LLRW Shipment Insp Repts 50-352/PA-92-02 & 50-353/PA-92-02 on 921116-18.No Violations or Deviations Noted.Major Areas Inspected:Licensee LLRW Shipment to Burial Site Including Shipping Documentation,Package Insp & Contamination SurveysML20127N881 |
Person / Time |
---|
Site: |
Limerick  |
---|
Issue date: |
12/31/1992 |
---|
From: |
Dornsife W, Maingi S PENNSYLVANIA, COMMONWEALTH OF |
---|
To: |
|
---|
Shared Package |
---|
ML20127N838 |
List: |
---|
References |
---|
NUDOCS 9302010111 |
Download: ML20127N881 (9) |
|
|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 B110078, GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 21998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20202B6231998-01-23023 January 1998 Non-proprietary Version of Rev 1 to ER-9605NP, Missile Probability Analysis Methodology for Limerick Generating Station,Units 1 & 2,w/Siemens Retrofit Turbines ML20198B3351997-06-30030 June 1997 Annual 10CFR50.59 & Commitment Rev Rept for 960701-970630, for Limerick Generating Station,Units 1 & 2 ML20135D7721996-04-30030 April 1996 Non-proprietary, Evaluation of Limerick Initial Core Channels for Re-Use on Ex-Shoreham Fuels Bundles ML20101F1901996-02-29029 February 1996 Evaluation of Limerick Unit-1 Core Shroud Insps (Refuel Outage 6) ML20099L6331995-06-30030 June 1995 Annual 10CFR50.59 & Commitment Rev Rept 940701 - 950630 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20086B1681995-06-26026 June 1995 Ipeee ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20078S3351994-02-10010 February 1994 Evaluation of Abnormal Wear at Limerick ML20059K6261993-10-26026 October 1993 SAR Licensing Rept for Spent Fuel Storage Capacity Expansion,Lgs Units 1 & 2 ML20046B5011993-06-27027 June 1993 Evaluation of Potential Internal Radiation Exposures Associated W/Contamination Events in Handling Traversing In-Core Probe (TIP) Tubing at Limerick Nuclear Generating Station & Recommendations for Evaluation & Control of . ML20034F4781993-02-28028 February 1993 Thermal Variance Request for Point Pleasant Diversion NPDES Permit PA-0052221 ML20127N8811992-12-31031 December 1992 LLRW Shipment Insp Repts 50-352/PA-92-02 & 50-353/PA-92-02 on 921116-18.No Violations or Deviations Noted.Major Areas Inspected:Licensee LLRW Shipment to Burial Site Including Shipping Documentation,Package Insp & Contamination Surveys ML20113D9801991-11-30030 November 1991 Industry Approach to Seismic Severe Accident Policy Implementation, for Nov 1991 ML20082N0471991-08-28028 August 1991 Annual Plan Mod Rept,Jul 1990 Through June 1991 ML20072R0121991-03-15015 March 1991 Common Plant Summary of ASME Section XI Repairs & Repalcements Completed from 890520-901217,Rept 3 ML20072R0071991-03-14014 March 1991 Common Plant Summary Rept for 890520-901217,Periodic Insp Rept 3 ML20066K7201991-01-31031 January 1991 Simulator Certification Submittal, Providing Supporting Info to Form NRC-474 ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20042E0901990-03-31031 March 1990 Description of Limerick Inadvertent Spray Actuation Analysis ML20246A8511989-08-15015 August 1989 Common Plant Summary of ASME Section XI Repairs or Replacements from 870901-890519,Rept 2 ML20248A0261989-06-30030 June 1989 Rev 1 to Response to NRC Bulletin 88-05 for Limerick Generating Station,Unit 2 ML20247J0521989-05-31031 May 1989 Vol Ii,Book 1 to Limerick Generating Station,Unit 2 Independent Design & Const Assessment, Hazards Program Evaluation Suppl ML20245A1031989-04-30030 April 1989 Vol II to Books 2,3 & 4 to Independent Design & Const Assessment,Design Observation Repts,DOR-001 to DOR-118 ML20245A0951989-04-30030 April 1989 Vol I of Book 1 to Independent Design & Const Assessment, Assessment Summary ML20245A0801989-04-30030 April 1989 Vol II of Book 1 to Independent Design & Const Assessment, Design Assessment ML20246P5671989-03-22022 March 1989 Safety Evaluation of Limerick 1,Cycle 3 Revised Core Loading Pattern ML20235Z5981989-02-28028 February 1989 Extension of Equipment Qualification Programs to Limerick Generating Station Unit 2 ML20235Y3811989-02-28028 February 1989 Rev 11 to Design Assessment Rept ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20148R7511988-03-0808 March 1988 Readiness Program Assessment for Limerick 2 ML20236V6631987-08-31031 