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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARSNRC-2134, Proposed Amend 11 to License NPF-82,requesting Deletion of TS & Environ Protection Plan in Entirety1994-01-20020 January 1994 Proposed Amend 11 to License NPF-82,requesting Deletion of TS & Environ Protection Plan in Entirety ML20059K1141993-11-0404 November 1993 License Change Application 2 to License NPF-82,deleting App A,Ts,App B,Environ Protection Plan (non-radiological) & Revising Pol NPF-82,Amend 9 ML20125D4991992-12-14014 December 1992 License Change Application 1 for License NPF-82,changing Defueled TS to Delete Ac Sources & Onsite Power Distribution Sys Requirements & Change Frequency of Radiological Effluent Release Reporting Requirements SNRC-1900, Suppl to 920113 Application for Amend to License NPF-82, Authorizing Long Island Power Authority to Implement Decommissioning Plan.Suppl Consists of Revised NSHC Analysis1992-01-24024 January 1992 Suppl to 920113 Application for Amend to License NPF-82, Authorizing Long Island Power Authority to Implement Decommissioning Plan.Suppl Consists of Revised NSHC Analysis SNRC-1883, Application for Conforming Amend to License NPF-82, Authorizing Implementation of Util Decommissioning Plan Presently Pending Before NRC1992-01-13013 January 1992 Application for Conforming Amend to License NPF-82, Authorizing Implementation of Util Decommissioning Plan Presently Pending Before NRC SNRC-1857, Suppl to 900105 & 0628 Applications for Amend to License NPF-82,authorizing Transfer of OL from Lilco to Long Island Power Authority & Adopting NRC-approved Program to Certify Personnel Currently Licensed Under 10CFR551991-10-31031 October 1991 Suppl to 900105 & 0628 Applications for Amend to License NPF-82,authorizing Transfer of OL from Lilco to Long Island Power Authority & Adopting NRC-approved Program to Certify Personnel Currently Licensed Under 10CFR55 SNRC-1819, Suppl to 900628 Joint Application of Lilco & Long Island Power Authority for Amend to License NPF-82,reflecting Facility Defueled possession-only Status & Modifying Position Descriptions as Listed on Encl1991-06-27027 June 1991 Suppl to 900628 Joint Application of Lilco & Long Island Power Authority for Amend to License NPF-82,reflecting Facility Defueled possession-only Status & Modifying Position Descriptions as Listed on Encl SNRC-1813, Suppl to 900628 Application for Amend to License NPF-82, Authorizing Transfer of Facility from Lilco to Long Island Power Authority (Lipa),Consisting of Agreement Re Coemployment of New York Power Authority & Lipa Employees1991-06-13013 June 1991 Suppl to 900628 Application for Amend to License NPF-82, Authorizing Transfer of Facility from Lilco to Long Island Power Authority (Lipa),Consisting of Agreement Re Coemployment of New York Power Authority & Lipa Employees SNRC-1770, Application for Amend to License NPF-82,replacing Tech Spec Pages 3/4 4-1 & 3/4 4-3 of Proposed Defueled Tech Specs1990-10-30030 October 1990 Application for Amend to License NPF-82,replacing Tech Spec Pages 3/4 4-1 & 3/4 4-3 of Proposed Defueled Tech Specs SNRC-1740, Application for Amend to License NPF-82,revising Tech Specs Re Defueled SAR1990-08-10010 August 1990 Application for Amend to License NPF-82,revising Tech Specs Re Defueled SAR ML20044A3701990-06-28028 June 1990 Joint Application for Amend to License NPF-82,designating Long Island Power Authority as Plant Licensee Upon or After NRC Amending of License to Nonoperating Status ML20006F4701990-02-20020 February 1990 License Change Application 5,amending License NPF-82 by Revising Tech Specs to Incorporate Guidance in Generic Ltr 89-01 Re Implementation of Programmatic Controls for Radiological Effluent Tech Specs ML20005F2461990-01-0505 January 1990 Application for Amend to License NPF-82,creating Defueled Facility OL ML19332G1561989-12-15015 December 1989 Application for Amend to License NPF-82,ceasing Offsite Emergency Preparedness Activities & Implementing Emergency Preparedness Plan for Facility ML20246N9651989-07-14014 July 1989 Application for Amend to License NPF-82,consisting of Change Application 1,revising Tech Specs to Remove Inconsistency in Plant Procedural Change