|
---|
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] |
Text
Long Shorc; ham Nuclear Power Station -
istand P.O. Box 628 Power North Country Road Authcoty Wading River, N.Y.11792 LSNRC-1883 UANJB 1992
~ ~'
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Applicat.on for an Amendment-to Facility Operating License NPF-82 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322-l Ref: (1) Long Island Power Authority, Shoreham Nuclear Power.
Station Decommissioning Plan (December 29, 1990)
I. Introduction Pursuant 1to 10 CFR 550.90,.Long Island: Power Authority: ("LIPA"), j with the support of the _ Long _ Island Lighting - Company -("LILCO") , .
hereby requests a conforming amendment to License =No. NPF-82, the Possession _Only License for the Shoreham NuclearfPower Station
("Shoreham"), to become effective as soon as possible after l Nuclear Regulatory. Commission-("NRC") _ approval of theLpending l Joint Application to Transfer the Shoreham Nuclear Power Station license from LILCO to LIPA, to reflect the NRC's approval of the Shoreham Decommissioning Plan (Ref. 1). The amendment would authorize implementation of the shoreham Decommissioning' Plan
! presently pending before.the NRC.
t By separate application dated June 28,[1990, LIPA1and LILCO.have d jointly sought approval of a license amendment authorizing .
- l L transfer of License No. NPF-82 from LILCO-to LIPA. -In1 addition, l on December:29, 1990, LIPA submitted-_its Shoreham; Decommissioning l Plan, which LILCO-requested the NRC to review and approve by L . letter dated. January.2, 1991. After-nearly a-year of review, on-December 23,_1991, the NRC published notice;of-;itsf intent to-approve the Shoreham Decommissioning Plan. See-56 Fed. Reg.
l 66459' (1991). The requested amendment.would. allow LIPA, after'it L has become the licensee', to implement _that Shoreham '
Decommissioning; Plan.
L9201160032 920113 (T(
j) i 9 I tPDRO ADOCK 05000322 I
LSNRC-1883 Page 2 i LIPA further requests that this license amendment be effective upon issuance pursuant to 10 CFR S50.91(a) (4) , and that it be processed expeditiously in light of-the Commission's previous notice of intent to approve the. Decommissioning-Plan and the cost increases and other harm outlined below that would occur if decommissioning is delayed.
II. Description of the Proposed Amendment The proposed amendment would add a new provision to Section 2.C of License No. NPF-82, stating as follows:
"(4) Decommissioning Authorization The licensee is authorized to decommission Shoreham in accordance with (a) the Shoreham Decommissioning Plan submitted on December-29, 1990, as supplemented by letters dated August 26, 1991, November 27, 1991 and December 6, 1991, and (b) the Commission's rules and regulations."
III. No Significant Hazards Determination LIPA has performed a "no significant hazards consideration" analysis, assessing the proposed amendment using the standards set forth in 10 CFR $50.92 (c) . This analysis, as-presented in an attachment hereto, demonstrates that the proposed amendment does not involve a significant hazards consideration.
IV. Request for Expedited Processing LIPA requests that the Commission review and arrange for publication of the amendment at the earliest possible date. . The Decommissioning Plan has been on file with the Commission for over a year. The public interest requires that LIPA be free to commence decommissioning as soon as possible for the following reasons:
j
- 1) Decommissioning activities are prioritized to. maximize-the ;
ability to dispose of radioactive waste materials in 1992 because of the potential for denial-of access to licensed radioactive waste burial-facilities as of January 1,-1993.
This prioritization minimizes the quantity offradioactive waste that could be required to be stored at-the Shoreham site on an interim basis after 1992, as well aF the higher costs to.ratepayers which would likely be associated with offsite disposal after 1992.
