ML020930604

Viacom Inc. Westinghouse Test Reactor TR-2; 2001 Annual Report

ML020930604
Person / Time
Site:	Waltz Mill
Issue date:	03/25/2002
From:	Rich Smith Viacom
To:	Document Control Desk, NRC/FSME
References
Download: ML020930604 (15)

Text

Viacom Inc.

11 Stanwix Street Pittsburgh, PA. 15222-1312 Richard K. Smith Director - Environmental Remediation Telephone: 412-642-3285 Facsimile: 412-642-3957 E-mail: Richard. Smith@viacom.com VIACOM.

March 25, 2002 Document Control Center U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Viacom Inc.

Westinghouse Test Reactor TR-2; Docket No. 50-22 2001 Annual Report In accordance with Section 6.6.1 of the Westinghouse Test Reactor (TR-2) Technical Specifications, a written annual report covering the status of the test reactor decommissioning is attached. The report covers the period beginning January 1, 2001 through December 31, 2001.

Also, pursuant to 10CFR50.59 (2) and as specified in 10CFR50.4, a report containing a brief description of the changes made in 2001 to the TR-2 license under the provisions of 10 CFR 50.59 including a summary of the safety evaluation has been incorporated.

If you have any questions regarding this matter, please write or call me at the above address and telephone number or contact Mr. Wayne Vogel at (724) 722-5924.

Sincerely, Richard K. Smith Director - Environmental Remediation Attachment I - 2001 Annual Report 14co D

cc:

Mr. Alexander Adams, Jr., Senior Project Manger Non-Power Reactors and Decommissioning Project Directorate Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington D.C. 20555-0001 Robert Maiers, Chief Decommissioning Section Commonwealth of Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mr. James Yusko, Regional Manager Radiation Protection Commonwealth of Pennsylvania Department of Environmental Protection 400 Waterfront Drive Pittsburgh, Pennsylvania 15222-4745 Wayne Vogel, Radiation Safety Officer Westinghouse Electric Company

Copies transmitted: 3 notarized and 5 conformed COMMONWEALTH OF PENNSYLVANIA )

) SS:

COUNTY OF ALLEGHENY )

Before me, the undersigned notary public, this day personally appeared Richard K. Smith, Viacom Inc., 11 Stanwix Street, Pittsburgh, PA 15222, to me known, who being duly sworn according to law, deposes and says: that the statements sworn to in this letter and attachment are correct and accurate to the best of his knowledge.

Signature of affiant Subscribed and sworn to before me this 25' day of March, 2002 Notary Public Notarkd s" Mae A.Podvorec, Notry Publi Ptsburgh, Allegheny county yCommission Expires Dec. 8, 2 00 3J Marr~bar enn' r A -J-.-5o f

Attachment 1 2001 Annual Report for the Waltz Mill Facility Westinghouse Test Reactor License No. TR-2 Docket No. 50-22 Viacom Inc.

January 1, 2001 - December 31, 2001

2001 ANNUAL INSPECTION REPORT FOR RETIRED WESTINGHOUSE TEST REACTOR U.S.N.R.C. LICENSE TR-2 DOCKET 50-22 EXECUTIVE

SUMMARY

During the reporting period of January 1, 2001 through December 31, 2001, the Waltz Mill Decommissioning Project Team (WMDT) continued implementing the Westinghouse Test Reactor (WTR) Final Decommissioning Plan as approved by the NRC in Amendment 8 of the TR-2 License.

The objective of the approved decommissioning plan is to terminate the TR-2 License. As described in the Decommissioning Plan, this is to be accomplished by removing the reactor tank, its internals and portions of the biological shield. This objective will also be met by providing the NRC sufficient documentation to demonstrate that the license termination requirements have been met including all documentation required for transferring the remaining residual radioactivity and WTR Facilities to the SNM-770 License.

