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MONTHYEARML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual Project stage: Other ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program Project stage: Other ML20155C8701986-03-24024 March 1986 Forwards Rev 1 to Solid Radwaste Process Control Program & Rev 1 to Offsite Dose Calculation Manual. Revs Involve Format Changes Only Project stage: Other ML20235P8421987-07-14014 July 1987 Safety Evaluation Re Acceptance of Offsite Dose Calculation Manual as Updated & Corrected Through 861231 Project stage: Approval 1986-03-24
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20106A6521992-02-29029 February 1992 Proposed Rev 3 to Ei Hatch Nuclear Plant Solid Radwaste PCP, Per GL 89-01 ML20106A6501992-02-0707 February 1992 Rev 7 to Ei Hatch Nuclear Plant ODCM, Reflecting Proposed Changes,Per GL 89-01 ML20056B3031990-08-0101 August 1990 Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval ML20149N1141988-01-0404 January 1988 Revised Second 10-Yr Interval Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20211H5491987-02-20020 February 1987 IGSCC-Susceptible Primary Pressure Boundary Stainless Steel Piping & Components Insp/Mitigation Program, 1987 Maint/Refueling Outage ML20245B8301986-12-10010 December 1986 Rev 0 to SO-OPS-05-1286, Spent Fuel Pool Transfer Canal Gates ML20245B8171986-12-0505 December 1986 Rev 0 to SO-OPS-02-1286, Processing of Water from Yard Drains ML20245B8201986-12-0505 December 1986 Rev 0 to SO-OPS-01-1286, Radwaste Discharges. Supporting Documentation Encl ML20203L9291986-08-0101 August 1986 Rev 0 to Training Procedure 72TR-TRN-002-0S, License Requalification Training Program ML20137V9031985-12-0505 December 1985 Rev 1 to Emergency Implementing Procedure 62RP-RAD-009-05, Airborne Radioactivity Concentration Determination ML20076J1871985-11-0808 November 1985 Rev 2 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp for Georgia Power Co ML20076J1911985-11-0404 November 1985 Rev 1 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20076J1961985-10-23023 October 1985 Rev 0 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20135F3161985-08-26026 August 1985 Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project ML20132E5471985-08-23023 August 1985 Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting ML20209F2391985-07-0101 July 1985 Recirculation,Rhr & Reactor Water Cleanup Sys Piping Weld Joint Insp/Mitigation Program for 1985 Maint/ Refueling Outage ML20128A0561985-06-25025 June 1985 Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20126E8331985-06-11011 June 1985 Emergency Plan Implementing Procedures & Deleted Title Sheets,Including Procedures HNP-8007 Re Decontamination of Clothing & Hats & HNP-8004 Re Dosimetry Issuance & Tracking ML20116D4401985-04-23023 April 1985 Revised Emergency Procedures HNP-8109 Re Continuous Air Monitors Models AM-3D & AM-33-1,HNP-8122 Re Radiation Monitor Model RM-16 & HNP-8146 Re Rascal Portable Rate Meter-Scaler/Model PRS-1 Operation & Calibr ML20245B7911985-04-17017 April 1985 Rev 0 to 10AC-MGR-04-0, Deficiency Control Sys. Supporting Documentation Encl ML20107G1421985-02-15015 February 1985 Revised Emergency Implementing Procedures,Including Rev 3 to HNP-8161 Re Eberline Model PCM-1 Portable Monitor Operation & Calibr & Rev 2 to HNP-8036 Re Waste Classification & Manifest Reporting Resin Shipments ML20215F7371984-12-26026 December 1984 Rev 1 to Administrative Control Procedure 40AC-FPX01-0, Fire Protection Program. Portions of Procedures 34AB-OPS-056-1S & 34AB-OPS-056-2S Encl ML20101B0551984-12-17017 December 1984 Rev 5 to Emergency Plan Implementing Procedure HNP-8134, Whole Body Counter Sys ML20108E0921984-11-29029 November 1984 Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3 ML20107H5701984-10-31031 October 1984 Detailed Control Room Design Review Program Plan ML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program ML20098G3401984-09-30030 September 1984 Offsite Dose Calculation Manual ML20098G3381984-09-30030 September 1984 Solid Radwaste Process Control Program ML20108E0741984-06-13013 June 1984 Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & Calibr ML20084H4971984-05-0101 May 1984 Rev 0 to Procedures Generation Package for Emergency Operating Procedures,Including plant-specific Technical Guidelines for Units 1 & 2,plant-specific Writers Guide & Implementation Plan for Emergency Response Project ML20086U4131984-02-29029 February 1984 Vendor Equipment Technical Info Program, Per Generic Ltr 83-28,Section 2.2.2,final Draft ML20087N9101984-01-26026 January 1984 Public Version of Transmittal & Title Page to Deleted Emergency Plan Implementing Procedures,Including Procedure HNP-8031 Re Determination of Specific Activity