Approval Process ML20205D2771988-10-19019 October 1988 Application for Amend to License NPF-36,consisting of License Change 16,changing Tech Specs to Allow for Exercising Control Rods to Help Prevent Corrosion of CRD Mechanisms & to Provide for Various Functional Tests ML20151D7071988-07-15015 July 1988 Application for Amend to License NPF-36,reducing Test Frequency of Emergency Diesel Generators Per Recommendations of Generic Ltr 84-15 ML20151D7351988-07-11011 July 1988 Application for Amend to License NPF-36,consisting of License Change Application 13,clarifying Method of Demonstrating Operability of Source Range Monitor Channels ML20154M6231988-05-24024 May 1988 Application for Amend to License NPF-36,consisting of License Change Application 12,revising Tech Specs to Change Method for Determining Setpoint for Main Control Room Vent Radiation Monitors ML20154H1411988-05-19019 May 1988 Application for Amend to License NPF-36,consisting of License Change Application 11,to Provide Clarification of Tech Specs ML20236C4501987-10-14014 October 1987 Application for Amend to License NPF-36,consisting of License Change Application 10,correcting Typos,Tech Spec Internal Inconsistency & Designation of Number of Valves on Table 3.6.3-1 ML20238C3871987-09-0404 September 1987 License Change Application 9 for Amend to License NPF-36, Changing Definition of & Some Footnotes Referring to Core Alteration ML20209D2311987-04-24024 April 1987 Application for Amend to License NPF-36,modifying Certain Emergency Diesel Generator License Conditions to Form Basis for Qualification of Tdi Emergency Diesel Generators Over Entire Life of Plant.Supporting Documentation Encl ML20210C7231987-02-0404 February 1987 Application for Amend to License NPF-36,consisting of License Change Application 7,changing Discharge Pressure in Tech Spec Section 4.1.5c from 1,190 to 1,220 Psig for Standby Liquid Control Sys.W/Certificate of Svc ML20212J4571987-01-21021 January 1987 Application for Amend to License NPF-36,incorporating License Change Application 6 & Revising Tech Specs to Implement Design Change to Lower Reactor Vessel Water Level Setpoint of MSIVs & Steam Line Drain Valves ML20207P9191987-01-12012 January 1987 Application for Amend to License NPF-36,consisting of License Change Application 5,clarifying Location of Meterological Towers & Correcting Inconsistency in Organization Charts ML20206P2611986-06-26026 June 1986 License Change Application 4 to License NPF-36,correcting Error in Listing of Types of Radwaste Shipping Containers & Solidification Agents & Clarifying Review of Operations Committee Responsibilities ML20140A7941986-01-20020 January 1986 License Change Application 3 for Amend to License NPF-36, Eliminating Performance of Sampling Analysis If No Waste Batch Released During Month & Correcting Error in Basis for Location of Milk Control Sample ML20136B4251985-11-16016 November 1985 Application to Amend License NPF-36,consisting of License Change Application 2,increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Surveillance Requirement ML20138C8731985-10-21021 October 1985 Application for Amend to License NPF-36,consisting of Change Request 1,revising Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Gas Radiation Monitor ML20127J2751985-06-19019 June 1985 Application for Amend to License NPF-19,changing Tech Spec 3.10.5 to Allow Suspension of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated 120 EFPD SNRC-1115, Application for Amend 52 to OL Application,Consisting of Rev 34 to FSAR1984-11-29029 November 1984 Application for Amend 52 to OL Application,Consisting of Rev 34 to FSAR SNRC-1085, Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR1984-09-25025 September 1984 Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR ML20082P8571983-12-0101 December 1983 Application for Amend 50 to OL Application,Consisting of Rev 32 to Fsar.W/Affidavit ML20024F0891983-09-0101 September 1983 Amend 49 to OL Application,Consisting of Rev 31 to FSAR ML20070N1611982-12-30030 December 1982 Application for Amend 46 to OL Application,Consisting of Rev 28 to Fsar.Affidavit Encl ML20052H7081982-05-10010 May 1982 Application for Amend 44 to CPPR-95,consisting of Revision 26 to Fsar.Affidavit