Site decommissioning activities are conducted in accordance with approved procedures, work packages and the TR-2 License. All WTR work packages are reviewed and approved by the TR-2 Radiation Safety Committee (RSC). The RSC monitors decommissioning operations to ensure they are performed safely and according to federal, state and local regulatory requirements (NRC, EPA, PADEP, DOT, etc.).

Both site and project radiological controls personnel continue to monitor the radiological conditions at the site to assure protection of the health and safety of the general public and site personnel.

This report reviews those activities as required by the Technical Specifications Section 6.6.1 and includes the following:

1. A narrative summary of facility activities.

2. Tabulation of the major preventative and corrective maintenance operations having safety significance.

3. A brief description of major changes in the reactor facility and procedures and activities significantly different from those performed previously and not described in the safety analysis report, and a summary of the safety evaluation that shows no unreviewed safety questions were involved (per 10CFR50.59 (2)).

4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective controls of the licensee as determined at or before the point of such releases or discharge. The summary shall include to the extent practical, an estimate of the major individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed or recommended, a statement to this effect is sufficient.

5. A summarized result of the environmental survey performed outside the facility.

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1. A Narrative Summary of Facility Activities.

Facility Operations In 2001, the Waltz Mill Decommissioning Team (WMDT) continued to implement the Westinghouse Test Reactor Final Decommissioning Plan as approved by the U.S. Nuclear Regulatory Commission by Amendment 8 to the TR-2 License on September 30, 1998. Some general area decontamination and clean up was also performed. A list of significant activities is provided below:

"* Decontamination and survey of the Primary Coolant Tunnel.

"* Decontamination and survey of the Top Loop Tunnels.

"* Decontamination and survey of the Transfer Canal.

"* Decontamination and survey of the Diesel Pump Pit.

"* Decontamination and survey of the Sub-Pile Room.

"* Decontamination and survey of the Containment Building.

"* Decontamination and survey of the Polar Crane.

ALARA Data All decommissioning activities were planned and conducted in accordance with the site ALARA policy and comprehensive safety programs. WMDT places the highest priority on conducting the Waltz Mill Decommissioning Project safely and maintaining exposure to ionizing radiation ALARA. An ALARA summary for the WTR facilities decommissioning activities is provided in attached Table A.

Regulatory Interfaces Throughout the year, the licensee communicated with the USNRC. These communications took place via written correspondence, telephone calls and meetings. Significant results are noted below:

• Viacom and Westinghouse submitted monthly updates to the NRC on the status of the decommissioning activities underway at Waltz Mill.

• A telephone conference call was held on January 23 with representatives from NRC Region 1 and Headquarters to discuss the process for transferring the Westinghouse Test Reactor facilities to the SNM-770 license and terminating the TR-2 license.

• 2000 Annual Report for the TR-2 License was issued on March 9, 2001.

Radiation Safety Committee Activities The Radiation Safety Committee (RSC) for the TR-2 license provided management oversight and review of the WTR decommissioning activities. During 2001, the RSC reviewed the status of the decommissioning project, results of audits and inspections, and performance against ALARA objectives.

In accordance with the Section 6.2.4 of the TR-2 Technical Specifications, the RSC conducted independent audits of decommissioning activities - specifically, an audit of "facility activities for conformance to the Technical Specifications and License" (6.2.4.1) and "The results of actions taken to correct those deficiencies that may occur in the reactor facility equipment, Page 2

systems, structures or methods of operations that affect facility safety" (6.2.4.3). These audits were performed on November 6, 7 and 8, 2001. Audit deficiencies were documented and corrective actions were immediately initiated by the project. The auditors concluded that the WTR facility activities were being conducted in accordance with the Technical Specifications and the TR-2 License.

Organizational Changes The current management organization relative to the administration of License TR-2 is as follows:

"* Richard K. Smith, Viacom Decommissioning Project Director, is the senior site manager having responsibility for the retired WTR facilities.

