ML20094E516

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Rev 10 to WVDP-019, Waste Mgt Plan
ML20094E516
Person / Time
Site: West Valley Demonstration Project
Issue date: 12/31/1991
From: Martin E, Weiss T
WEST VALLEY NUCLEAR SERVICES CO., INC.
To:
References
REF-PROJ-M-32 WVDP-019, WVDP-19, NUDOCS 9201240203
Download: ML20094E516 (109)


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Revision Number 10 l'

Revision Date 12-31-91 Controlled copy No. 25 FNNUAL WASTE MANAGEMENT PLAN PREPARED BY

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D. Martin

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Cognizant F: thor APPROVED BY uA*

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T. C. Weiss, Jr. ( Actin j)

/C0guitant Staf f papsger West Valley Nuclear Services Co., Inc.

nLAo265:R6 P.O. Box 191 West Valley, NY 14171-0191 I

WW1816, Rev.1

WVDP-019 Rev. 10 RECORD OP f!EVISION PPOCEDUSI-If there are changes to the procedure, the revision number increases by one.

These changes are indicated by placing a heavy vertical black line located in the right-hand margin adjacent to the sentence or paragraph which was revised.

Examolo:

The vertical line in the margin indicates a change.

j Revision on

-Rev. No.

Description of Changes Page(s)

Dated i

0 Original Issue All 07/03 1

Update

- All 07/83 2

Update All 09/83 2

(supplement) 05/84 3

Rertructure entire Document to All 12/84 format suggested in Attachment 1 of DOE Order 5820.2 4

Information Update All 10/85 5

Information Update All 10/86 6

Information Update All 10/07 7

Information Update-Complete Revision All 10/88 8

Information Update-complete Revision All 12/89 and title change from "WVDP Long-Term Radioactive Waste Management Plan" to

" Annual Waste Management Plan".

9 Information Update-Complete Revision All 02/91 10 Information Update-Ceneral Revision All 12/91 WV-1607A, Rev. O i

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t WDP-019 Rev. 10 RECOND OF REVISION (CONTINUATION SHEET)

Revision on Rev. No.

Description of Changes Page(s)

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i WVDP-019 Rev. 10 TARLE OF CONTENTS PME A.

EXECUTtVE

SUMMARY

1 B.

GENERAL SITE INFORMATION 5

1.

Organization and Administration 5

2.

Site Description 5

C.

RADICACTI%t AND MIXED WASTE MANAGEMENT 7

1.

High-Level Waste 7

4.

Overview and Background 7

b.

Current and Projected Inventories 8

c.

Status of Operations 8

2.

Transuranic Waste 9

a.

Overview and Background 9

b.

Current Problems and Issues 9

3.

Low-Level Waste 10 a.

Overview and Background 10 h.

Current Problems and Issues 12 4.

Mixed Waste 13 a.

Overview and Background 13 b.

Status of Operations 13 c.

Problems and Issues

'4 D.

RAEARDOUS WASTE MANAGEMENT 14 1.

Overvlaw and Background 14 2.

Status of operations 14 3.

Current Problems and Issues 15 E.

COST AND SCHEDULE

SUMMARY

15 1.

High-Level Waste Vitrification 16 2.

Low-Level and TRU Waste Handling (Including IRTS) 16 F.

ENVIRONMENTAL MONITORING 17 1.

Overview 17 2.

Nonradiological Monitoring 19 3.

Radiological Monitoring 19-4.

Special Monitoring 21 5.

Problems and Issues 26 111 RLA0265:R6

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4 WVDP-019 Rev. 10 L

TABLE OF CONTENTS CONTINUED G.

RELATED SUBJECTS 26 1.

Quality Assurance 26 2.

Personnel Training 26 3.

Tect.nology Demonstration 26 4.

Waste Manager ^ent Data Base 27 5.

Decontamination and Decommissioning Programs 27 6.

Environmartal Impact Statement Status 28 H.

REFERENCES 29 1.

Waste Management Documentation (References) 29 iv RLA0265:R6

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WVDP-019 Rev. 10 L!sT OF TARLES Table EAHA 1.

Major Pinnned Activities 33 2.

Summary of 'faste Management coe*.s 34 3.

WVDP 1990 SPDES Non Compliance Episodes 36 4.

Summary of Monitoring Program Changes Implemented in 1990 36 I

LIST OF FIGURES figure Eagg 1.-

WVDP Summary Project Schednle 37 2.

W9st Valley Project office organization (DOE) 38

'3.

WVHS organization 39 4.

Site Location of WNYNSC 40 3.

WVDP Site Plan 41 6.

West Valley Conceptual HLW Removal system 42 7.

West Valley Demor.stration Project Waste Streams 43 8.

Process of HLW Vitrification for WVDP 44 9.

HLW/LLW Process overview 45 7

10.

Simplified Process Flow Diagram 46 11.

RTS Orum Cell 47 12.

WVDP Decontaminction Activity 12-87 48 V

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WVDP-019 Rev. 10 APPrJtDICES APPENDIX At Program Schedule status (5820.2A Implementation Plan Status)

A-1/A-13 f-APPENDIX Be WVDP Waste Volumes in Storage As of B-1 November 15, 1991 APPENDIX Ce Low-Level Waste System & Facility Description C-1/C-5 APPENDIX Di 1990 Effluent on-Site and Off-site Honi*oring Program D-1/D-31 APPENDIX El Acronyms E-1/t 3 t

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WVDP-019 Rev. 10 ANNUAL WASTE MANAGEMENT PLAN A.

EXECUTIVE

SUMMARY

In May of 1963, the Atomic Energy Commission (AEC), under authority now vested in the Nuclear Regulatory Commission (NRC),-issued a permit authorising construction of the Western New York Nuclear Service Center.

The site and the principal facilities are the property of the State of New York.

Construction was completed in early 1966, and on April 19 of that year, the AEC issued a license to the newly formed Nuclear Fuel Services, Inc. (NFS), as operator, and the State of New York as owner, by and through a predecessor of the New York State Energy Research and Development Authority (NYSERDA), to reprocess fuel from both commercial and federally owned reactors. The first term of the lease between NYSERDA and NFS terminated at the end of calendar year (CY) 1980.

In 1972, while the plant was closed for modifications and expansion, more rigorous federal and state safety regulations were imposed. Most of the changes were aimed at the disposal of high-level radioactive liquid waste and at preventing earthquake damage to the f acilities.

Compliance with the new regulations was deemed not economically feasible and in 1976 NFS

. notified NYSERDA that it would not continue the fuel reprocessing operations. New York State (NYS)- requested that the Federal government take over operation and maintenance of the Center.

In 1980, Congrees enacted Public Law No.96-368, the West Valley Demonstration Project (WVDP) Act, which mandated the demonstration of technology for solidification and disposal of the liquid high-level radioactive waste (HLLW) that was produced by commercial fuel reprocessing at the center.

The WVDP Act required that containers suitable for transport and disposal of the high level waste (HLW) be developed, along with provisions to dispose of the low-level (LLW) and Transuranic (TRU) wastes resulting from solidification and vitrification of the HLW.

Also, the Act required the cleaning of tanks, facilities, materials, and hardware used in connection with the project.

In February 1984, the U.S. Department of Energy (DOE) Order 5820.2,

" Radioactive Waste Management," established policies, guidelines, and minimum requirements for managing radioactive and mixed wastes and -

contaminated facilities.

The revised order, DOE order 5820.2A, issued in September, 1988, reflects the DOE determination to provide more prescriptive requi tions for managing DOE wastes, much like counterpart regulations promulgated by the NRC and the Environmental Protection Agency

-(EPA).

Section 8.d.

(1) of DOE Order 5820.2A defines applicability of the order to WVDP operations under responsibilities of the Office of Assistant Secretary for Nuclear Energy (NE-1).- Hazardous and mixed waste operations at the WVDP are performed under regulations issued by the EPA and the New York State Department of Environmental Conservation (NYSDEC).

The WVDP submitted the Part A Resource Censervation and Recovery Act

-(RCRA) Interim Status permit application for the storage and treatment of hazardous wastes to the EPA and NYSDEC on June 4, 1990.

This was submitted in response to RMW becoming subject to the hazardous wasta regulations when NYS received authorization to regulate RMW under its hazardous waste program (effective June 6, 1990).

The WVDP is currently RLA0265:R6 1

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l WVDP-419 Nev. 20 negotiating a Federal and State Facilities Complianeu Agreement (FSFCA) with the regulatory agencies in addition to a RCRA 3CC8th) Consent Ordert.

1 Phase I includes the procassing of the HLLW, solidifluation of the HLW sludge, development of the glass containers, and dacontamination pt existing facilities required to support the solidificatien activities.

Phase I also includes the nogetiation of the FSFCA, T.nD and LLW management, facility operation and maintenance. To provide a logical, j

smooth transition to Pnase II-Pont 3olidification, negotiation of a RCRA 3008(h) Consent order, the FSECA, site characterization, National Environmental Policy Act of 1969 (NEPA), and initial strategic planning documentation have been initiated in Phase I.

Phase II includes activities associated with transport of HLW cantaters to a federal repository, dispostl of LLW and TRU Waste, and Decontamination and Decommicsioning (D&D) of equipment, tanks, hardware and facilities used in connection with the solidificati a procese.

HLW generated during operation of the NFS Reactor Fuel Ruproccasing i

Facility (RFRF) will be blended and vitrified into borosilicate glars, and l

contained in stainless steel canisters. This glass form is subject to a f ormal waste acceptance and cert ification program in accordance with

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requirements set forth by the DOE's Office of Civilian Radioactive Wasta j

Management (OCRWM).

LLW generating activities at West Valley have been primarily associated with the treatment of supernatant from the HLW tanks.

This liquid has been processed through lon-exchange coAumns and evaporators and is cement solidified in.27 m' (71 gallon) drums. Thia processed waste is classified as Class C LLW and is stored in the Radioactive Waste Treatment System (RTS) Drum Cell.

Other LLW streams at the WVDP result from plant work and conrist of compactable trash, construction mater'.als, ano equipment.

These forms of 1

LLW are treated by compaction and ef te-reduction, as appropriate, and placed in storage in the LAG Storage Area (LSA).

Alao, wastewater sources from plant drains, surface runoff, cooling tower blowdswn, the New York State (NYS) disposal. area, the NRC Licensed i

Disposal Area (NDA) and the laundry are currently treated by the existing Low-Level Wasta Treatment Facility (~LWTF).

TRU wastes have primarily resulted from past D&D activities at WVDP.

Currently, no D&D activities are being performed.

LLW was formerly disposed of by shallow-land burial within the WVDP boundaries; however, this was suspended in Fiscal Year (FY) 87, as a result of litigation by the coalition on West Valley Nuclear Waste (Civil No. 86-1052-C).- The out-of-court settlement stated that LLW could be disposed of on-site if the NEPA Environmental Impact Statement (EIS) i process is completed, or if NRC reviews and approves of the dirposal I

methodology.

An EIS submittal in 1982 fulfilled the mandate for HLW solidification, but did not address LLW disposal options.

Currently, an EIS Implementation Plan has been wiAtten that focuses on both on-site and off-sito disposal of waste at the KVDP.

However, there is a significant issue regarding the definition of TRU waste, and the NRC has advised the West Valley Project Office (WVPO) that the TRU waste definition must be affirmed in the EIS process.

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L WVDP-019 Rev. 10 rederal Register Vol. 53, No. 251, Friday, December 30, 1988, published a Notice of Intent for the DOE gnd NYSERDA to prepare an EIS.

The scope of r

this EIS includes potential impacts to the general public and on-site l

workers, the onvironment (land use, commitment of resources, erosien),

waste disposal on-site and off-site, concontration limits for TRU disposal, characterisation of previously disposed waste, interim storage of wastes at other locations, transportation to interim storage facilities or final repositories, D&D of facilities, and post closure maintenance and ronitoring.

The EIS process will identify alternative courses of action and associated potential impacts for WVDP related to the above topics, and allow for decisions to be made based on technical analyses and public input.

In April, 1989, WVDP issued the DOE order 5820.2A Implementation Plan that identified-areas of noncompliance. There is a requirement that noncompliance items be tracked and statused in.the Annual Waste Management Plan update.

This status is provided in Appendix A.

During 1991 W"DP established an objective, with the DOE, to develop a joint strategic plan for waste management.

A draft document " Waste Managemont Strategic Directions" has been developed and will serve an a roadmap to guide WVDP actions and measure progress in the areas of waste minimization, waste characterization, waste treatment, waste storage, and waste transportation and disposal.

Through 1991 approximately 80 percent of the supernatant in tank 8D-2 has been removed and approximately 10,400 drums of LLW have been produced for storage in the RTS Drum Cell The supernatant processing phase is complete. The remaining supernatant will be processed during the sludge washing phase (see Section c.1.c).

During 1991, construction of two new engineered fabric storage structures was completed.

Storage of LLW in these structures began on June 18, 1991.

Volume reduction of LLW continued during 1991. More than 555.8 m8 (19,624 f t') of pipes, equipment, vessels, and miscellaneous plant wastes were size reduced and placed into storage.

Significant progress was made during 1991 toward the remediation of processed LLWTF sludge drums located in storage.

Due to ineffective mixing, these drums have experienced raw sludge areas which cause liquid and sludge leakage.

These drums were overpacked during 1991 to ensure double containment.

Also, a 24 drum characterization / demonstration program was performed using physical segregation of the processed sludge drums.

This demonstration provided information used to establish a procedure for the safe-

'remediation of these drums. Approximately 220 drums are to be included in a production remediation effort using physical segregation.

This effort is scheduled to be completed by May 1992.

Investigations were msde during 1991 to determine the feasibilitft)y for removing radioactive contaminants from approximately 110,000 of soil stored on-site.

Soil washing technology may be applicable but has not been proven on clay type soils which comprise approximately 35 percent of our dirt inventory.- Waste Engineering has recommer.ded soil storage while continuing to monitor technology developments in this area.

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1 WVDP-019 Rev. 10 Two (2) vendors requested and received contaminated soil samples to perform R&D testing at their own expence. One of these vendors has provided WVNS with preliminary data resulting from their R&D efforts.

Fending a review of this data an on-site vendor presentation will be made to the W7DP.

Waste Management alternatives ter the treatn.ent/ disposal of radioactively 4

contaminated oil were also investigated.

Filtration / centrifugation processing and incineration options were evaluated during 1991.

Our current inventory of contaminated oil occupier a 300 f t' storage space which could effectively be used for the storage of other materials.

Authorization was received to pursue the incineration of oil during 1992.

r During 1991 cost estimates for a Waste Treatment and F.umediation. Facilat+

were refined to incorporate currently planned preliminary facility layouc features.- It is anticipated tnac work on this facility will be initiated during 1992 so as to insure proper packaging, characterization and storage t

of radioactive waste.

In 1991, eight samples of sludge were obtained through the High Level Waste Tank 8D-2 M-4 riser.

The first sample was taken in July and the final of the eight samoles was taken in September.

A total of 1260.94 grams of sample were removed from the tank and transferred to the Analytical Labs for sludge-waeh analysis, i

During 1990, the WVDP installed an interceptor trench (approximately 800 feet long) between the boundary of the NRC Licensed Disposal Area (NDA) and Erdmann Brook. The purpose of this trench is to intercept any liquid l

migration which might be. occurring along ganglia (stringers) or through

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fractures in the weathered till.

The liquid collected by the interceptor I

trench is a mixture of water and small amounts of solvent contaminated with radionuclides. The solvent, n-dodecane with up to 30 percent tributyl phosphate (TBP), was used to recover fissile material when the NFS fuel reprocessing plant operated from 1965-1972.

A Liquid Pretreatment System (LPS) has been assembled in the NDA Sprung Structure.

This system will process liquids recoved from the trench.

(see Section F.4)

Work on the LPS for the interceptor trench was completed on Octcber 21, 1991.

This work included installation of $systam cumponents, inspection by a consultant for compliance with NYS regulations, training of system operators, and operational testing of the system.

The readiness review and NYSDEC inspection of the system are scheduled to be completed in early 1992.

Information on Radioactive Mixed Waste and Hazardous Waste is provided in sections C.4. and D. of the this report.

l Figure 1 provides the WVDP Summary Project Schedule for long-term project i

actions.

Table 1 provides a c immary of Major Planned Activities for WVDP over the next several years.

Cost and schedule information contained in this plan is based on information presently used for planning purposes. This information is subject to change due to budget and acheduling modifications / approvals.

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WVDP-019 Rev. 10 B.

GENERAL SITE INP,QRMATION l

1.

QIcaningtion and Adminia.tration Responsibility for successful implementation of the WVDP lies with the U.S. Department of Energy, Idaho Field Office (DOE-ID); Assistant Manager for Nuclear Programs; and the Director, WVPO.

The West Valley Nuclear Services Company Inc. (PVNS), a wholly owned subsidiary of Westinghouse Electric Corporation;is the prime contractor and site operator under contract DEAC0781NE44139.

All waste generation and daily operational activities are controlled by the contractor. _The WVNS Master Records Center (MRC) is responsible for maintaining up-to-date copies of all reference materials including this Annual Waste Management Plan.

The WVDP Act of 1980, directed the DOE to carry out a high-level radioactive waste management demonstration project at the WVDP site.

The Act dironted review, consultation, and monitoring by the NRC to identify any potential radiological danger to public health and safety.

In addition, the WVDP is subject to NRC requirements for final D&D of tanks, facilities, material, and hardware used in connection with the project, runding for waste management is appropriated through project sources.

Phase I of the WVDP is funded ninety (90) percent by the U. S-DOC and ten (10) percent by NYSERDA.

The U.S. DOE-ID has been assigned the responsibility for implementing the WVDP Act.

U.S. DOE-ID has established a project office (WVPO) for the on-site administration of the project.

Since the State of New York is the owner of the sies and is required by the Act tc participate in the funding cf the Project, a cooperative Agreement between DC3 and NYSERDA has been established (DOE /NYSERDA, 1981). The State is represented on-e.ite by NYSERDA. The Act requires the U.S.

DOE to consult with the U.S. NRC concerning the substantive aspects of the project; and U.F. NRC approval of the final D&D' Plan, to bu

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implemented upon enmpletion of the Project, is required.

The Act also requires the U.S. DOE to consult with the U.S. Department of Transportation (DOT), the U.S. EPA, and the U.S. Geological Surv./

(USGS) in matters relating to their respective areas of expertise and concern.

The EPA and NYSDEC are also consultaa for review and approval on matters of environmental concern.

Dames and Moore (D&M) provides geotechnical, environmental, and safety assessment services i

for the Project as a subcontractor to WVNS.

Ebasco Services Inc., and Societs Generale pour les Techniques Noavellos (LCN) have been retained by WVHS for design services.

The project also consults with and is engaged in technology transfer on a national level with the Defense Wasto Procesking Facility (DWPP), and on an international level with German, French, and Japanese nuclear program organizations.

The DOE's WVPO organisation is shown in FAgure 2 and Figure 3 provides the WVNS organizational Chart.

2.

Site Descriotion The Western New York Nuclear Service conter (WNYNSC) is located in cattaraugus County, a rural area about 50 km (30 miles) southeast of Buffalo (figure 4).

The communities of heet valley, Riceville, Ashford Hollow, and Springville are located within 8 km (5 miles) oi RLA0265:R6 5

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WVDp-019 Rev. 10 the center. Average population density ci cattaraugus County is 25 person s /km', with the closest population center being Springville with approximately 4,300 people.

The center's 3345 acre facility (rigure 4

5) includes the shutdown commercial nuclear fuel reprocessing plant, a spent nuclear fuel receiving and storage f acility, disposal areas for solid radioactive wastes, and underground tanks containing liquid high-level radioactive wastes.

i The WNYNSC lies within the northeastern deciduous forest biome, and the diversity of its vegetation is typical of the region.

Equally divided between forest and open land, the site provides habitats especially attractive to white-tailed deer and various birds, reptiles, and small mammals indigenous to the ragion.

No endangered species are known to be preeent on the site property.

