC Electrical System Requirements	Safe Shutdown Shutdown Margin Ultimate heat sink Anticipated operational occurrence Post Accident Monitoring Internal Flooding Hydrostatic Probabilistic Risk Assessment Temporary Modification Large early release frequency Containment Hardened Vent Battery sizing Hardened vent Offsite Circuit
NL-03-0704, Measurement Uncertainty Recapture Power Uprate Request for Additional Information Response	7 April 2003	Measurement Uncertainty Recapture Power Uprate Request for Additional Information Response
NL-03-0723, Response to Request for Additional Information Regarding Risk Informed Inservice Inspection Program Submittal	23 April 2003	Response to Request for Additional Information Regarding Risk Informed Inservice Inspection Program Submittal	Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment VT-2 Dissimilar Metal Weld
NL-03-0750, Response to Request for Additional Information	7 April 2003	Response to Request for Additional Information
NL-03-0753, Request to Revise Technical Specifications Reactor Trip System Instrumentation Over Temperature Delta.	10 April 2003	Request to Revise Technical Specifications Reactor Trip System Instrumentation Over Temperature Delta.	GOTHIC
NL-03-0757, Cycle 18 Core Operating Limits Report (COLR)	7 April 2003	Cycle 18 Core Operating Limits Report (COLR)
NL-03-0759, March 2003 Monthly Operating Report for Edwin I. Hatch, Units 1 & 2	7 April 2003	March 2003 Monthly Operating Report for Edwin I. Hatch, Units 1 & 2
NL-03-0894, Annual Non-Radiological Environmental Operating Reports for 2002	28 April 2003	Annual Non-Radiological Environmental Operating Reports for 2002
NL-03-0939, Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1	30 April 2003	Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1	Health Physics Network Grab sample Met Tower
NL-03-0999, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2002	2 June 2003	10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2002
NL-03-1047, Report of Facility Changes, Tests & Experiments	14 May 2003	Report of Facility Changes, Tests & Experiments	Safe Shutdown Turbine Missile
NL-03-1078, Cycle 11 Core Operating Limits Report	13 May 2003	Cycle 11 Core Operating Limits Report	Shutdown Margin
NL-03-1090, Organization and Correspondence Routine Changes	16 May 2003	Organization and Correspondence Routine Changes
NL-03-1091, Organization and Correspondence Routine Changes	15 May 2003	Organization and Correspondence Routine Changes
NL-03-1124, Measurement Uncertainty Recapture Power Uprate, Request for Additional Information Response	21 May 2003	Measurement Uncertainty Recapture Power Uprate, Request for Additional Information Response
NL-03-1140, Changes to Technical Specification Bases	11 June 2003	Changes to Technical Specification Bases	Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level Stroke time Anticipated operational occurrence Safe Shutdown Earthquake Missed surveillance Power Operated Valves Fuel cladding Pressure Boundary Leakage Offsite Circuit Power change Unidentified leakage

Semantic search

Query log

Navigation menu

Search