"* Russell G. Cline remains as the Westinghouse Nuclear Services Manager, Environment, Health and Safety (EHS)

"* Wayne D. Vogel, Radiation Safety Officer, reports directly to Mr. Cline.

A current organizational chart is attached.

Summary In summary, work on the TR-2 Decommissioning Plan has been authorized by the NRC. Work on Phase I, Facility Preparations & Engineering, is complete. Phase II, Reactor Tank Removal, platform and structural interference and bioshield removal are complete. Phase III, Building &

Structures Remediation, was concluded on November 8, 2001. A current project schedule is attached.

2. Tabulation of the major preventative and corrective maintenance operations having safety significance.

Since reactor fuel was removed from the reactor and the site decades ago, the Westinghouse Test Reactor as described in the Decommissioning plan and in the Technical Specifications does not contain any nuclear safety related equipment.

3. A brief description of major changes in the reactor facility and procedures and activities significantly different from those performed previously and not described in the safety analysis report, and a summary of the safety evaluation that shows no unreviewed safety questions were involved.

In 2001, license reviews of work packages and procedures were performed to provide administrative controls over physical or procedural activities to preclude adverse impacts on the safe dismantling and decommissioning operations conducted under the TR-2 License. During this time, no proposed activity required a safety evaluation pursuant to 10 CFR50.59.

4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective controls of the licensee as determined at or before the point of such releases or discharge. The summary shall include to the extent practical, an estimate of the major individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed or recommended, a statement to this effect is sufficient.

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Low Level Radioactive Waste Low-level radioactive, solid debris and dry active waste from the WTR was collected, packaged and transported for either processing or burial at a licensed facility. During 2001, 13,282.5 cubic feet of LLW containing 2,008.5 mCi was shipped for disposal. The 2001 waste shipments are summarized in the Attachment B.

All 14,195 gallons of contaminated water from the WTR collected in 2001 was processed through an on-site water treatment system. The primary source of water was the transfer canal and diesel pump pit. This water was processed, analyzed and disposed by discharge to a public sanitary sewage treatment facility in accordance with 10CFR20.2003. The collected water was processed along with water from the SNM-770 license. All water disposed by discharged to the public sanitary sewage plant was less than 20% of the 10 CFR 20, Appendix B, Table 3 limits.

The total activity discharged from both licenses, utilizing the on-site water processing system, was 391 jiCi tritium and 424 1.Ci other beta-gamma emitters.

Airborne Releases In order to support decommissioning activities in the WTR, a HEPA ventilation unit was installed to maintain negative pressure in containment and to provide for a controlled and monitored discharge of airborne activity. The stack is continuously monitored for air particulate. The filter samples are typically collected weekly and analyzed for gross beta and alpha activity. The average monthly concentration is then determined from this data. During 2001, the estimated average release measured at the point of discharge was less than 25% of the 10 CFR 20, Table 2, Column 2 concentration. This determination was made using the most restrictive radionuclides possibly present (Sr-90/Pu-239). A summary of the releases from the WTR ventilation system is contained in Table C.

In accordance with Regulatory Guide 4.20, "Constraint on Releases of Airborne Radioactive Materials to The Environment For Licensees Other Than Power Reactors" the facility is in compliance with 10 CFR 20.1101 (d). This was determined using the COMPLY program (V 1.6) and the data from Table B. The COMPLY Code determined the facility was in compliance at Screening Level 1.

Liquid Effluent Releases There were no discharges of liquid effluents to the environs from the WTR in 2001. All liquid waste was processed and discharged to a public sanitary sewage facility in compliance with 10 CFR 20.2003.

5. A summarized result of the environmental survey performed outside the facility.

Environmental monitoring associated with the WTR decommissioning is in accordance with the programs and requirements of the SNM-770 license. Various environmental media and pathways are sampled under the SNM-770 License. Only media and pathways relevant to the WTR decommissioning are summarized in this report. Since there have been no discharges of liquids to the environs in 2001, the data presented is limited to the media and pathways relevant to airborne releases and direct radiation.