The land immediately adjacent to the WNYNSC is used primarily for agriculture and arboriculture.

Cattaraugus Creek to the north serves as a water r3 creation area (swimming, canoeing, and fishing).

Althougn limited irrigation of adjacent golf course greens and tres farms is taken from Cattaraugus Creek. no public water supply is drawn from the creek downstream of the WNYNSC.

The average annual temperature in the region is 7.2'c (45.07) with recorded extremas of 37*C (98.67) and ~42*C (-4 3. 67 ).

Rainfall is relatively high, averaging about 104 cm (41 inches) per year.

Precipitation is evenly distributed throughout the year and is markedly influenced by Lake Erie to the west and Lake Ontario to the north. All surface drainage from the WNYNSC is to Buttermilk Creek which flows intetCattaraugus Creek and ultimately into Lake Erie.

Regional winds are predominately from the west and south at over 4m/s (9 mph) d'aring most of the year.

g The geology of the site is characterized by glacial deposits of varying thickness in the valley areas underlain by sedimentary rorks which are exposed in the upper drainage channels in hillside.'.

The soll is principally silty till consisting of unconsolidated rock fragments, pebblea, sand, and clays.

The uppermost till unit is the Lavery, a very compact gray silty clay.

Below the Lavery till is a more granular unit referred to as the Lacustrine unit comprised of silte, sanda, and in some places, gravels which overlie a verve clay, r

7here are two aquifers in the site area.

The upper aquitur is a transient water table aquifer in the upper 6 m (20 feet) of weathered till and alluvial gravels concentrated near the western edge of the site.

High ground to the wait and the Du*.termilk Creek drminage to the east intersect this agaifer, precluding off-site continuity.

Several shallow, isolated, water-bearing strata also occur at various i

locations within the site boundary, but do not appear to be continuous. The zone at which the till meets bedrock forms another i

aquifer that ranges in depth frota 2m (6 foot) underground on the hillsides to 170m (560 feet) deep just east of the boundary of the facility exclusion area.

Undet the WVDP Act, ifYSERDA trars* erred custody of the " Project Premisco", to the DOE.

The Project Premisas consist primarily of the j

200 acre complex of facilities which were constructed and operated by

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NFS to reprocean sp?nt nuclear fuel.. Approximately 4,300 m (1$1,350 f t') of lower activity s411d LLW generated in conjunction with the NFS reprocessing activity were disposed of by challow land burial in an area referred to as the NDA.

DOE operations, in preparation for HLW supernatant reprocessing, have also used the NDA for disposal of plant RLA0265:R6 6

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I WVDP-019 Rev. 10 waste from 1982 to 1986. The NYSERDA retained possession and the right to use the ' Retained Premises", which comprises the remaining portion of the 3345 acre facility.

This includes the State Licensed Disposal Area (SDA), which is adjacant to and in the vicinity of the NDA.

The SDA was used for LLW disposal from colleges, hospitals, J

state institutions, power plants, and some NFS plant waste.

Approximately 67,000 :a' (2,366,038 f t') of waste was disposed of by shallow land burial from 1963 to 1975.

The SDA has not been used for disposal since 1975.

At presort, HLLW is stored in underground tanks, 8D=2 and 8D-4.

Tank 8D-1 is-a spare tank for SD-2 (The general design concepts of these tanks are shown in Figure 6), and tank 8D-3 is a spare tank for 8D-4.

Tanks SD-1 and 8D-2 are carbun steel tanks inside of concrete vaults and 8D-3 and BD-4 are stainless steel tanks, both inside of the same concrete vault.

All of the HLW storage tanks have systems in place for monitoring tank leakage.

TRU wacte has primarily been gtnerated from decontamination of plant cells in the processing LJilding. This TRU Waste is Contained in Type A containers,.21 m ' (55 gallon) 17 C drums and 1.98 m8 (70 f t')

boxes and has been classified and assayed.

It is placed into LAG Storage for storage until a disposal site is availabin and a waste certification plan can be implemented.

LLW stroons result from plant work, construction, decontamination activitier, and additional 11guld weste processing.

These wastes are stored in the LAG Storage S; stem.

Figure 7 provides an overview of all waste streams present at the WVDP (supernatant process, plant wasts, TRU waste, including Remote Handled (RH) TRU, and HLW).

Figure 8 illustrates the matn process syntam being developed at the WVDP to vitrify the HLW for permanent disposal.

Figure 9 provides a HLW and LLW overview resulting from the proceJaing of the HLW tanks.

C.

RADIOACTIVE AND MITED WASTE MANAGEMEEI 1.

Hich-Level wastg a.

Qyerview and BackaLQMDd Cn April 19, 1966, NFS, Inc. was licensed by the AEC to reprocess both commercial nuclear power reactor fuels and defense production reactor fuels at the WNYNSC.

In 1972, the facility was shut down for modifications, and never resumed operations.

During the six year period of operation, approximately 2,200,000 liters (580,000 gals) of HLW was generated as a result of the reprocessing activities. This waste is being stored in underground tanks.

Specific agreement requirements between DOE /NRC and DOE /NYSERDA are prescribed in-the WVDP Act.

These agreements arw iniplemunted and amplified in a Memorandum of Understanding (Mou) between DOE and the NRC executed in September 1981, and in a cooperative agreement between DOE-and NYSERDA executed October 1, 1980, and amended on September 18, 1981.

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WVDP-019 Rev. 10 f

The project scope for HLW activities are called out in the WVDP Act, and carried forth by the aforamentioned agreements includes o Solidification of the HLW currently stored at West Valloy in a form suitable for transportation and disposal.

l o Preparation of the project premises and facilities to accommodate these efforts, including decontamination of facilities and equipment.

o Development of containers suitable for permanent disposal of the HLW.

o Transportation, as soon as feasible, of the solidified and containerimed waste to an appropriate Federal waste management

facility, o D&D of the tanks and other hardware and f acilities used in carrying out the WVDP.

o Disposal of tne TRU and LLW waste produced in the solidification and vitrification efforts, b.

Current and Proiected Invent 2I111 Approximately 2.44 million liters (643,$06 gallons) are currently in HLW tanks 8D-1, 8D-2, and 8D-4, distributed as follows:

BD-1 226,288 qallong 8D-2:

402,218 gallons 8D-4:

15,000 gallone Tank 8D-2, which contains pludge from the reprocessing activities and water (supernatant) from plant decontamination efforts and reprocessing activities, has a capacity of approximately 2.73 million liters (720,000 gallons) and currently is storing about i

1.52 million liters (402,200 gallons).

Tank BD-2 levels have been increased by the addition of water from flushing the downstream decontaminated supernatant (LLW) storage tanks.

In addition, 10,000 gallons of concentrated caustic (sodium hydroxide) solution and 45,000 gallons of demineralized t.eter have been added to 8D-2 from sludge washing.

These volumes arm included in the totals listed above.

Tank 8D-4 is full,. isolated from further inflow, and contains Thorax waste. The vitrification process to begin in 1996 will result in emptying 8D-4.

1 Under the present scope of the WVDP, potential sources of HLW forais may bo 9 -atated from future decontamination operations of plant systems at.o CPC waste stored in the Waste Starage Area (WSA).

c.

Status of operations i

Supernatant in tank 8D-2 has been processed in an ongoing operation known as the Integrated Radioactive Waste Treatment System (IRTS),

which is discussed in more detail in the chapter on LLW, and in-I appendix C.

To date, approximately 2.32 million liters (613,000 gallons) of supernatant have been processed. The processed supernatant is reclassified as Class C LLW and is cement solidified l

into.27 nd (71 gallons) drums.

These drums are then stored in the RTS Drum Cell.

l I

i RLA0265:R6 8

l

_- ~

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4 I

WV0P-Olt Rev. 10 The supernatant processing phase of the project is complete and t!.e r

sludge washing phase has begun with the addition of caustic and water to SD-2.

The water / caustic /supernatant liquid in 6D-2 will be treated by ion exchange to remove Cesium 137, the most prevalent radionuclide.

The spent ton exchange media is retained in du-l.

The solution will be mixed with cement, solidified in 71-gallon drums, classified as LLW and stored in the RTS Drum Coll.

The sludge will then be combined with the cesium-loaded reolite resulting from processing the superaatant and the Thorex waste frota tank BD-4.

This total volume (approximately 171,000 liters (45,000 gallons)) will be blended and then slurry-fed to the vitrification facility, which is presently under construction.

There it will be concentrated, blended with glass-forming chemicals, and transferred to a Slurry Ted Ceramic Malter (SFCM).

This melter will operate between 2,000 and 2,200 degrees r, prodiscing molten glass.

The molten glass will be poured into stainless steel canisters, which will the; be sealed by welt.ng, decontaminated, and stored in the fcrmer Chemical Process cell (CPC) awaiting shiptnent to a rederal waste management facility.

Equipment and components were removed from the CPC during Phase I D&D (section 0.5).

Storage racks far storage of stainless steel canisters are scheduled to be placed in the CPC beginning in early 1992.

After the soliditication campaign has been completed, the facilities will be decontaminated and decommissioned.

t It is currently planned for the vitelfication racility (vr) to start hot operations during the second quarter of FY96.

In the near future, the melter used for test campaigns will be disassembled, examined and analyzed, and the equipment to be used for hot operations will be installed in the VP.

Additional Cost and Schedule information related to HLW vitrification and storage are provided in section E.

2.

Transuranic waste a.

Qverview and Backaregnd TRU Waste at WVDP 've primarily been generated f rom decontamination efforts in the process building.

The WVDP has a system in place to classify and assay waste for TRU de:ermination, which includes a segmented gamma scanner, radionuclide analysis, and weight vs done 4

conversion program.

Contact Handled (CH) TRU waste is not being generated at this time, as in-plant. major decor,tamination efforts are not in progress. A small amount of RH TRU waste from the spent fuel pool water treatment system is being generated en a routine basis.

This waste is being stored in High Integrity Containers (HIC) in the ?RS.

Future D&D efforts, specifically those identified la the site closure plan, are expected to result in the generation of significaat amounts of TRU waste. Current waste inventories are shown in appendix B.

i-t b.

Current Problems and Issues 2

DOE Order 5820.2A defines TRU waste as a radioactive waste 4

contaminated with alpha-emitting transuranium radionuclides with RLA0265:R6 9

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WVDP-019 Rev. 10 half-lives greater than 20 years and concentrations greater than 100 nci/g.

The WVDP Act defines TRU waste as material contaminated with elements which have an atomic number greater than 92, including neptunium, plutonium, americium, and curium, and which are in concentrations greater than 10 nCi/g, or in such other concentrations as the NRC may prescribe to protect the public health and safety.

The WVDP currently uses NRC guidelines to classify TRU waste.

The NRC has advised the WVPO tha. the TRU waste definition must be affirmed in the EIS process.

Within the requirements of DOE Order f820.2A only TRU waste estegorized as Defense waste is acceptable at the Waste Isolation Pilot Plant (WIPP).

The WVDP TRU waste resulted from past reprocessing of spent tJels from both commercial and Defense sources.

Therefore, TRU waste is not precently scheduled to be ahipped to WIPP.

WVDP-030, Rev.

1, is the TRJ Waste Certification Progtam Plan for the WVDP.

This plan invokes some elements of the W*PP-WAC program, but does not implement all (sur i?.s such as data requirements, certification requirements, or wa.ne storage requirement s.

(See Appendix A, Pages 3-6 for additional information).

At present, significar.t amounts of TRU waste are not teing generated.

Appendix A provides a status of compliaace actions identified in the DOE Order 5820.2A Implementation Plan.

Appendix B prov!. des current TRU waste inventories in storage.

Major IRU waste poneration will not resume until Phase II D&D efforts begin.

Section E provides an identification of costs associated with TRU waste management at WVDP.

3.

Lgw-Level was(g 4.

Overview and Rackcround Between 1982 and 1986, the WVDP disposed of approximately 5786 m' (204,000 f t') (625 curies) of LLW in the NDA.

As the result of an out-of-court agreement with the Coalition on West Valley Nuclear Wastes and Radioactive Waste Campaign, LLW disposal at West Valley ceased in FY87 pending development of the site clogure CIS.

The WVDP is currently utilizing the.NRC waste classification system prescribed in Code of Federal Regulations (10 CFR 61) for Class A, B,

& C wastes.

In this regard, WVDP is unique in the DOE system, as waste programs are operated in accordance with DOE Orders, yet LLW in classified according to NRC regulations.

One significant LLW stream at WVDP has been the decontaminated supernatant from the HLW tanks.

Supernatant has been processed through the Supernatant Treatment System (STS), an icn exchange process, which reducts the radionuclide concentration of the supernatant to permit reclassifiestion to LLW, and is then

  • ransferred to the evaporative Liquid Waste Treatment System i

(LWTS). The evaporscor bottoms are processed through the Cement solidification System (CSS), which includes cement solidification into.27 m' (71 gallons) square drums.

Figure 10 depicts this process.

These drums are transferred to the RTS Drum Cell for storage.

Figure 11 provides a view of ths RTS Drum Cell.

The IRTS waste form meets all current NRC and EPA disposal criteria for RLA0265:R6 10 I

WVDP-019 Rev. 10 waste form acceptance. Approximately 10,400 drums are currently in storage.

It is anticipated about 15,000 proceused CSS drums will be in storage when supernatant processing and sludge washing are completed.

Evrporator distillate from the LWTS is transferred to an interceptor tank system, then to Lagoon 2, processed through the LLWTF, a clarifier / filter / ion exchange process, and then onto Lagoon 4/5 for subsequent sampling. When discharge / release criteria are met, the final effluent is discharged to the environment under NY State Pollution Discharge Elimination System (SPDES) permit through Lagoon 3.

Clarifier sludge from the LLWTF have been cement-colidified in the past; however, problems with past recipes and procedures have resulted in cessation of this practice. Analysis and evaluation is continuing to define potential alternatives to treat, store, and dispose of this waste.

This waste is currently being stored in LAG storage in dewatered, uncemented form, pending these evaluations.

Prior solidified drums have excess free liquid and also require further treatment.

Item 3.f.(1.), Appendix A, Chapter III, Low Level Waste, identified specific actions to address this matter. Appendix C provides further detailed discussion.

LLW that is generated during general plant work, which is compactible natorial such as rags, bags, clothing, and some wood items, is collected in polyethylene Dag lined drums and transported to a 50 ton box compactor.

It is then compacted into a 2.55 m' (90 cu. ft) B25 metal box equipped with anti-springback devices. A volume reduction of 4 to 1 is achieved with this compactor. The compacted waste is then placed in storage.

Class A compactible materials, which are packaged in.21 m' (55 gallons) drums, such as small diameter piping, sheet metal, and wood products, are prncouwed by a 1000 ton supercompactor.

The drum and its contents are pressed into a compaction sleeve and overpacked into a steel box.

A volume reduction of 5 to 1 is achieved by this method. Receipt criteria for both compactors exclude liquida, hazardous materials, pressurized containers, flammables, and pyrophories.

Class B/C cemented LLW, f run the CSS, long-term intertm storage in the RTS Drum Cell in.27 mis currently being (put into 71 gallons) drums. This facility is intended to be the interim storage site for Class B/C waste generated prior to a decision on

'teposition.

11 1 LAG Su rage Building and associated LSA's are areas enclosed ei.her by "hard" building (LAG storage) or engineered fabric m'ructuros. These facilities provide weather protection for

,ackaged Class A, and some Class B/C wastes that result from operations, decontamination, maintenance, and construction activities.

Packaged wastes identified as TRU or suspect TRU are stored in LAG storage. The LAG Storage Building also houses radiometric equipment to classify waste packages to the criteria of 10 CFR 61.55.

Want 3'ckaged and stored in the LAG storage facilities, incluce some cG.tp :ted wastes, liquid and wet wastes immobilized Ln ecment, equi e t and hardware, and contaminated soil and concrete.

RLA0265:R6 11 1

a 4

WVDP-019 Rev. 10 Additional storage areas are provided on outdoor gravel pads for

]

the storage of large 1+, ems, or items that are too heavy to move l

Leside.

The WSA is a fabric storage structure that ccntains high-radiation

]

items resulting f rom decont amination operations - in the CpC, which I

are awaiting further conditioning and volume reduction.

Also contained in this facility are concrete overpacks and boxes containing packaged waste which are used to provide shielding.

Appendix B prov. des currently stored LLW inventories.

App *ndix C provideo further detailed discussion of LLW treatment, stora9* and disposal facilities.

b.

Current Prcb1gis and Issues In addition to the accions defined above, the DOE $820.2A Implementatinn-plan of April, 1989, identified a number of actions in the LLW area (Chapter III of DOE 5820.2A).

Appendix A to this report provides an update on the status of these 5d20.2A Implementation Plan action items. Appendix B provided current inventories of wastes in storage.

1 WVNS has completed a waste stream overview characterization flow diagram.

During 1992 efforts will include a database upgrade to ensure maintenance of all required data. Also, a task force will

.be organi;ed in January 1992 to verify if adequate data is available for cach WVDP waste stream. The wasto st.eams will be analyzed to determine if chemical, physical, and radiological data is available for each stremn on the flow diagram. Application of this effort to waste already in storage will be a major effort with the potential need to provide a facility to open, sample, and repackage waste containers as part of characterization and certification.

Appendix A, Low Level Waste, Chapter III, Item 3.d.1 provides a discussion of this characterization program.

An additicaal key action identified in Appendix A is the development of a Waste Management Systems performance A tessment.

Costs for WVDP LLW operations are includdd in Section E.

In November 1983, radioactive solvent was detected in a monitoring well just outside the boundary of the NRC Licensed Disposal Area.

Stepped-up monitoring ef forts and extensive oite investigations were implecented immediately following the discovery, j

An extensive network of wells has been monitored continuously since the discovery of solvent in late 1983 and the response investigations in 1984.

Following the exhumation of aight 1,000 gallon tanks from Special Hole (SH)-10 and n3-11 in-1986 and the installation of wolla over SH-5, -27, -28 ** 4 -29, the monitnring results remained static until August 1988, who. solvent was discovered in a monitoring well next to SH-5.

This wall, which has been monitored since its installation in 1986, showed no prjor evidence of solvent.

During 1989, activities were performed to locate and install exploratory wells to yield information on the depths and RLA0265:R6 12

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WVDP-019 Rsv. 10 f.

orientation of tanks in the six special (burial) holes, contamination levels of the soils, dimensions of the special holes, and conditions of the fill soil.

1 In addition, direct eviden of solvent leakage was observed An j

four of the disposal holes.

i l

The wells, besides giving evidence of solvent leakene, also revealed that a significant quantity of water had infiltrated into the hc-i. This could ultimately lead to complete filling and perhapa overflow of the disposal hole.

During 1990, the WVDP installed an inttreeptor trench (approximately 800 feet long) between the boundary of the NOA and Erdraann Brook.

The yarpose of this ditch in to intercept any migration which might be occurring along ganglia (strincers) or through fractures in the weathered till.

A treatment system (LPS) has been assembled in the NDA Sprung Structure.

this system will process liquide temoved from the trench.

Work en the treatment system for the Interceptor trench was completed on October 21, 1991. This work included installation of system components, inspection by a consultant for compliance with NYS regulations, training of system operators, and operatione.1 testing of the system. The ORRD review and NYSDEC inspection of the system are scheduled to be completed in early 1992.

1 4.

RLand_ Waste I

a. SIRLYitw and Bachggg,gnd The NVDP submitted the Part A Resour";e Conservation and Recovery Act (HCRA) Interim Status permit apn11 cation for the storage and treatment of hazardnus wastes to the EPA and NYSDEC on June 4, 1990. This was submitted in response to RMW becoming subject to the hazardous waste regulations when NYG received authorisation to regulate RMW-under its hasardous waste program (effective June 6, 1990). The W7DP is currently negotiating a rederal and State Facilities Compliance Agreement (FSFCA) with the regulatory agencies in addition to a RCRA 3000(h) Consent order.

i b.

Status of_Ocerationg Two new waste structures huve been constructed.

