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Category:NRC TECHNICAL REPORT
MONTHYEARML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML20204J6141988-08-31031 August 1988 AEOD/E807, Pump Damage Due to Low Flow Cavitation ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20245H9601988-04-15015 April 1988 BWR Overfill Events Resulting in Steam Line Flooding, AEOD Engineering Evaluation Rept ML20148D0671988-03-17017 March 1988 Headquarters Daily Rept for 880317 ML20148B3291988-03-14014 March 1988 Headquarters Daily Rept for 880314 ML20196H6351988-03-0808 March 1988 Headquarters Daily Rept for 880308 ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147E3961988-01-0606 January 1988 Rept of Interview W/Rg Lagrange on 841206 & 14 to Discuss Info Contained in B Hayes 841017 Memo Identifying Series of Submittals Received from Util Between 1980 & 1984 ML20147E3211988-01-0606 January 1988 Rept of Interview W/Rg Lagrange to Discuss Gpu 830520 & s Re Environ Qualification equipment.Marked-up 850409 Statement from H Hukill Also Encl ML20237L3001987-08-24024 August 1987 AEOD/E709 Engineering Evaluation Rept Re Auxiliary Feedwater Trips Caused by Low Suction Pressure.Draft Info Notice Encl ML20235C9311987-06-23023 June 1987 Rept to ACRS Re Humboldt Bay Unit 3 - Core II ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20214R4851986-10-0909 October 1986 Initial OL Review Rept for Seabrook Station Unit 1 ML20212K6641986-08-0707 August 1986 Inadvertent Recirculation Actuation Signals at C-E Plants, Technical Review Rept ML20206H0871986-03-0303 March 1986 Allegation Review Data Sheet for Case 4-85-A-013 Re Const Activities.Addl Info Requested from Alleger.Case Closed Due to Lack of Response.Related Info Encl ML20206H0761986-01-21021 January 1986 Allegation Review Data Sheet for Case 4-84-A-085 Re Alteration of Personnel Records.Based on Resolution of Allegation 4-84-A-094,case Closed ML20137X6151986-01-0909 January 1986 Engineering Evaluation of Deficient Operator Actions Following Dual Function Valve Failures ML20234F4751985-12-17017 December 1985 Licensing of Power Reactors by Aec ML20234F5601985-12-17017 December 1985 Draft Hazards Analysis ML20214T2211985-11-25025 November 1985 Initial OL Review Rept:Millstone Point Unit 3 ML20206H0621985-10-15015 October 1985 Allegation Review Data Sheet for Case 4-85-A-045 Re Inadequate Handling/Installation Procedures for Equipment, Vendor Control Programs & Spare Parts.Based on Insp Rept 50-482/85-22,case Closed ML20206H0371985-10-0202 October 1985 Allegation Review Data Sheet for Case 4-85-A-044 Re Lack of Effective QA Programs & QC Insps.Based on Insp Rept 50-482/85-22,allegation Closed IR 05000482/19850191985-09-30030 September 1985 Allegation Review Data Sheet for Case 4-85-A-050 Re Mishandling of Document Control Program.Concerns Addressed in Insp Rept 50-482/85-19.Dept of Labor & Allegation Cases Closed ML20206H0131985-09-27027 September 1985 Allegation Review Data Sheet for Case 4-84-A-076 Re Vague Administrative Procedures,Calibr Program Not Working,Test Engineer Authority & Harassment.Based on Insp Rept 50-482/85-03,case Closed ML20137B1231985-09-16016 September 1985 HPCS Sys Relief Valve Failures, Engineering Evaluation Rept ML20206G8431985-09-0303 September 1985 Allegation Review Data Sheet for Case 4-84-A-013 Re Improper Termination of Employee Due to Refusal to Weld Laminated Pipe.Welding non-safety Related.Case Closed on 850827.W/ 840315 Telcon Record & Addl Info IR 05000482/19850311985-08-28028 August 1985 Allegation Review Data Sheet for Case 4-85-A-077 Re 6 Rem Exposure in Containment Bldg Due to Pipe Break.Allegation Investigated During Insp 50-482/85-31 on 850715-19 & Found Unsubstantiated ML20206G8051985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-114 Re Drugs Planted at Plant.Evidence Destroyed in Testing.Based on Insp Rept 50-482/85-03 & Mullikin 850429 Memo,Case Closed ML20206G7781985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-195 Re Quality First.Fuel Load Issue Resolved in Insp Rept 50-482/85-10. Technical Issues to Be Resolved Prior to Full Power Licensing.Case Closed w/850815 Memo to File ML20209G3051985-08-0909 August 1985 Closure of ECCS Min Flow Valves, Engineering Evaluation Rept.Recommends IE Issue Info Notice to Remind Licensees of Importance of Min Flow Bypass Capability as Essential Pump Protection Feature ML20206H0801985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-007 Re Intimidation of QC Inspector.Forwards Documents Closing Allegation.W/O Encls ML20206H1021985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-008 Re Improper Const Practices.Insp Rept 50-482/84-12 Issued on 841012 & Closeout Ltr Sent on 850405 ML20147E4401985-06-20020 June 1985 Rept of Interview W/Cw Smyth on 850510.Smyth Advised of Unfamiliarity W/Environ Qualification Program in Technical Sense & W/Documentation Needed to Qualify Individual components.Marked-up Lw Harding Statement Encl ML20199G0701985-05-0303 May 1985 Partially Withheld Statement of Decision Re Allegation AQ-38 Concerning Alleged Harassment of QC Inspectors Upon Observation of Weld Defects on vendor-inspected Restraints. Allegation Substantiated.Addl Allegation Repts Encl ML20147H0101985-04-16016 April 1985 Draft Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20135E1471985-04-0808 April 1985 Synopsis of Shoreham Allegations ML20206G9151985-03-12012 March 1985 Allegation Review Data Sheet for Case 4-84-A-015 Re Harassment of Mechanical/Welding QC Inspector for Writing Nonconformance Rept Re Improper Welding Amperage by Superintendent.Util Rept Issued & Case Closed ML20147G9901985-01-31031 January 1985 Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20205Q7691985-01-18018 