Encl ML20073M1971982-04-12012 April 1982 Amend 47 to Application for OL Consisting of Rev 29 to Fsar. Rev Includes Changes to Correct Discrepancies Identified by Configuration Review Program for Specific Sys,Revised Steam Bypass Analysis & Scram Discharge Vol Mods ML20041B7641982-02-17017 February 1982 Application for Amend 43 to License Application,Consisting of Revision 25 to FSAR & Revision to Chapter 13 to Reflect Current QA Organization ML20010A3221981-08-0606 August 1981 Amend 40 to OL Application,Containing Revision 22 to Fsar.Revision Includes Revised Chapter 7,responses to NUREG-0737 & Minor Corrections/Clarifications.Affidavit Encl.W/O Revision 22 ML19345D4881980-12-0505 December 1980 Amend 38 to Application for Ol,Consisting of Revision 20 to FSAR ML19262C2061980-01-14014 January 1980 Amend 35 to Application for Ol,Updating Info Supplied Per 10CFR50.33 Requirements ML20235D0821969-04-18018 April 1969 Amend 4 to Application for Ol,Increasing Size of Reactor & Changing Estimated Costs for Const ML20235C8951968-06-18018 June 1968 Amend 1 to Application for Ol.Util Requests That Dates 721001 & 730501 Be Considered as Earliest & Latest Dates for Completion of Const of Facility 1994-01-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARSNRC-2134, Proposed Amend 11 to License NPF-82,requesting Deletion of TS & Environ Protection Plan in Entirety1994-01-20020 January 1994 Proposed Amend 11 to License NPF-82,requesting Deletion of TS & Environ Protection Plan in Entirety ML20059K1141993-11-0404 November 1993 License Change Application 2 to License NPF-82,deleting App A,Ts,App B,Environ Protection Plan (non-radiological) & Revising Pol NPF-82,Amend 9 ML20056C7171993-07-14014 July 1993 Amend 10 to License NPF-82,revising Defueled TS to Delete Requirement That Radioactive Effluent Release Rept Be Submitted on Semiannual Basis & Eliminating Requirements for Ac Sources & Onsite Power Distribution Sys ML20125D4991992-12-14014 December 1992 License Change Application 1 for License NPF-82,changing Defueled TS to Delete Ac Sources & Onsite Power Distribution Sys Requirements & Change Frequency of Radiological Effluent Release Reporting Requirements SNRC-1900, Suppl to 920113 Application for Amend to License NPF-82, Authorizing Long Island Power Authority to Implement Decommissioning Plan.Suppl Consists of Revised NSHC Analysis1992-01-24024 January 1992 Suppl to 920113 Application for Amend to License NPF-82, Authorizing Long Island Power Authority to Implement Decommissioning Plan.Suppl Consists of Revised NSHC Analysis SNRC-1883, Application for Conforming Amend to License NPF-82, Authorizing Implementation of Util Decommissioning Plan Presently Pending Before NRC1992-01-13013 January 1992 Application for Conforming Amend to License NPF-82, Authorizing Implementation of Util Decommissioning Plan Presently Pending Before NRC SNRC-1857, Suppl to 900105 & 0628 Applications for Amend to License NPF-82,authorizing Transfer of OL from Lilco to Long Island Power Authority & Adopting NRC-approved Program to Certify Personnel Currently Licensed Under 10CFR551991-10-31031 October 1991 Suppl to 900105 & 0628 Applications for Amend to License NPF-82,authorizing Transfer of OL from Lilco to Long Island Power Authority & Adopting NRC-approved Program to Certify Personnel Currently Licensed Under 10CFR55 SNRC-1819, Suppl to 900628 Joint Application of Lilco & Long Island Power Authority for Amend to License NPF-82,reflecting Facility Defueled possession-only Status & Modifying Position Descriptions as Listed on Encl1991-06-27027 June 1991 Suppl to 900628 Joint Application of Lilco & Long Island Power Authority for Amend to License NPF-82,reflecting Facility Defueled possession-only Status & Modifying Position Descriptions as Listed on Encl SNRC-1813, Suppl to 900628 Application for Amend to License NPF-82, Authorizing Transfer of Facility from Lilco to Long Island Power Authority (Lipa),Consisting of Agreement Re Coemployment of New York Power Authority & Lipa Employees1991-06-13013 June 1991 Suppl to 900628 Application for Amend to License NPF-82, Authorizing Transfer of Facility from Lilco to Long Island Power Authority (Lipa),Consisting of Agreement Re Coemployment