RHW that meets the specific waste acceptance criteria of these structures will be permitted for storage. These waste acceptance criteria are scheduled to be devoluped by July, 1992.

LtW determined to be RMW based on testing are stored in the Interim Waste Storage racility

( WSF), or may be moved to the now waste structures.

Liquid RMW is currently stored at the IWSr.

T As of January 1991, 12 LLH storage boxes and 25 LLW storage drums were identified as containing lead as waste.

Lead in these boxes and drums was mixed with other LLW materials.

The= contents of 9

. boxes and 24 drums were inspected and segregated during 1991.

The lead found was segregated by form (shaot, brick, shot, blanket, etc.) and all individual placas of lead were measured (dimension, m'

usight) and radiologically surveynd. The lead was repackaged into

-four boxes-and 12 crums.

Eighty-five kilograms of radiologically clean lead was separsted out for use on-site.

The loud repackaging effort resultan in a reduction of appronimately 4,330 kilograms of radioactive mixed waste (RMW) and 618 cubic feet of RMW volume.

A program is in development for characterization of site wastes and identification of other mixed waste. (See Section C.J.b) i RLA0265$R6 13

. ~ _

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' MD P-019 Rev. 10 The largest sourch of RMW at the RVDP is the HLW as discussed in section C.l.

This waste is rendered non-hatardcus through treatment (CSS solidification).

c.

ELgthiams and Ism,ggg Due to the lack of commercial treatment f acilities per.altted to accept RXW, both the VVDP and the entire DOE complex have been forced to maintain these wastes in storage, though treatment of HLW is undsrway.

Negotiations are continuing between the WVDP and Federal and State regulatory agencies in an effort to resolve a number of permit issues related to RCRA interim atatus requirements and the Land Disposal Restrictions. For certaAn site-specific issues, such as container inspection for RHW, equavalency is being requested between hazatdous waste requirements, the As Low As Reasonable Achievable (ALARA) policy, and radiological engineerLng barriers.

These issues are expected to be resolved during 1992.

Current mixed waste inventorien are shown in Appendix 8.

(HLW inventories are not included, see Section C.1)

D.

HAZARDOUS WA$1g MANAGEMENT 1.

QyfIy,1gx_and Backaround The Hazardous Waste Menagement Plan, WVDP-073, governs the handling of nen-radioactive hazaraous waste at WVDP.

The Environmental Compliance Croup oversees regulatory aspecte of er.vironmental concerns at the WVDP.

This group ensures that project I

generators of hazardoas waste properly hanale, label, and classify their waste iccording to RCRA regulations.

The Environmental compliance Department also identifies required remedial accions if hazardous material releases were to occur.

A WVDP Environmental Training Matrin has been developed as a compliance vehicle to track mandatcry environmental, safety and health (ES&H) training requirements for all personnel who perform work at the WVDP.

The hazardous matarial waste training requirements are included within this matrix. To ensure compliance to the matrix, the WVDP Training / Development department will conduct deteiled self-assessments against the requirements.

This program satisfles the requirements of 4C CFR 2627 NYCRR, Title 6, Part 373; and 29 CFR 1910.120.

2.

Status of Orerations There is no on-site disposal of hanardous waste at the WVDP.

Hazardoun waste is shipped off-site for disposal by licensed and approved transporters to permitted commercial Treatment, Storage, and Dispoca; (TSD) facilities.

In 1991, there wnre 5 shipments off-site for disposal and one shipment off-site to recycling facilities.

On May 17, 1991, DOE-HQ established a " Hazardous Waste Moratorium" which has temporarily suspended hazardous waste shipments f rom WVDP.

As requested by DOR-HQ, WVDP furnished a 11storical Data Report" in September 1991 and An November 1991 submitted the "Demonstretion of Compliance Addendum with EM-331 Performance Objective."

RLA0265:R6 14 V

p.

(

WVDP-019 Rev. 10 On December 20, 1,91 the WVDP received notification from DOE-HQ that the moratorium had bnen-conditions 11y lifted. This response will allow the WVDP to resume hazardous vaste shipments under the new perfortaance objecths.

Transportation of hazardous wastes hes been and 'till continue to be le

(

accordance with standard Operating Procedure (50P) 300-3 (Off-site Transportation of Hazardous Waste), which ensures compliance with applicable DOT and EPA hazardous waste regulations.

{

lour free-standing structures are utilized for hazardous waste storage. These structures have been included in the WVDP's Inturim status Permit Application.

Operation of this facility is conducted in accordance with SOP 300-6 (Hazardous Waste Storage Facility ope ration).

Hazardous wastes generated on-site from defined waste streams are accumulated in 90 day satellite Accumulation Areas (SAAs) before I

transfer to the HWSF for storage prior to off-site shipment.

Hazardous waste is accumulated at the following SAA'es Location IM htC22fA Blueprint Area 20 gallen drum Ammonium Hydroxide 30 gallon drum Developer solution Darkroom 1 gallon poly various developer and containers rinse solutions Maintenance 55 gallon drum oily rage and wipes Hot Lab 4 litar glass Plutonium extract tottle waste cts Lab 10 liter poly Acidic wastes from bottle TCLP/EP toxicity tests Wastes are stored in the IWSF if sampling / analysis is required to determine the radiological and chemical classification of the wantos.

3.

purrent Problems and Issues Due to the redefinition of radiological characteriaation across the DOE complex,-the amount of radiologically uncharacterized containers in storage has increased during tre first half of 1991.

The number of cantainers becoring classified as mixed 'nante may increase and the cost for characterizing these containers may be affected.

E.

COST AND SCHEDULE StiMMARY Tho'following presents summaries of the schedulee and major milestones associated with waste management activities at the WVPP. Cost summaries associated with these schedules are found on Table 2.

RLA0265:R6 15

e WVDP-019 Rev. 10 1.

Mich-Level Waste Vitr:;ig11;ign I1:22

}

centinue modifications of former chemical Process cell to store HLW canisters from vitrification process.

Begin mechanical / electrical construction activities in the vitrification facility.

Prapare Safety Analysis Reports for Vitvificatios Facility and RLW Interim Storage Facility.

construction activities relevai.t to furthet progress on the Vitrification Facility include initiation of mechanical / electrical consLruction activities in the Vitrification Facility, continuation of f abrication and installation of jumpers, installation of the new melter, and continuation of canictor racks f abrication and d*' ivery.

Analysis Roports will be prepared for the Vitrification rac.,

y and the KLW Interim Storage racility.

II:ll Preparatiens for vitrification will continue, with activities including:

mechanical / electrical construction, EDR Loadout f acility desi.gn, completion of turntable modifications, and procurement of agitar, transfer cart, jumpers, and sludge transfer equipinent. The waste form qualifwJation activities will continue, component and subsyntem checkout will continue.

Procurement of sparce and supplies for vitrification checkout operations start.

Extended Schedule Ef f og,1;3 o

Cold operations and remote checkout for hot operations of the vitrification system will be completed during early FY-96.

The vitritication campaign will commence in the third quarter of o

FY-96.

c The vitrification campaign will be completed in +.he fouten quarter of FY-98.

2.

Low-Level and TR6 Wast.e Handlinn FIncl. IRTS)

IXi?2 Effective management of radioactive, hazardous, and mixed _ wastes will continue. Other waste form recipes will be devcloped and tested as waste streams become defined. Ongoing maintenance of a documentation system, which includer the WVDP Annual Waste Management Plan (WVDP-019) and that specifies criteria and plans for management of radioactive wastes from generation to storage and ultimate-disposal, vili coutinue.

NDA monitoring and waste sample analysis will continue to address the hazardous and mixed waste management _ concerns of DOE order 5820.2A.

I RLA0265:R6 16 i

I J

l~

y.

L WVDP-019 I

Rov. IL Operatienti elements include initiation of sludge wauhing and processing of sludge wash liquid through the Integrated Radwaste

'freatment System.

Continue management (i.e.,

collection, storage, and monitoring) of radioactive mixed waste.

Continue operat.Lon of the Site Reduction

{

racility ano supercompactor.

f.L.1A Effective management of radi? active, hazardous, and mixed wastes will continue. Other waste form recipes will be developed and tasted as waste streons becomo defined. Ongoing.naintenance of a documentation system, which includes the WVDP Annual Waste Management Plan (WVDP-019) and that specifies criteria and plat s for managonant of radioactive wastes from generation to storage and ultimate diepvaal, will continue.

HDA monitoring and waste sample analysis will continue to addtess the hazardous and mixed waste management concerna of DOE ceder $820.2A.

sludge wash operations and process of sludge wauh liquid through the IRTS continues.

Site operations continuea to be supported.

Managemmnt of radioactive mixed wastos and size reduction operations also continue.

Continue mane 2ement (i.e., collection, storags, and monitoring) of radioactive mixed waste.

Continue operation of the Site Reduction Facilit) and Supercompactor.

F.

E1WIPONMEtlTAL Mofq1pjlRQ 1.

Qyn yiew The environmental monitoring progrnm for the West vallay Demcastration Project began in Yebrus.ry 1982.

This program has been developed to detect any changes in the envir7ranent resulting from project activition and to ansess the effect of any such changes on the human population and the environment eurrounding the site.

This monitoring program addresses both the radiological and nonradiological environment.

Details and results of the monitoring program are available in the WVDP Site Environmental Monitoring Report for CY 1990.

T4 e 1991 report is now in preparation, but will not be available for use until the middle of 1992.

This monitoring program will be continued by the DOE until the WVDP is completed.

Continued operation of the monitoring program will be the responsibility of the State of New York for the,eriod of institutional control.

The WVDP operates within the radiological guidelines of DOE Orders

'for the protection of health, safety, and the environment. The Project did not oxceed or approach any of the limits on radioactivity or radiation doses in 1990, including the emission standards promulgated by the EPA and incorporated in DOE Orders.

RLA0265:R6 t

WVDP-015 Rev. 10 The LLWTF contributes most of the activity released from the site in liquid effluents through the Lagoon 3 weir.

The 1990 annual average liquid effluent concentrations of radionuclides were below DOE release guidelines at the point of discharge.

During this period, the average concentration of radionuclides prenant in thn Lagoon 3 effluent were less than 30% of release guidelinas.

The main ventilation stack (ANSTAC.5) eimpling sys"mm remained the most significant airborne effluent point in li?).

Variations in monthly concentrationa or airborna radioactivity reflect the level of Project activities with.a the facliity. However, at the point of discharge, average radioactivity levels were already below concentration guidelines for airborne radioactivity in an unrestricted environment.

Further dilution from the st.nck to the site boundary reduces the concentration by an average factor of about 200,000.

Effects of Project activities upon site groundwaters are regulated by NYSDEC and the EPA.

Groundwater sampling and analyses confirm that groundwater quality has been and continuee to be affected both radiologically and nonradiologically by past facility operations.

Increased well drilling and sampling activities in 1990 intensified the investigation of these effects.

Although definite radiological and nonradiological offects upon on-site groundwaters can be seen, these do not affect public health or the off-site environment.

I In 1990 there were nine instances when individual water qualit; parameters exceeded perritted levels. (Table 3)

Six of these l

deviations resulted from the sewage treatment plant operating beyond I

its rated capacity. One excursion was attributed to a minor upset that released solida slightly above the permitted limits. Another unrelated excursion of hicu iron content it. the low-level waste treatment system effluent rewulted from what is believed to be a natural tron buildup.

This condition is being evaluated to determine how the poi.e.'tial for its recurrento can be reduced.

In each case, appropriate actions were taken to stibilize the condition and to rotify NYSOEC in accordance with permit requirements. There i 4ations resulted in no significant effect on the environment.

-wm the sewage treatment plant operation is being modified to pror ce:urrences.

Several changes were mad. in the routine environnentEl monitoring program in 1990 as part of a continuing effort to improve existing monitoring points and in respor.ae to regulatory changes (see summary Table 4).

The Project's inodified SFDES permit expanded monitorir.g of location WNSP001, the primary point of liquid ef fluent batch release from the site, to include analyses for several additional chemical parameters.

{

To demonstrate compliance with DOE Order 5400.5, which was effective May 1990, monitoring of sanitary waste sludge from the sowage treatment plant for radiological parameters was added to the program.

The existing mon!.toring program was expanded by adding several sampling locations: a new outf all collection point on-site, new locations for collection of site drinking water, and an underdrain collection point to better monitor subsurf ce drainage in the high-level waste stomage and prvcessing area.

Additional enalyses of I

RLA0265:R6 16 i

l

WVDP-019 Rev. 10 samples from existing locations, tritium analysis of beef and dear samples, and uranium analysis of selected soil samples were added in the 1990 program.

One on-site surf ace water monitoring point was upgraded for automated sample collection. This point monitors surface waters draining from the Lag storage area, where additaonal waste storage buildings have been added and elevated monitoring needs are anticipated.

2. Nonradioloeical Monitoring Nonradiological p* ant affluents are regulated by the NYSDEC and the EPA.

New York State inspects nonradiological air emission points periodically alt's-ugh air effluent monitoring is not currently required because of the very limited discharges.

Nonradiological liquid dischargws are monitored as a requirement of the Stata Pollutant Discharge Elimination System (SPDES).

Liquid is dischargod at permitted outfalls or points of final release to surface waters.

Project effluents are monitored for biochemical oxygen demand (BOD), suspended solids, ammonia, iron, pH, oil and

- ease, and other water quality indicators. Monitoring indicated tt-non-radiological liquid discharges had no ef fect on the of f-site t an enment.

T3+ i 90 groundwater monitoring network included on-site wells for n

ruten 11ance of solid waste management units and off-site wells for d e;M't ng water monitoring. The on-site system of seventeen

.u-a.it

-ing points was expended in 1990 to 106 points. These welle prov,e ed upgradient and downgradient mcnitoring of the LtWTF lagoone, ob algh-level waste tank complex, the NDA, and other solid waste management units.

Nella comprising the existing on-site groundwater monitoring network. re each sampled eight times during 1990.

All new wells were developed to produce water suitable for analysis and several solid wasts management units ware sampled for a complete set of parameters. After initial physica.

Janurements at each well, samples were cellected and analyzed for a variety of radiological and water quality parameters. The range of analyses performed was determin by regulatory requirements and site-specific concerns or needs.

.stlatical tests were performed to identify significant dif f er' Fetween up and downgradient wells.

3.

Eag es

.1 Monitorigg The 1v90 environmental monitoring program provided radiological measurements of site ef fluent discharges and of related on-site and off-site samples. Analysis of animal, soil, ano vegetation samples from the facility environs provided data from which the risk of exposure to radioactivity through ingestion path.ays could be determined. Control or background samples were taken to compare with on-or near-site samples.

Radiation doses estimated from maximum consumption rates of locally produced foods are similar in mognitude to the values reported in previous years.

RLA0265:R6 19 l

l WVDP-019 Rev. 10 The dose assessment described in the 1990 Site Environmental Report predicts an insignificant impact on the public's health as a result of radiological releases from the WVDP.

Airborne particulate radioactivity was sampled continuously at five site perimeter and four remote locations during 1990.

Sample filters wars collected weekly and snalyzed for gross alpha and beta radioactivity.

Airborne gross activity around the site boundary was, in all cases, indistinguishable from background concentrations measured at the remote locations and was well below the DOE limitu.

Direct monitoring of airborne af fluents at the main plant stack and other permitted release points showed all discharges to be well below DOE or EPA effluent limitations.

The largest single er ce of radioactivity released to surface waters from the Project is tne discharge from the LLWTF through the Lagoon 3 weir WNSP001 into Erdman Brook, a tributary of Frank's Creek.

There were fcur batch releases totaling about 42 million liters in 1990.

The effluent was grab-sampled daily during the forty-four days of re; esse and analyzed.

Six automatic samplers collected surface water at locations along site drainage channels.

Samples were analyzed for gross alpha, gross beta, gamma activity, tritium, and strontium-90. Analyses of carbon-14, iodine, 129, and americium-241 were added to the program requirements for several sampling pointa.

As a result both of past site activities and continuing treated liquid releases, average gross radioactivity concentrations continued to be higher in Buttermilk Creek below the West Vslley project site than at the upstream background sample point.

Yearly average concentrations in water below the Project site in Cattaraugus Creek during 1990 were indistinguishable from background concentrations measured in Buttermilk Creek upstream of the Project facilities.

All Cattaraugus Creek concentration observed are well below regulatory limits.

Concentrations of Cesium-137, strontium-90, and tritium were below DOE guidelines at all locations, including Frank's Creek at the inner site security fence more than three miles from Cattaraugus Creek.

Direct environmental radiation was measured quarterly in 1990, as in previous years, using thermoluminescent dosimeters (TLD's).

Monitoring is carried out at forty-one points distributed around the site perimeter and access road, at the waste management units, at the inner facility fence, and at various background locations.

No significant differences were noted among exposure rates measured at background stations and the WNYNSC perimeter locations.

Some TLD data were aleo collected within the restricted area boundary to monitor the exposure from nearby radioactive waste handling and storage facilities.

Data from groundwater monitoring around the LLWTF lagoons indicate that radionuclides from past plant operations have affected groundwater quality. Compared to background both tritium and gross beta concentrations are elevated in groundwater surrounding the lagoon system. However, the level of tritium contamination has declined steadily since 1982, as indicated by measurements at the french drain outfall. Levels of gross beta activity appear to be rising slightly in some locations, as measured at the french drain outfall and at wells monitoring groundwater in the vicinity of the LLWTF lagoons (WNW86-03, WNW86-04, WNW86-05).

Other measured RLA0265:R6 20 l

~

m WVDP-019 Rev. 10 parameters such as pH and conductivity have shown significant differences between upgradient and downgradient locations.

Most notable are the sodium and chloride concentrations at the upgradient well (WNW86-06) within this unit.

It is believed that these elevated salt concentrations are due to migration from the sludge ponds located just upgradient of well WNW86-06, f

Data from monitoring wells around the high-level waste tanks do not suggest any effect of the stored high-level radioactive waste on the groundwater. However, significant radiological differences between upgradient and downgradient wells do indicate that previous site activities have affected groundwater in this area. Most notable are elevated levels of gross beta activity and greater-than-detectable concentrations of 1,1-dichlorethane at wells WNW86-09 and WNW86-12.

Groundwater monitoring around the NDA indicates no discernable effects on the deeper deposits in the area, as indicated primarily by measurements for tritium. However, one shallow well in *Se vicinity of the NDA (WNW82-4A1) has consistently shown elevated tritium levels.

In addition, continued organic solvent migration was detected in other shallow wells within the NDA.

Migration of contaminated solvent is currently the focus of a control and remediation effort within the NDA (see Special Monitoring).

The potential effect of Project activities on near91te groundwater is monitored by annual sampling of groups of designated private drinking water wells as well as by the on-site measurements. Monitoring of drinking water wells off-site continues to demonstrate that the site has had no effect on residential drinking water supplies.

4.

Soeelal Monitorina In November.983, organic contamination was enccentered in-USGS series-82 groundwater monitoring well near the NRC-licensed disposal area.

Waste organic solvent composed of n-dodecane mixed with tributyl phosphate had been buried in tanks when the NFS, Inc.

reprocessing facility had been operating. Wells were drilled from 1984 to 1986 to monitor and recover the solvent from the disposal area. The apparent movement of solvent away from the buried location in-1988 initiated more extencive monitoring and characterization of the area.

Changes in the organic sc1 vent levels that were obsertad in some wells monitored in November 1989 by the WVNS waste managdaent group -

renewed concerns of migration.

In D'acember 1989 nonroutine sampling of wells 85-I-9, 89-5-N, and 89-14-E was carried out to' determine the chemical and radiological makeup of the solvent-contaminated groundwater.

These wells are selected because they had exhibited increases in organic levels.

Samples collected from the wells were submitted for a variety of analysas including volatile and semi-volatile organics, pesticidea, PCBs, and tributyl phosphate. A sufficient sample volume collected from well 85-I-9 allowed for additional te ?ing.

Metals, biological and chemical oxygen demand, water quality, and selected radiological and nonradiological parameters were included in the analyses.