August 1987 Summary of ASME Section XI Repairs & Replacements Completed from 840928-870831,Rept 1 ML20153G3091986-02-24024 February 1986 Summary of Validation Program for Spds ML20129C3861985-06-30030 June 1985 Control Room Design Review Supplemental Rept 2 to Final Rept of June 1984 ML20112E4491985-02-11011 February 1985 BNL Technical Review Rept & Handwritten Notes of 850121-25 Insp ML20083L7691984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-60 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20083L7901984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-61 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20107G6421984-10-31031 October 1984 Control Room Design Review, Final Rept,Suppl 1 ML20098E9061984-09-30030 September 1984 Rev 10 to Design Assessment Rept ML20129D7351984-09-30030 September 1984 Evaluation of Feedwater Containment Isolation Check Valves for Hypothetical Pipe Rupture Condition for Limerick Generating Station ML20093C9921984-09-17017 September 1984 Independent Design Review of Limerick Generating Station 1, Core Spray Sys, Bimonthly Status Rept 8 for Period Ending 840915.Related Correspondence ML20096C7651984-08-31031 August 1984 Environ Qualification Rept ML20095A6021984-08-0909 August 1984 Rev 0 to Raceway Separation Criteria. Raceway Separation Test Program Discussion Encl ML20093N6651984-07-31031 July 1984 Nonproprietary Rev 9 to Vol 1 of Design Assessment Rept ML20095D3101984-06-30030 June 1984 Rev 3 to Final Rept Overhead Handling Sys Review ML20092K9461984-06-30030 June 1984 Control Room Design Review,Final Rept 1999-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers 05000353/LER-1999-010, :on 990820,manual Actuation of Main CR Chlorine Isolation Mode Was Noted.Caused by Faint Chlorine Odor in Reactor Encl.Conducted Investigation & Was Unable to Locate Source of Odor1999-09-16016 September 1999
- on 990820,manual Actuation of Main CR Chlorine Isolation Mode Was Noted.Caused by Faint Chlorine Odor in Reactor Encl.Conducted Investigation & Was Unable to Locate Source of Odor
ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 05000352/LER-1999-009, :on 990802,maint Was Performed That Required Disabling Certain Monitoring Capabilities on Safeguard Sys. Caused by Failure to Properly Use Plant Procedure.Monitoring Capability Was Restored to Svc & Tested1999-09-0101 September 1999
- on 990802,maint Was Performed That Required Disabling Certain Monitoring Capabilities on Safeguard Sys. Caused by Failure to Properly Use Plant Procedure.Monitoring Capability Was Restored to Svc & Tested
ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 05000353/LER-1999-005-02, :on 990712,PCIV Isolation & Esfa Occurred Due to Blown Fuse.Caused by Mechanical Failure of Cold Solder Joing.Reset Isolation within Three Hours & 22 Minutes & Replaced Fuse1999-08-10010 August 1999
- on 990712,PCIV Isolation & Esfa Occurred Due to Blown Fuse.Caused by Mechanical Failure of Cold Solder Joing.Reset Isolation within Three Hours & 22 Minutes & Replaced Fuse
ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20210H7391999-07-29029 July 1999 Safety Evalution Supporting Amends 136 & 101 to Licenses NPF-39 & NPF-85,respectively 05000353/LER-1999-004-02, :on 990701,determined That Thirteen MSRVs Failed to Meet 1% Setpoint Tolerance Due to Setpoint Drift.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.All Fourteen Srvs Pilot Valves Were Replaced1999-07-23023 July 1999
- on 990701,determined That Thirteen MSRVs Failed to Meet 1% Setpoint Tolerance Due to Setpoint Drift.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.All Fourteen Srvs Pilot Valves Were Replaced
05000352/LER-1999-007, :on 990617,inadvertent Emergency Svc Water Start During Test Equipment Installation Occurred.Caused by Personnel Error.Procedure Revised.With1999-07-14014 July 1999
- on 990617,inadvertent Emergency Svc Water Start During Test Equipment Installation Occurred.Caused by Personnel Error.Procedure Revised.With
05000352/LER-1999-005, :on 990611,RPS & ESF Actuations Were Noted. Caused by Personnel Error During Turbine Routine Testing. Revised Backup Overspeed & Power/Load Unbalance Test Routine Test Procedure.With1999-07-0909 July 1999
