ML051370442

Westinghouse Test Reactor, 2004 Annual Report

ML051370442
Person / Time
Site:	Waltz Mill
Issue date:	05/10/2005
From:	Rich Smith Viacom
To:	Document Control Desk, NRC/FSME
References
Download: ML051370442 (9)

Text

Viacorn Inc.

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

May 10, 2005 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 2004 Annual Report In accordance with Section 6.5.1 of the Westinghouse Test Reactor (TR-2) Technical Specifications, a written annual report is attached. The report covers the period beginning January 1, 2004 through December 31, 2004.

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 Vice President - Environmental Remediation Attachment

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, Vice President, Environmental Remediation, Viacom Inc., 11 Stanwix Street, Pittsburgh, PA 15222-1384, 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 ffiant Subscribed and sworn to before me this 1 th day of May, 2005 N

N NotaryLublic Notaiial Seal Beth A.Stelgerwald, Notary Public Fofti Park Boro, Aflgh Caknty My Commission Expires Feb. 4,2007 Merber, PervMyaria Associa6n Of Notaries

cc: Regional Administrator U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Patrick Isaac, Project Manager Research and Test Reactors Section Office of Nuclear Reactor Regulation Mail Stop 0-12G13 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Mr. 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 G.Yusko, Regional Manager Radiation Protection Commonwealth of Pennsylvania Department of Environmental Protection 400 Waterfront Drive Pittsburgh, PA 15222-4745 Mr. Wayne Vogel, Radiation Safety Officer Westinghouse Electric Company LLC P.O. Box 158 Madison, PA 15663-0158

2004 Annual Report for the Waltz Mill Facility Westinghouse Test Reactor License No. TR-2 Docket No. 50-22 Viacom Inc.

January 1, 2004 - December 31, 2004

2004 ANNUAL INSPECTION REPORT FOR RETIRED WESTINGHOUSE TEST REACTOR U.S.N.R.C. LICENSE TR-2 DOCKET 50-22 EXECUTIVE

SUMMARY

Site 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 6.5.1 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 10 CFR 50.59 (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.

Page I

1. A Narrative Summary of Facility Activities.

Facility Operations In 2004, no decommissioning activities or significant maintenance activities occurred. Activities were limited to routine tours and inspections including an annual routine HP survey in July. Conditions were as expected, no abnormal conditions were observed. No waste shipments or restricted activities as defined by technical specifications occurred. The stack was not operated and there were no air or liquid effluent releases.

Reaulatorv 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 supplemental submittal to the NRC's Request for Additional Information dated February 6, 2004.

• 2003 Annual Report for the TR-2 License was issued on April 29, 2004.

• Viacom consented to the issuance of an order imposing requirements for protecting certain Safeguard Information in correspondence dated November 16, 2004.

Radiation Safety Committee Activities The Radiation Safety Committee (RSC) for the TR-2 license held one meeting on November 23, 2004 to review the status of the decommissioning project, results of audits and inspections, and performance against ALARA objectives. Since there were no decommissioning activities performed in 2003, no independent audits in accordance with Section 6.2.4 of the TR-2 Technical Specifications were performed and no additional RSC meetings were held.

Organizational Chances 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.

Page 2

1. Summary Work on the TR-2 Decommissioning Plan has been authorized by the NRC. WVork on Phase I, Facility Preparations & Engineering; Phase II, Reactor Tank Removal, platform and structural interference and bioshield removal and Phase III, Building & Structures Remediation has been completed. Table A provides an ALARA summary of the previous decommissioning activities.

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 2004 there were no decommissioning or other significant activities performed. Therefore no license reviews of work packages or safety evaluations pursuant to 10 CFR 50.59 were performed.

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.

Low Level Radioactive NN Tastc No low-level radioactive, solid debris or dry active waste from the WTR was collected, packaged or transported for either processing or burial at a licensed facility in 2004.

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. In 2004 there were no decommissioning activities, the HEPA unit was not operated and there were no airborne releases.

Liquid Effluent Releases There were no discharges of liquid effluents to the environs from the WTR in 2004.

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 or airborne contaminants to the environs in 2004, the data presented is limited to direct radiation.

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 B.

Radiation levels recorded include those associated with activities under the SNM-770 license.

Page 3

Table A WTR Facilities Decommissioning Activities ALARA Summary NVIR Facility Area j Proposed Decommissioning Activity Estimated Exposure 1 ALARA Exposure Goal 1 Actual Exposure by l Status (Person-rem} (Person-rem) SRD (Person-rem) (6) l Pre-Decommissioning Activities Establish Radiological Controls. 0.050 0.040 0 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) Complete internal component removal Components removed, concrete Sub Pile Room decontamination and partial or full 0.850 0.680 0.292 (1), (2) Complete demolition.

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

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

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

Water drained, sediment removed, Transfer Canal concrete decontaminated, and partial or 7.930 6.344 4.945 (1), (2) 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 Complete decontaminated, and Polar Crane decontaminated.

Totals . 31.000 24.800 14.040 (I) Dose attributed to the installation of temporary power and lighting, installation of new ventilation, routine tours, routine maintenance, asbestos removal, installation of the Truck Lock door, inspection and repair of the Polar Crane, and routine HEPAunit/vacuum maintenance prior to the year2000 was divided equally between the major activities of Reactor VesselfBioshield, Sub Pile Room, Test Loop Cubicles/Dump Tank Pits, and Vapor Containment Building/misc. systems and components as they were preliminary or continuing integral pats of the major activities. Dose attributed to routine tours and HEPA unit/vacuum maintenance for the year 2000 was divided equally beween Reactor VesselBioshield 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 year2001 was divided equallybetween Transfer Canal, Primary Coolant Pipe Tunnel, and Vapor Containment Building/misc. systems and components.

(2) Dose attributed to Iealth Physics support prior to the year 2000 was divided equally between the four identified active major activities in (I) and the Primary Coolant Pipe Tunnel. Dose attributed to Health Physics Support for the year 2000 was divided equallybetween Reactor Vesse/Bioshield and TransferCanal. Dose attributed to Health Physics support for the year2001 was divided equallybetween 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 inaddition to (I) 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 ( I) 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 ENVIRONNIENTAL RADIOLOGICAL MONITORING PROGRAM SUNMNMARY Facility: Westinghouse Test Reactor Location: Westmoreland County Docket No.: 50-22 Reporting Period: January 1 to December 31, 2004 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 (mnrem/year) TLD (5) 0.1 56.0 +/- 10.5 56.9 mrem/qtr (40.3 - 68.3) (5400-ft W of Rx)

Location mremlvr 500 ft S of Rx 40.3 90-ft W of Rx 52.2 200-ft NW of Rx 57.7 400-ft NE of Rx 68.3 1150-ft E of Rx 66.8