RLA0265:R6 21

WVDP-019 Rev. 10 Analytical results of an independent laboratory were presented in the 1989 Site Environmental Report. Their findings yielded results below analytical detection limits with only a few exceptions (see WVDP Site Environmental Report for Calendar Year 1989). Additional i

e positive results for a variety of unknown ecmpounds, mainly saturated hydrocarbons, were also reported. These findings support beliefs that the detacted compounds originated from the organic solvent used dur.tng reprocessing operations.

In response to the migrating organic solvent, an interceptor trench bordering the northeast and northwest boundaries of the NDA was

\\

installed in 1990. The trench, measuring approximately 250 meters l

(800 ft.) in length and having a maximum depth of 6.4 meters (21 feet), was const ructed over an eighteen-month period.

The purpose o' the trench system is to intercept and collect any organic solvent contaminated groundwater. Once in the trench, the contaminated groundwater will be routed to the LPS where solvent will be separated from the water and the water will be pre-treated to remove iodine-129. The remaining water will be directed to the LLWTF for further processing. The LPS is scheduled to be approved for operation in early 1992.

Monitoring of 85-and 89-series wells' continued through 1990 by the WVNS waste management group.

Wells are examined routinely for water and solvent level. Eeveral new 90-series wells located along the northeast corner of the NDA were sampled in 1990 for selected parameters, including analysis for volatile organics.

The results, as determined by a subcontracted laboratory, indicated no volatile organic contamination.

Monitoring of critical walls and liquid drainage to the trench will continue in an effort to track the migration patterns of the solvent contaminated groundwater.

The LPS will ba capable of handling an' estimated flow rate of 11 liters (3 gal.) per minute through the trench. This would result in an annual treatment of approximately 6 million liters (1.6 million gal.) of contaminated water.

The interceptor trench and LPS will be operated within the limits of DOE orders and other applicable state and federal regulations.

The system as a whole has been designed and is begin operated in such a manner as to prevent the spread of organic solvent into the surface j

waters of New YorA State.

The to!1owing descriptD wa of waste management units provide basic infbrmation about the super solid waste management units (SSRMUs) as detaile6 in the site's Sampling and Analysis Plan (SAP): Groundwater Monitoring Network (WVNS 1990). Monitoring wells were installed and well development was completed for all super solid waste management units (SSWMUs) during 1990.

f' SSWMU #1 - LLWTF l

The LLWTF is comprised of four active lagoons: Lagoons 2, 3, 4, and 5 l

and Lagoon 1, an inactive lagoon that has been filled in and coverei i

l Lagoons 1, 4,

and 5 were constructed in the surficial sand and gravel L

strata and Lagoons 2 and 3 penetrate into the Lavery till beneath the I

surficial sand and gravel.

Lagoons 4 and 5 have membrane liners.

a RLA0265:R6 22 I

1

a WVDP-019 Rev. 10 french drain (sampling point WNSP008) had been installed on the north and west sides of Lagoons 2 and 3 by the original operator of the reprocessing plant, NFS, in order to intercept and reduce groundwater seepage into Lagoons 2 and 3.

The drain consists of a 15-cm diameter perforated pipe buried approximately 3 meters below grade.

The drain

(.

extends almost to the top of the Lavery till and discharges to Erdman

(

Brook, east of Lagoon 3.

During 1990 SSbdU #1 was monitored by six existing wells, a ground seep, and monitoring point WNSP008.

Under the expanded monitoring network the seep, WNSP008, and the 86-series walls were combined with the twelve new 90-series wells for a more comprehensive monitoring program. This new monitoring system was sampled for selected contamination indicator parameters during December 1990.

SSWHU #2 - Miscellaneous Small Unita SSWMU #2 consists of four small facilities east of the southern end of the former reprocessing plant. They were grouped together as a super solid waste management unit because of their close proximity and because of the similarity of subsurface conditions beneath the units.

The individual facilities in SSWMU #2 aret The sludge pond, which contains domineralized tackwash sludges from the process plant water treatment system.

The sludge pond consists to two shallow, excavated beds in the uurficial sand unit.

The solvent dike, was used to catch and temporarily retain runoff frsm the reprocessing plant's solvent storage terrace. This unit has been closed and backfilled.

The effluent mixing basin, which receives mixed non-radioactive utility room and treated sanitary waste _ waters before discharge.

The paper incinerator, which was used to dispose of cartons received in the warehouse and general paper waste generated in non-radicactive areas of the facility.

Monitoring of SSWMU #2 will focus on the surficial sand and gravel layer and the till-sand unit.

The upgradient and downgradient wells used to monitor SSWMU #2 are shown in section 3.0,

" Groundwater Monitoring", of the 1990 Site Environmental Report.

SSWMU #3 - Liquid Waste Treatment System The LWTS contains decontaminated liquid effluent from the supernatant treatment system (SSWHU #4).

The liquid effluent from the LWTS is processed by the cement solidification system, producing a solid, low-level radioactive waste form suitable for disposal.

RLA0265tR6 23

WVDP-019 Rev. 10 The wwlls used to monitor SSWMU #3 are shown in section 3.0,

" Groundwater Monitoring *, of the 1990 Site Environmental Report.

Since monitoring of the two upper sand units (the surficial sand and gravel and till-sand) will provide evidence of a release, the lacustrine-kame delta deposits will not be monitored.

SSWMU #4 - High-level Wasta Storage and Processing Area The high-level waste storage (HLWS) and processing area includes the high-level radioactive waste tanks, the supernatant treatment system, and the vitrification facility.

The high-level waste is stored in underground steel tanks inside reinforced concrete vaults.

The vaults extend 40 feet below the surface into the Lavery till.

It is this high-level waste that will be processed into a stable, glass waste form.

The 1990 monitoring network used a series of four monitoring wells:

one upgradient well, WNW80-02, and three downgradient wells, WNW86-07, WNW85-08, and WNW86-09.

Two additional sampling locations (WNW86-12 and WNDMPNE) were monitored with this unit to provide comparisons with a representative upgradient well.

These additional locations monitor the former nonradioactive construction and demolition debris landfill (CDDL), which was closed in 1986.

The CDDL is now classified as a separate SSWMU in the new program.

The expanded monitoring network will phase out previously existing well WNW80-02 and incorporate eleven new welle for a total of fourteen monitoring locations.

SSWMU.#5 - Maintenance Shop Sanitary Leach P.i'ld Groundwater monitoring will focus on a former leach field once used by the plant's maintenance shop to proceas cewage that shop generated.

Two wells - one upgradient well (WNWO501) and one downgradient (WNWO502);- were added to this unit.

As the upgradient well is downgradient of many other super solid warte management units, the background conditions will be monitored by wells WNWO301 and WNWO401.

SSWMU #6 - Low-Level Waste Storage Area The LLWS includes metal and fabric structures housing low-level radioactive wastes being stored for future disposal. Currently the area contains one metal and five fabric storage structures.

Additional downgradient wells will be used from adjacent SSWMUs.

The area also includes the site of the old hardstand, which was used by NFS to temporarily store radioactive materials. The hardstand and r

the soils around it are still slightly radioactively contaminated.

SSWMU #7 - Chemical Process Cell Waste Storage Area I

The CPC waste storage area is a fabric-covered structure placed on a l

compacted gravel _ floor.

The CPC waste storage area contains packaged pipes, vessels, and debris from the decontamination and cleanup of l

l RLA0265:R6 24 l

L.

=

WVDP-019 Rev. 10 the chemical process cell in the former reprocessing plant that are being stored until they can be conditioned in the planned noncontact sazo reduction facility for eventual disposal.

Seven new 90-series wells will be used for this groundwater monitoring network.

Samples were collected from these wells for selected contamination indicator parameters during 1990.

f SSWMU #8 - Construction and Demolition Debris Landfill The disposal area was used by both NFS and WVDP to dispose of f

nonhazardous and non-radioactive materials.

There is no record of disposal of hazardous materials in this facility; however, there is also no evidence of waste acceptance precedures that would exclude them.

The unit was approved for closure by NYSDEC and closed in 1986 by a covering of a compacted clay till.

Four new 90-series walls will be used along with wells WNW86-03 and WNW86-12 to monitor SSWMU #8.

The new 90-series wells were sampled for selected contamination Indicator parameters during 1990.

y

.SSWMU #9 - NDA i

The NDA contains radioactive wastes gnnerated by NFS and the WVDP, including leached fuel assembly hulls and ends, sludges, spent solvents, discarded vessels and piping.and other miscellaneous items.

Groundwater monitoring-of the NDA will use eight of the new 90-series walls and two previously existing 86-series wells (WNW86-10 and WNW86-ll).

Background information will_be provided by wolle WNW1008b and WNW1000c. Upgradiant conditions will be monitored by three new 90-sortes walls. Locations of the walls are shown in section 3.0,

" Groundwater Monitoring *, of the 1990 Site Environmental Report.

SSWMU #10 - Integrated Radioactive Waste Treatment System Drum Cell The IRTS drum cell contains stored cement-stabilized low-level radic. active waste produced in the cement solidification system of the liquid waste trektment system (SCWMU #3).

In the future, cement-stabilized sludge wash water and cleaning water from the noncontact size reduction facility will be stored here.- This waste is currsntly classified as nonhazardous. The-new 90-series monitoring wells will sury '1 the groundwater-in this area.

SSWMU #11 - SDA The NYSDEC requested that the SDA be monitored.

This function is a NYSERDA project and as such is not part of the WVDP.

Twenty-one groundwater walls have been insta11cd to monitor both the weathered and unweathered till and the lacustrine deposits beneath the SDA.

The SDA was operated by Nuclear Fuel Services, Inc. as a commercial low-level disposal facility.

In addition to a' wide variety of utility, industrial, ard institutional customers, the SDA received a large volume of wastes from the NFS reprocessing operations. Between 1963 and 1975, 2.35 million cubic feet of low-level radioactive waste was disposed of in the SDA trenches.

RLA0265:R6 25

~

WVDP-019 Rev. 10 The groundwater aonitoring program for 1990 included sampling the twenty-one wells for gross alpha, gross beta, tritium, and ganima emitters. The full groundwater monitoring program for the SDA is planned to begin in mid-1991.

5.

Problems and Issues On-sito areas where soils could have been contaminated from past or present storage activities need to be characterized to determine if stabilization or near-term remediation is warranted.

This is a part of the Phase II Site Characterization program which is currently being implemented.

G.

RELATED SUBJECTS 1.

Qgality Assurance

(

The overall Quality Assurance Program at WVDP is established in accordance with ASME NQA-1 1989 and DOE /RW-0214, Rev.

4, and the current revisions of DOE Order 5700.6C, " Quality Assurance", and DOE-ID 5700.6C, " Quality Assurance" are being incorporated.

The Quality i

Assurance Program is defined in the WVNS Quality Assurance Program Plan (WVDP-002) which includes the Quality Management Manual (QHM).

Quality Assurance procedures are contained in the Quality Assurance a

Procedures Manual.

Departments at the WVDP involved in waste management are responsible for establishing and implementing policios and procedures which control the quality of their work in accordance with the QHM.

Responsibility for compliance to this plan and related procedures rwsts with all involved personnel.

2.

Personnel Training p

A formal waate managerant operator specific training program designed to comply with DOE order 5480.b has been established at the WVDP.

This program consists of an initial generic waste Management Qualification Standard, " Waste Management B",

which requires approximately four months to complete. -This training is followed by specific "A" operator training in one of five areas; RTS Drum Cell, Waste Management Storage Operations, Waste Management Handling Operations, Wasta Managecent Radiological Projects, and Hazardous Waste Operations.- Each of these specific qualification standards require 6 to 9-months to complete which includes 2 to 3 months on-the-job training (OJT). All of this training is defined in qualification standards that prescribe testing requirements, annual refresher training requirements, and requalification requirements every 2 years.

3.

Igchnoloov Demonstration Two areas in the West Valley Waste Management Program are appropriate for discussion as technology development efforts.

RLA0265:R6 26

WVDP-019 Rev. 10 First, _the vitrification of RLW (the primary project mission) is undergoing a continuing process of testing and evaluation in conjunction with the NRC and the DOE OCRWM to ensure that the w& ate form and the canister meet the specifications for ecceptence at a f

Federal Waste Panagement Facility.

International experience in waite

}-

solidification from the Federal Republic of Germany, France, and Japan have been factored into this development program.

Waste pledge mobilization experience from savannah River Plant and Har. ford have also been integrated into project development.

A second related technology demonstration process developed at WVDP is that of the treatment and solidification of supernatant from the HLW storage tanks. This overall IRTS produces a cement -solidified I

waste form contained in.27 m (71 gallons) drums, which meets current 2

EPA and NRC waste disposal requirements, as Class C low-level waste.

The RTS Drum Cell is the storage facility for the.27 m' (71 gallomst drums.

Future plans include evaluation of thin facility as a j

tumulus-type final disposal system.

1 The IRTS process is described in detail in Appendix C of this report.

4.

Waste Manacement Da* _ Base The data bar.a developed at the WVDP has provi(ed input to the DOE Integrated Data Base (IDB) Program starting in FY85.

The 1989 data base information for WVDP has been upgraded and transmitted to Oak Ridge National Laboratory.

The WVDP uses a computerized waste inventory system to manifest waste package data with the physical and chemical characteristics of all waste, volume of waste, weight of waste, and major radionuclides and their concenttations. This program will characterize waste with sufficient accuracy to permit proper segregation, treatment, storage and disposal.- The procedures associated with this system were revised during 1990.

5.

gecontamination and Decommissionino Procrams Past decontamination activities at WVDP 3 ave included clean up of the old process building CPC that will be utiAized for-interim storsge of HLW glass filled canisters.

In addition, the XC-3 extraction cell, Product Purification Call (PPC)-extraction cell, extraction chemical room (XCR), chemical crane room, EDR, the solvent storage terrace, and associated valve cubicles havc been cleaned up fer rouse.

Old radiochemistry laboratories have been cleaned out and now house new. laboratory facilities in support of the HLW treatment process.

The' Extraction Sample Aisle is being roused for laboratory storage.

Figure 12 provides a status of past D&D completions in the major areas of the process building.

Several of the decontamination efforts have primarily been in support of the IRTS which is the primary operation leading up to HLW Vitrification.

There are currently no active decontamination programs at WVDP.

Also, there are no facilities declared surplus at this time.

RLh0265:R6 27

e WVDP-019 Rev. 10 Future D&D activities will be determined by operational needs and final closure requirements being developed for the EIS procesa now in progress.

A study of alternative postsolidification activities is being prepared to provide the DOE a basis for Phase II budget planning.

The requirements of the WVDP Act and the NYSERDA/ DOE Cooperative 3

Agreement, the NRC/ DOE MOU, and requirements of interim storage and transportation of solidified NLW and TRU wastes, site maintenance, disposal of LLW and final D&D are being considered in the study preparation.

The NRC and the U.S. EPA are currently coordinating efforts to develop residual radioactivity standards for decommissioned NRC-licensed plants.

Criteria for decommissioning have been developed by the NRC.

These criteria do Xot establish the residual radioactivity level standards at this time (USNRC 1985).

The WVDP Act of 1980 required that the decommissioning of project facilities be done in accordance with criteria established by the NRC.

The WVDP and NRC have had several meetings regarding project completion.

Agreement has been reached, in principle, that NRC will be a cooperating agency for the WVDP Phase II EIS.

The cooperating agency status will expedite resolution of the D&D criteria through the EIS process.

The EIS will use a programmatic approach to develop the necessary safety and environmental documentation required to support decisions on final D&D of Project facilities.

The EIS will focus on issues, analysis, and review to assure orderly development of the final D&D plans including timely completion and approval of the necessary safety and environmental documentation. Additionally, issues portinent to specilic Project premises and facilities which require further investigations and regulatory decisions for resolution will be addreseed.

A broad range-of alternatives for project completion and site closure will be evaluated in the EIS process. Most major facilities, areas, and systems at WVDP present several viable courses of action. These will be considered both individually and in combination with one another.

Six closure alternatives are proposed for study as follows:

0- Greenfield O Exhumation, on-site waste storage and perpetual care-0 In-situ decommissioning and on-site low-level waste disposal O In-situ decommissioning with limited reuse and no new on-site disposal areas O Storage followed by in-situ decommissioning O No action 6.

Environmental Imoact Statement Status The currect schedule for major milestones associated with development of the EIS are as follows:

ACTIVITY TARGET / ACTUAL COMPLETION DATE Publish Notice of Intent (NOI)

December 30, 1988 (complete)

Scoping Meetings February 9, 1989 (complete)

Scoping Period Closes February 23, 1989 (complete)

Implementation Plan Approva)

In Progress j

RLn0265:R6 28 l

WVDP-019 Rev. 10 EIS Contract Award

October, 1992 Draft EIS (DEIS) Notice of June, 1994 Availability Close of DEIS Comment Period December, 1994 Final EIS (FEIS) Notice of Availability March, 1995 Record of Decision Published October, 1995 Follow-On Environmental and Safety Reviews TBD H.

PETERENCES 1.

Ham.te Manacement Documentation (References)

This section lists the required principal documentation applicable to HLW, TRU, LLW and D&D waste management operations specified by DOE Order-5820.2A.

Applicable documentacion for hazardous waste is also included.

t Hich-level Wants a.

Safety Analysis Reports (SARs) 1, WVDP, Vitrification System, WVNS-SAR-003, Vol. III, See C.,

Rev. 1, 8/25/88.

2.

WVDP, Exiscing Plant and Operations, WVNS-SAR-002, Vol II, Sec. B, Rev. 2, 06/22/89.

3.

WVDP, Supernatant Treatment System, WVNS-SAR-004, Vol III, Sec. D, Rev. 6, 10/36/91.

b.

Assessments of HLW Storage Taska 1.

WVDP, Maintenance of Carbon Steel High-Level Waste Tank Integrity, OSR-IRTS-1, Rev. 3, 8/27/91.

2.

WVDP, Maintenance of Spare HLW Storage Capacity,.

OSR*IRTS-3, Rev. 3, 8/27/91.

3.

WVNS Co.,

Inc., Waste Tank Operations, SOP 8-1, Rev. 20 FC#1 10/91, FC#2 10.91, FC#3 12/91 c.

Contingency Actions of the Past Year Contingency Actions on the HLWTF are currently being upgraded.

Day-to-day contingency actions have been employed to monitor the HLW tanks to determine if any leaks or spills occur.

TRU WASTE-a.

Waste certification Plan 1.

U.S. DOE, Data Package Format for Certiflod TRU Waste for WIPP.

WIPP-DOE-157, Rev. 1, 9/85.

RLA0265:R6 29

WVDP-019 Rev. 10 2.

U.S. DOE, TRU Waste Acceptance Criteria for WIPP.

WIPP-DOE-069, Rev. 2, Carlsbad, New Mexico, 9/95.

3.

WVDP, TRU Waste Certification Program Plan for WVDP, (WVDP-030), Rev. 1, 8/84.

4.

U.S. DOE, Defense Waste Management Plan for Defense TRU Waste Progre.m.

DOE-JIO-023, Albuquerque, New Mexico, 7/87.

b.

Operating and closure Plans for Interim Storage 1.

WVDP, WVNS-SAR-009, Volume IV for Lag Storage and Supercompactor Operations, See J.7, Waste Confinement and Management, (EH 86:0010), Rev. 1, 8/23/88.

2.

DOE 1540,1 and 49 CFR 173. Waste shipments and b

vehicles must comply with these documents.

3.

WVDP, Storage Requirements for Llif, OSR-TR-GP-6, Rev. 2, 8/27/91 4.

Vol 53, No. 251, Federal Register, U.S. DOE Notice of Intent to Prepare an EIS, 12/88.

j c.

Major Documents for Buried TRU 1.

WVDP Radioactive Waste Disposal Records 2.

Final Closuris EIS Low-Level Waste a.

Overall W3ste Management Systems Performance 1.

WVDP, Project Overview and General Information, Volume I & II (WVNS-SAR-001),.Rev. O, 08/23/88.