of New York Power Authority & Lipa Employees SNRC-1770, Application for Amend to License NPF-82,replacing Tech Spec Pages 3/4 4-1 & 3/4 4-3 of Proposed Defueled Tech Specs1990-10-30030 October 1990 Application for Amend to License NPF-82,replacing Tech Spec Pages 3/4 4-1 & 3/4 4-3 of Proposed Defueled Tech Specs SNRC-1740, Application for Amend to License NPF-82,revising Tech Specs Re Defueled SAR1990-08-10010 August 1990 Application for Amend to License NPF-82,revising Tech Specs Re Defueled SAR ML20056A1991990-07-31031 July 1990 Amend 6 to License NPF-82,allowing Licensee to Cease Offsite Emergency Preparedness Activities ML20044A3701990-06-28028 June 1990 Joint Application for Amend to License NPF-82,designating Long Island Power Authority as Plant Licensee Upon or After NRC Amending of License to Nonoperating Status ML20055E3871990-06-25025 June 1990 Amend 5 to License NPF-82,changing Administrative Section of Tech Specs & Moving Procedural Details Re Radioactive Effluent Monitoring Instrumentation,Equipment Requirements & Control of Liquid & Gaseous Effluents to ODCM ML20006F4701990-02-20020 February 1990 License Change Application 5,amending License NPF-82 by Revising Tech Specs to Incorporate Guidance in Generic Ltr 89-01 Re Implementation of Programmatic Controls for Radiological Effluent Tech Specs ML20005F2461990-01-0505 January 1990 Application for Amend to License NPF-82,creating Defueled Facility OL ML19332G1561989-12-15015 December 1989 Application for Amend to License NPF-82,ceasing Offsite Emergency Preparedness Activities & Implementing Emergency Preparedness Plan for Facility ML20246N9651989-07-14014 July 1989 Application for Amend to License NPF-82,consisting of Change Application 1,revising Tech Specs to Remove Inconsistency in Plant Procedural Change Approval Process ML20245B8901989-04-21021 April 1989 License NPF-82,authorizing Operation of Core Levels Not to Exceed 2,436 Mwt ML20196E5781988-11-30030 November 1988 Amend 10 to License NPF-36,changing Definition of Core Alteration in Tech Specs to Include Certain Exceptions & Footnotes in Tech Specs to Be Consistent W/New Definition ML20196B6711988-11-30030 November 1988 Amend 9 to License NPF-36,revising Attachment 3 to Plant License Re Maint & Surveillance Program for Tdi Diesel Generators ML20205D2771988-10-19019 October 1988 Application for Amend to License NPF-36,consisting of License Change 16,changing Tech Specs to Allow for Exercising Control Rods to Help Prevent Corrosion of CRD Mechanisms & to Provide for Various Functional Tests ML20151D7071988-07-15015 July 1988 Application for Amend to License NPF-36,reducing Test Frequency of Emergency Diesel Generators Per Recommendations of Generic Ltr 84-15 ML20151D7351988-07-11011 July 1988 Application for Amend to License NPF-36,consisting of License Change Application 13,clarifying Method of Demonstrating Operability of Source Range Monitor Channels ML20154M6231988-05-24024 May 1988 Application for Amend to License NPF-36,consisting of License Change Application 12,revising Tech Specs to Change Method for Determining Setpoint for Main Control Room Vent Radiation Monitors ML20154H1411988-05-19019 May 1988 Application for Amend to License NPF-36,consisting of License Change Application 11,to Provide Clarification of Tech Specs ML20236F6741987-10-19019 October 1987 Amend 8 to License NPF-36,changing Tech Specs Re Location of Two Meteorological Towers ML20236C4501987-10-14014 October 1987 Application for Amend to License NPF-36,consisting of License Change Application 10,correcting Typos,Tech Spec Internal Inconsistency & Designation of Number of Valves on Table 3.6.3-1 ML20238C3871987-09-0404 September 1987 License Change Application 9 for Amend to License NPF-36, Changing Definition of & Some Footnotes Referring to Core Alteration ML20237L3231987-08-31031 August 1987 Corrected Pages 3/4 3-81,3/4 3-81a,3/4 3-83 & 3/4 3-84 of Amend 7 to License NPF-36 Re Fire Detection Instrumentation Limiting Condition for Operation & Radioactive Liquid Effluent Monitoring Instrumentation ML20237G4601987-08-14014 August 1987 Amend 7 to License NPF-36,changing Footnote of Surveillance Requirement 4.4.3.1.c on RCS Leakage Detection Sys & Tech Spec Section 