- on 990611,RPS & ESF Actuations Were Noted. Caused by Personnel Error During Turbine Routine Testing. Revised Backup Overspeed & Power/Load Unbalance Test Routine Test Procedure.With
05000353/LER-1999-003-02, :on 990607,bypass of RW Cleanup Sys Leak Detection Sys Isolation Functions on Three Separate Occasions Was Noted.Caused by Inadequate Review & Approval of Change to Sys Procedure.Procedure S44.7.C Revised1999-07-0707 July 1999
- on 990607,bypass of RW Cleanup Sys Leak Detection Sys Isolation Functions on Three Separate Occasions Was Noted.Caused by Inadequate Review & Approval of Change to Sys Procedure.Procedure S44.7.C Revised
05000352/LER-1999-004-01, :on 990606,ADS Was Inoperable During Planned Maint & Applicable TS Was Not Met.Caused by Inadequate Review Operability Requirements.Clearance Was Removed from Backup ADS Gas Bottles & Sys Was Returned to Service1999-07-0101 July 1999
- on 990606,ADS Was Inoperable During Planned Maint & Applicable TS Was Not Met.Caused by Inadequate Review Operability Requirements.Clearance Was Removed from Backup ADS Gas Bottles & Sys Was Returned to Service
ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20209F2381999-05-24024 May 1999 Safety Evaluation Supporting Amends 135 & 100 to Licenses NPF-39 & NPF-85,respectively ML20206U6911999-05-19019 May 1999 Safety Evaluation Supporting Amend 99 to License NPF-85 05000352/LER-1999-003-01, :on 990420,RPS & PCRVICS Actuations Were Noted, Due to Loss of FW Transient.Caused by Spuriously Opening Breaker.Deep Bed Condensate Deminerlizer Sys Was Replaced1999-05-19019 May 1999
- on 990420,RPS & PCRVICS Actuations Were Noted, Due to Loss of FW Transient.Caused by Spuriously Opening Breaker.Deep Bed Condensate Deminerlizer Sys Was Replaced
05000353/LER-1999-002-03, :on 990419,various ESF Actuations Due to Loss of Power to 2A Rps/Ups Distribution Panel,Occurred.Caused by Loose Bus Bar Connection in RPS Breaker panel.Bus-bar Connection Inspected,Cleaned & re-tightened1999-05-18018 May 1999
- on 990419,various ESF Actuations Due to Loss of Power to 2A Rps/Ups Distribution Panel,Occurred.Caused by Loose Bus Bar Connection in RPS Breaker panel.Bus-bar Connection Inspected,Cleaned & re-tightened
ML20206U4991999-05-17017 May 1999 Safety Evaluation Supporting Amend 98 to License NPF-85 ML20206P8871999-05-14014 May 1999 Safety Evaluation Supporting Amend 97 to License NPF-85 ML20206N5761999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 96 to Licenses NPF-39 & NPF-85,respectively ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified 05000352/LER-1999-002-01, :on 990303,failure to Perform TS Surveillance Required Locked Valve Insp Occurred.Caused by Personnel Error.Procedures Revised.With1999-04-0101 April 1999
- on 990303,failure to Perform TS Surveillance Required Locked Valve Insp Occurred.Caused by Personnel Error.Procedures Revised.With
ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With 05000352/LER-1999-001-02, :on 990217,old Rev of LGS PSP Was Discovered on Hard Drive of self-contained Computer in Security Ofc Area. Caused by Less than Adequate Ac.Security Force Was Placed on Heightened Awareness to Compensate for Compromise of SG1999-03-16016 March 1999
- on 990217,old Rev of LGS PSP Was Discovered on Hard Drive of self-contained Computer in Security Ofc Area. Caused by Less than Adequate Ac.Security Force Was Placed on Heightened Awareness to Compensate for Compromise of SGI
ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 ML20199D8321999-01-12012 January 1999 Safety Evaluation Supporting Amends 133 & 95 to Licenses NPF-39 & NPF-85,respectively ML20206R7881999-01-12012 January 1999 Safety Evaluation Supporting Amend 94 to License NPF-85 05000353/LER-1998-008-02, :on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced1999-01-0707 January 1999
- on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced
ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With 05000352/LER-1998-019, :on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk1998-12-23023 December 1998
- on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk
ML20198E0191998-12-14014 December 1998 Safety Evaluation Supporting Amends 132 & 93 to Licenses NPF-39 & NPF-85,respectively ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 1999-09-30
[Table view] |
Text
-
~_.
