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Results
Other: AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal, AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility, AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules, AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas, AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks, AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818, ML20117C275, ML20117C283, ML20203G517, ML20205D440, ML20205E845, ML20205E852, ML20205T067, ML20209G129, ML20212N039
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MONTHYEARML20117C2831985-05-0606 May 1985 Licensing Rept,High-Density Spent Fuel Racks Project stage: Other ML20117C2611985-05-0606 May 1985 Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Request ML20117C2751985-05-0606 May 1985 Proposed Tech Specs Allowing Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Other AECM-85-0143, Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid1985-05-0606 May 1985 Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid Project stage: Request ML20129F9581985-07-0505 July 1985 Forwards Request for Addl Info Re High Density Spent Fuel Racks in Upper Containment Pool & in Spent Fuel Storage Pool.Response Due by 850715 Project stage: RAI ML20133A1781985-07-26026 July 1985 Forwards Request for Addl Info Re Application to Amend License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & Spent Fuel Storage Pool.Info Requested by 850815 Project stage: RAI AECM-85-0229, Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress1985-07-29029 July 1985 Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress Project stage: Request ML20136H1801985-08-0909 August 1985 Forwards Request for Addl Info Re 850506 Request for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & in Spent Storage Pool.Info Requested by 850826 Project stage: RAI AECM-85-0252, Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl1985-08-15015 August 1985 Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl Project stage: Request AECM-85-0272, Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis1985-08-30030 August 1985 Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis Project stage: Request ML20209G1291985-09-0606 September 1985 Evaluation of Spent Fuel Racks Structural Analysis,Grand Gulf Nuclear Station Unit 1, Technical Evaluation Rept Project stage: Other AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility1985-09-11011 September 1985 Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility Project stage: Other AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal1985-09-12012 September 1985 Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal Project stage: Other AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules1985-11-0101 November 1985 Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules Project stage: Other AECM-85-0410, Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks1985-12-18018 December 1985 Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks Project stage: Request AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas1986-03-14014 March 1986 Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas Project stage: Other AECM-86-0011, Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks1986-03-15015 March 1986 Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks Project stage: Request AECM-86-0176, Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl1986-06-0505 June 1986 Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl Project stage: Request ML20205T3631986-06-0505 June 1986 Proposed Changes to Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks Project stage: Request ML20205T0671986-06-0909 June 1986 Revised Tech Spec Page 5-6 Re High Density Spent Fuel Racks Project stage: Other AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks1986-06-0909 June 1986 Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks Project stage: Other ML20203G5171986-07-14014 July 1986 Notice of Consideration of Issuance of Amend to License NPR-29 & Proposed NSHC Determination & Opportunity for Hearing to Revise Tech Spec Section 5.6, Fuel Storage, Allowing Increased Upper Containment Pool Capacity Project stage: Other AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 8608181986-07-25025 July 1986 Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818 Project stage: Other ML20205D4401986-07-28028 July 1986 Notice of Violation from Insp on 860613-0714 Project stage: Other ML20205E8521986-08-12012 August 1986 Notice of Availability of Environ Assessment & Finding of No Significant Impact Re Application for Amend to License NPF-29,revising Tech Specs to Authorize Spent Fuel Pool Expansion Project stage: Other ML20205E8451986-08-12012 August 1986 Environ Assessment Re Mod of Spent Fuel Storage Racks at Plant Project stage: Other ML20212N0561986-08-18018 August 1986 Safety Evaluation Supporting Issuance of Amend 17 to License NPF-29 Project stage: Approval ML20212N0391986-08-18018 August 1986 Amend 17 to License NPF-29,revising Tech Spec Section 5.6, Fuel Storage to Allow Increased Upper Containment Pool Capacity & Increased Spent Fuel Storage Pool Capacity Project stage: Other ML17219A2551986-12-0505 December 1986 Safety Evaluation Re Util Fire Protection Deviation Requests from App a to Branch Technical Position Asb 9.5-1 & App R to 10CFR50.Listed Deviations Granted.Deviation Re Lack of Fire Rated Barrier Denied Project stage: Approval 1985-09-12
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION MISSISSIPPI POWER & LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 NOTICE OF AVAILABILITY OF ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-29, issued to Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Power Association, (the licensees), for operation of the Grand Gulf Nuclear Station, Unit 1, located in Claiborne County, Mississippi.