2.

WVDP, SAR for Cement Solidification System, see G.7.0, Waste Confinement and Management, (WVDP-037), SAR-008, Volume IV,.Rev. 1, 09/07/88.

3.

WVDP, SAR for Liquid Waste Treatment System, See H.7.0,1 Waste confinement and Management, (WVDP-049),

WVNS-SAR-005, Rev. 3, 09/27/91.

4.

WVDP, Low-Level and TRU Waste Assay and Methodology, Supplement J 7.2. WVNS Co., Inc., DOE /NE/44139--16, 3/87.

5.

WVDP, Existing Plant and Operations, (WVNS-SAR-002),

Volume II Rev. 2, 06/22/89 - ECN Pending.

b.

Storage and Disposal Facilities 1.

WVDP, SAR for Low-Level Class B and Class C Radioactive Waste Handling and Storage Operations for RLA0265:R6 30

--r

/

WVDP-019 Rev. 10 the Radwaste Treatment System Drum Coll, (DOE /EA-0295), SAR-007 Rev. 2, 8/23/88.

2.

WVDP, SAR for Low-Level Class A Radioactive Waste Handling and Disposal Operations, see K.7.0, Waste Confinement and Management, (DOE /EA-0295), SAR-006, Rev. 1, 09/07/88.

3.

U.S. DOE, Environmental Assessment for Disposal of l

Project Low-Level Waste, (DOE /EA-0295), WV, New York, 04/86.

4.

WVDP, Operational Safety Requirements, Storage Requirements for Low-Level Waste, OSR/TR-GP-6, Rev.

2, 8/27/91 5.

WVDP, Storage Canister Loading and Spacing, OSR/GP-11, Rev. 2 12/21/88.

c.

Disposal Site Closure Plan and Waste Forecasts 1.

Final closure EAS.

2.

DOE Integrated Data Base for 1989, DOE (IDB) for 1988:

Spent fuel and Radioactive Waste Inventories, Projections, and Characteristics, (DOE /RW-0006), Rev.

5, November 1989, d.

Decommissioning of Radioactive Contaminated Facilities 1.

WVDP, SAR for Existing Plant and Operations, Sec.

B.6,0, Decontamination of Primary Cells in the Support of the HLW Solidification, SAR-002, Rev.

2, 6/22/89. -

ECN Pending 2.

Final closure EIS.

3.

WVNS, WVDP Post-Solidification Project Decommissicaing Alternatives Study, Feb. 1989.

Hazardeue Waste 1.

WVDP-073, Hazardous Waste Mane.gement Plan, Rev.

3, 6/15/89 2.

WV-660, Off-Site Transportation of Hazardous Materials / Waste, Rev.

5, 07/26/91 3.

WV-996, Hazardous Waste Management Program, Rev. 1, 6/15/90 General References 1.

WVNS, DOE 5820.2A Implementation Plan, 09/26/88 RLA0265:R6 31 l

WVDP-019 R2v. 10 2.

WVNS, WVDP Sito Environt.r,ntal Monitoring Rsport for CY1990, Final Draft, 5/91 3.

WVDP-019, Annual Waste Management Plan, Rev.

9, 2/91 4.

WVDP-077, Mixed Waste Management Plan, Rev. O, 11/89

{

b m

i 1

)

l J

RLA0265:R6 32

?.* " *, y-.

s..

s wor ~cI9 Rev. 10 RB_LE 1 - MAJOR FLANNED F.CTIVITIES SCHEDULE /

MILESTONES ACTIVITY AREA PLf_NJLED ACTIVETY

}EW Sludge Wash Initiate sludge washing ard process through FY92 IRTS.

Vitrification Continue modifications of former chemical FY92 Facility Process Cell lo store High 1<svel Waste Canisters from the vitrification process.

FY92 Begin :nochantca3 / electrical construction activities in the vitrification facility.

FY93 Design Equip *nt Decontanikaation Room loadost facility and procure sludge transfer equipment.

FY96 Vitrification hot operations start FY96 l

vitrification operations completed

)

l l

TRU Fuel AssembYies Ship remaining fuel assemolles from the fuel storage TBD l

pool to another DOE site for ultimste storage l

and/or dispasal.

L,2 Develop new procedures, install egoipment, and place TBD new solidification process for unprocessed sludge j

I into operation.

ETS Contract Award Determinu contractor to prepare the EIS.

FY93 Record of Decision Published for CIS.

F196 NOTE: Refer to Program rehedule Status for further details (Appendix A) l s

RLA0265:R6 33

= -.. -.

=

~

.)

WVDP-019 Rsv. 10 TABLE 2 SUMMARE_OF WASTE MANA,QEMENT COSTS (Thousands of Dollars)

IhAIJ11 / WORT @h El-S FY-92 El-M Z"L-M II-M

'HLW VITRIFICATION (1) 40,008 43,519 48,763 41,799 28,023 TOTAL - EgpqEIA

'LLW/TRU/ HAZARDOUS 15,319 16,995 15,775 14,348 13,111 WASTE M?.NAGEMEllT BJ.5CELLANEOUS BUDQ"IS,1

)

WITHIN LLW/Y3U/HAZ WASTE MANAGEMENT BULGET WASTE OPERATIONS MANAGEMINT 879 1,039 1,061 1,064 926-kADICACTIVE WASTE' OPS SUPPORT 868 512 469 469 469 STORAGE STRUCTURES 9

219 54 54 54 SLUDGE REMEDIATION 97 171 293 293 293 WASTE'ENOINEERING MANAGEMENT 176 242 248 248 248-HAZARDOUS WASTE MANAGEMENT 303 404 337-337 337 WASTE SAMPLINO-AND ANALYSIS 772 410 413 359 359 RAD. WASTE CHARACTERIZATION /

0 150 47 47 47

'OLASSIFICATION WASTE MINIMIZATION O

46 47 47 47

'1IXED WASTE MANAGEMENT 13 23 99 99 99 INTERCEPTOR TRENCH. OPERATIONS 483 46 47 47 47 STEAM JET REMOVAL 291 114 0

0 0

RhZ WASTE TRANSPORTATIOM DEPT 86

.279 188 188 188 HLW TANK MANAGEMENT 210 187 242 242 240:

STS OPERATIONS (2) 674 LWTS' OPERATIONS (3) 262 CSS OPERATIONS- '

237-8-

DRUM CELL OPERATIONS 227 SLUDCC WASHING.

0 1,721 104 0

0-SUPER COMPACTOR OPERATION 23 108 85 85 86 CONTACT SIZE: REDUCTION 212 223 229

.229

.231 FACILITY OPERATIONS TRU WASTE PLANNING 0

0 141 141 0

PHASE II -- EIS

'3,843 C,309 11,667 11,771 21,047l

( 1 ) 1 -- Includes denign, construction, installation, and check out of all equipment and ufccilities-

-NGTE: These costs are constaat year dollars (non-escalated) and do not contain reserves, 4

ote.

i

-- No information available at time of printing 1

i RLA0265:R6 34

)

WVDP-019 Rev. 10 v

TABLE 3 WEST VALLEY DEMONSTRATION PROJECT 1990 SPDES NONCOMPLIANCE EPISODES p_q,3 ortfa11 Pa r7. met e r Limu YA1ER E9fE211tJlt Feb 90 Sum 001,C07 NH 2.1 mg/L 3.46 og/L STP Flow Through 3

-008 Feb 90 Sum 001,007 NH

?.1 mg/L 3.86 mg/L STP Flow Through 3

008 Feb 90 Sum 001,007 NH 2.1 mg/L 3.27 mg/L STP Flow Through 3

{

008 Fcb 90 Sem 001,007 NH 2.1 mg/L 2.81 mg/L STP Flow Through 3

008 Feb 90 Sum 001,007 NH

?.1 mg/L 5.21 mg/L STP Flow Through 3

008 Feb 90 Sum 001,007 NF:

2.1 n.g/L 3.97 mg/L STP Flow Through 009

Feb 90 Sum 001,007 BOD-5 5.0 mg/L 12.04 mg/L Related to above 008 Nov 90 Sum C01,007 Fe 0.31 mg/L 0.87 mg/L 001 Fe high 000 Nov 90 007 Settle-0.3 mL/L 0.5 mL/L Floc material 4

able Solids f

RLA0265:R6 35

WVDP-019 Rev. 10 TABLE 4 agmgarv of Monitqgina Procram Chances Imolementog in 199Q WNSPOO1 Analyses added to routine site sampling: To. routine discharge grab samples added dichlorodifluoromethane, trichlorofluoromethane, 3,3-dichlorobenzidine, tributylphosphate, and vanadium.

To semiannual grab samples added bis (2-ethylhexyl) phthalate and 4-dodecene.

WNSTPBS New sample location / type added: Sampling of sanitary waste sludge for alpha / beta, H-3.

WNSW74A Txisting site upgraded: Automated sampling put on line in 1990.

In

.1989 site was grab sampled menthly and analyzed foe gross alpha / beta, H-3 and pH.

In 1990, composite sampled weekly for gross alpha / beta, H-3, pH and conductivity, a monthly composite analyzed for gtmma isotopic and Sr-90, and a quarterly composite analyzed for C-14, I-129, Pu/U isotopic and Am-241.

WNSDIDR New sampling location added: Added weekly sampling of high-level waste tank farm underdrain for Groar alpha / beta, H-3, pH, and monthly composite for gauma isotopic and Sr-90.

WNDRNKW 1989 point WNDRNKW (site drinking water) replaced by four new pointa monitoring drinking water in the Environmental Laboratory (WNDENKEL),

maintenance shop (WNDNKMS), storage tank (WNONKUR), and main plant (WNDNKMP).

ANROFOP New fallout pot at rain gauge by Met tower on site.

SFRSPRD,.SFBOREN and SFORVAL Added U isotopic analysis at these three soil l

collection sites.

N BFB--,

BFD--- Added tritium analysis to beef and deer samples.

l i-l l

l-RLA0265:R6 36

WVDP Summary Project Schedule FY91 FY92 FY93

-FY94 FY95 FY96 hS

P t' '~

oiI o2 I o31 o4 oil o2 l o31 o4 oil o21031 o4 oil 02 I o31 o4 Oi!021o31o4 Oil 02103104

-1 CML/ STRUCTURAL CONSTRUCTON

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FY95 FY96

West Valley Project Office

"*"'Y Director venscanon T. J. Flow!and Manager B Mazurowski secretary j

A. Masterson l

~

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Tectrilcal Regulatory Prograsn Program CompiLance hegradon omca omca or:e l

3 I

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N Tedviology OpseMaint-E S H & CV Program W.

gm Manager Const Mgr.

Fyograrn Mgr.

_ P.Vanteen y

W. S. Ketels J. A. Yeazef R. 8. Provencts Haz. & Maed Plant LLW Osw oweyv.,deanen '

Firs W &

Weste Mgmt Maint & Sne Support Eng. Support MJet H. Moore 1

l LL & TPM Vd Ctakotd EnwonroeC.at Comrn. Rel.

Wasie Mgmt

& Ops sasety

& Tranng S. Wee D. Cook

  • Matthews l

F Eroneenng &

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% 84W Constuctm Sateey

& Conras P. Abrams W. Hurd C. Eckert j

y 2l.o I

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A WEST VALLEY NUCLEAR SERVICES n m s ox President &

General Manager W. G. Poc! son Executive Vice President

[

Deputy General Manager l

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M Site Serrices l

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Vitrification Vice Presiden!

w Resources Environmental Project l

& Support Operations uar.ager Manager Manager Safoty Health &

Manager Controller QA Manager j

R.A. Humphrey i

R.F. Gessne:

J.R. Greenquist J.L Knabenscheh R.E. Lawrence Jr.

M.H. Sgrol

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WDP-019 Rev. 10 Appsudix Al Program Schedulo status The following " Implementation Summary Table", for the DOE Orders 5820.2A Implementation Plan has been updated to reflect progress during the past year. Cast and schiviule projections have been revised as necessary to reflect curs.ent estimated completion dates.

Items completed prior to 1991 have beda dulated.

- A

' \\h

- {l.4 3!

A RLA0265:R6 A-1 l

1

b1VDP-019 Rev. 10 Appendix A: Program Schedule Status DOE Order 5820.2A IMPTEMENTATION SIDOUutY TABLE WEST VALLEY h m SERVICES Chapter I - High-Level Waste (1) Refer to.the West Valley Implementation Plan and the Final Assessment Report (2) Arranged:in order of proposed priority.

5820.2A Order Estimated

' Number Current Practice / Statement.of Need Action Required Costs Detailed Schedule 3.o.(1)(b)

DOE Order 6430.1, 40 CFR 264 and EH Part I cf this effort Complete orders are being evaluated. Actions has been performed.

to be taken will be determined Part II is required during this evaluation.

to complete this action.

Complete evaluation of 6430.1 and define requirements.

3.b.(2)(h).

Operational control are set at 80%

Vitrification of HLW None October, 1993 maximum tank level on process 3 of will process the 4 tanks. Level indications and contents of tank BD-alarms are provided and monitored.

4 Tank 8D-4 is full.

Alarms have been reset and recalibrated. Tank BD-4 has been isolated from all inflow.

RLA0265:R6 A-2

4i WVDD-019 Rev. 20 Appendix A: Program Schedule 3tatus DOE Order 5820.2A IMPI.EMENTATION S12 MART TABLE WEST VAILEY NUCLEAR SERVICES Chapter II - Transuranic Waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Report (2) Arranged in order of proposed priority.

5820.2A Ozder Estimated Number Current Practice / Statement of Need Action Required Costs Detailed Schedule 3.a.(1)

WV TRU waste has not been ast.ayed or Review records of TBD TBD 3.b.(2) classified for hazardous materials.

existing TRU weste, 3.b.(3)

A program to assess and determine develop a hazardous characteristics of West characterization Valley TRU waste should be developed mixed waste progras and RCRA requirements should be and issue requtred included. New York State is procedures.

scheduled to receive RCRA primacy in 4.

calendar year 1989. At that time, Characterize TRU TBD TBD this classification program will be wasta in storage.

required.

3.b.(1)

West Valley generates only minor quantities of RH TRU waste from the spent fuel pool water treatment system CH TRU waste generation has primarily been a result of major decontamination work which is not being performed at this time.

Future (Phase II) D&D will result in the generation of significant amounts of CH TRU.and RH TRU waste.

A waste generation reduction Develop a TRU waste TBD TBD l

program, meeting the intent of DOE minimization program Order 5820.2A, should be developed which applies to the and implemented for future TRU weste Phase II D&D program generating activities.

activity.

l' 1

RLA0265:R6 A-3

Win.,P-013 R:;nr. 10 Appendix A: Paw ram Schedule Status DOE ORDER 5820.2A IMPLEMENTATION SUDMARY TABLE 4

WS7 VALLEt NUCLEAR SERVICES i

-Chapter II - Transuranic Waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Repert (2) Arranged in order of proposed priority.

s 4

5820.2A Order Estimated Number Current Practice / Statement of Need Action Required Costa Detailed Schedule 3.c.(O)

At the present time, TRU waste Develop.a TRU waste TBD TBD disposition at West Valley is not certification program defined.

and issue the required procedures j

WV TRU is presently not. scheduled to be shipped to WIPP as it was generated onder commercial contract.

j WDP-030, Rev. 1, is the TRU Waste Certification Program Plan for the WVDP.

This plan invokes some elements of the WIPP-WAC program, but does not implement all details such as data requirements, i

certification requirements, or waste storage requitaments.

i The WVDP requested DOE assietance to i

identify an off-site facility for l

the disposal of WVDP TRU wastes in l

i letter WD 90
0494, dated May 4, 1990.

When direction is received i

from DOE a schedule will be developed to revise the current certification plan and prepare the j

necessary procedures.

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WVDP-019 Rev. 10 Appendix.A Program Schedule Status DOE ORDER 5820.2A IMPLEMENT 4TIO8f

SUMMARY

TABLE Wc.ST VAI.LET NUCLEAR SERVICES Chapter II - Transuranic Waste (1) Refer to the West valley Implementation Plan and the Final Assessment Report (2) Arranged in order of proposed priority.

5820.2A Order Estimated 4

Number Current Practice / Statement of Need Action Required Cox +

Detailed Schedule 3.f.(1)

TRU waste disposal has not been Develop and issue a TBC TED defined for West valley. WV TRU is TRU waste shipping presently not scheduled to be plan.

shipped to WIPP as it was generated i:

under commercial contract. For Define and provide TBD TBD-Pending these reasons current shipping plans' facilities to load EIS j

for West valley TRU waste are not and ship TRU waste.

developed. As identified in itera 3.c.(8), these items will be scheduled when direction is received from DOE.

1-3.g.(2)

These criteria are for new interim Issue a West valley C w lete storage facilities. New facilities overall waste storage will be required at West valley in plan.

support of Phase II D&D.

These 3

facilities should be developed to satisfy certified / uncertified waste segregation, RCRA requirements and all requirements of 5820.2A.

During 1991, WDP formed a task force to develop a.. strategic plan for waste management. The product of this task force,

  • Waste Management. Strategic Directions" has been developed in draft version.

The WPO conveyed its support of this effort in letter DW:91:0616, dated August 9, 1991, and

~ "'

acknowledged that the strategic plannl m "G rt superseded the i

developrnent of a Long Range Storage Plan.

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10 Appendix As Program Schedule Status 00E ORDER 5820.2A IMPLEME3fTATIOtt SING 4ARY TABLE WEST VALLET NUCLEAR SERVICES Chapter II - Transuranic waste (1) Refer to the West Valley Implementation Plan and the Final Asseessment Re;mrt (2) Arranged in order of proposed priority.

5820.2A Order Estimated

(* umber Current Practice / Statement of Need Action Required Costs Detailed Schedule 3.g.(5) west valley has data requirements, Upgrade SOP TBD TBD for current storage defined in the requirements for SOP system. As identified in item waste package data.

3.c.(8?, necessary actions will be performed when direction is received from DOE.

l nr.an?6%pA A-6

WVDP-019 Rev. 10 Appendix As Program Schedule Status DOE ORDER 5820.2A IMPLEME3rTATIOW stDMART TABLE WEST VALLEY NUCLEAR SERVICES Chapter III - Low-Level Waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Report i

(2) Arranged in order of proposed priority.

I 5820.2A Order Estimated Number current Practice / Statement of Need Action Required Costs Detailed Schedule l

3.b.(2)

A waste management system A system performance 5100K TBD performance assessment of this scope assessment to has not been performed at West determine specific valley. DOE /LLW-63T, " Guidance for compliance with DOE Conduct of Waste Management Systems Order 5820.2A should Performance Assessment

  • dated June be scheduled and i

A 1988, has been issued and pr vides performed.

guidance for conducting the performance assessment.

3.c.(1)

Waste minimization / reduction goals Upgrade and implement Corplete 3.c.(2) are established. WVNS has developed a formai vaste qL a Waste Minimization Plan, issued on generation reduction March 27, 1991, which identifies program.

j waste reduction / minimization goals for WVDP.

Based on this document training modules are being j.

Implemented by WVDP.

1

WVD P--Ol9 Rev. 10 Appendix As Program Schedule Status DOE ORDER 5820.2A IMPLEMENTATION StP9(ARY TABLE WEST VALLEY NUCLEAR SERVICES Chapter III - Iow-Level Waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Report (2) Arranged in order of proposed priority.

5820.2A Estimated Order Number Current' Practice / Statement of Need Action Required Costs Detailed Schedule 3.d.(1)

Currently, radioactive LLW is Develop, implement TBD 3.f.(3)(a) classified in accordance with 10 CFR and perform a formal 61 requirements.

SOP's for material characterization status determination for hazardous program.

materials and storage and record keeping for hazardous waste have been issued.

A waste stream certification program for LLW should be developed and implemented as part of a LLW characterization program in order to formalize and retain data on a long term basis.

A task force will be organized j

during January 1992 to initiate the development of this characterization l

program.

