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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20064G1081994-02-14014 February 1994 Quad-Cities Nuclear Station 1994 Mgt Plan ML20063H8141994-02-11011 February 1994 Revised Procedures,Including Rev 16 to Qep 120-0, Technical Director Index 58 & Rev 3 to Qep 120-T10, Key Point History Listing ML20063F9231994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to ODCM,Quad-Cities Station ML20062J3681993-10-28028 October 1993 Station,Third Ten-Yr Interval IST Plan ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20099B9741992-07-27027 July 1992 Temporary Procedure Secondary Containment Preventative Maint Program ML20102A5971992-07-0202 July 1992 Corrected Chapter 11 to, Environ Radiological Monitoring Table of Contents, Odcm,Revs 0.C & G ML20097G0781992-05-31031 May 1992 Rev 0.G to Odcm,Chapter 11,pages 11-i,11-6,11-9,11-10,11-12 & 11-15 ML20079H0121991-10-0202 October 1991 Tech Spec Upgrade Program ML20082H1951991-08-15015 August 1991 Tech Spec Upgrade Program,Proposed Amend Section 3.4/4.4, 'Standby Liquid Control Sys.' ML20085B5901991-07-29029 July 1991 Tech Spec Upgrade Program ML20082M2261991-04-30030 April 1991 Rev 10 to Quad-Cities Process Control Program for Processing of Radioactive Wet Waste ML20055E8101990-07-0101 July 1990 Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2 ML20029B1981990-04-30030 April 1990 Rev 9 to, Quad-Cities Process Control Program for Processing Radioactive Wet Waste. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20059C7341989-02-28028 February 1989 Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste ML20235N4731989-01-31031 January 1989 Guidelines for Neutron Radioassay Measurements at Quad-Cities Unit One Spent Fuel Storage Pool ML20235N8151988-12-31031 December 1988 Quad-Cities Station Process Control Program for Processing Radioactive Wet Waste ML20235A8921988-07-31031 July 1988 Rev 6 to, Process Control Program for Processing of Radioactive Wet Waste ML20237J8081987-08-31031 August 1987 Rev 0 to Emergency Plan Implementing Procedure EPIP 200-T4, Containment Radiation Time Dependent Correction Factors ML20212H5851987-02-11011 February 1987 Rev 5 to Process Control Program for Processing of Radioactive Wet Waste ML20210E2111986-12-31031 December 1986 General Abnormal Manual ML20203L3551986-04-30030 April 1986 Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor ML20205F5581985-12-31031 December 1985 Rev 11 to Offsite Dose Calculation Manual List of Tables for Quad-Cities Section 7.2 ML20112G4691984-10-31031 October 1984 Inservice Insp & Testing Program,Quad Cities Nuclear Power Station,Units 1 & 2 ML20108A6551984-10-30030 October 1984 Emergency Operating Procedures Generation Package ML20093M6781984-10-0505 October 1984 Suppl 2 to Detailed Control Room Design Review Program Plan ML20087P5611984-03-0202 March 1984 Public Version of Revised Emergency Plan Implementing Procedures QEP-310-O, Notification of Responsible Authorities & QEP-310-T3, Prioritized Notification Listing. W/Jm Felton 840323 Release Memo ML20087Q0641984-01-20020 January 1984 Public Version of Revised Emergency Plan Implementing Procedure Qep 340-7 Re Chemical Spill Cleanup & Qep 520-2 Re Training for Offsite Support Agencies.W/Jm Felton 840326 Release Memo ML20086J6011983-12-19019 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure Qep 200-2 Re Classification of Incident Involving Hazardous Matls & Qep 310-1 Re Initial Notification ML20083J4771983-11-15015 November 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 350-T1, Recommended Protective Actions for Gaseous Release & Qep 350-2, Emergency Drills ML20081B7011983-11-0303 November 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 110-0 Re Station Director & Qep 110-2 Re Acting Station Directory (Shift Engineer).W/Jm Felton Release Memo ML20081L8921983-10-13013 October 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 310-1, Initial Notification & Qep 340-4, Action to Be Taken in Event of Oil Spill to Mississippi River ML20090G7031983-10-0606 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 550-1 Re First Aid & Decontamination Facilities,Qep 550-2 Re