5 a
u Pa. Department of Environmental Resources j
Bureau of Radiation Protection J
-Division of Nuclear Safety Report Nos.
50-352/PA-92-02 50-353/PA-92-02 Docket Nos.
50-352 50-353 License Nos. NPF-39 NPF-85 Licensee Philadelphia Electric Company Correspondence Control Desk P.O. Box 195 Wayne, PA 19087-0195 Facility Name:
Limerick Generating Station, Units 1 and 2 Inspection Dates November 16, 17 & 18, 1992 Inspectors:
,6
/
3[!92 S.P.
Maing1, Nucleat/ 2ngineer
' Dats Approved by:
/t1
/ fck W.
Dornsife, Director Dat6 Bureau of Radiation Protection Inspection Summary:
Inspection on November 18, 1992-(Inspection Report Nos. 50-352/PA-92-02; 50-353/PA-92-02)
Areas Inspected:
Announced inspection of the licensee's low level radioactive waste shipment to the burial cite including:
shipping documentation, package inspection,-labeling, marking, placarding, vehicle inspection, radiation and contamination surveys.
Results:
No violations or deviations were identified.
A
^
9302010111 930119 PDR ADOCK 05000352 O
PDR 4'
DETAILS 1.0 Individuals Contacted 1.1 Licensee Personnel
Cenci, Senior Engineer Radwaste
- L. Wells, Radwaste Supervisor Services
Paust, Radwaste Physicist
Harmon, Radwaste Physicist
Campanini, Radwaste Technical Assistant
- D. Voigt, Quality Verification Inspector
Rutkowski, Health Physics Technician
Roach, Superintendent - Services
- Denotes those had meetings with as part of the exit.
2.0 Scope of the Inspection This inspection was conducted in accordance with the Memorandum of Understanding (MOU) between the Commonwealth of Pennsylvania and the U.S. Nuclear Regulatory Commission.
The State inspector reviewed the licensee's low level radioactive waste shipment no.
LG-037-92 to the Barnwell Waste Management Facility according to the attached inspection checklist.
This was the third of the three shipments of the irradiated core components to Barnwell LLRW Disposal Site.
The various components had been collected in the Spent Fuel Pool over the period of operations at LGS.
Due to the impending closing of the LLRW disposal sites the licensee made the timely decision to clean up the spent fuel pools of the extraneous materials hanging around in the spent fuel pools and shipout for disposal.
These components had been cut and collected in three 3-55 steel liners and were being shipped in CNS-3-55 casks.
This shipment contained 26,800 curies of irradtated core components with a waute volume of 3.3 cubic feet packaged in a 3-55 steel liner with a disposable volume of 57.4 cubic feet.
The container was shipped in the CNS-3-55-2, NRC certified Type B shipping cask.
4 The inspector observed the receipt inspection of the empty cask and unloading activities of the cask by the licensee staff and contractors.
Prior to lowering of the cask into the loading bay for placement of the liner in the cask, the inspector reviewed the pre-use inspection documentation for the liner; certificate of compliance for the cask; cad-handling procedure and observed the licensee perform an inspection cf the cask to ensure that the cask was in a satisfactory material condition for the shipment.