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WVDP-01D Rev. 10 Appendix A: P.ogram Schedule Status DOE ORDER 5820.2A IMPLEME'fTATION SIDetARY TABLE WEST VALLEY NUCLEAR SERVICES Chapter III - Low-Level Waste (1) Refer to the West Valley Irtplementation Plan and the Final Assessment Report (2) Arranged in order of proposed prjority.

5820.2A Order Estimated Number Currenc Practice / Statement of Need Action Required Costs Detailed Schedule 3.f.(1)

LLWTF System aludge and zwlite are Complete revised April 30, 1989 3.1.{5)(b) presently being stored in a recipe development (complete) dewatered uncemented form. The prict and order new cemented form is unacceptable and equipment.

requires resolution. Approximately 2000 drums of prior cemented waste Develop new TBD TBD and 1300 drums of recently generated procedures, install dewatered waste are in storage as of equipment, and place December 9, 1991.

new solidification process in operation.

Approximately 220 drums are to be Resolve approximttely TBD TBD initiated on a production 3300 drums in

.remediation effort basis schedubd storage.

to be completed by May 1992.

The LLWTF system has been upgraded Complete to improve treatment processing.

The chemicals used for flocculation /

clarification were replaced.

Previously used were ferrous sulfate, caustic, carbonate, and polyelectrolyte. The LLWTF process is now using potassium ferrate, potassium hydroxide, and polyelectrolyte. This change has resulted in an up to 834 reduction in the sludge produced by the system.

1 k

WVDP-Ol9 Rev. IO Appendix As Program Schedule Status DOE ORDER 5820.24 IMPLENDITATIOtt SUte1ARY TABIE WEST VALLEY KUCLEAR SERVICES Chapter III - Low-Level waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Report (2) Arranged in order of proposed priority.

5820.2A Order Estimated Number Current Practice / Statement of Need Action Required Costs Detailed Schedule 3.f(3)(a)

A waste characterization program as Develop, implement See TBD discussed in 3.d.(1).above eapports' and perforts the waste 3.d.(1) this requirement.

In addition the characterization above.

overall system performance program defined in assessment of 3.b.(2) will support 3.d.(1) above.

the definition of specific requirements.

Develop and issue a TBD document that analyzes waste stream characterization for selection of treatment options.

3.h.(3)(a)

Past storage facilities have been Issue a West Valley Complete 3.h.(3)(b) obtained as needed and have been Long Range Storage justified on a short. range Plan. Interface with requirement basis. A detailed review Chapter II item of future waste storage requirements 3.g.(2).

should be conducted. This is particularly appropriate in view of the fact that LLW waste disposal' paths are currently unresolved for-West Valley. A compacehensive long-t range storage plan, that considers ALARA, waste segregation and RCRA regulations should be developed.

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WVDP-Ol9 Fev. 10 Appendix At Program Schedule Status DOE ORDER 5820.2A IMPLDEENTATION StpetARY TABLE WEST VALLEY NUCLEAR SERVICES Chapter III - Low-Level Waste (1) Refer to the West Valley Implementation Plan and the Final Assessment Report (2) Arranged in order of proposed priority.

5820.2A Order Estimated Number Current Practice / Statement of Need Action Recuired Costs Detailed Schedule 3.h.(3)(b)

During 1991, WVDP formed a task (cont) force to develop a strategic plan for waste management. The product of this task force, " Waste Management Strategic Directions

  • has been developed in draft version.

The WVPO conveyed its support of this effort in letter DW:91:0616, dated August 9, 1991,'and acknowledged that the strategic planning effort superseded the development of a Long Range Storage Plan.

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tND P-019 F:ev. 10 Appendix A: Program Schedule Status DOE ORDER 5820.2A IMPLEMENTATION

SUMMARY

TABLE WEST VALLEY NUCLEAR SERVICES Chapter V - Decommissioning of Radioactively Contaminated Iacilities (1) Refer to the West Valley Implementation Plan and the Final Assessment Repcrt (2) Arranged in order of proposed priority.

. SS20.2A Estimated l Ordctr f Numb 2r Curre".t Practice /Statenent of Need Act8on Required Costs Detailed Schedule 3.a.(2)

A Nuclear Fuel Services document, Update the Facility 540K-TBD dated June 12, 1981, provider a Utilization Report.

550K

  • History of Decontamination", 1971-1981.

Facility characterization data are available in the Facilities Utilization Report, WVDP-Ol7, West i

valley main process facilities prior to 1983.

3.a.(3)

Decontamination prugram work is not Prepare and issue a TBD TBD cusrently being performed at West compreheneive D&D valley. For future D&D work a Plan.

comprehensive D&D Plan that defines all steps to initiate and complete a D&D project, and provides criteria for aelection of alternatives, characterization, report ing, and data keeping requirements should be developed.

8 I

A-12 pr anpr,s: F6

WVDP-Ol9 Rev. 10 Appendix At Program Schedule Status DOE ORDER SC20.2A IMPLEMENTATION SUte6ARY TAPJ&

WEST VALLEY NUCLEAR St.RVICES Chapter V - Decomrnissioning of Radioactively Contaminated Facilities (1) Refer to the West Valley Implementation Plan and the Final Asses e nt Report (2) Arranged in order of proposed priority.

5820.2A Order Action Required Costa Detal. led Schedule Number Current Practice / Statement of Need Estimated 3.c.(1)(c)

West valley currently has no active Establish RCRA flGCK-TBD-FY 1993 D&D projects. Final D&D actions will program requiremscta

$150K be determined by Phase II D&D and incorporate with program (post vitrification) and the the D&D program plan site EIS.

West Valley does not prior to Phase II D&D currently have a RCRA compliance work.

program for D&D type work.

These requirements should be developed for future D&D work.

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WVDP-019 l

Rev. 10 L

Appendit B WVDP Waste Volumes in Storage As of Novenbor 15, 1991 Volume or Maes Waste in Storages 1RTS Drum Cell (Class C) 95,400 ft

( 2,702 m')

8 8

Other Low Level Wasto A 158,440 ft

( 4. 4 87 m')

(by Class)

B 18,132 f t' (513 m')

C 3,672 f t' (104 m')

TRU Wante (Includes Suspect TRU) 8,844 ft

( 2 50 m')

8 Undetermined / Unclassified Status 81,200 ft' (2,300 m')

8 CPC Waste /High Radiation Itums 30,000 ft (850 m')

Roll-off Containers of soll 26,460 ft' (750 m')

Mixed Waste - Lead in Storage 14,042 kg Mixed Waste in Interim 1,868.5 lb Wasta Storage racility flatardous Waste 507 lb Recyclable Oil 1,023 lb RLA0265:R6 B-1

RvDP-Ot9 l

Rcv. 10 Appendix C Low Level Waste Systee and racility Description A.

Low-Level Waste Categories The LLW is divided into three categories based upon physical properties (1) trash and miscellaneous dry solidn, (2) liquid and wet solid wastes immobilized in cement; and (3) equipcent and hardware.

1.

Trash and miscellangous. dry E211AA consist of radioactively contaminated protective clothing, paper, plastic, and other dry solid materials. The bulk density of these wastes is assumed to be 0.53 g/cm' (33.09 lbs/f t') after compaction.

Alternative procet 31ng techniques are under consideration and will be used if they are determined to be cost-effective and would reduce the potential environmental impacts for each particular westo stream.

Such processing will not alter the evrin content of the waste but might alter its physical form.

2.

Liould and wet solid wantog immobilized in efm2D1 include solidified uranyl nitrate solution, decontaminated supernatant, and sludge wash solution. All of these wastes will be solidified in comont with an average density of approximately 1.7 g/cm' (106.13 lbs/ f t') and packaged in standard.21 m' (55 gallon) round drums and.27 m' (71 gallon) square drums filled to at least 85 percent of their capacity.

3.

Ecaiocent and hardware are basically contaminatea metallie objects requiring disposal. These components will be segregated, as practical, and volume-reduced. The bulk density of this waste form 8

is assumed to be 2 g/cm (124. 86 lbs/ f t') after compaction.

B.

The '"tegrated Radioactive Waste Treatment Syntem 1.

The IRTS escentially consists of four parts:

the STS; the LWTS; the CSS; and the RTS Drum Coll.

The STS is basically a catch ion-exchange system utilizing scolite as the exchange medium for extracting Cesium-137.

This is depicted in figare 11.

The teolite ion-exchange columns are installed in tank 80-1.

When the zoolite in a column tas become loaded with Cesiur, it is dropped into the bottom of tank BD-1, and new reolite is added to the column.

The LWTS conoists of two parallel process str6ams, one for proconsing decontaminated supernatant and other liquid waste streams with high total dissolvec solids (TDS), and the second one for processing low TDS waste.

The high TDS waste procest.ing train includes 6vaporation and ion exchango pollahing of condensates. Evaporator concentrates are pumped to the CSS for solidification. The low TDS waste processing train includes filtration and ion exchange.

Tha CSS is a batch procesa system, which is automatically controlled to provide the optimum mixing time and waste-to-cement ratio for the particular liquid wasto to be processed.

The CSS consists of three subsystems: 1) the waste encapsulation system, which consists of the high-shear mixer and associated equipment; 2) the coment storage and transfer system, which consists of the pilo, the cement storage bin for the day's operation, and the transfer system for motoring the cement to the mixer; and 3) the material handling system, which moves RLA0265:6RM C-1

e WVDP-0 Rev. 1 i

and monitors the drums from the drum storage mixing station,-capping station, survey station, and through vaste storage an.c loadout.

The heart of the CSS is the high-shear mixer system.

This has the

(

ability to encapsulate the decontaminated supernatant by providing a strong mechanical action resulting in excellent waste /coment homogeneity. A simplified flow sheet for the CSS is rhown in figure 12.

)

The Drum cell is a shielded f acility cor.structed f or storage and potrot tal disposal of the solidified LLW (see figure 13).

It has the capacity loc 17,600 square drums, which are handled remotely using a y

ecmpaterized crane system.

The stacked drums are surrounded by a 20-inch thick concrete shield wall and the facility in heated during winter for cement curing.

2.

Low-Level Wasle Treatment Facility (LLWTF)

Waste water sources from plant drains, surface runoff, cooling tower

~

. blowdown, NWS disposal area, and the laundry are currently treated by the existing LLWTF.

I The LLWTF As located in a two-story concrete block building 7.3 m x 9.4 m x 8.8 m high (24 ft x 31 ft x 29 ft high).

Additional equipment is located outside adjacent t-the buf.1 ding.

The facility is an addition to the original plant and was put into service in 1971.

It currently operates 25 weeks per year.nd proceuses as much as 56 x 10* liters (15 x 10' gallons) of liquid wastw per year.

The LLWTF syst(su can presently process a maximum of.760,300 liters (200,000 gallone) per day.

A high percentage of the equipment and piping is stainless steel and is instrumented to opacato unattended i

for several hours at a time.

The facility has a controlled ventilation system with air passing through High Efficiency Particulate Air (HEPA) filters before release to the atmosphere.

The facility is supplied with steen air, softened water and chemicals from the main plant systems.

Ths waste-streams are treated in the LLWTF using a seavenging-precipitation, ion-exchange process developed at Oak Ridge Naticnal Laboratory.

The system, which can process at an optimum rate of 380 liters (100 gallons) per minute (maximum process rate of 530 liters / minute (140 gpm)) is specifically-designed to remove Cs-134, s

Cs-137, Sr-83, and Sr-90.

The overflow from the clarifier gos:s to a marge tank and then is

- s pumped to an anthracite filter.

The 2-foot deep filtc ; reroores particles greater than 5 microns.

The filter is periodically 1

backwashed with previously filtered water which is then sont to Lagoon 2.

The filtered water is passed through one of two ion-exchange columns-to renove ' the remaining (50 to 70 weight - percent) cestum and -

strontium.

The columna aro la parallel.so that one can be eluted-while the other is on-line.- Each column, 1.2 m (4 feet) in df,ameter j

by 2.7 m (9 font) high, contains up to 1.8 m' (65 f t*) of a teolite

~

tssin mixture (IE-95 and A-01).

The effluent is released to Lagoon 4 or L through an acid blendor, which reduces the pH.

Each column is on-line ar. average of 11.4 million liters (3 million pallons) i throughput before Cs-137 breakthrough occurs.

i RLA0265 : 67tM C-2

.., _ _ - ~ _, _. _., _, _ _ _. _ _ _ - - _ _ _. - _. _ - _ _ -. _

Wyt,P-019 Rev. 30 C.

Site and Volume Reduction 1.

gpntact fire Reducti2D l

f The project also requires a capability for mise reduction and TRU decontaminatica of materiale collected during the D&D process.

The CSRF was originally intended to be located entirely in the former FRS area.

Due to the delay in FRS availability, a-werk-around plan i

was developed which provided a CSRF in both the Master Slave j

Manipulator Repair Shop (MSMRS) and LAG storage buildings. A Liquid Abrasive Decontamination Booth and a Supercompactor were procured.

Hot operations started in November 1987 af ter receiving an EPA permit.

This facility is used to size reduce contaminated process tanks, piping, and other metallic scrap and then either package theos pieces for disposal or feed the material to the Supercompactor for further voluma reduction. The nectioning of metallic equipment is pectormed in a room which has stainless steel covering the walls, floor, and ceiling.

The purpose of the stainless steel skin is to facilitate decontamination of the room when necessary.

Volume reduction in the CSRF is accocplished using an air plasma are toren, but standard mechanical teolo such as nibblers and portable band saws are also available. A ventilation system with several stages of filtration was it.stallud for this facility to capture the large quantities of smoke produced by the air plasma are toAch.

Located adjaceut to the cutting room are two decontamination facilities, one facility is a walk-in spray booth wherm large items can be washed down with a hydrobrush or steam cleaned. The seconc f acility is a Liquid Abrssive Decot.tamination System (LADS).

The LADS uses a stream of abrasive particles, water, and air to clean contaminated surfaces.

The abrasive slurry is recycled to reduce thw volune of secondary waste generated.

The work is enclosed in a booth and the operator works through glove ports to direct the abrasive stream on the work piece.

2.

gynercomosetion The Supercompactor arrived at the WVDP in FY87 and was installed adjacent to the LAG Storage Building.

cold operations were successfully completed and hot operations started in October 1987 after receiving an air discharge permit for the HEPA.Vilter system.

An average of 44 drums can be accommodated in a single 2.55 m (90 8

ift) vastu Fox; the maximum quantity that was achieved was 51..The F

average Volume Reduction Factor !VRF) is 5:1.

D. NDA Liquid Pretreatment System Liquid collected by the. interceptor trench will be a mixture of water and ems 11 amounts of solvent contaminaced with radionuclides. The solvent, n-dodacaro with up to 30 percent TSP, was used to recover fissile material when the

',*S fusi feprocessing plant operated in 1965-1972. The degraded solvent was-transferred to 1000 gallon tanks and buried in the NDA.

The NDA Interceptor Trench LPS is housed inside a sprung steel structure. The system will process the. collected liquid in two phaness solvent separation RLA0265:6RM C-3

WVDP 0 Rev. 1 And water prutreatment (to remove iron and I-129).

The solvent which has a lower density than the water, will be skimir.ed from the 1000 gallon tanks once approxico.ately 100 gallons have accumulated.

It will then be stored in 55 gallon drums until arrangements are made ivr a contractor to solidify the solvent into a stable waste f,.irra meeting the USNRC's Dranth Technical Position an Waste Form.

The LPS consists c' a heated enclosure which houses a particult.te removal o

filter connect /2

'.4 swr'es with two Granular Activated Catbon ( C. AC ) units.

The former wilt ta i '. 96 ; o remove most of the iron from the water, while the letter will uen, cq remove organic n'aterial with which the 1-129 is corrpl e x e d.

Lt @ vatt h passes through the system will be transferred to Lagoon 2.

hte: 11s. tegoon 2 is pumped to the 02 plant for further treatment and et nic a itelease of f-site through the Lagorm 3 outf all.

E.

Waste Storage aml: Laptoal 1.

LLW/TRUJM gQthujie Building In FYB4,, a pe,ennineered mntal storage building was constructed and placed intc4 serv we.

The Luiloing provides LAG or surge storage for pckaged LLW u i 1.ong-ter.? storage of packaged TRU waste for evantual of f-site harmb).

The buiMing is egoipped with ventilators, insulation, interior, exteriew and personnel door exit lighting, remote actuated roll up door, jonization smoke detectors, and radiation monitors.

The building atcros CH waste iackages (<100 mR/hr) only.

In FY87, a section of the LAG Storage Duilding was convertad to a waste assay area and a staging area for the Su;;ercompactor.

The assay area is comprised of the segmented gamcaa sesnner and passive 4 P3 neutrtn det rector systerns.

2.

gRC Wast.t_1.tsdag Building In FY85, ti tenlien weather structuru was constructed and placed into service.

The building containe high-radiation items resulting from decontaminatien >perations in the CPC.

This waste is contained in boxes in the center of the structure.

Concrete ovorpacks containing packagma waste are located around the inside perimeter of the facility to provide chielding.

J.

LSA O and L Q,f2 In TYS7 - 88 two additional tencion weather structures were conatructed 'to accommodate the storage of packaged LLW.

4.

LJ A # 3 af)LLS A #4 construction of two new tension weather structures began in 1990.

The f ar::ilities will accommodate the storage of low-level and radioactive mixed wastes.

Storage in these facilities began on June 18, 1991.

5.

11Ag_d icensed DiariosaJ Area f NDM RLA0265:6RM C-4 l

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-_ _ _ _ _._.___m________.._m-

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WVDP-019 Rev. 10 I

8 3

The NDA has a gross area of 20,000 m (215,300 f t ). Waste generated and buried by the former owner, NTS has used more than half of this area. At the present time, the WVDP has used a 61 m x 82 m (200 tt x

)

269 ft) area of the NDA of which approximately 4,600 m8 8

(483,500 f t )

remain.

Lased on a utilization factor of 1.5 cubic meters per squara j

8 8

motor, this c.rea could receive 7,100 m (250,700 f t ) noro waste if it f

is used for further disposal.

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e WVDP-019 Rev. 10 1990 ErrLUENT OH-SITE AND Orr-SITE MONITORING PROGRAM The following schedule represents the WVDP routine Environmental Honitoring Pregram which was in place in 1990. This schedule meets or excaeda the min kum program needed to satisfy the requirements of DOE Order $400.1, which superseded DOE 5484.lA, thapter III, in late 1988.

It also meets.!equirements of DOE $400.C and Draft DOE order 5400.6.

Specific methods and recommended monitoring program elements are referenced in DOE /EF-0096, " Effluent Monitoring" and DOE /EP-0023 (*2nvironmental Surveillance), and are the bases for selecting most of the schedule specifics.

Additional monitoring A mandated by OSRs and air and water discharge permits (40 CPR 61 and St.(b),

which also requires a formal report generation.

These specific cases are identified in the schedule under Monitoring / Reporting Requirements. The overall Environmental Ptogram schedule is referented in OSR-OP-4.

SCHEDULE OF ENVIRONMENTAL RAMPLING The following table presents a schedule of environmental sampling.

Locations of the sampling poLnts are shown on Fiqures D-1 through D-9.

The headings for the tables are explained in the following paragraphs. An index is provided to locate semple information and to provide an overview of sample types and names.

Sample Location and I.D. Code - The physical location where the sample is collected is described.

The I.D.

is a seven-charactor code, the first character of which identifies the sample medium as Air, Water, Soil / Sediment, Biological, or Direct Heasurement.

The soccnd charactor opacities on-site or off-site. The ren41ning characters describs the specific location (e.g.,

AradVAL is Air off-site at Great Valley).

Monitoring / Reporting Requirements - The basis for monitoring that location and any additional references to permits or OSRs are noted, as well as the reports generated from cample data.

Sampling Type /Hedium - Describes collection method, and the physical characteristics of the mediuin.

Collection Frequency - Sample collection frequency.

Total Annual Samples - Discrete physical samples collected annually, not including composites of collected samples.

Analysia Perrurned/ Composite Frequency - Describes the individual analyseO cn the samples or composites of samples, and the frequency of analysis.

