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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] |
Text
o
[ LONG ISLAND LIGHTING.' COMPANY Operating 7,1 cense NPF-36 Docket 50-322 License Change Application 15
.This: License Change Application requests modification to Operating License NPF-36 for the Shoreham Nuclear Power Station to-reduce. test l frequency of the Emergency Diesel Generators (EDGs) in accordance with the recommendations of Generic Letter 15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability", and to run the diesel generators at a minimum load during this testing, based on the recommendations of ip -the diesel generator manufacturer, in order to lessen EDG wear and_ degradation.
.g The request and supporting documentation are contained in Attachments 1 and 2 to this License Change Application.
A Long Island Lighting Company l
By . ;w_ k h6k4 oh D. Leonard, Jr.
N Vice President - Nuclear erations Subscribed and sworn to before me this /f* day of July 1988.
l Not' ark Public of N6w Yafk My Commission Expires: /% red 20 /99d UNDA A. CRAUy NOTARY PU8ut st,t, og ,;,, yg No.4816267 Qualifed in Suffe County
&mmisson Empires March 30.192p
..8807250206 DR 880715 ADOCK 05000322 PDC _.
_ _ _ _ _ ___-___-____.._u____________________2.________a_ _____________m ____________
i'
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UNITED STATES OF AMERICA P NUCLEAR REGULATORY-COMMISSION g
a In the Matter of
).
Long Island-Lighting CompanyJ
)- Docket No. 50-322
)
.)'
' ~
SHORFHAM. NUCLEAR' POWER STATION - UNIT 1
' CERTIFICATE OF SERVICE I hereby certify that copias'of License Change Application 15 to t
the Operating License for Shoreham Nuclear Power Station _ Unit
'S l',' dated July g -1988,- have been served on the following by hand-deliver gor by deposit in~the United States ma n , first class, this _M_-' day.of Ju1*/.1988:
Mr. Jay Dunkleberger New York State-Energy Office 2 Rockefeller Plaza
'k Albany, New York 12223
.L. F. Britt, Manager Nuclear Licensing and Regulatory Affairs Subscribed and sworn to before me this /d day of July 1988 4
Notary Public of New p rk' My Commission Expires [/ared JO, /7%
llN04 A. CRATTY NOTARY PUBUC. State of Ne, yo,g No.4816261 QUS% 6 $dssk %nt bmmtS900 Espres Magg p'ggyg
4 , -
'" SNRC-1481 Attachment 1 Page 1 of 4 b Attachment 1 To License Change Application 15
1.0 DESCRIPTION
OF CHANGE' This change-reduces the number of starts and runs of the EDGs due to an engine or offsite circuit out of service, incorpor-
-ates loading of the EDGs during this testing, revises the
-table for determining diesel surveillance frequency, and provides for determination of EDG testing frequency on an individual engine basis. The changes as described below are shown inLAttachment 2, identified by revision bars in the right margins.
Action Statement 3.8.1.1.a has been revised to address only an inoperable offsite circuit rather than one inoperable off-site circuit or diesel generator. Individual diesel gener-ators will undergo Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 (with the diesel generators loaded to 1400 KW) if they.have not been successfully tested within-a prc/ious 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The current requirement is to demonstrate their operability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
Action Statement 3.8.1.1.b has been revised to addrets only an inoperable diesel generator rather than one inoperable offsite circuit and one inoperable diesel generator. The remaining operable diesel generators shall be demonstrated operable by performance of Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 if the first diesel generator has become inoperable due to any cause other than preplanned preventive maintenance or testing, such as fuel oil pump, jacket water pump, or cam galley inspections and/or mainten-
.ance. The current requirement is to demonstrate their operability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. The requirement for restoration of at least two offsite circuits and the remaining diesel generators is deleted. The inoperable diesel generator must be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> rather than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Action Statement 3.8.1.1.c is a new action statement to address inoperability of one offsite circuit and one diesel generator. The remaining A.C. sources must be demonstrated operable as in Action Statements 3.8.1.1.a and b. The inope able A.C. sources must be restored within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or the reactor must be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restoration of at least 2 offsite circuits and all of the required diesel generators must be restored as in Action Statements 3.8.1.1.a and b.
s
osn?
gjf?Q" . .
SNRC-1481 Attachment 1 Page 2 of 4 Action Statement 3.8.1.1.d _(previcusly Action Statement c) involves an editorial revision to change the referenced Action Statements to "b" and "c" rather than "a" and "b".
Action Statement 3.8.1.1.e (previously Action Statement d) has been revised to require performance of Surveillance Requirement 4.8.1.1.2.a.5 (with the diesel generator loaded to 1400 KW) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rather than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least every 8. hours thereafter. Successful performance of Surveillance Requirements 4.8.1.1.2.a.4 and 5 satisfies diesel generator test requirements for Action Statement 3.8.1.1.a.
Table 4.8.1.1.2-1 has been revised to review the results of diesel generator testing after 20 valid tests and 100 valid tests. The test schedule'is determined on a per diesel generator basis and criteria for determining the required test frequency have been added in the footnotes.