LSNRC-1883 a
Page 3
- 2) Prolonged delay in the initiation of decommissioning, and hence, in the completion of decommissioning, will increase the costs to ratepayers because of the need to maintain station staffing levels over a longer period of time. Also, a prolonged delay in the start of decommissioning could result in additional costs from contractots who are now preparing to mobilize at the Shoreham site, as well as in the potential loss of availability of selected contractor personnel and/or equipment to other projects.
- 3) The project schedule currently takes advantage of the near-term availability of the Reactor Building Polar Crane for activities other than f'ael disposition. Once fuel disposition is underway (possibly as early as July 1992) the availability of the Polar Crane for other activities will be greatly reduced. Thus, the decommissioning project schedule would likely be extended.
Therefore, LIPA respectfully requests that this matter be processed as expeditiously as possible and noticed promptly in ,
the Federal Register, to avoid further delay in decommissioning.
Long Island Power Authority By LFM. 11111 Resident Manager Shoreham Nuclear Power' Station Subscribed and sworn to me this /J d day of January, 1992.
s k M Notary Public of New York My Commission Expires: Ma t/ /8, /N3
/
cc: D. Ross MMES A UTTLE S. Brown NOTARY PUBUC State of New York No. 4886267, Suffolk Coun T. T. Martin u 8,1 -
L. Doerflein J. D. Leonard, Jr.
L. Bel.1 B. Norris
.- -~ ~ _. - . . - . . .. -. _ .-
s Page 1 of 3 APPENDIX ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION LIPA has performed a "no sigaificant hazards consideration" analysis, assessing the proposed-amendment using the standards set forth in 10 CFR 550.92(c). This analysis demonstrates that the proposed amendment does not involve a significant hazards consideration.
A. Requirements of 10 C.F.R. S 50.92.
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 consequences of an accident previously evaluated, or (2) Create the possibility of a new-or different kind of accident from any previously evaluated; or (3) Involve a significant reduction ~in a margin of safety."
Decommissioning activities at Shoreham would_not involve a significant hazards consideration, as shown below.
B. Condition of Shoreham' Confirms No Significant- Hazards Given the limited operating history of-Shoreham-(less than'two effective full-power. days), the levels of-radioactivity-and amounts of contamination at Shoreham~are much lowerJthan at a plant that has operated for.a significant timeaat full power.
This greatly reduces the scope and. complexity of decommissioning.
activities. The Shoreham Decommissioning Plan contains an-Accident-Analysis for. decommissioning activities and for Spent.
Fuel' Storage and-Handling. .This analysis. establishes'that, given.
the defueled and non-operating. status of the plant-and 1 the limitations in the Technical Specifications applicable'to the plant, continued maintenance and decommissioning of Shoreham pose.-
minimal radiological risk.
The radiologically bounding accident -- a fuelL damage accident -- 3 is described _in Section 3.4.1.8 of the-Decommissioning Plan. l This.same postulated event wac~ analyzed-by LILCO-in its Defueled i Safety-Analysis Report-and reviewed'and approved by the NRC Staff in itsl Safety Evaluation Related to Amendment No'. 7 To Facility.
Operating License NPF-82 dated June 14, 1991._ Because this-
- postulated event is-still the applicablefradiologically_ bounding. i accident, the previous findings'of no significant hazard 1
- +-
. Page 2 of 3 consideration remain valid. (See Section 4.0 of NRC Staff Safety Evaluation referenced above.) As further evidence.of the minimal-radiological risk associated with this bounding-postulated event, it is noted that the same bounding event also formed the basis r for NRC aut' 'ization to cease offsite emergency preparedness activities Shoreham, again, with a determination of no significant hazards consideration.
C. The Requirements of 10 CPR 550.92'Are Meb The following discussion-provides a specific analysis of the proposed change against-the three standards 1 delineated in 10 CFR-50.92. It confirms that-the proposed license amendment is administrative in nature, designed to achieve consistency _with the Commission's Decommissioning-Order to be issued in accordance r with 10 CFR 550.82(e), and therefore involves no matters that would' pose a signifi' cant ~ hazards consideration.