4 RLA0265:6RM D-1 i

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  • WVDP-0 R2v. It INDEX OF ENVIRONMENTAL MONITORING PROGRAM SAMPLE POINTS ban On-Site Effluent - Air (Figure D-1)

ANSTACK - Main Plant D-4 ANSTSTK - Supernatant Treatment D-4 ANCSSTK - Cement Solidificatian D-5 ANCSRFK - Site Reduction Facility D-5 ANSUPCV - Supercompactor D-6 On-site Liquid Effluent - Water and surface Water (Figure D-2)

WNSPOO1 - Lagoon 3 Weir Point D-7 WNSP006 - Facility Main Drainage D-8 WNSP007 - Sanitary Waste Discharge D-8 WNSTPDS - Saaitary Waste Sludge D-8 WNSWAMP - Swamp Drainage Point D-9 WNSW74A - Swamp Drainage Point D-9 WNBD1DR - Waste Farm Underdrain D-9 WN3P000 - French Drain LLWT Area D-9 WNSP005 - South Fact.lity Drainage D-10 WNCOOLW - Cooling Tower

  • D-10 WNDNK Series - Potable Water
  • D-10 WNDRNKW - Potable Water

D-10 WNFRC67 - Frank *s Creek East D-11 WNERU53 - Erdman Brook D-Il WNNDADR - Dieposal Arua Drainage 0-11 WN9CELD - Drum Cell Drainage D-11 WI3 TAW Series - Standing Water

  • D-12 On-Site aroundwater and Seeps (Figure D-3)

H' Tank Unit Wells and WNDMPNE D-13 Lagoon Unit Wells, WNC$EEP and WNSP008 D-13 NDA Unit Wells D-13 Facility Area Welle D-14 NDA Area Wells D-14 Fuel Storage Tank Well D-14 Off-Site Surface Water (Figure D-4)

WFFELBR

a. Cattaraugus at Felton Dr.

D-15 t'T3CTC8 - Buttermilk at Thomas 3orners D-15 iTBCSKG - Buttermilk Background D-15 Off-Site Grouwi 'ater (Figures D-5 and D-9)

WFWEL Serxes - Private Local Wella D-16

  • Not detailed on map.

RLA0265:6RM D-2 I

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w WVDP-019 Rev. 10 Off-site Ambient Air (Figurn D-6)

AFFXVRD ~ Fox Valley Sampler D-17 AFTCORD - Thomas Corners Sampler D-17 AFRT240 - Route 240 Sampler D-17 AFRSPRD - Rock Springs Road Sampler D-17 AFCRVAL - Great Valley (background)

D-17 AFSPRVL = Springvills Sampler D-17 APVEVAL - West Valley Sampler D-17 RFDNKRK - Dunkirk (background)

D-17 AFBOEHN - Dutch Hill Road Sampler D-17 l

AFDCFOP - Dutch Hill Fallout

  • D-18 i

AFFXFOP - Fox V421ey Fallout

  • D-18 AFTCTOP - Thomar 9erners Fallout
  • D-18 AF24 FOP ~ Route 140 Fallout
  • D-18 INRCFOP - Rain Gage Fallout D-18 Off-site soil / sediment
  • SFSOL Serios - Air Sampler Area Soil D-18 SFTCSED - Thomas Corners Sediment D-18 SFDCSED - Buttermilk Background Sed.

D-18 STSD3ED - Cattaraugus at Springville Dam D-18 SFBISED - Cattaraugus Background Sed.

D-18 SFCCSED - Cattaraugus at Felton Dr.

D-18 Off-site Biologiesi (Figures D-5 and D-9)

BFFCATC - Cattaraugus Creek Fish Downatream D-19 BFFCATD - Cattaraugus creek Fish ;ownstream D-19 i

BFFCTRL - Cattaraugus Creek Fish Background D-19 BFMREZO - NNW Milk D-19

'BFMCOCO - WNW Milk D-19 BFHWIDR - SE Milk D-19 DFHHAUR - SSW Milk D-19 DTHCTLS - S Milk Background D-19 BFMCTLN - N Milk Background D-19 BTVNEAR - Produce Hearsite D-20 BTVCTRL - Produce Background D-20 BFHNEAR - Forage Nearsite D-20 BFHCTLS - Forage Background South D-20 BFHCTLH - Forage Background North D-20 BFBNEAR - Beef Nearsite D-20 BFBCTRL - Boof Background D-20 2:0NEAR Venison Nearsite D-20 BFDCTRL - Venison Background D-20 Direct Measurement Dosiestry (Figures D-7, D-8, and D-9)

DFTLD Series - Off-Site Dosimetry D-21 DNTLD Series - Or-Site Dosimetry D-22

  • Not detailed on map.

RLA0265 6RM D-3 l

1990 f FFLUEW? AWD 04-(HLMQgE(ffE WDP '

Rev.

$ AMPLE LOCAfl0N MONITORING /tfPORilWG SAMPLING COLLECTION TC ANNULL ANALYSl$ P[kIORMfD/

J D !.D. C E REQUltfMfWYS

_T YP8 /Mf D RM FRf00fbCY y 'L Cf)4PO$lf f F8[QUEWCY Main Plant Alrborre redleectsve Continucus off-Contirm us N/A Real time ntphe and beta Ventilation effluent point line air peasurement of ponitoring Exhcust Stack including LW15 and particulate fined f ILter, ANSTACK vt te ii! rat ton of f +

ronitor reptaced weekly Gas Supernatant hggitr1}rs Cont truous of f-Weekly 104 (52 per Gross at@a/ bete, game irs:tsent 054/1A LP 1 tire air locatlan)

Isotopic.* Querserly Systeve ($15) 40 CFP 61 particulate etcposite f or $r 90, Pu/U Ventilation fl(ter Isotopic, v.m*241, game txhaust footopic ANSTSTK perort ed:

ContIrmue of f-Week ly

  • 04 (52 per N3 Mmthly line desiccant location)

Envi rcrvnental colw n for Monitoring frerd water vapor Analysis collectice Anrual Ef fluent ard Cont f ruous of f

  • Weekly 104 (52 Quarterly ecnv4 site fur On Site Discharge line charcoal ccuposited 1 129 Report cartridge to 4 per location)

Annuet Environmental Monitoring Report Air tsission Annual Report (NESMAP)

  • Weikly game isotopic only if gross activity rises significantly RLA0265*6RM D-4

)

1900 f f FtV[tti ahD oni $1Tf wwlitelkG P#02f3 M P 019 tey 10 1AMPLt (OCATION MON 110RlhG/RIPORflNG LAMPLIWG COLLLCflON TOTAL AkWUAL AN AL10lt PERFO!tMCD/

AND 1.D. CfXL

_ #foUltfufwit _

T VPtjff D IU88 JELAOCY

_5AWPL f t _

d Qs2051TE fitoy B Q,._

Cesent Airborra radioective Contirmus of f-Cont t rwus N/A Rest tire elsea arvJ 14t8 lotidificatlAs effluent point Line air nessurement $f nonitoring Systerr. (C$$)

particulate flaed filter, Ventitation fynj.ttdigt noniter during reptac.ed weekiy fahaust 05R/19 LP 1 operation AMCSSTR 40 Cft 61 Contact site Pfa,rled:

Co-tirw.as of f-Wekly 104 ($2 per Gross alph4/Leta, garme teduc t ion Montht) tine tir t oc e t t or.)

Isotopic.* Quart er ly facility Invirormental particulate ccuv<, site f or Er 90, Pu/J tahaust Morettoring freed filter f ootopic, Am 241, gam AMCSRF %

Ano tysis isotopic.

Annuot Ef fluent and Cont f ruoun of f-Weekly 104 (52 ouarterly ecoposite f or On site Dischstge tins charcoal contesited 1-129 regort cartridge.

to 4 per location)

Armal Environmental Monitoring Report Air Emissions Anrust Report (NESMAP)

  • Weekly ganme isotopic only if gress activity rises significantly.

RLA0265:6RM D-5

'e 1990 tFfLUtWi AWD OWayMt NOWt1C*It*(ifff!(i g V@P-t Rev.

CAMPLE LOCAfl0W NomifCAlkC/REPOR1tWG

$AMPLING COLLitfl0N TOTAL ANWUAL AWALT1f5 M RfDRMfD/

_f WL 1.D Ctte

  1. fouleEMEWit itPf/MfDitM J #19JfWCY 1AMPit$

CCp4P0lltf f #f 0Vf NCY lupeectepacu.r AIrburris radtosctIve Cuntinuous of f.

Cont truous W/A Real tine beta ponitoring Exheust offluent point lire air measurement of j

ANSUPCV particulate fisef filter, 26 filters icf' press 3

Lt24redya monitor dartr3 collected and ales / tete, genene 05a/ft bp.e operation replaced every isotopic' upon collection A0 CfR 61 teven operating days, of at 26 Quarterly cornposites:

Lt1911t1:

Cont iruous of f -

least sonthly composited filters f or tr 90, pun Monthly litw air when unit is to 6 isotopic Am-261, geves invirormwrntal particulate eserated isotopic Monitoring frerd filter.

Analysis (smalass of 26 operating weens Annual Ef fluent and expened) 1 On site Di$ charge keport Arrunt Onvirorwental Monitoring Report I

Air Emissions Anruel Report (NL1 HAP) 4 Wedly genena isotopic only if gross activity rises significantly.

I RLA0265:6PR D-6

-o-I 1990 EFFLUENT AND ON-SITE MONIl0 RING PROGRAM WDP 019

~

R ev. 10

!-SAMPLEEOCAfl0N MONITORING / REPORTING SAMPLING COLLECTION TOTAL ANNUAL AkALTSES PEkf 0RMED/

AND I.D. CODE REQUIREMENTS TYPE / MEDIUM F2EoVENCY EAMPLES COMPOSITE FREOUENCY La7 eon 3-Prinary point of Grab liquid Discharge Weir licpid 4.viuent

~

Daily, chring 40 80 Daily gross beta, Lagoon 3 corductivity, pH. Every

WNSP.901 batch release discharge sixth daily samples grose alpha / beta, H+3, EtqyjIELbyt -

Sr*CO, ennr64 isotopic.

3SR/ip GP 2-Weighted monthly

$PDES Permit conposite of daily sanples s gross gy gr alpha / beta, H 3, C 14, Monthly NPDES 'NR sr 90, 1 129,-Jamma Isotopic, Pu/U isotopic, Ara 241 Annual Ef fluent and Composite Twice during 8 10 Tha 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> composites 0" alte Discharge liquid discharge, near f or Al, NH, As, I;0D $,

3 R port start, and near Fe, 2n, pH, suspended end solids; $0,, NO, NO,

3 3

Cr * *, Cd, Cu, Pb, N i Anruel Environnental Crab tiquid twice during 8 10 settteable solids, pH, Monitoring Report discharge, same cyanide, amenable to es conposite chlorination, oil and

grease, Dichlorodif;uoromethane, Trichtefoituoromethans, 3,3 Dichtorober.zidine, Tributytphosphate, vanadium Composite Annualty 1

Annually, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> liquid composite for Cr, Se, Ba, Sb Grab liquid Annually 1

Chtoroform Grab liquid semiannually 2

Bis (2 Ethythexyl)

Phthalate, 4*0odec na PLAU265:6RK D-7

1990 EFFLUEWT AND ON.tTE tmlTORlPG PROCR A_M WDP '

Rev.

$ AMPLE Lt? CATION MONITORING /REPORTlh0 1AMPI.lWG COLLECT 106 TOTAL ANNUAL ANALY$E$ PERf0RMED/

AWD 1.D. COOL REQUIREMENTS TYPEfffDIUM.

FREQUENCY EM3L COM'%LLf Riour wCy.

Erdman Brook at Ccebined f acility 18avd

' Weekly 52 Gross alpha / beta, N 3,

$:curity Fence litpid discharge continuous pH, corviuctivity.

WNSP006 conposite Mont* o, : vpositet sama

!.ngired14:

Liquid i so-

'd Sr 90.

0$A/lk-GP 2 Que te aposite:

C-h.

, Pu/U Btpar, igg:

isot m e Am 241.

Monthly Eriviromental Monitoring Trend Analysis Annual Environmental Monitoring Report 5:nitary Wacte Liquid effluent 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3/ month 36 Gross alpha / beta, H 1 Discharge pint for sanitary conposi te suspeMed solids, NH,

3 WNSP007 ard utility plant liquid 800 5, Fe conticed otscharge Required 6.n Grab liquid Weekly 52 pH, settleable solids SPDES Permit Reported:

Grab liquid Annually 1

Chloroto-in Monthly NPDES DMR Monthly in line monitor Continuous N/A pH Environmental with alarm Monitoring irend Analysis Amual Ef fluen; and On-site Discharge Report annual Enviromental Monitoring Report Stnitary Waste Operational sip Grab sludge on demand (at 12 Alpha / Beta, H 3 Sludge Monitoring least monthly)

WNSTPBS

  • Samples were collected simultaneously for NYSDOtt.

I BLA0265:6RM D-8 w-____________-_-____-_.-_____-_-__--_______________-_______-________________-________________-___--

1990 EFFLUEN1AND ON-SITE MON 110#1NG P90G9,13 WOP 019 R ev. 10

$ AMPLE LOCATION MOWITORING/REPORilNG SAMPLlWG ColLECTIDW TOTAL ANNUAL AhALYSES PERFORMED /

AND f.D. CODE

  1. E0VIPENENTS lt PRt'f DIUM FREQUENCY S amp! E S COMPOSITE FREQUENCY N.E. Swamp site surface Grab liquid Monthly 12 Gross alpha / beta, H-3, pH Dralncgi drair. age WNS W AMP' North Swano h22Lifq Timed Weekly

$2 Gross Alpha / beta, M 3, Dralnegi Annual Effluent ard contituous pH, conductivity WNSW74A On-site Discharge composite Report liquid Monthly coppositet garrea Isotopic, Sr-90, Quarterly conpositet C-14, 1 129, Pu/U isotopic Am-241 Nigh tevel Drains subsurf ace Grab tiquid Weekly 52 Gross..pha/ beta, M 3, (u:steform w

water from HLW pH. Monthly conpositet nderdrain storage tank area.

ganma isotopic, St-90.

WN8D1DR hl? ort edt Monthly Environmental Monitoring Trend Analysis French Drain Drains subsurface Grab tiquid 3/ month 36 pH, conductivity, B00-5, WNdP008 water f rern LLW1 fe Lagoon aren Peautred by:

Monthly 12 Gross alpha /bota, M 1 SPDES Permit rem rted.

Annually 1

Ag,Zn Monthly SPDES CMR Annual Ef fluent and On-3f te Discharge Report Annual Environmental Monitoring Report

  • $arr>Les collected simultaneously for NYSDOH.

l l

j990 EFFlutNT AND C" SITE MONITORING PROGR Att VVDP-Rev.

SAMPLE LOCAfl0N MONIT(AtlNG/ REPORT ING

"*NG COL LE CT ION TOTAL ANNUAL ANALYSES PERFORMED /

, j,ptG*,

FREQUENCY SAMPLE L,

COMPOS 11f FRf0VINCY AND t.D. COD L Rfou!REMENTS Condensate and Ca bined drainage Grab tiquid Monthly 12 Grof s alpha / beta, H 3, pH Cooling Water f rom f tcility yard Ditch aree WNSP005 R ecorted:

Internet Review Cooling Tower Coots plant utility Grab liquid Monthly 12 Gross alpha / beta, H-3, pH Basin steam system water WNCOOLW Pfc9tted:

Internet Review Site *otable Source of water Grab liquid Monthly 48 (12 per Gress alpha / beta, H 3, pH Watcr within site location)

WNDRNKW perimeter Repor'ed:

Annually 2

Toxic metals, pesticides internal Review chemical pot."' ants reint enanc e Si ti Drinking Wat:r WNDNKMS P: table Water C!orage Tank (UR) WNDNKUR hain Plant Drinking Veter WNDNKMP SDA Holding State Disposal Area Grab tiquid Annually (as 1

Gross alpha / beta, H 3, Lagoon HoWing Lagoon required)

C-14, pH, garrma isotopic, WNSP003

$r-90, 1 129, Pu/U isotopic Reoort e<j:

Annual Envirorynental Monitoring Report NYSERDA RLA0265:6RM D-10

.. ~. _,

.... - ~. -

~.

i ~ ;*

'1990 EFFtVENT AMD ON SlfE MON 170 RING PROGRAM :

WDP* 019 R ev. 10 -

.' SAMPLE [0CATIDW

~ MONITORING /RFPORilNG -

SAMPLING COLLECTION TOTAL ANNUAL

. ANALYSES PERFORMED / -

AND 1.D. CODE REQUIREMENTS TYPE / MEDIUM FREQUENCY SAMPLES COMPOSITE FREQUENCY frank's Creek E ~ ~ Dreine NYS Low-Level Crab Liquid
  • Monthly 12 Gross alpha / beta, N*3, pn I

.~of SDA-Weste Dieposet Area

' WNFRC87 t

review NYSERDA Erdman Brook N :

Dralne NYS and WDP-Grab liquid Weekly 52 Gross alpha / beta, H 3, pH of Disposst -

disposal areas-Atsee

- WNERS63 "

Recortedt

  • Monthly f;

. Internal review-NYSERDA Ditch N of WDP Drains WDP disposal Timed Weekly 52 pH NDA & SDA.

and storage eres-continuous Monthly conposites gross a

L WNNOADR:

composite alpha / beta, genna liquid isotopic, M 3. Quart.rty composite Sr 90,-I 129-F,ecorteds

. Internal review Enviroremental-Monitoring Trend -

-Analysis.

- Drsinage S of.

Reported:..

Grab liquid Weekly-52 pH -

I

^ Drts C2ti-Internet. review Monthly corpposites scoss

'.WNDCELD 2 alpha / beta, swwo e

isotopic, M 3.- Quarterly -

,compositet Sr 90, 1 129 v

1

+ -

L T

Clanples isere collected almuttaneously for_ NYS00H.

E G

l

'-!RLA0265t6RM D-11 p

cy,---,

v..

s.

b.% i

1990 EFFLUENT AND ON StTE MONITORtWC PROGRAM WDP 0 Rev. 1(

SAMPLE LOCATION MONITORING / REPORTING SAMPLING COLLECTION TOTAL ANNUAL ANALYSES PERIORMED/

_AND 1.0. CODE Rt0VIPEMENTS TYPE / MEDIUM FPEQUENCY SAMPLES CCMPOSITE Frf ouENCY On site

' Water within Grab liquid Anrually 7 10*

Gross alpha / beta, H 3, Standire Water vicinity of plant pH, conductivity, (ponds not airtorne or ground chloride, Fe, Mn, Na, rec 31ving water ef fluent phenols, sulfate 6ffluent)

R eorted:

Internet Review Test Pit N of HLW Area WNSTAW1 SloV0h SW of RTS Drun Cetl WNSTAW2 Pond SE of Heinz Road WNSTAW3 Birder Pond S of AFRT240 WNSTAW4 Border Pond SW af DFTLD13 WNSTAW5 Birrow Pit NE of Project

. Facilities WNSTAW6 4

Pond SW of Project F:cilities W of stock Springs Road WNSTAW7 Slough N of

. Quarry Creek WNSTAW8 2*rth Reservoir Nxr Intake WNSTAW9 Background Pond Ct Sprague Brook Maintenance Building

- WNSTAWB

  • Nurber of points sampled will depend upan on-site ponding conditions during the year.