3.3.7.9 on Fire Detection Instrumentation ML20214K3881987-05-18018 May 1987 Amend 6 to License NPF-36,revising Tech Specs to Reflect Util Plan to Enrich Boron in Standby Liquid Control Sys to 85 Atom Percent B-10 Per 10CFR50.62(c)(4) ML20215M3981987-05-0404 May 1987 Amend 5 to License NPF-36,revising Tech Specs to Change Reactor Vessel Water Level Setpoint for Closure of Main Steam Isolation & Line Drain Valves from Level 2 to Lower Level of Level 1 ML20209D2311987-04-24024 April 1987 Application for Amend to License NPF-36,modifying Certain Emergency Diesel Generator License Conditions to Form Basis for Qualification of Tdi Emergency Diesel Generators Over Entire Life of Plant.Supporting Documentation Encl ML20210C7231987-02-0404 February 1987 Application for Amend to License NPF-36,consisting of License Change Application 7,changing Discharge Pressure in Tech Spec Section 4.1.5c from 1,190 to 1,220 Psig for Standby Liquid Control Sys.W/Certificate of Svc ML20212J4571987-01-21021 January 1987 Application for Amend to License NPF-36,incorporating License Change Application 6 & Revising Tech Specs to Implement Design Change to Lower Reactor Vessel Water Level Setpoint of MSIVs & Steam Line Drain Valves ML20207P9191987-01-12012 January 1987 Application for Amend to License NPF-36,consisting of License Change Application 5,clarifying Location of Meterological Towers & Correcting Inconsistency in Organization Charts ML20211N5831986-12-0909 December 1986 Amend 4 to License NPF-36,revising Tech Specs to Eliminate Need for Performing Monthly Sampling & Analysis for Dissolved & Entrained Gases If No Waste Batch of Liquid Effluents Released During Month ML20213D4971986-11-0303 November 1986 Amend 3 to License NPF-36,correcting Internal Inconsistency in Tech Specs Re Process Control Program for Radwaste Shipping Containers & Solidification Agents ML20206P2611986-06-26026 June 1986 License Change Application 4 to License NPF-36,correcting Error in Listing of Types of Radwaste Shipping Containers & Solidification Agents & Clarifying Review of Operations Committee Responsibilities ML20154L9641986-03-0404 March 1986 Amend 2 to License NPF-36,revising Tech Specs to Reflect Conversion of One of Two Low Range Reactor Bldg Standby Vent Sys Noble Gas Radiation Monitors to Low Range Plant Vent Stack Noble Gas Radiation Monitor ML20140A7941986-01-20020 January 1986 License Change Application 3 for Amend to License NPF-36, Eliminating Performance of Sampling Analysis If No Waste Batch Released During Month & Correcting Error in Basis for Location of Milk Control Sample ML20138N6501985-12-0606 December 1985 Amend 1 to License NPF-36,extending Deadline for Completion of Environ Qualification of Electrical Equipment Until 851231 ML20136B4251985-11-16016 November 1985 Application to Amend License NPF-36,consisting of License Change Application 2,increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Surveillance Requirement ML20138C8731985-10-21021 October 1985 Application for Amend to License NPF-36,consisting of Change Request 1,revising Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Gas Radiation Monitor ML20132G7631985-07-0303 July 1985 License NPF-36 for Facility ML20127J2751985-06-19019 June 1985 Application for Amend to License NPF-19,changing Tech Spec 3.10.5 to Allow Suspension of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated 120 EFPD SNRC-1115, Application for Amend 52 to OL Application,Consisting of Rev 34 to FSAR1984-11-29029 November 1984 Application for Amend 52 to OL Application,Consisting of Rev 34 to FSAR SNRC-1113, Application for Amend to CPPR-95,extending Const Completion Date from 841231 to 850330,due to Litigation on Tdi Emergency Diesel Generator.Decision Expected in Early 19851984-11-26026 November 1984 Application for Amend to CPPR-95,extending Const Completion Date from 841231 to 850330,due to Litigation on Tdi Emergency Diesel Generator.Decision Expected in Early 1985 SNRC-1085, Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR1984-09-25025 September 1984 Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR 1994-01-20
[Table view] |
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ATTACHMENT 1 TO SNRC-1664 l
Appl cation to: Amend .
