This study was designed to describe aspects of the life history strategies of spring chinook salmon in the Grande Ronde basin. During the past year we focused on rearing and migration patterns of juveniles and surveys of spawning adults. The specific objectives for the early life history portion of the study were: Objective 1, document the annual in-basin migration patterns for spring chinook salmon juveniles in the upper Grande Ronde River, including the abundance of migrants, migration timing and duration; Objective 2, estimate and compare smolt survival indices to mainstem Columbia and Snake River dams for fall and spring migrating spring chinook salmon; Objective 3 initiate study of the winter habitat utilized by spring chinook salmon in the Grande Ronde River basin. The specific objectives for the spawning ground surveys were: Objective 4, conduct extensive and supplemental spring chinook salmon spawning ground surveys in spawning streams in the Grande Ronde and Imnaha basin, Objective 5; determine how adequately historic index area surveys index spawner abundance by comparing index counts to extensive and supplemental redd counts; Objective 6, determine what changes in index areas and timing of index surveys would improve the accuracy of index surveys; Objective 7, determine the relationship …

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas.

The Acceptance Test Procedure for the 241-AN-107 Caustic Addition Mixer Pump Data logger, WHC-SD-WM-ATP-149, was started on September 25, 1995, and completed November 13, 1995. K.G. Carothers of Tank Waste Remediation Engineering requested the test procedure and ICF Kaiser Control Systems Engineering group wrote the test procedure and executed it at the 305 building in 300 area and at the 241-AN Tank Farm in 200 East area. The purpose of this report is to document that the Caustic addition Mixer Pump Data logger, functioned as intended as installed at 241-AN-107 tank farm.

At the Hanford Site organic compounds were measured in tank supernate simulant solutions during FY 1995. This solubility information will be used to determine if these organic salts could exist in solid phases (saltcake or sludges) in the waste where they might react violently with the nitrate or nitrite salts present in the tanks. Solubilities of sodium glycolate, succinate, and caproate salts; iron and aluminum and butylphosphate salts; and aluminum oxalate were measured in simulated waste supernate solutions at 25 {degree}C, 30 {degree}C, 40 {degree}C, and 50 {degree}C. The organic compounds were selected because they are expected to exist in relatively high concentrations in the tanks. The solubilities of sodium glycolate, succinate, caproate, and butylphosphate in HLW tank supernate solutions were high over the temperature and sodium hydroxide concentration ranges expected in the tanks. High solubilities will prevent solid sodium salts of these organic acids from precipitating from tank supernate solutions. The total organic carbon concentrations (YOC) of actual tank supernates are generally much lower than the TOC ranges for simulated supernate solutions saturated (at the solubility limit) with the organic salts. This is so even if all the dissolved carbon in a given tank and supernate is due to …

The Spent Nuclear Fuel (SNF) Project Engineering Support group cold-tested the Eductor System a 15 horsepower multi-stage centrifugal pump manufactured by the Grunfos Corporation with the housing manufactured and sold with the pump by the Tri-Nuclear Corporation and a 3-inch diameter water jet eductor manufactured by the Fox Valve Corporation. The Eductor System was tested to gather and document information to optimize sludge retrieval operations for use in the 105 K Basins. The cold-testing took place during February 12 through February 29, 1996 in the 305 Cold Test Facility basin located in the 300 area. The pump, utilized in conjunction with the eductor, makes up the core of the Eductor System. The pumping unit consists of a 15 hp stainless steel multi-stage centrifugal Grunfos pump which is seated in a stainless steel fabricated housing. Two baskets or filter elements make up part of the housing on the suction side of the pump. The pump can be used independent of the housing but the housing has two identified purposes. The first use is to stabilize the centrifugal pump and give the pneumatic valves and pump discharge piping a solid platform so the Eductor System can be more easily mobilized within the …

Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks.