January 1985 Status Rept Mechanical/Piping Area. Related Info Encl ML20206G8861985-01-0909 January 1985 Allegation Review Data Sheet for Case 4-85-A-004 Re Electrical Installations.Insp Required.Related Info Encl ML20214R5681984-12-31031 December 1984 Shoreham Nuclear Power Station Initial OL Readiness Assessment ML20214T7251984-11-30030 November 1984 Summary Rept for Regional Evaluation of Diablo Canyon Unit 2 ML20206G8131984-10-0303 October 1984 Allegation Review Data Sheet for Case 4-84-A-102 Re Visual Insp Through Paint,Unfair Intimidation to Produce Results, Rejection of Previous Inspected Welds,Defective Welds & Missing Beams.Addl Info Encl ML20206G7731984-10-0101 October 1984 Allegation Review Data Sheet for Case 4-84-A-098 Re Qa/Qc Program Allegations Re Matl Verification, post-ok Reviews by Engineers & Improper Verification of Snubber Transaction Assemblies ML20206H2431984-09-13013 September 1984 Allegation Review Data Sheet for Case 4-84-A-89 Re Kickbacks & Coverups in QA Dept.State of Ks Interested.No Federal Regulations Violated If Kickback Allegations true.W/840912 Telcon Record.Related Info Encl ML20205Q7591984-08-31031 August 1984 Preliminary Summary of Allegations for Comanche Peak Steam Electric Station,Units 1 & 2 1989-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1987-0121990-05-16016 May 1990 LER 87-012-01:on 870504,uplanned Actuation of ESF Occurred. Caused by Technician Loosing Footing & Accidently Hitting Outside Cover of Level Switch.Permanent Ladders & Platforms Installed at Head Tank Level Switches 05000322/LER-1986-0391990-05-16016 May 1990 LER 86-039-01:on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated 05000322/LER-1988-0171990-05-16016 May 1990 LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned 05000322/LER-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1986-0141990-05-16016 May 1990 LER 86-014-01:on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 1997-05-01
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-JFFHCHAL USE4NL M5 1968 U. S. ATOMIC ENERGY COMMISSION DIVISION OF REACTOR LICENSING REPORT TO ADVISORY COMMITTEE ON REACTOR SAFEGUARDS IN THE MATTER OF PRELIMINARY ASPECTS OF LONG ISLAND LIGHTING COMPANY'S APPLICATION FOR A CONSTRUCTION PERMIT FOR ITS PROPOSED SHOREHAM NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-322 8709240556 070721 PDR FOIA MENZB7-111 PDR Note by the Director, Division of Reactor Licensing The attached report has been prepared by the Division of Reactor Licensing for the use of the Advisory Committee on Reactor Safeguards.
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%. E E uvud"aua v was %v&M I. INTRODUCTION The Long Island Lighting Company (LILCO) has submitted an application, filed May'15, 1968, for a construction permit and operating license for a nuclear electric generating plant to be called the Shoreham Nuclear Power Station, Unit 1. The plant will initially consist of a single BWR unit and is to be located on a 450 acre site on the north shore of Long Island, adjacent to the Brookhaven National Laboratory. The unit is initially to be operated at a power level of 1593 Mwt, but the applicant anticipates that it will be capable of operation at powers up to 1665 Mwt.
The nuclear steam supply system will be provided by GE and Stone and Wcoster Engineering Corporation will design the balance of the station and act ar construction managers. Construction work will be subcontracted.
LILCO has essentially no experience in the nuclear field other than that as a member of APDA, PRDC and ESADA.
II. HICHLIGHTS OF THE APPLICATION The Shoreham plant will use a boiling water reactor very similar in general design and power level to the Vermont Yankee Nuclear Power Station, Unit 1. The major difference is that the primary containment-vapor suppres-sion system will consist of a steel-lined, reinforced concrete structure rather than the usual light bulb and torus steci vessels. In addition, the !
radioactive waste gas system will provide for a longer holdup period (8 hrs, to 3 days) than the 30 minutes generally provided in BWR plants and there will
. be no stack so that gases will be released from a vent on the reactor building 1
roof. The effects of not having an elevated stack release in the event of an
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accident will have to be considered in relation to the relatively small exclu-sion distance of 1000 f t. (305 meters) provided by the proposed site to assure that' potential doses are acceptable.
Another unusual feature of the proposed facility is that one of the redun-cant sources of "offsite" power (Criterion 39) is to be provided by a 55 Mw ^'
gas turbine-driven generator located on the site. Redundant sources of "onsite" !
electric power will be provided by two stand-by diesel generators.
1 The proposed site has an unusual feature in that a Nike missile base is 'i located within the general bounds of the site, 4000 f t. from the proposed i s i reactor location. The potential interaction of these facilities will be con-sidered in the review.
At the applicant's request, a meeting has already been held to discuss the performance requirements and the proposed design of the flexible seal-joint at the juncture of the walls of the concrete primary containment and the base slab of the plant. Additional analysis and possibly some test work relative to this design detail is indicated.
III. CONCLUSION On the basis of our preliminary review of' the application, the only major potential problem area identified is the unique reinforced concrete primary containment, and we expect that this can be resolved satisfactorily.
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