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PDR P
D f IONG-ISLAND LIGHTING COMPANY l ,M; SHOREHAM NUCLEAR POWER STATION
-Docket No. 50-322 It j APPLICATION FOR AN AMENDMENT TO -
FACILITY OPERATING LICENSE NPF-82 1 I. Introduction Pursuant to 10CFR50.90, Long-Island Lighting Company (LILCO) hereby requests an amendment to Facility Operating License NPF-82 for the'Shoreham Nuclear Power Station (Shoreham). LILCO seeks to amend NPF-82 through a series of' revisions that, in sum, create a Defueled Facility Operating License.
f'N II. Description of the Proposed Amendment N-]
To facilitate the NRC's review of the-license amendment request, LILCO has rewritten NPF-32 in its entirety to include the changes it proposes to make to reflect Shoreham's defueled condition.
The license as rewritten, including revised technical specifications (NUREG-1357), is Attachment 2 to this submittal.
The revised technical specifications have been changed to include a new set of Limiting Conditions for Fuel Handling and to eliminate all current Limiting Conditions for Operation. The principal changes to NPF-82 and to Shoreham's technical specifications are summarized below.
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rRT A. Principal Changes to NPF-82
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(1) Paragraph 2.A has been amended to include a reference to the Defueled Safety Analysis Report, which provides a description of Shoreham in its defueled condition.
4 (2) Paragraph 2.B. (1) has been1reviEed to state that LILCO is authorized by the NRC to " possess, use, but not operate the facility . . . ." (emphasis added).
(3) Paragraph 2.C. (1) has been rewritten-to provide that LILCO is "not authorized to operate'the facility at any core power i level."
(4) The license conditions contained 'in paragraph 2.C. (3) i through (13) , which are relevant only to operation, have
, been removed.
(5) . A new license condition C. (3) has been added to paragraph 2 to require that LILCO obtain prior approval from the NRC Staff before placing any fuel assemblies in the reactor' vessel.
(6) Paragraph 2.D has been changed to impose requirements for the Fire Protection program as described in the Fire Hazards Analysis Report and the Defueled Safety Analysis Report.
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(7) Paragraph 2.E has been changed to refer to the revised security plan entitled "Shoreham Nuclear Power Station' Security Plan for Fuel Storage in the Spent Fuel Pool.
B. Principal Changes to NUREG-1357 (1) All Limiting Conditions for Operation have been removed; Limiting Conditions for Fuel Handling Operations have been !
I established.
(2) The " Definitions" section has been shortened to reflect the changes made to the balance of the technical specifications.
(3) The section containing the plant's Safety Limits, which are applicable only to plant operation, has been removed.
(4) The " Administrative Controls" section has been revised to reflect the organization described in the Defueled Safety Analysis Report, which is adequate to maintain the plant safely in its defueled condition and to conduct fuel handling operations.
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III. Defueled Safety Analysis Report <
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In addition to the "no significant hazards consideration" analysis set forth in Section IV below, the license amendment i request incorporates by reference the Defueled Safety Analysis Report (DSAR), which'has been prepared by LILCO's Office of Nuclear Operations. The DSAR, which is Attachment 3 to this submittal, provides both a description of the defueled condition in which Shoreham will be placed if LILCO's license amendment request is granted, as well as the technical analysis to support the license amendment request.
IV. Analysis of No Significant Hazards Consideration r'T . Pursuant to 10CFR50.91(a) (1) , ,LILCO has performed a "no :
- r significant hazards consideration" analysis, assessing the proposed amendment using the. standards set forth in 10CFR50.92(c).- Based on this-analysis, as presented below, LILCO has determined that the proposed. amendment to NPF-82 does not involve a_significant hazards consideration.
