Similar Documents at Salem |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. ML18106A2571998-01-19019 January 1998 Nuclear Business Unit Future Objectives. ML18106A2131997-12-15015 December 1997 Safety Evaluation Supporting Rev to TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18102B3331997-02-28028 February 1997 Rev 0 to Cfcu Return Piping Inside CTMT,221F Temp Effect. ML20133D2201996-12-0606 December 1996 Root Cause Analysis of Struthers-Dunn Operate-Reset Relay Latch Failures for Salem Generating Station ML20133D2251996-10-30030 October 1996 Struthers-Dunn Model 255XCXP Relay Root Cause Evaluation for Salem Nuclear Generation Station ML18102A3231996-07-0101 July 1996 Reg Guide 1.121 Assessment of Indications at Salem Unit 2. ML18102A1591996-06-0404 June 1996 Fuel Handling Accident Analysis Radiological Evaluation. ML20101M6601996-03-24024 March 1996 Supplemental Submittal in Response to NRC GL 87-02/USI A-46, 'Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.' ML18102A1321996-03-15015 March 1996 Change 2EC-3332 to Rev 0 to Design Analysis, 125 Vdc Battery Charger Replacement. ML18102B0201996-02-28028 February 1996 Rev 0 to Evaluation of Structures for Increased Temps Due to Updated Main Steam Line Break. ML20129K1031995-07-10010 July 1995 Exam of Fasteners from Salem Nuclear Generating Station ML18101A7481995-05-19019 May 1995 Safe Shutdown Equipment List Rept for Salem Generating Station Units 1 & 2 ML18101A7491995-04-25025 April 1995 Relay Evaluation Rept, Volumes 1 & 2, for Salem Generating Station Units 1 & 2 ML18101A7501995-04-20020 April 1995 Seismic Evaluation Rept, for Salem Generating Station ML20134K1031995-03-24024 March 1995 Organizational Effectiveness Assessment Rept for Sngs, ML18102B6541995-03-24024 March 1995 Organizational Effectiveness Assessment Rept for Plant, Redacted Version ML18101A4391994-12-21021 December 1994 Fire Protection Review of Salem Reactor Coolant Pump Oil Collection Sys, Dtd 941221 ML20134C5791994-10-23023 October 1994 Salem/Maint SC.MD-GP.SW-0001(Q) Svc Water Silt Survey, Rev 5 ML18106B0541994-01-31031 January 1994 Criticality Analysis of Salem Units 1 & 2 Fresh Fuels Racks. ML18100A7971993-12-23023 December 1993 Simulator Four-Year Certification Rept. ML20069M2221993-10-15015 October 1993 Flux Thimble Thermocouple Ultrasonic Profilometry & Eddy Current Encircling Coil Insp of Stored Thimble Tubes Jul-Aug 1993 ML18100A6281993-09-16016 September 1993 Updated Page A4-4 of Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis, Changing Figure Numbers A5-1 & A5-2 to A4-1 & A4-2 at End of First Paragraph ML18100A6801993-08-20020 August 1993 Engineering Evaluation of Sgs 1 & 2 Control Room Evacuation for Fire Induced MOV Hot Shorts as Discussed in NRC Info Notice 92-018. ML20045B8801993-05-21021 May 1993 Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis for Salem Nuclear Generating Station, Units 1 & 2. ML18100A3401993-04-28028 April 1993 Licensing Rept for Spent Fuel Storage Capacity Expansion Pse&G,Salem Generation Station,Units 1 & 2. ML18096B3561993-02-11011 February 1993 Cycle 8 Peaking Factor Limit Rept. ML20135A8141992-12-29029 December 1992 Control Room Overhead Annunciator Lock-Up of 921213 ML18096B1661992-11-13013 November 1992 Rev 1 to Fracture Toughness Analysis for Salem Units 1 & 2 Reactor Pressure Vessels to Protect Against Pressurized Thermal Shock Events,10CFR50.61. ML18096B0081992-09-0202 September 1992 Analytical Data Rept, for Project 28173 ML18096A8061992-06-17017 June 1992 Rev 0 to Salem Unit 2 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.' ML18096A8051992-06-17017 June 1992 Rev 0 to Salem Unit 1 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.' ML18096A5831992-03-31031 March 1992 Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations. ML18095A5151990-07-31031 July 1990 Vol 1 to Spring 1990 NDE of Selected Class 1 & Class 2 Components of Salem Generating Station,Unit 2. ML18095A3691990-07-26026 July 1990 Unit 1 Decommissioning Rept. ML18095A3681990-07-26026 July 1990 Unit 2 Decommissioning Rept. ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co. ML18094B2241989-12-28028 December 1989 Simulator NRC Certification, Vols I-III ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20086U2571989-03-31031 March 1989 Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations ML18093B2021988-09-30030 September 1988 Special Rept on Spare CRD Mechanism Weld Refurbishments. ML18093A7601988-02-18018 February 1988 Appendix R/Breaker Coordination as-Found Review (Pre-Audit 1987). ML18093A5471987-12-10010 December 1987 Breaker Coordination W/Respect to External & Internal Hazards. ML18093A4531987-10-14014 October 1987 Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns. ML18093A4131987-10-0101 October 1987 Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns. ML18093A3781987-09-16016 September 1987 Rev 7 to, Westinghouse Engineering Svcs Rept for Salem Nuclear Generating Station Units 1 & 2 Concerning RHR Sys Mid-Loop Operation Re NRC Generic Ltr 87-12. 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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- ~ INTECH BIOLABS DIVISION 158 TicH Lane Eul Brunswick, New Jersey 08816 (908) 257-1050 Fax (908) 257-2790 ANALYTICAL DATA REPORT No. I208154 Project: 28173 prepared for:
ANALYTIKEM 28 Sprinqdale Road Cherry Hill, NJ 08003 Date Sampled: Auqust 14, 1992 Report Date: September 2, 1992 Prepared by LABORATORY RESOURCES, INC.
INTECH DIVISION bani,~n
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Laboratory Director NJDEP certification No. 12427 PADER certification No.68-420
LABORATORY RESOURCES, INC. INTECH ANALYTICAL REPORT NO. I208154 ANALYTIKEM ANALYTICAL RESULTS: TOXICITY CHARACTERISTIC LEACHATE PROCEDURE Intech Sam~le Number: 01 Client Oesiqnation: 28173-1 Bias Adjustment sample: 8090-01 MS Results Results Regulatory (Unadjusted) (Adjusted) Limits Parameter (mg/L) (mg/L) (mg/L) 2,4-0 -----------
< 0.0005 -----------
< 0.00057 -----------
10 2,4,5-TP (Sil vex) < 0.0002 < 0.00056 1. 00 (1 .-
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LABORATORY RESOURCES, INC. INTECH ANALYTICAL REPORT NO. I208154 ANALYTIKEM ANALYTICAL RESULTS: TOXICITY CHARACTERISTIC LEACHATE PROCEDURE Intech Sample Number: 02 Client Desiqnation: 28173-2 Bias Adjustment Sample: 8090-01 MS Results Results Regulatory (Unadjusted) (Adjusted) Limits Parameter (mq/L) (mq/L) (mq/L) 2,4-D -----------
< 0.0005 -----------
< 0.00057 10 2,4,5-TP (Sil vex) < 0.0002 < 0.00056 1. 00 n f")
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LABORATORY RESOURCES, INC. INTECH ANALYTICAL REPORT NO. I208154 ANAL YT I KEM TABLE OF ABBREVIATIONS B Compound detected in blank.
BTEX Benzene, Toluene, Ethylbenzene, and Xylenes.
BTX Benzene, Toluene, and Xylenes.
CCC Calibration check compound.
D Concentration calculated from analysis of diluted sample.
DI Deionized water.
IND Indeterminate; result cannot be adjusted for bias because spike was not recovered.
J Compound was detected at levels below the quantitation limit. The level reported is approximate.
MS Matrix spike.
MSD Matrix spike duplicate.
ND Not detected.
PCB Polychlorinated Biphenyls.
PHC Petroleum Hydrocarbons, Total Recoverable.
RPO Relative percent difference.
RSD Relative standard deviation.
SPCC System performance check compound.
svo Samivolatile orqanics.
