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ML20128M13731 July 1985Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company)
ML20138C87921 October 1985Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor
ML20138K68030 November 1985a Review of the Shoreham Nuclear Power Station Probabilistic Risk Assessment.Internal Events and Core Damage Frequency
ML20154F39514 September 1988Safety Evaluation Supporting Request to Operate Facility at 25% Power Re Accident Evaluation
ML20154L9644 March 1986Amend 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
ML20155F3436 October 1988Safety Evaluation Supporting Util Request to Operate Facility at 25% Power Re Accident Evaluation
ML20203D42714 July 1986SALP Rept 50-322/85-98 for Mar 1985 - Feb 1986
ML20206H44314 April 1987Request for Authorization to Increase Power to 25% & Motion for Expedited Commission Consideration.* Apps 1-11 & Certificate of Svc Encl.Related Correspondence
ML20206J9379 February 1987Forwards Quarterly Status Rept for Fourth Quarter of Calendar Year 1986,in Response to Direction Given in House Rept 97-850.NRC Licensing Activity During Period of Rept Includes Issuance of full-power License for Perry Unit 1
ML20210L9565 February 1987Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1
ML20212J45721 January 1987Application 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
ML20212J47521 January 1987Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1
ML20214U20231 January 1987Technical Rept 86.2SH Verification of IPE for Shoreham. W/ 870313 Release Memo
ML20215H63512 June 1987Considerations Re Certain Aspects of Severe Accident Mitigation Afforded by Operation of Shoreham at Reduced Power, Final Ltr Rept
ML20215K71312 June 1987Considerations Re Certain Aspects of Severe Accident Mitigation Afforded by Operation of Shoreham at Reduced Power, Final Ltr Rept
ML20215M3024 May 1987Forwards Amend 5 to License NPF-36 & Safety Evaluation. Amend Revises Tech Specs to Change Reactor Water Level Setpoints for Closure of Main Steam Isolation & Line Drain Valves from Level 2 to Lower Level of Level 1
ML20215M3984 May 1987Amend 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
ML20215M4184 May 1987Safety Evaluation Supporting Amend 5 to License NPF-36
ML20235E59826 June 1987Assessment of Shoreham Nuclear Power Station Secondary Containment Severe Accident Mitigation Capability, Final Ltr Rept
ML20236E17310 March 1989Requests Review of Encl camera-ready Tech Specs to Document & Certify Accuracy W/Facility Usar,Per 890301 Meeting
ML20244B44519 June 1985Forwards Response of Licensee to Motion for Stay of Low Power License,For Filing.W/Certificate of Svc
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NUREG-1126, Forwards camera-ready Version of Tech Specs for Review15 November 1988Forwards camera-ready Version of Tech Specs for Review
PNO-I-85-053, on 850726,scram Signal Generated Due to Low Reactor Water Level.Normal Suction Valve from Suppression Pool for Loop a Opened Before Alternate Suction for Shutdown Cooling Valve Closed.Approx 3,000 Gallons Drained26 July 1985PNO-I-85-053:on 850726,scram Signal Generated Due to Low Reactor Water Level.Normal Suction Valve from Suppression Pool for Loop a Opened Before Alternate Suction for Shutdown Cooling Valve Closed.Approx 3,000 Gallons Drained
SNRC-1026, Forwards Supplemental Motion for Low Power OL21 March 1984Forwards Supplemental Motion for Low Power OL
SNRC-1075, Forwards Updated Onshift Advisor (OSA) Resume,Osa Exam Key & Summary of OSA Operating Experience.All OSAs Satisfactorily Completed Training.No Survey Done by Util Group on Operating Shift Experience6 September 1984Forwards Updated Onshift Advisor (OSA) Resume,Osa Exam Key & Summary of OSA Operating Experience.All OSAs Satisfactorily Completed Training.No Survey Done by Util Group on Operating Shift Experience
SNRC-1131, Responds to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs. Issues Addressed in Generic Ltr Previously Considered & Answered in 821028,1104 & s & 821208 Resolution of Suffolk County Contention 828 December 1984Responds to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs. Issues Addressed in Generic Ltr Previously Considered & Answered in 821028,1104 & s & 821208 Resolution of Suffolk County Contention 8
SNRC-1215, Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage12 November 1985Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage
SNRC-1261, Rev 1 to Transient Analysis Lesson Plan30 May 1986Rev 1 to Transient Analysis Lesson Plan
SNRC-1308, Forwards 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.W/Certificate of Svc.Fee Paid21 January 1987Forwards 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.W/Certificate of Svc.Fee Paid
SNRC-1397, Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl4 December 1987Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl
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