Letter Sequence Supplement |
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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
Entergy Nuclear Operations, inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 September 21, 2007 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Supplemental Information Regarding Alternative Source Term License Amendment Request (TAC No. MD3087)
Dear Sir or Madam:
By letter dated September 25, 2006, Nuclear Management Company, LLC, the former licensee for the Palisades Nuclear Plant (PNP), requested Nuclear Regulatory Commission (NRC) review and approval of a license amendment request (LAR) for PNP. The LAR would modify the PNP licensing basis to adopt the alternative source term methodology. On September 7, 2007, Entergy Nuclear Operations, Inc., (ENO) provided supplemental information. The submittal included one new commitment.
In a September 20, 2007, telephone conference call with the NRC, it was determined that the commitment should be revised. EN0 is revising the commitment as shown below.
No other information in the September 25, 2006, LAR is affected by this additional information. The No Significant Hazards Consideration and the Environmental Consideration provided in Enclosure 1 of the September 25, 2006, submittal are not affected by this change.
Summary of Commitments This letter contains no new commitments and one revision to an existing commitment.
Previous commitment:
Prior to loading the Cycle 21 core, EN0 will revise the procedure used to check the adequacy of a core design to include an evaluation on the pin powerlburnup of the design core against the following criteria:
Document Control Desk Page 2 of 2 Fewer than 21 rods in any one assembly violate the "5416.3" criterion.
Fewer than 20 assemblies in any core design contain at least one rod that violates the "5416.3" criterion.
All rods that violate the "5416.3" criterion have a rod average linear heat generation rate of less than 6.7 kW1ft.
All rods that violate the "5416.3" criterion have a rod burnup of less than 58.5 GWDIMTU.
In any assembly containing any rods that violate the "5416.3" criterion there are at least four times as many rods that have total radial peaking factor of less than % of the total radial peaking factor limit of 2.04.
Revised commitment:
Prior to restart (Mode 2) from the 2007 refueling outage, EN0 will revise Section 2.4, "Total Radial Peaking Factor," of the Core Operating Limits Report to include an evaluation on the pin powerlburnup of the design core against the following criteria:
a Fewer than 21 rods in any one assembly violate the "5416.3" criterion.
a Fewer than 20 assemblies in any core design contain at least one rod that violates the "5416.3" criterion.
All rods that violate the "5416.3" criterion have a rod average linear heat generation rate of less than 6.7 kW1ft.
All rods that violate the "5416.3" criterion have a rod burnup of less than 58.5 GWDIMTU.
In any assembly containing any rods that violate the "5416.3" criterion there are at least four times as many rods that have total radial peaking factor of less than % of the total radial peaking factor limit of 2.04.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 21, 2007.
Site Vice President Palisades Nuclear Plant CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