Emergency Equipment Inventory & Qep 550-T1 Re Environ Sampling Supplies ML20078M7891983-09-30030 September 1983 Rev 10 to Offsite Dose Calculation Manual for LaSalle & Quad Cities ML20078E8701983-09-0808 September 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 550-0 Re Emergency Equipment & Supplies & Qep 550-T4 Re Emergency Operations Facility Supplies ML20078G0761983-09-0808 September 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 110-2 Re Acting Station Director (Shift Director) & Procedure Qep 310-1 Re Initial Notification ML20078M8091983-08-31031 August 1983 Rev 9 to Offsite Dose Calculation Manual for Braidwood, Consisting of Chapters 7.2 & 8.0 ML20024B9721983-06-30030 June 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 330-0 Re Assessment Actions & Qep 330-11 Re Estimation of I-131 Release by Field Team Measurements.Revised Index Encl ML20085N1321983-06-0707 June 1983 Public Version of Rev 14 to Emergency Plan Implementing Procedures Qep 310-0, Notification of Responsible Authorities & Rev 8 to Qep 310-T3, Prioritized Notification Listing ML20024E1751983-06-0303 June 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 330-0 Re Assessment Actions & Qep 330-11 Re Estimation of I-131 Release by Field Team Measurements ML20081F1401983-05-24024 May 1983 Public Version of Revised Emergency Plan Implementing Procedures Qep 200-T1 Re Emergency Action Levels & Qep 310-T3 Re Prioritized Notification Listing ML20024A1901983-05-0404 May 1983 Public Version of Rev 11 to Emergency Plan Implementing Procedure Qep 550-0, Emergency Equipment & Supplies & Rev 5 to Qep 550-T1, Environ Sampling Supplies. Receipt Form Encl ML20069L0021983-04-0404 April 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 160-1 Re Administrative Director,Qep 530-0 Re Exercises & Drills & Qep 200-0 Re Emergency Conditions ML20077B9231983-03-31031 March 1983 Rev 3,to Process Control Program for Solidification of Radwaste 1999-06-30
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L '0UAD-CITIES STATION 1
PROCESS CONTROL PROGRAM .
t-i FOR ,
f PROCESSING OF RADIOACTIVE WET WASTE
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s I. PURPOSE
-The purpose of this Process Control Program (PCP) is to insure that all low tevel radioactive wet wastes solidified or dewatered at Quad-Cities Nuclear Power Station meet the applicable federal, state, and burial site requirements. This PCP sets forth the steps used to solidify or dewater. radioactive wet wastes and to verify the final product meets the applicable requirements. This program covers the in-plant cement, i- vendor cement and vendor dewatering systems. Wet wastes at Quad-Cities Station consist of filter media (powdered resin and fiber) and bead
. resin. When expended, these wastes are transferred to various storage tanks.
[
- 11. IN-PLANT CEMENT SOLID WASTE SYSTEM DESCRIPTION (Class A unstable waste form only)
The resin slurry is transferred to one of two centrifuges for l
dewatering'. The centrifuges have a capacity of 25 gpm. The solids are
( separated from the water and drop into a hopper associate'd with each centrifuge. The water is routed back to a storage tank.
Each hopper has a 40 cubic foot capacity. At the bottom of the hopper there is a hopper discharge valve. This is a remotely operated, air-operated, fail closed valve. Connected to the hopper discharge valve is the sludge chute and the drum feed valve. The sludge chute is 8 inches l
in diameter and 6 feet 5 inches long, with a capacity of 2.2 cubic feet.
i l The drum feed valve is also remotely operated, air operated, and l
l: fail-closed. The hopper discharge valve and the drum feed valve are l
interlocked to prevent both valves from being open simultaneously.
Coment is added to a drum from the cement silo. The cement silo has a capacity of 620 cubic feet. Cement is fed through a i
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. . . rotcry feed 3r dL:n a transfer tuba through tha mixer herd, into the drum. The mixer goes into the drum and forms a seal to prevent dispersi6n of cement dust or spillage during mixing. The mixer has two speeds, 100 rpm and 200 rpm, that are programmed into the mix cycle.