of Spent Resin & Curie Contents of Liner & 840322 Memo ML20087M7911984-01-25025 January 1984 Public Version of Transmittal & Title Pages of Deleted Emergency Plan Implementing Procedures HNP-8019, Insp of Steel Radwaste Shipping Drums & HNP-8422, Handling & Loading of Chem-Nuclear Cask & 840322 Memo ML20087M9321984-01-20020 January 1984 Public Version of Rev 7 to Emergency Plan Implementing Procedure HNP-8101, Teletector Model 6112B/D Operation & Calibr & Jm Felton 840322 Release Memo ML20081B6731984-01-18018 January 1984 Public Version of Rev 0 to Emergency Plan Implementing Procedure HNP-8161, Eberline Model PCM-1 Portal Monitor & Rev 17 to HNP-8008, Radiation Work Permit & Jm Felton 830307 Release Memo ML20087P0191984-01-13013 January 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8038 Re Waste Classification & Manifest Reporting & HNP-8042 Re Radiological Work Practices & 840326 Memo ML20079H9011983-12-0707 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8035 Re Pulmonary Function Screening Program & HNP-8016 Re Shipment of Radioactive Matl ML20093D4881983-10-31031 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
[Table view] |
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SOLID RADI0 ACTIVE WASTE PROCESS CONTROL PROGRAM FOR THE GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT I SEPTEMBER 1984 I
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I DISTRIBUTION LIST Recipient Title /Lecation No. of Copies E. C. Sorrell Supervisor-Document Control 8 Plant Hatch S. C. Ewald Manager-Radiation Safety 4 Georgia Power Company 333 Piedmont, 14th Floor Atlanta, Georgia I L. T. Gucwa Manager-Nuclear Engineering and Chief Nuclear Engineer Georgia Power Company 1
I jg 333 Piedmont, 14th Floor l3 Atlanta, Georgia i
B. L. Maulsby Supervisor-Environmental Center I
2 Georgia Power Company '
Decatur, Georgia W. F. Garner Manager-Nuclear Plant Support-Hatch 1 Southern Company Services Inverness Center i Building 10, Room 300 Birmingham, Alabama
,g J. N. McLeod Supervisor-Safety Analysis 1 i lg Southern Company Services
)
l Inverness Center Building 40, 6th Floor l Birmingham, Alabama i
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EDWIN I. HATCH NUCLEAR PLANT SOLID RADI0 ACTIVE WASTE PROCESS CONTROL PROGRAM I. PURPOSE The processing of radioactive waste for disposal at a licensed radioactive waste burial site requires that the waste be appropriately analyzed, processed, and packaged, thus representing a final waste form that is acceptable for transportation to and burial at a licensed radioactive waste disposal site. The purpose of this Process Control Program is to document the radioactive waste processing methods and the quality control steps that are taken at the Hatch Nuclear Plant to verify compliance with applicable regulatory requirements and, in particular, to assure an acceptable waste product meeting the applicable waste stability characteristics of 10 CFR 61.56.
At Plant Hatch, the routine processing systems that generate radioactive waste requiring of fsite disposal are:
+ The reactor water clean-up system.
- The condensate clean-up system.
. The spent fuel pool clean-up system.
- The liquid radwaste system.
All of these systems employ the use of either bead ion exchange resins or the powdered ion exchange resins as the processing medium. Spent resins are dewatered in an appropriate liner based on the waste class and burial site criteria. In addition to these processing systems, two other types of radioactive wastes th:t are routinely processed are the cortpactable and noncompactable trash (DAW) and slightly radioactively contaminated oils.
I This Process Control Program addresses the processing of these types of wastes and the measures which are in-place to assure the generation of an acceptable waste product. Operating criteria for spent resin transfer to an appropriate liner and in-liner dewatering are addressed, as are also the ,
1
criteria for the processing of DAW (compactable and noncompactable trash) and miscellaneous contaminated liquids (including oils).
II. REGULATORY OVERVIEW I All waste processing, packaging, and shipping are conducted in accordance with approved procedures to assure compliance with applicable federal, state, I and burial site requirements. Waste processed for disposal is evaluated per approved plant procedures for compliance with the following:
. Waste classification requirements of 10 CFR 61.55.
. Waste characteristic requirements of 10 CFR 61.56.
. Manifest reporting requirements of 10 CFR 20.311.
Packaging of waste is in containers which meet 00T specifications and are appropriate for the applicable waste class. Shipments are conducted in accordance with the requirements of 49 CFR 172-177 and 10 CFR 71.