2.0 REASON FOR CIJANGE This change is requested in accordance with the recommenda-tions of Generic Letter 84-15 to reduce the frequency of diesel generator testing and, in accordance with the recom-mendations of the diesel generator manufacturer, to start and run the diesels at a minimum loud thereby reducing the amount of wear and degradation of the diesels. These changes should serve to-increase diesel generator availability by testing diesel generators on an individual basis and should improve relisbility by reducing the frequency of tests and runs.
Diesel ger.erators will also undergo testing at a load which will reduce engine stresses. The bases for the specific changes are presented in the following items a, b and c.
a) Individual testing of the diesel generators, which have not been successfully tested within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, has been incorporated to delete the requirement to test all remaining diesel generators. More frequent testing wou'd not provide significant additional assur-ance of operabi.ity and would increase engine wear.
b) Action Statements 3.8.8.1 a, b, c,e, and f have been modified with a footnote to run diesel generators at a load of 1400 KW. The requirement to run diesel gener-ators at 1400 KW during this testing is in compliance with, and well above, the manufacturer's recommended minimum load of 1050 KW, which corresponds to an intake air manifold pressure of 10 inches of mercury. Running diesel generators at 1400 KW per action statement requirements will help to decrease engine stresses associated with testing at the qualified load of 3300 KW and will help to reduce er.gine wear associated with operation at no or low load.
. . . l SNRC-1481 1
~
Attachment 1 j
'Page 3 of 4 c) The revised test-schedule, based on the number of l failures in the previous 20 and 100 valid tests on a per diesel generator basis, is in accordance with the recommendation in Generic Letter 84-15 and allows fc_
the-evaluation of diesel generator operability more
~
frequently-than if the results of only 100 valid tests are examined. The revisions in the "Test Frequency" column of Table 4.8.1.1.1-1 reduce the actual frequency to once per.7 days, so as to reduce engine wear and degradation.
3.0 BASIS FOR NO SIGNIFICANT HAZARDS FINDING The proposed Jicense change does not involve a significant hazards consideration because operation of the Shoreham Nuclear Power Station, in accordance with this change, would not:
(1)' involve a significant increase in the probability or consequences of an accident previously evaluated as it does not alter the onsite standby power supply system design or the system's operability and availability requirements. The diesel generators are required to supply the same emergency load service regardless of the
-proposed change. The reduction of test frequency, the independent testing and the loading to 1400 KW should reduce the potential for failures caused by excessive testing and running diesels at low or no load. Surveil-lance Testing of the diesel generators at a load of 3300 KW will continue to be performed every 31 days.
(2) create the possibility of a new or different kind of accident from any accident previously evaluated as on-site standby power supply system design and operability requirements are not affected by the proposed change.
(3) involve a significant reduction in a margin of safety as the diesel generators are required to supply the same emergency load service, regardless of the proposed change. Performance of diesel generator testing within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, upon inoperability of one or more offsite circuits (3.8.1.1 a, e), provides little additional assurance of diesel generator opera-bility than testing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a previous surveillance test or within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Upon loss of offsite circuits, diesel generator reliability is not expected to be adversely affected, thus, surveillance testing within 24 or 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provides adequate assurance of diesel generator operability. It also allows time l for pre-test inspection, if required, and sequential l tcsting of diesel generators. The proposed requirement (3.8.1.1.b,c) that upon unplanned inoperability of the L _ _ _ , , _
SNRC-1481.
ei Attachment 1 Page 4 of 4 L
- diesel b'eing tested, the remaining. diesels.are indi-vidually tested-within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, is incorporated to determine if.a common mode-failure exists. Otherwise, testing of the remaining diesel generators is;not frequired. The addition of; Surveillance Requirement 4.8.1.l'.2.a.5 which includes running the diesel gener-ators at 1400 KW,.will demonstrate operability and availability without subjecting diesel generators to
- operating stresses which.can' occur by testing at the qualified load of 3300 KW. This requirement will also reduce the amount of wear associated with running diesel generators at no or low loads. Each diesel generator
' has aLtest' schedule based on its individual performance in previous surveillance. tests. Test schedules will now be determined by the number of fai-lures per 20 consecu-tive tests in addition to thn'100 consecutive tests originally identified (Table 4.8.1.1.2-1). The proposed tech spec changes are consistent with the guidelines of Generic. Letter 84-15. They will serve to reduce the number of diesel starts and runs, thereby reducing wear and tear and ultimately degradation and failure. The proposed changes should improve overall safety.
The Commission has provided guidance concerning the applicability of standards for determining whether a significant hazard consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideration. Example (vii) relaten to a change to make a license conform to changes in regulations where the license change results in very minor changes to facility operations clearly in keeping with the regulations. While Generic Letter 84-15 is not a regulation, i.e., not mandatory, it comprises NRC guidelines which LILCO, by requesting this license
= change, is complying with. Similar to example (vii) no changes to facility operations are involved. The limiting conditions for operation and monthly diesel generator surveillance testing remain unchanged.
Based upon the above considerations and analyses, LILCO has determined that this proposed change does not involve e significant hazards consideration.
4.0 TIMING OF CHANGE Since this change should improve diesel generator reliability and availability, thereby enhance overall plant safety, LILCO requests that this change become effective as soon as possible.
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