A

)

.l

-1 l

l l

l l

RLA0265:6RM D-12

1990 EFFLUENT AND ON* SITE MON 110 RING PR02M WDP* 019 Fev,10 SAMPLE LOCATION

' MONITORING /REPORilNG

$AMPL]NG COLLECTION TOTAL ANWUAL ANALYSit PERFORMED /

AND 1.D. CODE

  1. f 0V!PE MENi$

TYPE / MEDIUM _

FPEQUfNCY

$AMPl[$

_ QPpjlff FPE0VENCY On site Grour+

Groun &ater Grab t iquid 4 times 144 Groas alpha / beta, N 3, water monitoring wells semiennuelty (8 genna lootopic, chloride, around site solid sanples yearly sulfste, phenols, F, waste managespent per wett)**

nit rate,10C,10H, As, unite Ba, Cs, Cr, Fe, Pb, Mn, Ng, $e, Ag, Na

~ N!W Tart

@ gr:

Direct Before ord 288 (2 Tenperature, p1, GW Monitoring Annual F,nvircrvnental measurenent of after grab sensurements conductivity j

Unit

  • Monitoring Report senple sapple per sanple l

Wette WNW discharge water collection collect ion 30 2 event) 96-7 86-8 "36 9 86 128-

> Surface WNDMPNE' Lagoon GW Monitoring Unit -

.Wetts: WNW

.She 86-3

' 86 4 86 5 80-5 80-6

! Surfaces

. WNGSEEP WNSP008 NDA GW

Monitoring
Uni t -

Wells:. WNW 83 10 86 10

. 86-11

. 921D

  • $:rves fcrmer Construction ed demolition debe1s LandfILi (CDDC)

M anpling and analysis conducted as outlined in the RCRA Groundwater Technical Enforcement Guidanc;e Docunent (EPA 0$WER 9950.1) and 5

the Stettstical Analysis of Monitoring Data at RCRA Facilities (EPA /530 SW 89 026).

RLA0265 6RM D-13 V

.--f-

-. --- - --~

.J 1990 ErrtVENT AND oN s!YE loNITo#ING PROGRAM WDP +0 Rev. 1 SAMPLE LOCATION.

MONITORING / REPORTING

$AMPLING COLLECTION-TOTAL ANNUAL.

ANALTSES PERFORMED /

AND 1.D. CCOE REQUIREMENTS TYPF/ MEDIUM FREQUENCY

$AMPLES COMPO$1TE FPEuUEN L On site Gromd.

Grounssater-Grab liquid Seelannually 22' (2 per Gross alpha /taeta, H 3, j

-watcr monitoring wells location) game isotopic j

around site facilities

. Facility / Plant Repor ed:

Ofrect Before and 44* (two Teeperature, pH, Arce Wells:

Annus Envi ronmental measurement of af ter greb.

measurements conductivity

_WNW Monitoring Report sanple senple per sample 30 3 discharge water collection collection

.i

.80 4 event)

NDA Ares Wlls: WNW w 1A

p. 'S-N sC.

'st 28 32 2C 82 3A e

324A1 32 4A2 32 4A3 '-

~ ' Fuel Storage'.

Reported:

Grab liquid temiannually 2

Gross alphs/be'ta, H+3,

~

+

Tank Subsurf ace Amuel Enviromental game isotopic, phenols,

. Monitoring Monitoring Roport TOC. benzene, tcluene.

ell WNW

.mytene.

W 13 Direct Before and Tenperature, pH, sensurement of af ter grab corductivity discharge water sapple collection-0

' *Nunber of sangles. variable; occasionally we.ls are dry.

RLA0265i6RM D-14

+.

1990 EFFLUENT AND ON SITE MONITORING Pe0cRA.M WDP 019 R ev.10

- SAMPLE LOCATION MONITORING / REPORTING

$AMPLING COLLECTION TOTAL ANNUAL ANALYSES PERFORMED /

_AND 1.D. CODE REQUIREMENTS TYPE / MEDIUM FREQUENCY

_gAMPLES COMP 05ffE rREQUENCY C;tteraugue Unrestricted surf ace Timed Weekly

$2 Gross alphe/ bete, M 3, Creek et Felton waters rec 2iving cont ity.acsis pM. Flow weighted Bridge plant ef fluenta cmpositc

' Week Ly f or month!y composite for WFFELBR

~

tiquid monthly gamne ttotopic and sr 90 conposit e R.ftnr t ed t Monthly Envirornental Monitoring Trend Analysis Annual Environmental Monitoring Report BUtttrailk Restricted surface.

Timed

'Blueekly 26 pH.

Creek, Upstream waters receiving continuous Monthly for gross tf Ctttaraugus plant ef flueMa cmposite alpha /bota, M*3.

Creek tiquid Quarterly composite for Confluence at Peported:

gansna isotopic and $r 90 Thanan Ccrners -

Annual Envircrvnental Roed Monitoring Report WFBCTCS I

Butters:l t k Restricted surf ace -

Timed

  • Biweekly 26 pH.
Creek ne:r Fox water background continuous Monthly for gross V:llty conposit e sipha/ bete, H 3.

WFBCBKO Reported:

Liquid Quarterly composite for Monthly gansne isotopic and Sr 90 Envirorvnental -

Monitoring Trend Analysis' Annual Envirorvnental Monitoring Report

' Samples tre split with NYSDOH.

RLA0265:6RM D-15

e

_1990 EFFtVENT AND ON 51TE MONITORING PROGR AM WDP '

Rev.

SAMPLE LOCATION MONITORING / REPORTING

$AMPLING COLLECTION TOTAL ANtUAL ANALYSES PERFORMED /

AND 1.D. CCOE REQUIREMENTS TYPE / MEDIUM FREQUENCY SAMPg'L COMPOSl1E FREQUENCY WFWEL Series Drinking supply Grab tiquid Annual 10 Gross alphs/ bete H 3, Wel(4 near WDP greater near genme isotopic, pH, outside WNYNSC facility cornuctivi ty P:tiseter Re w teds 3.0 km WNW A' met Envirorwental WFWELO1 Monitoring Report 1.5 km WW WFWELO2 4.0 km WW WFWEL O3

- 3.0 km WW WFWELO4 2.5 km SW WFWEto5 29 km 5 l

WFWELO6 (background) -

4.0 km NNE

.WFWELD7 -

2.5 km ENE

- WFWELOS 3.0 km SE WFWELOS 7.0 km W WFWEL10 l'

i I

RLA02F5:6RM D-16 1

e H90 Ef FL UENT !ND ON*$1TE MONITORING PROGR AM WDP 019 R ev, 10

$ AMPLE LOCATION MONITORlWC/REPOR11NG SAMPLING COLLECil0N TOTAL ANNUAL ANALYSES PE*f CAMED/

t.ND 1.D. CCVE o!Q'll RE* E NT S TYPELMJpDitM FRE0VENCY

_ SAMPt.E$

CCMPOSITE Fwf 0VENCY 3.0 km ssE et Particulate air Continuous air Weekly 468 (52 per Gross alpha / beta Fox Valley samples around particulate location)

AFFXVRD WWYWSC perimeter fitter 3.7 km WNV at Le w teds Quarterly conposite for Thomas Corners Annual Environmental Sr-90, game isotopic Road Report AFTCORD 2.0 kr NE on Monthly Continuous Weekly (2 nites 104 (52 per N3 Route 240 Environmental desiccant

    • )

site)

AFRT240 Monitoring trend colunn f',

Analysis (four sites water va-only*)

collecti, 1.5 km NW on Continuous Rock Springs charcoal 104 (52 per Quarterty conposite f or site) 1 129 Road cartridge AFRSPRD 29 km $ at Great Valley (background)
AFGRVAI, 7 km N et soringville AFSPRVL 6 km $$E at West Valtoy AFWEVAL 50 km W at Dunkirk (background)

AFDNKRK 2.3 km SW on Dutch MILL Road AFBO DIN

+ aFRT240, AFR$PRD, AFGRVAL, and AFBOENN.

    • AFRSPRD and AFGRVAL.

RLA0265:6RM D-17

g_

-, L.

f 1990 EFFtVENT AND ON SITE MONITORINC PROGRAM ~

WDP Rev.

-. SAMPLE LOCATION-MONITORING / REPORTING SAMPLING COLLECTION TOTAL ANNUAL ANALYSES PERFORMED /--

AND 1.D. CODE

' REQUIREMENTS TYPE / MEDIUM FREQUENCY SAMPLES COMPOSITE FREQUENCY

' 2.5'ka sW'.

' Collection of Integrating Monthly 60 (12 par Gross alpha / beta, N 3, pH AFDHFDP' fattout particulata liquid site) and precipitetlon --

~

3.0 km SSE around WYNSC

' AFFXFOP

.perleeter 3.7 km NNW Lt gr.

-AFTCFOP Annual Envirornental Report.

2.0 km NE AF24 FOP -

Met Tower on.

site ANRGFOP -

- Surf ace Soil--

Long term f attout surface plug Annually 10 Ganma isotopic, Sr 90, -

'(at sach of nine acctmulat ton.

conwsite soll Pu 239, Am-241 U isotopic air sanplers '.

at SRFSPRD, SFBOENN and plus 26 km SSW Reported:

SFGRVAL at Little -

Annual Environmental

'v2ltey).

Monitoring Report (year of collection)

SF So8 Series:

LButtermilk Deposition in.

Grab stream Sealannually

. 10 Gross alpha / beta, 1 Creek at themes sediment downstream -

sediment 1st sanple of isotopic ganets and Sr-90 '

Corners Road of f acility SFSCSED and

.SUCSED**

offtuents-SFSDSED each spring

  • Buttsreitk:

Reported.

~ Annually (2 2

U/Pu isotopic, Am-241 Cretk at Fox Annual Envirormental sites only")

'Vtl tty Road :

Monitoring Report

- (backgromd)

SFBCSED*'

-Cattiraugus Cresk at S;ringville Dam SFSDSED ---

Catteraugus-Creek at lBigstow Bridge:

(backgreuzf)-

SFBISED -

.Catteraugus Creek at Felton '

Bridge SFCCSED' s

  • Sample to be split with NYSDOH..

-**Anslysis on one of.two semiannual collections at SFTCSED and SFBCSED.

RLA0265a6RM~

D @

1

+

1900 FFFLUENT AND OW SITE MONITORING PROGRAM WDP 019 ' l

- Rev.10 -

'S' AMP'LE LOCATION MON 110RlWG/ REPORTING

$AMPLING COLLECTION TOTAL ANNUAL ANALYSES PERFORMED / -

=Als f.D. COD 1 REQUIREMENTS TYPE / MEDIUM FREQUCNC L SAMPLES COMPOSITE FREQUENCY i

Cattaraugus'

- Fish in Meters to atd ' Individuet Seelannually 5

Isotopic gama and Sr 90 i

Creek doMnstream of collection, teach sanple in edible portions of downstrcam of facility effluents biological.

is 10 fish) each individual fish

. the tuttermilk-

'-Creek-Reported -

L confluence Annuel Envirorenental BFFC ATC *

, Monitoring Report Control Sanple I

, 'l from notrtry i

strtas not

- gffected by' 1

Wo? (7 km or.

i more upstream of site affluont i

. BFFCTRL*po nt) --

'Cett reugus~

' Annual 1 (each -

Game isotopic ar ! sr 90 Creek-sample is 10 in edible portions of downstr o n of-fish) each individual fish

.Coringvilu Dam -

'RFFCATD-

'rab biological Monthly -

48 (12 per Gamma isotopic, $r 90, Ostry Fars,.

Milk from animals G

3.8 km NNW.

foraging scourd

(*BFMREED, site)

H 3 and 1 129 on annual BFMREED*

- f acitity parimeter

3FMC090, samples and quarterly
8FMCTLS, composites of monthly

' D3f ry Ftre, -

Recorted 8FMCTLN)

sarnptes 1.9 km WNW Arruel Envirotinental

.BFMCOBO Monitoring Report Dairy Form,._

Annual 2

3.5 k:2SE of:

(BFMWIDR, sits -

B!MMAUR)

. BFMWIDR 02iry Farm 2.5.km ssW -

. BFMHAUR '-

Control' tocation 25 km S-BFMCTLb L ontrat C

' toc 2 tion 30 km N

BFMCTLN -

r$anples chared with NY$DOli 3

I RLA0265*6RM.

D-19

[

---1990 EFFLUENT AND ON SITE MONITORING PROGR AM'-

WDP R eV. j

-SAMPLE LOCATION MONITORING / REPORTING SAMPLING COLLECTION TOTAL ANNUAL.

ANALYSES PERFORMED / -

AND 1.0. CODE REQUIREMENTS' TYPE /M(DfUM FREQUENCY SAMPLES COMPOSITE FREQUf WCY f

-Nearby Fruit and vegetables Grab biologicat

  • Annually, et 6

Ganma isotopic and Sr 90 locations grown near f acility _

. 3 each)

BFVMEAR_

perimeter downwind

'(

harvest analysis of edible -

portions, H 3 in free if possible moisture Remote' Reported:'

. toc:tione-Annual EnvirormentaL

- (16 km or more

' Monitoring Report f rom f acility)

BFVCTRL

. Reef cattle Grab biological

-Annually 2

Game isotopic, Sr 90

[

fsrage from i

nesr site toestion N BFHNEAR T

. Mitk cow f orage

- from control

.' south location or north location

- BFHCTLs or -

-- BFHCTLN.

-Beef animat_

Meet-beef foraging Grab biological Semiannuelty 4

Caen isotopic and Sr 90; from nearby

- near f aclLity.

analysis of meat, H 3 in

]

. fcru in perimeter, downwind free moisture downwind-

_if possible -

direction-iSFBNEAR

- Beef animmt Reported from control.

Annual Envirornental location (16 km.. Monitoring Report or more from

-facility)'

BFBCTRL iin vicinity of

~ Meat deer foraging Indivi&at

  • Annually,.

3' Gama isotopi and Sr 90 4

thi site (3)

' near f acility collection

& ring hunting

-analysis of. neat, N 3 in.

BFDNEAR-perimeter-

. biological.

season free moisture Control animals Reported.

  • 0uring year as 3

(3) (16 km or

< Annual-Environmental c avaltabte L

more from Monitoring Report facility).

i BFDCTRL j

' ? Sample to be split with NYSDOH 4

RLA0265:6RM D-20 ll 1.

e 1990 E F FLUENT AND OdEMONITORING PROGR A$

WDP 019 R ev. 10

$ AMPLE LOCATION MON!ToftlNG/REPORilWG SAMPLING Collitfl0N TOTAL ANNUAL ANALYSIS PERIORMfD/

JND1.D. CODE

  1. EQUIREMENit TYPE /MEDitM fPtol)[NCY___

SAMP C COMJySl1E fFE M NCY Th rmoluelnes-Direct radiation Integrating Lif Quarterly 460 (5 TLD's Quarterly genne radiation cent Dostestry around facility TLD at each of 23 exposure (TLD) sff sites loc 6tions, DFTLD Series collected 4 times per year)

At cach of 16 EC22fitYl compa:s Monthly secters, et Envirorwental noircet Monitoring Trend tccessible Analysis perimet:r point

  1. 1 16 Annual Envirorwental Monitoring Report g

"5 Psints" land fill, 19 ka S*J

-(backgro W )

  1. 17 1500 0 NW (downwind receptor ) #20 Springvllle 7 ka N #21 West V:lley 5 km SSE #22 it Vstley, 42 $

j (background)

  1. 23 DunkIrk, 50 km --

WW (backkround) 837

$;rdinic Savage RL 24 k2 NE (background) 841 EA0265:6RM D-21

9 1990 EFrtOENT AND ON Site MONITOR!NG PROGRAM WD P-Rsv.

$ AMPLE LOCATION MONITORING /REPORf!NG SAMPLING COLLECTION 101AL ANNUAL ANALYSES PEkf0RMED/

MQQ Rf0VIREMENTS TYPE /MCDIUM FRf0VENCY SAMPtfS COMPOSITE 8Rf'0VENCY Th rmoltnines.

Direct radiation on Integrating LIF Quarterly 360 (5 TLD's Quarterly game radiation cent Dosimetry f acility gromds TLD at each of 18 Aposure (1LD) on-sites ettes DNTLD Series collected 4 times per year)

At three Reported cornere of SDA Monthly

  1. 18, 19, 33 Environmental Monitoring Trend Analysis (9) et security Annual Environmental fencs atomd Monitoring Report sito #26, 26 34 (5) on-site near operctional.

arers #35, 36, 38-40 Rock 5priNs Road 500 m NNW

- of plant #25 l

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WVDP-019 Rev. 10 Appendix Et Acronyms SD-1 Spare High-Level Waste Tank 8D-2 High-Level Waste Tank BD-3 STS Hold Tank BD-4 Thorax Wuste Storage Tank AEr Atomic Energy Commission ALhRA As Low as Reasonably Achievable CFR Coda of Federal Regulationu CH Contact Handled CPC Chemical Proceen Cell CSRF Contact Site Reduction Facility CSS Cement Solidification System CTS Component Test Stand CY Calendar Year D&D Decontaminatien and Decommissioning D&H Dames and Moore DEIS Draf t Environmental Impact Statement DOE Department of Energy DOE-HQ U.S. Department of Energy-Headquarters DOE-ID U.S. Department of Energy-Idaho Operations Of fice DOT Department of Transportation DWPF Defense Waste Processing Facility EDR Equipment Decontamination Room EIS Environmental Impact dtatement EPA U.S. Environmental Protection Agency FEIS Final Environmental Impact Statsment FRS Fuel Receiving and Storage FSFCA Federal & State facilities complianco Agreement FY Fiscal Year HEPA High Ef ficiency Particulate Air Filter HIC High Integrity Container HLLW High-Levcl Liquid Wasto HLW High-Level Waste HWMP Hazardous Maste Management Program HWSF Hazardous Naste Storage Facility IDB Integrated Data Base IRTS Intograted Radwaste Treatment System IWSF Interim Waste Storage racility LADS Liquid Abrasive Decontamination System LAG LAG or Surge Storage LLW Low-Level Waste LLWT Low-Level Waste Treatment LLWTF Low-Level Waste Treatment Facility LSA LAG Storage Area LWTS Liqui.d Waste Treatment System RLA0265scRM E-1

s

  • WVDP-0{

Rev. lj

MOU Memorandum of Understanding mRihr Milli-Rnm Per Hour MSMRS Master Slave Manipulator Repair Shop MWMP Mixed Waste Managw.ent Program nCL/gm Nano Curie Per Gram NDA NRC Licensed Disposal Area NE Of fice of Assistant Sccrstary for Nuclear Energy NEPA National Environmental Policy Act of 1969 h

NESMAP National Emission Standards for Harardour Air o

Pollutants NFS Nuclear Fuel Services NOI Notice of Intent NM U.S. Nuclear Regulatory Commission j

NYS New York State NYSDEC New York State Departmant of Environmental Conservation NYSERDA New York State Energy Research and Develotenent Authority OCRWM/DP Of fice of Civilian Radioactive Waste Management / Assistant Secretary for Defense Program OJT On-the-Job Training OSR Operational Safety Requirements

-QMM Quality Management Manual RCRA Resource Conservation and Recovery Act RFRF Reactor Fuel Reprocessing Facility RH Remote Handled 4

RTS Radioactive Waste Treatment System SAA Satellite Accumulation' Area SAR Safety Analysis Report

.SDA State Licensed Disposal Area SFCM Slurry-Fed Ceramic Molter SGN Societe Generale pour les Techniques Nouvelles SH Special Hole SOP Standard Operatir.g Procedure.

SPDES State Pollution Discharge Elimination System STP

- Sewage Treatment Plant-f;

.STS Supernatant Treatment Systen TBP Tributyl Phosphate TDS Total Didsolved Solvents TLD Thermatuminescent Dosimeters TRU Transuranic TSP Treattuent, Storage', and Disposal USGS United State Geological Survey VF.

Vitrification Facility VRF-Volume Reduction Factor i

RLA0265:6RM E-2 l

{

O

9 F... ' =. 6 WVD P-0.19 f-Rev. 10 WCP-Waste Form Compliance Plan WIPP-Waste Isclation Pilot Plant WNYNSC Western New York Nuclear Service Center WSA.

Waste Storage Area WS3 Waste Storage Bullding WVDP.

West Valley Demonstration project WVNS West Valley Nuclear _ Services Company, Inc.

WVPO West Valley Project Office j

XCR Extraction Chemical Room I

.-l l

l l

i 1

HLA02E5:6RM E-3 L

_