Identification of Proposed Action: The amendment would consist of changes to theoperatinglicenseandTechnicalSpecifications(TSs)andwouldauthorize an increase of the storage capacity of the spent fuel pool (SFP) from 1270 fuel assemblies to 2324 fuel assemblies and an increase of the storage capacity i
of the upper containment pool (UCP) from 170 to 800 fuel assemblies.
The amendment to the TSs.is yesponsive to the licensee's submittal, dated May 6, 1985. The NRC staff has prepared an Environmental Assessment of the Proposed Action, " Environmental Assessment Related to the Modification of the Spent Fuel Storage Racks at Grand Gulf Nuclear Station, Unit 1, Facility Operating License No. NPF-29 Mississippi Power & Light Company, Middle South Energy. Inc., South Mississippi Electric Power Association," dated August 12, 1986.
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. Summary of Environmental Assessment: The Final Generic Environmental Impact Statement (FGEIS) on Handling and Storage of Spent Light Water Power Reactor Fuel (NUREG-0575), Volumes 1-3, concluded that the environmental impact of interirc. storage of spent fuel was negligible and the dose of the various alternatives reflects the advantage of continued generation of nuclear power with the acccrrpanying spent fuel storage. Because of the differences in SFP designs, the FGEIS recommended licensing SFP expansions on a case-by-case basis.
For Grand Gulf Nuclear Station, Unit 1, the expansion of the storage capacity of the spent fuel pool and the upper containment pool will not create any significant additional radiological effects or non-radiological environmental impacts.
The additional whole body dose that might be received by an individual at the site boundary is less than 0.1 millirem per year; the estimated dose to the population within a 50-mile radius is estimated to be less than 0.1 person-rem per year. These doses are small compared to the fluctuatior.:: in the annual dose this population receives from exposure to background radiation.
The increases in occupational exposures for the proposed operation of the l
modified spent fuel pool are estimated to add less than one percent to the total annual occupational radiation doses at the plant. This small increase in occupational radiation doses should not affect the licensee's ability to main-i tain individual occupational doses within the limits of 10 CFR 20.
The only non-radiological discharge altered by the modifications to the SFP and UCP is the waste heat rejected to the Mississippi River. The total l
. load to the Mississippi River will be increased less than 0.03 percent. Thus, there is no significant environmental impact attributable to the discharge waste heat from the station due to this very small increase.
FINDING OF NO SIGNIFICANT IMPACT The staff has reviewed the proposed modifications to the facilities relative to the requirements set forth in 10 CFR Part 51. Based on this assessment, the staff concludes that there are no significant radiological or non-radiological impacts associated with the proposed action and that the issuance of the proposed amendment to the license will have no significant iripact on the quality of the human environment. Therefore, pursuant to 10 CFR 51.31, an environmental impact statement need not be prepared for this action.
For further details with respect to this action, see (1) the application for amendment to the Technical Specifications dated May 6,1985 and supple-mental letters dated July 29, August 15, August 30, September 11, September 12, November 1, and December 18, 1985, and March 14, March 15, June 5, June 9, and July 25, 1986, (2) the FGEIS on Handling and Storage of Spent Light Water Power Reactor Fuel (NUREG-0575), (3) the Final Environmental Statement for Grand Gulf Nuclear Station, Unit 1, issued September 1981, and (4) the Environmental Assess-ment dated August 12, 1986 These documents are available for public inspection I
at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C.
i 20555 and at the Hinds Junior College, McLendon Library, Raymond, Mississippi 39154.
. Dated at Bethesda, Maryland, this 12th day of August 1986.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing I
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