Drums are capped at the load-out conveyor area before loading into a shipping cask. A cap is set in place and a seal ring is snapped over it. A threaded bolt is used to tighten the seal ring.
Drum storage consists of three conveyor lines, with room for 25 drums on each line. Drums stored on the storage lines are removed and either shipped, stored in storage bins located in the radwaste facility, or stored in the Interim Radwaste Storage facility.
Ill. OPERATION OF THE IN-PLANT CEMENT SOLID WASTE SYSTEM In order to insure solidification of spent resins with no free water, tests were conducted at Quad-Cities Station using unspent resin.
Fresh resins were mixed up in the proportions that would be expected to be normally processed. These resins were then put into a drum and the drum was processed through the cement system. The drum was capped as normal and allowed to set in storage for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the drum was cut open lengthwise and inspected. The results of the inspection resulted in a change of the proportions of water and cement until the final product was solid and free of water. A series of drums were processed using spent resins, and the drums were visually inspected for no free water prior to shipping. No free water was observed.
The general procedure that is followed to process spent resins is
- described below. Specific plant operating procedures are followed by the l operator.
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- A. Tha empty drum is c:vered nith a plastic big and taped in pirce to prevent external contamination.
B. A half'of a bag of dry cement is added to the empty drum.
C. .The empty drums are loaded on a conveyor.
D. . One empty drum from the conveyor is loaded on a transfer cart (remote operation).
E. The transfer cart is advanced to the selected hopper station (remote operation).
F. Water is added (remote operation). Normally 12 gallons of water are added to each drum. This amount can be varied if necessary for complete solidification. The amount of water required is selected, and a flow integrator gives the inlet valve a closed signal when that amount is delivered.
G. The drum is filled with resins to a prescribed level (remote operation). The resin is transferred from the hopper to the drum through the sludge chute. The discharge valve on the sludge chute is a manually operated remote valve. The operator views the drum through a mirror and fills the drum to the first roll hoop f rom the top of the drum. Although this method of adding resin to the drum is not precise, it can be controlled to a high degree. If an operator determines that the quantity of resins varies from the prescribed level, he can compensate with water and/or cement.
H. The drum is transferred to the mixing station (remote operation).
- 1. The cement timer is set.
J. The mixer cycle (remote operation) is started. The mixer lowers into the drum and forms a tight seal. The mixer will begin to 01530
,, ,- rotats at slow sp2ed. Tha air slide bloxsr end dust collector are
< started. The cement feeder end vibrators start and cement is metered to the drum. The mixer increases to fast speed. The cement feeder stops and the air slide blower and dust collector stop. When the mixer completes the cycle, the RPM meter will start to decrease. At this point, the mixer control switch is moved from AUTO to FAST and the mixer is given an additional 5 minutes on fast speed. The switch is then returned to AUTO, and the mixer cycle is complete.
K. The drum is transferred to the inspection station (remote operation).
L. The mixed drum contact radiatior, reading are logged and the contents of the drum are observed. If it is determined that more cement is required, the drum is returned to the mixer and additional cement is added. When the mix is satisfactory, the drum is transferred to the drum storage lines.
IV. VERIFICATION OF IN-PLANT CEMENT SYSTEM SOLIDIFICATION The solidified drum is verified to be void of free water prior to shipping or storage. The drum is transferred from the storage lines to the load-out conveyor. At this point, the drum is visually verified to be void of free water, the protective plastic bag is removed, and the drum is capped. The drum is then surveyed for smearable contamination and dose rate. The drum is then loaded into the shipping vehicle or placed in storage.
If a drum is found to contain free water, it will be noted as such.
Dry cement will be added such that all of the free water is, absorbed or the drum will be recycled through the mixing line as required. The drum will not be shipped until all free water is absorbed.
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.. , V. VENDOR SUPPLIED SOLIDIFICATION SYSTEM (Stablo Waste. Forms)
Contractor solidification services are utilized at the Station for wastes which are required to be classified as stable waste per 10 CFR 61 and/or burial site licenses. The contractor must have a PCP (Process Control Program) to produce a waste form which is stable as defined in 10 CFR 61. Solidification is done in either the cask or a process shield i
and offers the advantage of reduced radiation exposure to personnel involved in performing the necessary package handling operations.
