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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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LONG ISLAND LIGHTING COMPANY Operating License NPF-36 Docket 50-322 License Change Application 8 This License Change Application requests modification of certain emergency diesel generator (EDG) license conditions. Operating License NPF-36 for the Shoreham Nuclear Power Station mandates certain EDG conditions as described in Attachment 3 to the license. These license conditions provide a basis for the qualification of the TDI EDGs through the first cycle of plant operation. This request proposes licensing conditions that form a basis for qualification of the TDI EDGs over the entire life of the plant. The new conditions are a combination of the existing license conditions, required during the first fuel cycle and through the first refueling outage, and the requirements of NUREG-1216 for the balance of the plant life.
The request and supporting documentation are contained in the Attachment to this License Change Application.
Long Island Lighting Company By h ,q 24 Jo sy. Leonard, Jr. /'
Og42gg((((0003g2 Vi e I resident - Nuclear O e::ations P
Subscribed and sworn to before me this dY day of April 1987.
NOTARY BL C Sta e f cw Ycelr (
QuahfM m sum cowy Notary'Public of New Ydlif Ocmmissen spores March 30, IJf My Commission Expires: N/areb 30. )3I
O Attachment To License Change Application 8
1.0 DESCRIPTION
OF CHANGE The detailed maintenance and surveillance requirements are shown in Exhibit A, Pages 1 - 7 (Attachment 3 to NPF-36).
The new proposed license amendments combine the existing license conditions during the first fuel cycle and through the first refueling and then utilize the requirements of NUREG-1216 for the balance of plant life.
2.0 REASON FOR CHANGE These changes allow LILCO to implement the staff's requirements which establish the basis for the continued qualification, reliability and operability of the TDI engines over the entire life of the plant. These license condition changes involve detailed maintenance and surveillance activities for critical engine components. When implemented they will ensure proper and safe operation of the engines and maintain their adequacy and availability for nuclear standby service. These proposed license condition changes do not affect any plant conditions or parameters nor do they involve any Technical Specification changes. Finally, these proposed license changes incorporate all of the TDI Owner's Group or PNL recommendations, which were reviewed and approved by the Staff in NUREG 1216.
3.0 BASIS FOR NO SIGNIFICANT HAZARDS FINDING The proposed license condition changes do not involve a significant hazards consideration because operation of the Shoreham Nuclear Power Station Unit 1, in accordance with this change, would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed license conditions as mandated through the Staff's final SER (NUREG-1216), establish the basis for the continued design adequacy and qualification of the SNPS TDI engines for nuclear standby service, as required by GDC 17 of Appendix A to 10 CFR 50. The incorporation of the most critical periodic maintenance /
surveillance inspections for certain Phase I engine components as license conditions will ensure continued reliability and operability of these units over the life of the plant. These proposed license conditions do not involve any changes in the system's design and operability requirements nor in the plant operating conditions or parameters.
(2) create the possibility of an accident that is different than already evaluated in the USAR. The proposed license conditions involve maintenance and surveillance activities for critical engine components in order to ensure proper and safe operation of the engines and maintain the adequacy and availability of these units for nuclear standby service. These proposed license condition amendments do not affect any plant conditions or parameters nor do they alter the system design and operability requirements. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated cannot be created.
(3) involve a significant reduction in the margin of safety as defined in the bases to Technical Specifications 3/4.8. All required inspections for critical engine components that are incorporated in these proposed license conditions meet or exceed those recommended by the vendor and the TDI EDG Owner's Group DR/QR program.
These inspections do not alter the functional safety requirements of the emergency diesel generators, thus there is no impact on the results and conclusions of the USAR Chapter 15 analyses and no impact on the margin of safety. Also, all requirements of the existing license conditions as imposed by the NRC are maintained until startup from the first refueling outage. Furthermore, all proposed new license conditions for post first fuel cycle have been reviewed and approved by the NRC staff and documented in NUREG-1216. Therefore, the proposed license changes do not involve a significant reduction in the margin of safety.
CONCLUSION The Commission has provided guidance concerning the application of standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideration. Example (ii) relates to a change that consitutes an additional limitation, restriction or control not presently included in the technical specifications:
for example, a more stringent surveillance requirement. Example (vii) relates to a change to make a license conform to changes in the regulations.
In this case, the proposed changes described above are similar to both Example (ii) and Example (vii).
First, these proposed license changes constitute additional controls and conditions not presently included in facility operating license NPF-36. For example, the conditions pertaining to the turbochargers do not currently exist. Second, these l proposed changes will make NPF-36 conform to the finding and l recommendations in the NRC Staff Safety Evaluation Report of the Operability / Reliability of Emergency Diesel Generators manufactured by Transamerica Delaval, Inc. (NUREG-1216).
Therefore, based upon the above considerations, TDI Owners Group analyses, PNL analysis and the NRC Staff Safety Evaluation Report, LILCO has determined that this proposed change does not involve a significant hazards consideration.