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Direct radiation was measured with a series of TLDs deployed throughout the site and along the perimeter of the Central Operations Area. The TLDs contain aluminum oxide TL material with a dose reporting level of 0.1 mrem/quarter. Data collected from the TLDs near the WTR facility is summarized in Table D. Radiation levels recorded include those associated with activities under the SNM-770 license.

An environmental air sampling station is located approximately 3600-ft downwind of the WTR stack. A second station is located approximately 500-ft upwind of the stack. A measured volume of air is drawn through a particulate filter. The filters are collected and analyzed weekly for gross alpha and beta activity using a gas-flow proportional counter. The downwind air samplers are also downwind of several stacks associated with the SNM-770 license.

Surface soil samples are collected annually from four locations north, south, east, and west along the site boundary. The samples are collected to a depth of 15-cm. Gamma isotopic and strontium-90 analyses are performed on each sample.

Vegetation samples are collected annually at the same locations as the soil samples. Gamma isotopic and strontium-90 analyses are performed on each sample.

A summary of the SNM-770 environmental measurements relevant to the WTR Decommissioning Project is contained in Table D.

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Table A WTR Facilities Decommissioning Activities ALARA Summary WTR Facility Area Proposed DecommissioningActivity Estimated Exposure ALARA Exposure Goal Actual Exposure by Status I I (Person-rem) (Person-rem) SRD (Person-rem) (6)

Pre-Decommissioning Activities Establish Radiological Controls. 0.050 0.040 0 Inactive - Complete.

Reactor Vessel, Internal Contents, Biological Shield sectioning and and Biological Shield removal, one piece Reactor Vessel & 18.91 (5) 15.128 7.368 (4) Inactive - Complete.

internal component removal Components removed, concrete Sub Pile Room decontamination, and partial or full 0.850 0.680 0.292 (1), (2) Inactive - Complete demolition.

Components removed, concrete Rabbit Pump Room decontamination, and partial or full 0.080 0.064 0.017 Inactive - Complete demolition.

Components removed, concrete Test Loop Cubicles/Dump Tank decontamination, and partial or full 0.410 0.328 0.208 (1), (2) Inactive - Complete Pits demolition.

Piping removed, concrete Primary Coolant Pipe Tunnel decontamination, and partial or full 1.880 1.504 0.683 (2) Inactive - Complete demolition.

Water drained, sediment removed, Transfer Canal concrete decontaminated, and partial or 7.930 6.344 4.945 (1), (2) Inactive - Complete full demolition.

Miscellaneous systems and components Vapor Containment Building and decontaminated and/or removed, 0.890 0.712 0.527 (3)

Misc. systems and components concrete and structure surfaces Inactive - Complete decontaminated, and Polar Crane decontaminated.

Totals 31.000 24.800 14.040 (1) Dose attributed to the installation of temporary power and lighting, installation ot new ventilation, routine tours, routine maintenance, Asbestos removal, installation ofthe Truck Lock door, inspection and repair of the Polar Crane, and routine HEPA unit/vacuum maintenance prior to the year 2000 was divided equally between the major activities of Reactor Vessel/Bioshield, Sub Pile Room, Test Loop Cubicles/Dump Tank Pits, and Vapor Containment Building/misc. systems and components as they were preliminary or continuing integral parts of the major activities. Dose attributed to routine tours and HEPA unit/vacuum maintenance for the year 2000 was divided equally between Reactor Vessel/Bioshield and Transfer Canal. Dose attributed to routine maintenance for the year 2000 was divided equally between Reactor Vessel/Bioshield, Transfer Canal, and Vapor Containment Building/misc. systems and components. Dose attributed to routine tours, HEPA unit/vacuum maintenance, and routine maintenance for the year 2001 was divided equally between Transfer Canal, Primary Coolant Pipe Tunnel, and Vapor Containment Building/misc. systems and components.