The 100-D Ponds facility is regulated under the Resource Conservation and Recovery Act of 1976. The pH of groundwater in a downgradient well is statistically different than local background, triggering an assessment of groundwater contamination under 40 CFR 265.93. Results of a similar assessment, conducted in 1993, show that the elevated pH is caused by the presence of alkaline ash sediments beneath the ponds, which are not part of the RCRA unit. The 100-D Ponds should remain in indicator evaluation monitoring.

Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX Plant, as well as waste received from other on-site sources.

This report presents the results of a comprehensive third party needs assessment of the Hanford Fire Department (HFD), conducted by Hughes Associates Inc. The assessment was commissioned with the intent of obtaining an unbiased report which could be used as a basis for identifying needed changes/modifications to the fire department and its services. This report serves several functions: (1) it documents current and future site operations and associated hazards and risks identified as a result of document review, site and facility surveys, and interviews with knowledgeable personnel; (2) describes the HFD in terms of organization, existing resources and response capabilities; (3) identifies regulatory and other requirements that are applicable to the HFD and includes a discussion of associated legal liabilities; and (4) provides recommendations based on applicable requirements and existing conditions. Each recommendation is followed by a supporting statement to clarify the intent or justification of the recommendation. This report will be followed by a Master Plan document which will present an implementation method for the recommendations (with associated costs) considered to be essential to maintaining adequate, cost effective emergency services at the Hanford site in the next five to seven years.

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD …

The purpose of this Acceptance Test Report is to provide documentation for the acceptance testing of the rotary mode core sample trucks 3 and 4, designated as HO-68K-4600 and HO-68K-4647, respectively. This report conforms to the guidelines established in WHC-IP-1026, ``Engineering Practice Guidelines,`` Appendix M, ``Acceptance Test Procedures and Reports.`` Rotary mode core sample trucks 3 and 4 were based upon the design of the second core sample truck (HO-68K-4345) which was constructed to implement rotary mode sampling of the waste tanks at Hanford. Successful completion of acceptance testing on June 30, 1995 verified that all design requirements were met. This report is divided into four sections, beginning with general information. Acceptance testing was performed on trucks 3 and 4 during the months of March through June, 1995. All testing was performed at the ``Rock Slinger`` test site in the 200 West area. The sequence of testing was determined by equipment availability, and the initial revision of the Acceptance Test Procedure (ATP) was used for both trucks. Testing was directed by ICF-KH, with the support of WHC Characterization Equipment Engineering and Characterization Project Operations. Testing was completed per the ATP without discrepancies or deviations, except as noted.

This document presents the natural phenomena hazard (NPH) loads for use in implementing DOE Order 5480.28, Natural Phenomena Hazards Mitigation, at the Hanford Site in south-central Washington State. The purpose of this document is twofold: (1) summarize the NPH that are important to the design and evaluation of structures, systems, and components at the Hanford Site; (2) develop the appropriate natural phenomena loads for use in the implementation of DOE Order 5480.28. The supporting standards, DOE-STD-1020-94, Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities (DOE 1994a); DOE-STD-1022-94, Natural Phenomena Hazards Site Characteristics Criteria (DOE 1994b); and DOE-STD-1023-95, Natural Phenomena Hazards Assessment Criteria (DOE 1995) are the basis for developing the NPH loads.

The objective for this problem is to calculate the ground-level release dispersion factors (X/Q) and unit doses for onsite facility and offsite receptors at the site boundary and at Highway 240 for plume meander, building wake effect, plume rise, and the combined effect. The release location is at Central Waste Complex Building P4 in the 200 West Area. The onsite facility is located at Building P7. Acute ground level release 99.5 percentile dispersion factors (X/Q) were generated using the GXQ. The unit doses were calculated using the GENII code. The dimensions of Building P4 are 15 m in W x 24 m in L x 6 m in H.