4.0 TIMING OF CHANGE This proposed license conditions will require several station procedure changes. LILCO expects to have the appropriate station procedures changed and approved by the end of June, 1987.
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EXHIBIT A ATTACHMENT 3 Emergency Diesel Generator (EDG) 101, 102 and 103 License Conditions A. General Changes to the maintenance and surveillance program for the TDI diesel engines, as identified in NUREG-1216, Section 2.3,
" Maintenance / Surveillance Program" shall be subject to the provisions of 10 CFR 50.59.
The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.1, " Overhaul Frequency" in Revision 2 of Appendix II of the Design Review / Quality Revalidation report which was transmitted by letter dated May 1, 1986, from J. George, Owners Group, to H. Denton, NRC.
B. Cylinder Block The following inspection requirements are as defined in Failure Analysis Associates, Inc. (FaAA) report entitled,
" Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no. FaAA-84-9-ll.1) and dated December 1984. The inspection intervals (i.e.,
frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report.
Liquid-penetrant testing or a similarly sensitive nondestruc-tive testing technique should be used to detect cracking, and eddy current should be used as appropriate to determine the crack depth.
- 1. EDG 101, 102 and 103 cylinder block top surface shall be inspected for " ligament" cracks, " stud-to-stud" cracks and " stud-to-end" cracks at each major engine overhaul.
- 2. The licensee shall perform eddy current testing or boroscopic examination between adjacent cylinder heads l after any operation of EDG 101 or 102 at greater than ;
1750 KW. -
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- 3. EDG 101 and 102 cylinder block top surface shall be partially inspected at each refueling outage to deter-mine whether or not cracks have initiated on the top surface exposed by the removal of two cylinder heads.
This process should be repeated over four refueling outages until the entire block top has been inspected.
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- 4. If any inspection reveals cracks in the cylinder blccks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions have been approved by the NRC staff.
- 5. In addition to the above, the following license conditions are applicable during the first fuel cycle and through the first refueling outage. l
- a. During any period of continuous operation following automatic diesel generator initiation, the licensee shall perform daily visual inspections of the area between adjacent cylinder heads and the general block top. The licensee shall also perform visual inspections of the same areas under intense light during the monthly surveillance testing. This condition is applicable to EDGs 101, 102, 103.
- b. Following any loss of offsite power event which results in the automatic starting of any EDG, the licensee shall inspect the top surface of the block exposed by the removal of two appropriate cylinder heads from each of the three EDG engines. Inspec-tions shall be by liquid penetrant, with eddy current for any identified cracks, to determine the
- presence of new cracks and the depth of any new or old cracks.
- c. The licensee shall perform a liquid penetrant and, as appropriate, UT inspection of the cylinder liner landing at any time a cylinder liner is removed for any other reason. This condition is applicable to EDGs 101, 102 and 103.
- d. Examination of the block top between cylinder heads as required by item 2 above will be performed by eddy current inspection only.
C. Cylinder Block Cam Gallery Cracks Cam gallery saddle locations nos. 2 and 8 on the EDG 101 and 102 blocks will be inspected by LILCO every three months, or after 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> of operation at or above a load of 1800 KW, whichever comes first. These inspections shall be performed from the time the EDGs are initially placed in operation for emergency standby service until the first refueling outage.
Liquid penetrant examinations of the nos. 2 and 8 saddle locations shall be performed to monitor the length of the cracks, followed by TSI depth gauge measurements of the cracks to monitor their depth.
7 D. Crankshafts
- 1. EDGs 101, 102, and 103 shall not be operated at power levels greater than_3400 KW*, as indicated by the l installed power meter in the Shoreham control room. If.
an' engine is operated at a power level greater than 3400 KW, for any time, (1) the engine shall be removed,from service as soon as is safely possible, (2) the engine '
shall be declared inoperable, and (3) the crankshaft "
shall be inspected in accordance with the provisions of conditions D.4 and D.5.
- 2. For the first fuel cycle EDGs 101, 102, and 103 are each limited to two hours of cumulative operation at loads between 3300 and 3400 KW, in addition to the monthly surveillance tests. If this limit is exceeded, (1) the engine shall be removed from service.as soon as is safely possible, (2) the engine shall be declared i inoperable, and (3) the crankshaft shall be inspected in 1 accordance with the provisions of conditions D.4 and D.5 below.
! 3. Following the satisfactory inspections of the EDGs 101, 102 and 103 crankshafts at the first refueling outage, if the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ** cumulative load limit of 3300 to 3400 KW, described in D.2 above is exceeded, a crankshaft inspection pursuant to items D.4 and D.5 shall be performed at the next refueling outage.
- 4. At each refueling outage, the licensee shall measure and record hot and cold web deflection readings on each of the diesels.