(2) Dose attributed to Health Physics support prior to the year 2000 was divided equally between the four identified active major activities in (1) and the Primary Coolant Pipe Tunnel. Dose attributed to Health Physics Support for the year 2000 was divided equally between Reactor Vessel/Bioshield and Transfer Canal. Dose attributed to Health Physics support for the year 2001 was divided equally between Transfer Canal, Primary Coolant Pipe Tunnel, and Vapor Containment Building/misc. systems and components.

(3) Contains dose attributed to miscellaneous structural removal, existing electrical removal, miscellaneous piping and component removal, and existing ventilation removal in addition to (1) and (2) above.

(4) Contains dose attributed to the major activity, exploratory work on the Reactor Vessel, core stabilization, and trunnion reinforcement in addition to (1) and (2) above.

(5) Estimate is for Option (3), which includes the removal of the Biological Shield, attachment of shielding plates to the Reactor Vessel, and down-ending and removal of the Reactor Vessel, with internal components intact, out of the Containment Building through the Truck Lock.

(6) Data through 11-08-01

Table B 2001 Solid Radioactive Waste Shipments Shipment Id. Date Destination Activity Gross Gross Waste Type mCi Pounds Cubic Feet LRW 2001-337-RT 10/10/01 Alaron 499.60 5,021 103.5 Pb. Acid Batteries / Activated Metals LRW 2001-332-RT 9/19/01 Duratek 315.00 17,000 1,216 Compactable LRW 2001-047-RT 1/25/01 Duratek 312.70 16,500 576 Comp Metals LRW2001-151-RT 4/11/01 MSC 301.00 22,000 1,360 Lead-WTR LRW 2001-128-RT 4/9/01 Duratek 106.00 28,100 2,720 DAW / Metal Comp. S L LRW 2001-119-RT 4/4/01 Duratek 98.70 26,750 960 Metal Melt & DAW LRW 2001-124-RT 3/29/01 MSC 97.00 9,275 113 Lead - WTR LRW 2001-133-RT 4/4/01 Duratek 80.80 15,250 1,056 Metal Melt & DAW LRW 2001-241 -RT 6/11/01 Duratek 59.20 22,450 1,152 Metal Melt / DAW LRW 2001-240-RT 6/11/01 Duratek 48.50 16,900 1,152 Metal Melt/ DAW LRW 2001-294-RT 8/16/01 Duratek 44.50 14,300 1,029 Metal Melt / DAW LRW 2001-321-RT 9/13/01 Duratek 28.60 10,875 467 Metal Melt / DAW LRW 2001-078-RT 2/21/01 Envirocare 16.90 76,600 1,378 Scabble Dust Totals 2008.5 281,021 13,282.5 Alaron 499.60 5,021 103.5 Duratek 1,094 168,125 10,328 MSC 398 31,275 1,473 Envirocare 16.90 76,600 1,378 Page 7

Table C Summary of Releases from the WTR Ventilation System Month Average Beta Activity Average Alpha Activity of Samples) Gross Beta (Range) Discharged D ishre Gross Alpha (Range) Discharged D cishre Samples) *iCi/ml _Ci__Ci/ml__ _i Jan-01 9.8E-15 7.2e-16 (4) (6.7E 9.0E-14) (3.6E 1.3E15)

Feb-01 8.3e-15 3.3E-16 (4) (4.1E 1.9E-14) (2.6E 3.9E-16)

Mar-01 8.1E-15 4.5E-16 (4) (4.1E 1.2E-14) (1.8E 7.7E-16)

Apr-01 8.5E-15 4.9E-16 (5) (7.3E 1.1E-14) (1.8E 1.3E-15)

May-01 9.1E-15 2.6E-16 (5) (5.4E 5.4E-14) (-3.3E 5.4E-16)

Jun-01 7.2E-15 5.7E- 16 (5) (3.5e-15 -2.7E-14) (1.6E 1.5E-15)