Pursuant to the removal of the cask from the loading bay and to preclude leaching out of the contamination during transit to disposal site, swipe samples were periodically taken after de:ontamination for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, to validate stabilization.
The inspector witnessed the loading of cask on the trailer, placement and bolting down of the personnel barrier and placement of the security seals.
The inspector observed licensee personnel perform the radiological survey of the shipment and performed independent radiological survey of the shipping cask with the liner before and after installation of the personnel barrier.
The highest reading detected at contact with the personnel barrier mounted over the cask was 22 mR/hr and no removable contamination was detected from the smear samples taken at the representative locations on the surface of the barrier and the vehicle.
The inspector witnessed the Quality Verification Representative review the shipment documentation and physical transfer of shipping documentation to the driver.
A visual inspection of the vehicle was performed to ensure that the vehicle was in acceptable condition for transport.
The inspector performed an independent verification of the licensee's calculations for waste classification for DOT TYPE and
~ Burial Class determination.
The shipping papers were reviewed for completeness and accuracy.
No discrepancies were noted.
3.0 Exit Meeting The inspector met with the licensee representatives denoted in Section 1.0 at the conclusion of the inspection.
The inspector summarized the scope and findings of the inspection.
l
PENNSYLVANIA DEPARTMENTOF ENVIRONMENTAL RESOURCES BUREAU OF RADIATION PROTECTION DIVISION OF NUCLEAR SAFETY ~
LOW LEVEL R ADIO ACTIVE WASTE StilPMENT INSPECTION REPORT
' REVISION I 50-352/PA-92-02 Report No. 50-353/P A-92-02 A.
General Information L
Date ofinspection 11-16,17 & 18, 1992 2.
Name of Shipper I,imerick Generating Stntion 3.
Name of Carrier Chem Nuclear Systems, Inc.
4.
Destination 11arnwell Disposal Site, SC 5,
Verify Advanced Notification to the Consignee Yes, and notifiention updated.
[ Fissile materials, and Type B or highway route controlled quantities - 49 CFR 172.22(c)1 6.
Verify Advanced Notification to the State (s)
Yes to PA; MDs _W VA: VA: NC; SC and NRC
[(Type B packages only - 10 CFR 71.97)]
7.
Package (s) Used X
Cask CNS 3-55-2 HIC X
Liner 3-55 Stcel liner Drums Boxes Other(Specify) 8.
Number of Packages one 9.
Method ofShipment A.
X Exclusive Use B.
Non Exclusive Use 10.
Transport Vehicle Open X
Closed with personnel barrier bolted over the cask.
B.
Shipping Documentation Checklist 1.
X Shipping papers present(49 CFR 172.200,201,202,203) l 2.
X Proper shipping name and hazard class (172.202(a)]
3.
X Proper I.D. number (172.202(a)J h!$[ rfel EcfE,"v0100N[lkIO{kOr'3 iO!l}"sYu$N bh C
4.
X Waste Description total quantity by weight (lbs)(172.202(a)]
Liner 7582.2 "26,800 volume (cu. ft.)(172.202(a))
57.4 cuble feet. activity (Ci)(172.203(d)l
- 19. '
'X
- Radioauclides identmed (10 CFR 20,311(b) & 49 CFR 172.203(d)l:
l6.
X Total quantity of radionuclides S3, C 14, Tc-99 and I-129 shawn (10 CFR 20.311(b))
7.
X Waste classified and characterized properly (61.55,61.56 and BTP) -
(Perform a review of documentation for classification and characterization to determine if '
= classification is correct and reasonable)
- 8. -
X
. Description of chemical / physical form (172.2.03(d))
L 9.
' Y-Ill - Category oflabel applied to each package (172.203(d))
10.
NA T.I. assigned to each package bearing Y II or Y !!!(172.203(d)] '
11.
X-
= Shipper's certification (172,204(a))
12.
X Instructions to carrier provided (173.441(c),173.425(b)] (exclusive use only)
C.
Packaging / Package Inspection a.
