ML041260206
| ML041260206 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 04/29/2004 |
| From: | Rich Smith Viacom |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML041260206 (9) | |
Text
Viacom 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.Smitligviacom.com VIACOM.
April 29, 2004 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 2003 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, 2003 through December 31, 2003.
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 00'9D
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 of Affiant Subscribed and sworn to before me this 29th day of April, 2004
<R>W~otar~y.Public<. _wc.;;. - -
r4 COMMONWEALTH OF PENNSYLVANIA
- Notrial Seal - .
iMrie AssPociaton OuNobaries My Comso C Expr ec. 2X :-
Member. Pennsylvania Association 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
2003 Annual Report for the WValtz Mill Facility Westinghouse Test Reactor License No. TR-2 Docket No. 50-22 Viacom Inc.
January 1, 2003 - December 31, 2003
2003 ANNUAL INSPECTION REPORT FOR RETIRED WVESTINGIIOUSE TEST REACTOR U.S.N.R.C. LICENSE TR-2 DOCKET 50-22 EXECUTIVE SUIMIMARY 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 2003, 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.
Remulatorv 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:
- 2002 Annual Report for the TR-2 License was issued on May 1, 2003.
- NRC request for additional information (RAI) to Viacom regarding the application to terminate the 10 CFR Part 50 portion of the Westinghouse Test Reactor TR-2 license dated August 26, 2003.
- Viacom response to the NRC's RAI dated September 26, 2003.
- Routine announced inspection was conducted by the NRC on October 6-7, 2003. Based on the results of the inspection, no safety concerns or noncompliances with NRC requirements were identified.
- Viacom submittal to the NRC of the Westinghouse Test Reactor Licensed Facilities Radiological Status Report dated November 4, 2003.
- Viacom supplemental submittal to the NRC's RAI dated November 12, 2003.
- NRC Inspection Report No. 50-22/2003-201 was issued on November 21,2003.
Radiation Safety Committee Activities The Radiation Safety Committee (RSC) for the TR-2 license held one meeting on April 8, 2003 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.
Oreanizational 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. Work on Phase I, Facility Preparations & Engineering; Phase 11, 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 2003 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 Waste 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 2003.
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 2003 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 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 or airborne contaminants to the environs in 2003, 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 NVTR Facility Area Proposed Decommissioning Activity Estimated Exposure j ALARA Exposure Goal j Actual Exposure by l Status (Persn-rem) (Person-rem) SRD (Person-rem) (6)
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 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 Cubiclcs/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 IIEPA 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 Vesscl/Bioshield, Transfer Canal, and Vapor Containment Building/misc. systems and components. Dose attributed to routine tours, IIEPA 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 (l) 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 year2001 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, emisting electrical removal, miscellaneous piping and component removal, and existing ventilation removal in addition 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 I 1-08-01
TABLE B ENVIRONMlENTAL RADIOLOGICALIMONITORING PROGRANM SUNINIARY Facility: Westinghouse Test Reactor Location: Westmoreland County Docket No.: 50-22 Reporting Period: January 1 to December 31, 2003 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 56.4 +/- 12.3 52.1 mrem/qtr (41.3 - 70.5) (5400-ft W of Rx)
Location mremlvr 500 ft S of Rx 41.3 90-ft W of Rx 50.7 200-ft NW of Rx 51.9 400-ft NE of Rx 70.5 1150-ft E of Rx 67.7