Jul-01 6.8E-15 1.8E-16 (4) (5.5E 1.7E-14) (7.9E 2.6E-16)

Aug-01 6.2E-15 3.3E-16 (4) (5.3E 3.3E-14) (1.3E 1.6E-15)

Sep-01 5.3E-15 6.5E-16 (5) (2.3E 7.5E-15) (3.3E 7.9E-16)

Oct-01 4.3E-15 6.5E-16 (3) (1.4E 8.8E-15) (3.6E 1.1E-15)

Nov-01 Not Operating Not Operating Dec-01 Not Operating Not Operating Annual 7.3E-15 4.6E- 16 (43) (1.4E 9.OE-14) (-3.3E-16 - 5.4E-15)

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TABLE D ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Facility: Westinghouse Test Reactor Location: Westmoreland County Docket No.: 50-22 Reporting Period: January 1 to December 31, 2001 Medium or Type and Lower Limit All Indicator Locations Control pathway Number of Of Mean Location Sampled Analyses Detection (Range) Result (Unit of Performed (LLD)

Measurement)

Direct Radiation (mrem/year) TLD (5) 0.1 mrem/qtr 57.5 +/- 8.7 52.6 (43.4 - 64.9) (5400-ft W of Rx)

Location mrem/yr 500 ft S of Rx 43.4 90-ft W of Rx 56.5 200-ft NW of Rx 58.6 400-ft NE of Rx 64.9 1150-ft E of Rx 64.5 Air Particulate (pCi/m 3) Gross Beta (52) 0.003 0.057 +/- 0.017 0.056 +/- 0.016 (0.029 - 0.104) (0.028 - 0.097)

Gross Alpha (52) 0.001 0.002 +/- 0.001 0.002 +/- 0.001 (0.000 - 0.006) (0.000 - 0.006)

Surface Soil Gamma Spec (4)

(pCi/gram-dry) Cs-137 0.05 0.58 +/- 0.40 0.165 +/- 0.039

(-0.002 - 0.851)

Co-60 0.05 -0.014 +/- 0.003 0.004 +/- 0.019

(-0.017 - -0.010)

Strontium-90 0.4 0.222 +/- 0.191 0.374 +/- 0.320 (0.044 - 0.430)

Vegetation (pCi/gram-ash) Gamma Spec (4)

Cs-137 0.05 0.006 +/- 0.012 0.0249 +/- 0.026

(-0.006 - 0.021)

Co-60 0.05 0.007 +/- 0.011 0.0314 +/- 0.028

(-0.003 - 0.021)

Strontium-90 0.4 0.434 +/- 0.139 0.543 +/- 0.26 (0.258 - 0.590)

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WALTZ MILL DECOMMISSIONING PROJECT PROJECT SCHEDULE 1999 2000 2001 SJF MA M J JASON D J F MA M J JASO N D J F MDA M J JASON RT Removal Engineering Top Level Plan -H Design Specifications Facilities Preparations Temp Power/Lighfing Ventilation System Asbestos Abatement Investigation &Exploratory Repair Truck Lock Door Repair Polar Crane Reactor Tank (RT) Removal Remove Bio-Shield Interferences Stabilize Core Region Wire Cut Bio-Shield Remove Reactor Tank Ship Reactor Tank Building &Structures Sub-Pile Room Test Loop Cubicles & Pits Remove Retired Electrical Remove Retired Ventilation Transfer Canal Primary Coolant Pipe Tunnels Remove Misc. Piping Rabbit Pump Room Decon Polar Crane Top Loop Tunnels Containment Decon 1/31/02 Page 10

WTR DECOMMISSIONING PROJECT ORGANIZATION N otes:

1) The Radiation Safety Officer reports to the Westinghouse, EHS Manager and is also the Secretary of the Radiation Safety Committee.

2) Denotes a contractual relationship.

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