Packaging Compliance X
Are authorized packages used? (173.415,173.416]
Package types used:
NA LSA strong tight (173,425(b))
DOT 7A, Type A NA
- Performance test records on file? [173.415(a)]
NRC Certified X
Current NRC COC's on file? [10 CFR 71.12(c)]
X Registered with NRC NMSS as user? [71.12(c)) -
(Prior to the licensee's first t.se of the package) -
b.
Security Seals and Pack' age Integrity X
Security seals (173.412(b)](LSA-Exclusive use, closed vehicle exempt)
X Lids secure (173.475(c)]
X No visible damage or leakage (173.425(b))
X packages surveyed for radiation (173,441] and contamination (173.4431 7
1 o m m.m_,, w - ~m.,..
n-~~
~
~
~<+---n'-~-~~~*
~~~~ '~~~ -*'
~~
~'
p.
- D.-'
-Labeling, Siarking and Placarding Checklist
'a.
Labeling X
Packages labeled W-1, Y-II, Y III(172.403(b),(c)) Y-Ill (LSA - Exclusive use exempt)
X
" Contents" a nd " Activity" en tered [172.403(g))
X Transport Index afTixed on Y-!!. Y-III labels [172.403(g))
b.
Starking X
Packages marked properly, i.e., proper shipping name, identification number, DOT Spec.
number, NRC COC number, consignee or consignor's name and address, etc. (172.301,304,306)
X Type A/ type B package marked " Type A"or" Type B"[172.310(a))
X
- Gross weight marked if package exceeds 110 pounds (172.310(all '
X Waste class marked A-B-C stable / unstable [10 CPR 20.311(d)(2)]
NA LSA Exclusive use package marked " RADIOACTIVE-LSA"[173.425(b)]-
c.
Placarding X
Placards on each end and sides of vehicle for Y III, LSA exclusive use and highway route controlled quantity [172.504(a), 506, 507,173.425(b))
E.
Vehicle Inspection Checklist X
Verify that vehicle was monitored and inspected by the licensee upon arrival.
X Shipment blocked, braced, tied down in vehicle [173.425(b)]
X Ensure that the licensee surveys the shipment adequately using proper instruments. Review the licensee's survey map (s) to verify that all the required readings are performed and they are in ~
reasonable agreement with inspector's.
P.
~ Radiation / Contamination Survey [49 CFR 173.441,173.443]
a.
Exclusive Use Vehicles 0.1 Not exceed 2 mR/hr in any occupied position in the vehicle 3.8 Not exceed 10 mR/hr at 2 meters (6.6 ft) from the vehicle I'
19.0 Not exceed 200 mR/hr on outer surface (including upper or lower) of the vehicle 22.0 Not exceed 1,000 mR/hr on the external surface of the package (closed transport vehicle)
NA Not exceed 200 mR/hr on the external surface of the package (open transport vehicle) b.
Non-Exclusive Use Vehicles L
NA Not exceed 10 mR/hr n 1 meter (3.3 ft) from package NA' Not exceed 200 mR/hr on the external surface of the package 3-
. c.
Highsst Contamination Dstectsd i
Not exceed 22 dpm/cm2 (beta & gamma)
~'
(Wipe sample for 300 cm2)
Highest Contamination Detected 52 CPM Background Reading 39 CPM Difference /Above Background 13 CPM-Divide by Instrument Efficiency (0,10) 130-Divide by(300 cm2) 0.43 DPM/CM2 RADIATION / CONTAMINATION SURVEY (transport vehicle)
Surfaco 22
- mR/hr 2 meters 38
- mR/hr Cab / Sleeper Surface (bottom)
Surface 11 mR/hr 0.1 mR/hr 19 mR/hr 2 meters 0.8 mR/hr -
Surface 22 mR/hr 2 meters 3 0,,, mR/hr.
i --
1-l o
4
e 3
'Di
I.
Violations /Non Ccmpliance Within the scope of this inspection, no violations were observed.
II. Comments Instruments Used Instrument (s)
Serial Calibration Expiration Tvoe No.
Date Dose Rate Eberline ESP-2 00309 2-24-93 Instrument U E~2 Contamination Eberline ESP-2 00309 2-24-93 Instrument IIP-210' Inspector's Name S. P. Maingi l
t i
l :
u