VOA Volatile orqanics analysiso TNTC Too numerous to count t"\
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'1 29SpringdaleRoad Cherry Hill, New Jersey 08003 (609) 751-1122 * (215) 923-2068 r~o 11~h Analytll(EM 9
An American NuKE M Company f-Custody 454 So~h AM"~" BT~T' Ao*d Rock Hill, South Carolina 29730 (803) 329-9690 Fax: (609) 751-0824 Fax: (803) 329-9689 Client lw &l ,t* lbl Projed: 2-b1~ AnalytiKEM Contact 1lAr l1 A-f L.u:>
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- 1. Field Measurements: II. Field Conditions/Comments: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- Oata Sheets: Y N Filtered: Y Not Required Ill. Special I n s t r u c t i o n s : - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
(Deledion Limits, Data Package, elc.)
Relinquished By: Time/Date: Received By: Time/Date:
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ATTACHMENT 2 CASE NO. 92-07-09-0909-38
ATTACHMENT 2 (continued)
DISCHARGE CONFIRMATION REPORT CASE No. 92-07-09-0909-38 DISCHARGE LOCATION:
Salem Generating Station End of Buttonwood Road Block#: 26 Lot#: 4.01 Municipality: Lower Alloways Creek Township County: Salem County Zip Code: 08038 Tax #: 22-1212-800 EPA ID#: NJD077070811 (Map enclosed - See Figures 3 and 4)
CHEMICAL DISCHARGED:
No. 2 Fuel Oil CAS Number: 068-476-302 QUANTITY DISCHARGED: 10-15 gallons DATE/TIME DISCHARGE BEGAN: July 9, 1992 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> DATE/TIME DISCHARGE ENDED: July 9, 1992 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> DATE/TIME DISCHARGE DISCOVERED: July 9, 1992 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> DATE/TIME DISCHARGE REPORTED July 9, 1992 0909 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.458745e-4 months <br /> TO NJDEPE HOTLINE:
MEASURES TAKEN TO CONTAIN, CLEANUP AND REMOVE THE DISCHARGE:
Operations personnel immediately notified the Senior Nuclear Shift Supervisor (SNSS) of the discharge. The SNSS then contacted Site Services personnel and reported the discharge to the NJDEPE Hotline. Operations and Site Services personnel excavated the gravel and soil in the affected area and placed the material into nine (9) drums for disposal. The drums were then sampled and analyzed to determine the material's waste classification and ultimate disposal plan.
Upon review of the analytical results of the excavated soil, the material was classified as a non~hazardous Type 27 Industrial Waste and is being disposed of at the Salem County Solid Waste Facility. The estimated cost for cleanup and disposal of the material is $2,400.
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ATTACHMENT 2 (continued)
DISCHARGE CONFIRMATION REPORT CASE No. 92-07-09-0909-38 CORRECTIVE MEASURES:
PSE&G is in the process of designing a secondary containment for the MFOST filter house in accordance with the criteria outlined in NJAC 7:1E-2. This containment will collect all spills and leaks from the filter house and direct them to a new treatment system. The estimated completion date for this project is December 31, 1993.
INDIVIDUAL INVOLVED IN CONTAINMENT/CLEANUP:
The individual responsible for the cleanup and disposal of the contaminated material is:
R. B. Lockwood Yard Supervisor Site.Services Maintenance Public Service Electric and Gas Nuclear Department P. O. Box 236, M/C N34 Hancocks Bridge, New Jersey 08038 (609) 339-5092 TYPE, QUANTITY, LOCATION AND DATE OF SAMPLES:
Due to the similarities between this discharge and a second discharge of fuel oil at this location on the previous day (reported to NJDEPE as Case No. 92-07-08-0820-51), the material from both discharges was combined for disposal. A sample aliquot was obtained from each drum of excavated material from a depth of 6 inches to 2 feet. These aliquots were then composited to form a single sample for analysis. A Toxicity Characteristic Leachate Procedure (TCLP) analysis was conducted by AnalytiKEM, Inc. A copy of the results of this analysis are attached.
INDIVIDUAL CONDUCTING ANALYSIS: Gregory A. Pruna Laboratory Manager AnalytiKEM, Inc.
28 Springdale Road Cherry Hill, NJ 08003 QUALITY ASSURANCE PROCEDURES: See attached report.
SAMPLE METHODOLOGY: See attached report.