- 5. At the first refueling outage, the licensee shall inspect the crankpin journals numbered 5, 6 and 7 and the main bearing journals between crankpins 5, 6 and 7, including the associated oil holes and fillets in all of these journals, using LP and ET as appropriate. This condition is applicable to EDGs 101, 102 and 103.
- 6. During the second and third refueling outages, inspect the fillets and oil holes of two of the three most heavily loaded crankpin journals in each crankshaft, using liquid penetrant. Indications found should also be evaluated with eddy current methods as appropriate.
- 7. Following the third refueling outage, inspect the fillets and oil. holes of the (a) three most heavily loaded crankpin journals (Nos. 5, 6, and 7) and (b) the main journals located between crankpin journals 5, 6 and 7, at the refueling outage corresponding to an approximately five year interval between crankshaft inspections.
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- Momentary transients (not exceeding 5 sec) that result from i changing bus loads need not be considered as an overload.
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- If there are multiple overload events since the previous l
crankshaft inspection, then the time criterion applies to the total accumulated time in the load' range.
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E. Cylinder Heads
- 1. Cylinder heads purchased as replacements will be inspected in accordance with paragraphs (a) and (b) are subject to paragraph (c) below.
(a) Perform an ultrasonic inspection of the firedeck of all the cylinder heads at six locations to verify that the minimum thickness requirements of .400 inch is met. The six locations are specified as follows:
(i) The first location is on the firedeck between the exhaust gas ports approximately directly between the two exhaust gas ports.
(ii) The second location is approximately 1 1/2" from the first location in a direction toward the exhaust side of the cylinder head.
(iii) The third location is approximately 2" from the first location in a direction toward the intake side of the cylinder head.
(iv) The fourth location is approximately midway j between the injector port and the exhaust port on the governor side . the head.
(v) The fifth location is approximately directly between the two intake gas ports.
(vi) The sixth location is approximately midway between the injector and exhaust port on the flywheel side of the head.
l Cylinder heads not meeting this thickness requirement l shall not be used.
(b) Perform surface inspection (either liquid penetrant i or magnetic particle) of intake and exhaust valve seats and the firedeck area between the exhaust valves to verify that they are free of unacceptable {
surface defects. Cylinder heads with unacceptable and irreparable surface defects shall not be used.
Acceptance criteria are as specified in ASME III, paragraph NB-5350.
(c) Ascertain from shop records or otherwise whether any heads have through-wall weld repairs of the firedeck where the repair is performed from one side only. Any such heads shall not be used.
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- 2. Any head which leaks due to a crack shall be replaced.
- 3. The air roll test described below shall be performed as specified except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources:
( The licensee shall bar the engines over with the barring device and roll the engines over with the airstart system, with the cylinder stopcocks open, prior to each l planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. In addition, after engine operation, the engines shall be barred and rolled over with-the air-start system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown. In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks-open at the time it is returned to service. The origin of any water detected in the cylinder must be determined and any cylinder head which leaks due to a crack shall be replaced. The above post operational air roll test may be discontinued following the first refueling outage subject to the following conditions:
(a) All cylinder heads are Group III heads (i.e., cast after September 1980).
(b) Quality revalidation inspections, as required by El above, have been completed for all cylinder heads.
(c) Group III heads continue to demonstrate leak free performance. This should be confirmed with TDI prior to deleting air roll tests.
F. Turbochargers
- 1. The turbocharger thrust bearings shall be visually inspected for excessive wear after 40 non-prelubed starts since the previous visual inspection.
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- 2. Turbocharger rotor axial clearance shall be measured at each refueling outage to verify compliance with TDI/
Elliott specifications. In addition, thrust bearing measurements shall be compared with measurements taken previously to determine a need for further inspection or corrective action.
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- 3. Spectrographic and ferrographic-engine-oil analysis shall be performed quarterly to provide early evidence of bearing degradation. Particular attention shall be paid to copper level and particulate size which could signify thrust bearing degradation.
- 4. The nozzle ring components and inlet guide vanes shall be visually inspected for missing parts or parts showing distress on a one-turbocharger-per-refueling-outage basis. -In-addition,-these inspections shall be per-formed for all turbochargers at each turbocharger over-haul (i.e., at approximately 5-year intervals). If any missing parts or distress is noted, the entire ring assembly shall be replaced and the subject turbocharger shall be reinspected a the next refueling outage.
G. EDG 3300 KW Alarm The licensee shall install-a distinctive visual and audible alarm for each diesel generator in the main control room that will be set no higher than 3300 KW for operation.
H. Procedures and Training
' Prior to operation at reactor power levels greater than 5%,
the licensee shall complete, in a manner acceptable to NRC staff, the development of suitable procedures and training to minimize the likelihood of operator errors that could result-in EDG overload.
I. Inspection Results and Restart If any of the engine inspections required by paragraphs B, C and D above identify a degraded component condition, the associated engine shall be declared inoperable until the results of the inspection and further analyses by the licensee of the degraded condition have been reviewed, and further operation of the engine has been approved by the NRC staff.
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