- 1. The Proposed Changes Does Not Involve a Significant Increase in the Probability _or' Consequences of an Accident Previously-Evaluated The proposed amendment will do-nothing more than authorize decommissioning of Shoreham in accordance_with the NRC approved Shoreham Decommissioning-Plan.- The Decommissioning Plan contains-accident analyses which already have been reviewed by=the NRC.
The amendment will in<no way alter the probability or consequences of the accidents previously analyzed in-the Decommissioning Plan, but will simply authorize-that those decommissioning activities be performed'according to the Plan.
The fuel will not.be further irradiated.- Theinon-operating,= ,
defueled_ condition of the reactor.further reduces the-probability of an operational accident. The~ potential accident consequences for the low burn-up fuel in the spent = fuel ~ pool 4have been analyzed assuming a fuel damage accident.- Further,'the analysis.
conservatively assumed maximum fission. product release (release '
of all fuel gap activity). All of the postulated-decommissioning accident analyses demonstrate that accident; consequences would be substantially lower than1the previous Updated SafetyfAnalysis Report (USAR) accident analyses results=and-well within-regulatory limits.
The fuel, radioactive waste and material will not_be' handled or.
treated in.a-different manner than assumed in previous safety analyses and evaluations. The small:nmounts of radioactive 1 waste and materials at Shoreham'are contained in systems-and components specifically_ designed for their control. Fuel handling'will.bef j performeu'by certified personnel,-with approved equipment and ,
approved procedures. The low burn-up fuel'is stored in the spent H fuel pool. Storage of the fuel in_any on-site' location other -
than the spent fuel pool would require a further-license amendment, i
- y. ,--i.- en -
g .-r-y+9 4 %
. - _ _ _ _ _ . . _ _ . . _ _ _ _ _ _ _ . _. __ _ _ _ = .
, Page 3 of 3 Therefore, the proposed amendment to NPF-82 does not involve a significant increase in the. probability or consequences of an accident previously evaluated.
? The Proposed Changec ','ll Not Create The Possibility of a New Different Kind of Accident from Any Accident r '~. Evaluated The proposed amendment ask i serntwaion to conduct activities in accordance wl: ' decommissioning plan.
Therefore, the amendment-by d<' , 't create the possibility of a new or dif fe vide;t from any previously evaluated.
Because the reactor will not be op _4ted, re is no possibility.
of any operation related accident. The only remaining potential accidents would involve fuel handling and radioactive material storage activities. The fuel and radioactive waste'and material will be handled or treated in the manner described in the Decommissioning Plan, and the amendment involves no modification to spent fuel pool. storage or handling systems. Licensee activities will include maintenance and decommissioning of certain systems according to the Shoreham' Decommissioning Ple.4 as approved by the NRC.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated by the NRC.
- 3. The Proposed Changes Do-Not Involve a Significant Reduction in a Margin of Safety The proposed amendmentLdoes not involve.a reduction-in-any margin of safety. As noted, the license amendment will permit.
decommissioning to_ occur as planned and approved and will be consistent with the Commission's regulations and orders. The margin of. safety reflected in the analyses presented in-the Decommissioning Plan are unaltered by this proposed' amendment.
The fuel handl4ng-and-radioactive' waste storage accidents'were reanalyzed-for the low-burn-up, decay ~ heat, and radioactive inventory conditions of Shoreham in,the Decommissioning. Plan.
These analyses confirmedia significant increase in~-the margin of-safety from those analyzed for long-term, full power operations-in the USAR.. Further, the Defueled Technical Specifications;and' Environmental Protection Plan provide acceptable assurance to protect the public health and' safety for the defueled condition.
As . indicated in the Decommissioning Plan, decommi ioning "
activities will be conducted-in accordance.with-the requirements of these documents..
Therefore, the proposed. amendment does not involve a significant' reduction-in the margin of safety.
- , - , ,. . . - . -. .