I All waste processing is performed in a manner consistent with the principles of ALARA. The procedures that have been developed to cover waste processing operations address appropriate radiation safety measures, such as job preplanning, radiation source shielding, job prerequisites, and material -
I requirements so as to minimize stay times.
III. DEWATERING OF RESINS The processing of the liquid streams by ion exchange resins (bead or powdered) results in a waste product that is most appropriately dewatered in a suitable disposable liner (carbon steel or high-integrity container).
Prior to transfer of the spent resin to a liner, a sample is collected and analyzed by gamma spectroscopy to quantify the radioactive material concentration. Based on this information, the waste is appropriately classified in accordance with approved procedures per the criteria of 10 CFR I 61.55. If a sample of the resin cannot be collected prior to transf er to a liner due to either design or operational limitations, a sample collected af ter transfer or an external radiation level measurement may be used in accordance with approved procedures for determining waste class.
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E The dewatering process is conducted in accordance with approved procedures with appropriate operating parameters to assure a waste product with as little freestanding water as pussible but, in no case, in excess of 1 percent by volume (i.e., meeting the waste stability criteria of 10 CFR 61.56). The specifics of the dewatering process vary depending on the type of dewatering process employed
- and the type of resin (bead or powdered). However, the common approach to dewatering is the removal of essentially all interstitial I water. Appropriate verifications (dependent on the process method) are conducted to assure an acceptable waste form.
IV. PACKAGING OF DAW (COMPACTABLE AND NONM MPACTABLE TRASH)
All radioactively contaminated trash is appropriately packaged, surveyed, and labeled prior to shipment for disposal. Bagged wastes are opened to assure exclusion of unacceptable waste products, such as water and oil. Compactable trash is processed by compaction to reduce the volume of the waste; noncompactable materials are segregated and normally packaged separately.
After packaging, the waste containers are stored awaiting shipment. Periodic inspection of the storage area is conducted to assure container integrity.
V. PROCESSING OF OILS Periodically, it may become necessary to process slightly radioactively contaminated oils for offsite disposal. These liquid wastes are either processed by absorption or solidification. Absorption is accomplished using at least twice as much absorbant as is necessary to completely absorb the liquid; only an absorbant approved by the burial site is used. Any solidification of liquids is conducted in accordance with approved plant procedures or a contractor-supplied solidification procedure that has been I specifically developed for the solidification process. (Refer to Section VI for the use of a contractor of contractor-supplied process for waste processing.)
I
- The dewatering process at Plant Hatch is a contractor-supplied system.
Refer to Section VI for the process controls that are applicable.
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The solidification of liquids (including oils) utilizing the onsite mixing unit is conducted in accordance with approved operating procedures and parameters (HNP-8043 and HNP-8044). Per HNP-8043, test samples are conducted every tentn batch to verify the pre-established mixing ratios. Any unacceptable products require a re-evaluation of the mixing ratios; any unacceptable waste containers are identified (by visual inspection), and appropriate actions are taken to assure that the waste as shipped meets the applicable waste stability requirements of 10 CFR 61.56. Additionally, all containers of the solidified waste are inspected prior to closure to assure a solidified matrix absent of any freestanding water.
VI. USE OF CONTRACTOR FOR WASTE PROCESSING Contractor-supplied process and/or service may be used at Plant Hatch for the processing of radioactive waste for offsite disposal. For the operation of such a process, it may be desirable to use process control measures and procedures developed by the contractor specifically for the system or process. Therefore, previously addressed process control measures for a I particular type waste may be superseded by contractor-supplied measures, as appropriate.
Prior to the use of a contractor-supplied process or service for waste processing at Plant Hatch, a management review of the contractor's process control and procedures is performed to assure that the operation is compatible with plant operation and is in accordance with regulatory requirements.
I For the processing of waste that is intended to be shipped for dispusal at a licensed radioactive waste burial site, additional precautions are taken to assure a final waste product that meets the appropriate waste stability requirements of 10 CFR 61.56. In particular, the following items, as applicable, are to be documented by the contractor (or Plant Hatch manuals or procedures) prior to utilization for waste processing:
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. A general description of the solidification or dewatering process, including type solidification agent (if applicable), major process equipment and interface with plant equipment, types of waste that can be processed, and operating parameters.
I . Process control measures that provide for the verification of the generation of a suitable waste product, including items (as may be appropriate for the process method), such as representative sampling, laboratory tests, and acceptance criteria.
. Specifically approved procedures for the operation of the process equipment that will assure operation within the bounds as delineated by the process control measures.
I . Appropriate acceptance criteria for evaluating the acceptability of the final waste product.
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