The methodology used in the production of the Hazard Category 2 TQs is verified and presented in the above calculations (Section 3.0). The analysis is done as consistently to that prescribed in DOE-STD-1027-92 as is possible. Determining the TQ limits with the standard`s variables consistently produced the listed Hazard Category 2 TQs for the six major isotopes present in the CWC waste (100% of the isotopes attempted in their analysis) and verifies their approach without changing release fractions or receptor locations. An example of a modification of the TQ for a change in the release fraction is provided in the standard Attachment 1, pages A-6 through A-10. However, the change in TQs receptor location is another issue. Modification to the TQ because of facility location is allowed in the standard, but there is no definite approach described in the standard. This change is best represented through the change in the XIQ value. This paper provides a defensible interface with DOE guidance DOE-STD-1027-92, and an established proposed methodology for standardizing changes in the TQs because of release fractions or receptor locations. By using this information as the basis for the construction of the TQs as presented in DOE-STD-1027-92, it is determined …

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The First Quarter 1996 survey results and the status of actions required from current and past reports are summarized: All the routine environmental radiological surveys scheduled during January, February, and March 1996 were completed. One hundred four environmental radiological surveys were performed during the first quarter of 1996, thirty at the active waste sites and seventy four at the inactive waste sites. Contamination above background levels was found at six of the active waste sites and eight of the inactive waste sites. Contamination levels as high as > 1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys, all were in Underground Radioactive Material (URM) areas. The contamination found within eleven of the URH areas was immediately cleaned up and no further action was required. In the remaining three sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR`s) were issued and the sites were turned over to the landlord for further action if required.

The Clean Salt Process (CSP) is the fractional crystallization of nitrate salts from tank waste stored on the Hanford Site. This study reviews disposition options for a CSP product made from Hanford Site tank waste. These options range from public release to onsite low-level waste disposal to no action. Process, production, safety, environment, cost, schedule, and the amount of CSP material which may be used are factors considered in each option. The preferred alternative is offsite release of clean salt. Savings all be generated by excluding the material from low-level waste stabilization. Income would be received from sales of salt products. Savings and income from this alternative amount to $1,027 million, excluding the cost of CSP operations. Unless public sale of CSP products is approved, the material should be calcined. The carbonate form of the CSP could then be used as ballast in tank closure and stabilization efforts. Not including the cost of CSP operations, savings of $632 million would be realized. These savings would result from excluding the material from low-level waste stabilization and reducing purchases of chemicals for caustic recycle and stabilization and closure. Dose considerations for either alternative are favorable. No other cost-effective alternatives that were considered …

The Hanford Nuclear Reservation Tank Farms` underground waste tanks have been used to store liquid radioactive waste from defense materials production since the 1940`s. Waste in certain of the tanks may contain material in the form of ferrocyanide or various organic compounds which could potentially be susceptible to condensed phase chemical reactions. Because of the presence of oxidizing materials (nitrate compounds) and heat sources (radioactive decay and chemical reactions), the ferrocyanide or organic material could potentially fuel a propagating exothermic reaction with undesirable consequences. Analysis and experiments indicate that the reaction propagation and/or initiation may be prevented by the presence of sufficient moisture in the waste. Because the reaction would probably be initiated at the surface of the waste, evidence of sufficient moisture concentration would help provide evidence that the tank waste can continue to be safely stored. The Surface Moisture Measurement System (SMMS) was developed to collect data on the surface moisture in the waste by inserting two types of probes (singly) into a waste tank-a neutron probe and an electromagnetic inductance (EMI) probe. The sensor probes will be placed on the surface of the waste utilizing a moveable deployment arm to lower them through an available riser. The …

A meteorological database has been developed to aid in the prediction of indoor radon concentrations in the United States. The database contains predicted typical monthly meteorological statistics at the county level derived from hourly meteorological data from 208 (234 for precipitation) geographically distinct monitoring stations. Interpolation and extrapolation techniques were used to predict statistics for counties not containing a meteorological monitoring site. The LBNL database includes statistics for meteorological variables including dry-bulb temperature, dew-point temperature, barometric pressure, wind speed, wind direction, hours of precipitation, precipitation, and derived infiltration degree-days. The database consists of individual files of derived statistics for each weather variable and is potentially useful for indoor radon modeling as well as for other purposes. Each file contains data values for all 12 months and an aggregation of the 12 months up to a yearly statistic for all county centroids. A test was conducted to assess the quality of interpolated values. Examples showing the use of the database for mapping infiltration degree-days and an application of the database to a statistical correlation analysis attempting to find meteorological factors influencing indoor radon levels in the United States is discussed.