A batching tank is utilized to collect the radwaste to be solidified. The tank can be filled from any of the following:
Condensate Phase Separators.
A.
B. Cleanup Phase Separators.
C. Spent Resin Tanks.
D. Waste Sludge Tank.
E. Floor Drain Demineralizer.
After the tank is filled with radwaste, a decant pump is used to remove water from the top of the settled sludge. When the decanting operation is completed, the tank contains about 1,900 gallons of sludge.
The mixing tank is operated on recirculation in order to allow a l
tank sample to be taken for analysis and sample solidification tests.
A temperature monitor in the liner is used to note the maximum temperature during the exotherm. After sufficient cooling the liner is prepared for shipment or storage.
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- , s VI . OPERATION OF THE VENDOR SOLI 0lFICATION SYSTEM A liner. is prepared for use by installing a thermocouple and tubing for level indication. The fill _ head is placed over the. liner and locked in-place.
The radwaste is added to the liner. The mixing tank is first mixed for about 10 minutes. The proper amount of radwaste is delivered by the radwaste pu.np. Waste flow to the liner is monitored by a TV camera. The radwaste pipe lines and waste transfer hose to the fill head are then flushed.
After the radwaste has been put into the liner the process is L
completed by the contractor. The contractor adds cement and additives in accordance with their approved PCP. After final mixing the temperature is monitored and the maximum temperature is noted. When the solidified liner has suf ficiently cooled the contractor visually inspects the product and verifies that it is an acceptable product. The liner is then-covered with a lid, secured, surveyed and shipped or stored in the j interim Radwaste Storage Facility.
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l l' Vll. VERIFICATION OF VENDOR SUPPLIED SOLIDIFICATION SYSTEM Verification of solidification first involves sampling the radwaste prior to solidification in order to determine the proper proportions of the ingredients that will produce an acceptable product. A l
representative laboratory sample of waste is taken from the sampling 1
line. Small, scaled-down amounts of cement and additives are added in the proper quantities. Based on an acceptable product, scale-up factors are developed for the full scale solidification.
To further verify solidification, a visual inspection of the liner is performed prior to installing the lid. The visual inspection verifies that the product is acceptable per the contractors PCP.
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, , pl I . VENDOR SUPPLIED DEWATERING SYSTEM (STABLE WASTE FORMS)
Contractor dewatering services may be utilized at the Station in lieu of solidification for stable waste forms as directed by station operating personnel. The contractor cust have a Process Control Program (PCP) to produce a waste form which meets all the requirements of 10CFR61 and the applicable burial site criteria. Dewatering may either be done in a cask or a process shield.
A mixing tank is utilized to collect the radwaste to be dewatered.
The tank can be filled from any of the following:
A. Condensate Phase Separators B. Cleanup Phase Separators C. Spent Resin Tanks D. Waste Sludge Tank After the tank is filled with radwaste, a decant pump is used to remove water from the top of the settled sludge. When the decanting operation is completed, the tank contains about 1,900 gallons of sludge.
The mixing tank is operated on recirculation in order to allow a tank sample to be taken for analysis.
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, ,, L X . OPERATION OF THE VENDOR DEWATERING SYSTEM A High: Integrity Container (HIC) is prepared for use by installing a thermocouple, if not already installed, tubing for level indication, and inspecting dewatering elements and thermocouple leads, if installed. The fill head is placed over the liner and locked in-place.
The radwaste is added to the HlC. The mixing tank is first mixed for approximately 10 minutes. The proper amount of radwaste is delivered by the radwaste pump. Waste flow to the HIC is monitored by a TV camera. The radwaste pipe lines and waste transfer hose to the fill head are then flushed.
After the radwaste has been put into the HIC, the process is completed by the contractor. The contractor dewaters in accordance'with their approved PCP until the acceptance criteria is met. When the process is complete, the contractor verifies that it is an acceptable product. The HIC is then covered with a lid, secured, surveyed and shipped or stored in the Interim Radwaste Storage Facility.
X. VERIFICATION OF VENDOR SUPPLIED DEWATERING SYSTEM Verification of an acceptable dewatered product is delineated in the l
contractors Process Control Program and operating procedures. The criteria is dependent upon the type of dewatering system used and the l
material dewatered.
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