Section 50.92 provides that the NRC may make a determination "that a proposed amendment to an operating license . . . involves no significant hazards consideration" if " operation of the facility in accordance with the proposed amendment" would not (1) Involve a significant increase in the probability or
-3 consequences of an accident previously evaluated; or i 6
'# (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or
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7 9-
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!J (3) Involve a significant reduction in.a margin of safety.
(emphasis added). Since the requested amendment to NPF-82 3 c onstitutes, 'in sum, a request by LILCO that it not be allowed to operate Shoreham, as a threshold matter it is evident that the amendment to the license does not involve a "significant hazards consideration."
-A.- The Proposed Amendment Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated )
I First,1the proposed amendment to NPF-82'does not involve a N- ,
significant increase in either the probability.or the' ] i consequences of an' accident previously evaluated. The proposed s
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amendment, if granted, would-remove LILCO's operating authority
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and recognize Shoreham's current non-operating and permanently defueled condition.
l With Shoreham remaining in a defueled condition,'the probability I l
of previously analyzed accidents has,-in fact, been significantly reduced.- As is noted in the Chapter 15 of the DSAR, Shoreham's spent fuel in is a low burnup condition, and the amount of decay i
L heat being generated by the fuel as of June 1989 is negligible --
L approximately 550 watts. With the fuel in such-a low burnup .
condition, the DSAR indicates that active systems for pool water makeup are not required and that passive cooling in the fuel pool is sufficient to maintain fuel cladding integrity.
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fy 'f .The DSAR also' establishes that the consequences of previously e
evaluated ^ accidents are greatly decreased with Shoreham in a c defueled status. The DSAR reviews the spectrum of accidents evaluated in the Shoreham Updated Safety Analysis Report (USAR) and indentifies those events that apply to the storage e.nd-l- handling of spent fuel.- Two events have been found to be y relevant: (1) Fuel Handling Accident (USAR Section 15.1.36), and (2) . Liquid Radwaste Tank Rupture (USAR Section 15.1.32). For the Fuel-Handling Accident, the DSAR calculates that the integrated whole body and skin doses are less than .00005% of the 10CFR Part 100 limits. For the Liquid Radwaste Tank Rupture, the integrated whole body, skin, and maximum organ (lung) doses are less than
.0000004% of the 10CFR Part 100 limits.- In addition, the DSAR .j
!; O V also postulates a " worst case" radiological event,'in which the entire gaseous inventory of the entire core is released to the reactor building. For this event the integrated whole body and 3
skin doses-are less than .031% of the dose limits established by 10CFR Part 100.
B. The Proposed Amendment Will Not Create the Possibility of a New or Different Kind of Accident from Any Accident Previously Evaluated i Second, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The amendment does not affect the function or operation of any system or equipment that has been determined to
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LJ remain in an OPERABLE condition but, rather, conforms Shoreham's license with the plant's existing non-operating and defueled condition. The removal of LILCO's operating authority clearly i.
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( does-not create the-possibility.of,a new or different kind of accident,Lsince,-as noted above, the only. remaining credible j
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events are those associated with-fuel handling and storage l activities,'which have already been# analyzed in the USAR and.
- which'are reanalyzed foraLnew set of: initial conditions in'the- 1 DSAR.
C. The Proposed Amendment Does Not Involve a l
- Significant Reduction in a Margin of Safety Third,.the proposed amendment does not involve a reduction in,a significant margin of safety. While the amendment, if approved, ;
would' remove a'large portion of Shoreham's technical
. specifications, including the Safety Limits section, those p
() - technical. specifications that would be eliminated are relevant only.to' activities that would not be permitted under the amended .i license. Indeed, the proposed new set of technical y
specif'ications represent those technical specifications that are needed to store and handle safely Shoreham's irradiated fuel.
Since fuel storage and handling'are'the only activities that will be permitted at Shoreham under the amended license, it necessarily follows that the proposed changes will not reduce the margin of safety that currently exists under the license.
Long Island Lighting Company By #1' rk i William L. Steige6 /JW Assistant Vice President
( Nuclear Operations Subscribed and sworn to me this 5 d day of January 1990.
JAMES A. UTTLE f(OTARY PUBUC. State of Nm York .
th 48E6267, Suffv!k Co Term Expnes May 18,1 u Notar M lic of New York