This document summarizes information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-104. Sampling and analyses meet safety screening and historical data quality objectives. This report supports the requirements of Tri-party Agreement Milestone M-44-09. his characterization report summoned the available information on the historical uses and the current status of single-shell tank 241-B-104, and presents the analytical results of the June 1995 sampling and analysis effort. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-44-09 (Ecology et al. 1994). Tank 241-B-104 is a single-shell underground waste storage tank located in the 200 East Area B Tank Farm on the Hanford Site. It is the first tank in a three-tank cascade series. The tank went into service in August 1946 with a transfer of second-cycle decontamination waste generated from the bismuth phosphate process. The tank continued to receive this waste type until the third quarter of 1950, when it began receiving first-cycle decontamination waste also produced during the bismuth phosphate process. Following this, the tank received evaporator bottoms sludge from the 242-B Evaporator and waste generated from the flushing of transfer lines. A description and …

The Hanford Site Integrated Pest Management Plan (HSIPMP) defines the Integrated Pest Management (IPM) decision process and subsequent strategies by which pest problems are to be solved at all Hanford Site properties per DOE-RL Site Infrastructure Division memo (WHC 9505090). The HSIPMP defines the roles that contractor organizations play in supporting the IPM process. In short the IPM process anticipates and prevents pest activity and infestation by combining several strategies to achieve long-term pest control solutions.

This is the final sample analysis report for tank 241-BX-104 (BX-104), cores 126 and 127. Two segments from each core yielded a total of 11 samples which were analyzed. The data quality objectives (DQOs) applicable to this sampling event were the Safety Screening DQO (Dukelow et al. 1995) and the Organic Safety DQO (Turner et al. 1995). The samples were received, extruded and analyzed at PNNL 325 Analytical Chemistry Laboratory (ACL). The analyses were performed in accordance with the Sample Analysis Plan (Gretsinger 1996) and indicated that the tank is safe with respect to the criteria in the Safety Screening and Organic DQO. Detailed analytical results were described in the analytical laboratory 45-day Report (Attachment 1, WHC-SD-WM-DP-171, REV. 0) and final report (Attachment 2, PNL-BX-104 REV.1) prepared by PNNL, 325 Laboratory. Corrections and/or exceptions to the PNNL final report are provided.

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the containers expected to be used for these waste shipments from 1996 through the remaining life cycle of the Hanford Site. In previous years, forecast data have been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to the more detailed report on waste volumes: WHC-EP0900, FY 1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary. Both of these documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on the types of containers that will be used for packaging low-level mixed waste (LLMW) and transuranic waste (both …

This plan has been developed by Westinghouse Hanford Company (WHC), and its subcontractors ICF Kaiser Hanford (ICF KH) and BCS Richland, Inc. (BCSR), at the direction of the US Department of Energy (DOE), Richland Operations Office (RL). WHC and its subcontractors are hereafter referred to as the Maintenance and Operations (M and O) Contractor. The plan identifies actions involving the M and O Contractor that are critical to (1) prepare for a smooth transition to the Project Hanford Management Contractor (PHMC), and (2) support and assist the PHMC and RL in achieving transition as planned, with no or minimal impact to ongoing baseline activities. The plan is structured around two primary phases. The first is the pre-award phase, which started in mid-February 1996 and is currently scheduled to be completed on June 1, 1996, at which time the contract is currently planned to be awarded. The second is the follow-on four-month post-award phase from June 1, 1996, until October 1, 1996. Considering the magnitude and complexity of the scope of work being transitioned, completion in four months will require significant effort by all parties. To better ensure success, the M and O Contractor has developed a pre-award phase that is …

This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances.