Letter Sequence Other |
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Results
Other: ML072470667, ML072540790, ML072540792, ML072540793, ML072540795, ML072540797, ML072540802, ML072540803, ML072540806, ML072540807, ML072540809, ML072540811, ML072540814, ML072540816, ML072540818, ML072540819, ML072540820, ML072550056, ML072550058, ML072550059, ML072680179, ML072680188, ML072680191, ML072680192, ML072740013, ML080660133
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MONTHYEARML0725407921968-06-0404 June 1968
Drawing 11D-190, 6 Inch Roof Vent
Project stage: Other
ML0725408181974-10-22022 October 1974
Drawing M-79, Rev. 3, Main Steam Relief Valve Discharge Stack Modification
Project stage: Other
ML0725500591984-01-0606 January 1984
Drawing M-990, Rev. 0, General Arrangement 14 Dia. Intake Line from Top of Service Bldg. to the Mechanical Room Addition
Project stage: Other
ML0725407931989-01-30030 January 1989
Drawing C-18, Rev, 6, Erection Diagram. Sheet 67
Project stage: Other
ML0725500581991-11-11011 November 1991
Drawing M-140, Rev. 7, Penetrations Containment Building Wall
Project stage: Other
ML0725408191994-06-21021 June 1994
Drawing M-113, Rev. 11, Heating & Ventilation Turbine Building Plan of Elev. - 625 - 0
Project stage: Other
ML0725408141996-02-23023 February 1996
Drawing M-42, Rev. 32, Piping Drawing Area 3 Sections
Project stage: Other
ML0725408201996-04-24024 April 1996
Drawing M-119, Rev. 7, Heating and Ventilating Mechanical Room Roof Plan Sections and Details. Sheet 3
Project stage: Other
ML0725408161997-01-17017 January 1997
Drawing M-65, Rev. 13, Piping Drawing Main Steam System
Project stage: Other
ML0725408111997-02-27027 February 1997
Drawing M-40, Rev. 29, Piping Drawing Area 3 Plan of El. 625 - 0 & Sections
Project stage: Other
ML0725408091997-11-0404 November 1997
Drawing M-29, Rev. 13, Piping Drawing Area 2 Plan of El. 625 - 0
Project stage: Other
ML0725500561998-01-14014 January 1998
Drawing M-119, Rev. 8, Heating and Ventilation Mechanical Equipment Room Plan and Sections El. 629 -2. Sheet 4
Project stage: Other
ML0725407971998-02-25025 February 1998
Drawing C-50, Rev. 20, Architectural Auxiliary & Reactor Buildings Floor Plan at El 625-0
Project stage: Other
ML0725407951998-10-0505 October 1998
Drawing C-38, Rev. 6, Field Erected Tanks. Sheet 2
Project stage: Other
ML0725408061998-10-12012 October 1998
Drawing C-141, Rev. 5, Containment Ventilation Stack
Project stage: Other
ML0725408031999-04-0808 April 1999
Drawing C-127, Rev. 2, Containment Vessel Typical Details
Project stage: Other
ML0725407902006-01-11011 January 2006
Drawing C-2, Rev. 16, Plant Area and Switchyard Plan. Sheet 1
Project stage: Other
ML0726801792006-01-12012 January 2006
Drawing C-52, Rev. 15, Architectural Roof Plan
Project stage: Other
ML0725408022006-11-15015 November 2006
Drawing C-51, Rev. 30, Architectural Auxillary & Reacator Building Floor Plans at 639 - 0 and 649-0
Project stage: Other
ML0727007542006-12-0505 December 2006
Draft RAI on Alternate Source Term Amendment
Project stage: Draft RAI
ML0725408072007-01-12012 January 2007
Drawing M-15, Rev. 12, Equipment Location Turbine Building Sections
Project stage: Other
ML0705800842007-02-26026 February 2007
Draft RAI on Proposed AST Amendment
Project stage: Draft RAI
ML0727002592007-03-29029 March 2007
Draft RAI on Alternate Source Term (AST) Amendment
Project stage: Draft RAI
ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007
Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16
Project stage: Request
ML0726801882007-06-26026 June 2007
Drawing C-52, Rev. 23, Heating & Ventilation Auxiliary & Containment Plan at Elevation 639-0 & 649 -0
Project stage: Other
ML0718005132007-06-29029 June 2007
Revision to Voluntary Response to NRC Regulatory Issue Summary 2006-15: Preparation and Scheduling of Operator Licensing Examinations
Project stage: Request
ML0718700072007-07-0505 July 2007
Request for Additional Information Re. Alternative Source Term
Project stage: RAI
ML0723203922007-08-20020 August 2007
Response to Request for Additional Information - License Amendment Request for Replacement of Containment Sump Buffer
Project stage: Response to RAI
ML0725407842007-09-0707 September 2007
Supplemental Information Regarding Alternative Source Term License Amendment Request
Project stage: Supplement
ML0726801912007-09-14014 September 2007
NAI Report Release - NAI-1149-002, Rev. 1, Determination of Atmospheric Dispersion Factors for Palisades, Enclosure 2, Revised Calculations
Project stage: Other
ML0726801922007-09-14014 September 2007
NAI Report Release - NAI-1 149-018, Rev. 2, Palisades Design Basis Main Steam Line Break AST Radiological Analysis, Revised Calculations
Project stage: Other
ML0726801762007-09-20020 September 2007
Transmittal of Supplemental Information Regarding Alternative Source Term License Amendment Request
Project stage: Supplement
ML0726406082007-09-21021 September 2007
Supplemental Information Regarding Alternative Source Term License Amendment Request
Project stage: Supplement
ML0727400132007-09-28028 September 2007
Technical Specifications, Implemented Alternative Radiological Source Term
Project stage: Other
ML0724706672007-09-28028 September 2007
License Amendment, Implemented Alternative Radiological Source Term
Project stage: Other
ML0806601332008-05-0707 May 2008
Alternative Radiological Source Term Correction Letter
Project stage: Other
2006-01-11
[Table View] |
Text
Definitions 1.1 1.1 Definitions CHANNEL FUNCTIONAL TEST
- b.
Digital channels - the use of diagnostic programs to test (continued) digital hardware and the injection of simulated process data into the channel to verify OPERABILITY, of all devices in the channel required for channel OPERABILITY.
The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)
DOSE EQUIVALENT 1-131 LEAKAGE CORE ALTERATION shall be the movement of any fuel, sources, or control rods within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
The COLR is the plant specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion," 1989; (Table 2.1, Exposure-to-Dose Conversion Factors for Inhalation).
LEAKAGE shall be:
- a.
Identified LEAKAGE
- 1.
LEAKAGE, such as that from pump seals or valve packing (except Primary Coolant Pump seal water leakoff), that is captured and conducted to collection systems or a sump or collecting tank; Palisades Nuclear Plant 1.1-3 Amendment No. 4-8 226
