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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D0681999-10-0707 October 1999 Forwards First of Planned Series of Progress Repts Re Status of Remediation & Decommissioning Work Underway at W Waltz Mill Site Near Madison,Pa ML20216K0441999-10-0404 October 1999 Forwards Proposed Replacement Pages to TR-2 Ts,In Order to Provide Addl Clarifications & to Accommodate Minor Editorial Changes.Ts Amend Would Clarify Facility Boundaries ML20216J7501999-10-0101 October 1999 Forwards Proposed Replacement Pages to Decommissioning Plan & for Ts.Pages Are Being Submitted to Replace Similar Pages Previously Transmitted in ML20195H4271999-06-14014 June 1999 Forwards Annual Insp of Retired Wtr Per License TR-2 for 1998.Physical Status of Retired Facility Remains Same as It Was at Time of Last Rept ML20205C8671999-03-26026 March 1999 Forwards ,Addressing Concern Raised in Insp Findings at Westinghouse Test Reactor at Waltz Mill,Pa Under Rept Number 50-022/99-201 ML20205C7461999-03-25025 March 1999 Forwards Amend 9 to License TR-2 & Safety Evaluation.Amend Revises License to Reflect Change in Legal Name of Licensee for W Test Reactor to CBS Corp ML20204F6351999-03-18018 March 1999 Expresses Appreciation to NRC for Forwarding Copy of Insp Rept 50-022/99-201 Reflecting Results of 990203 Insp of W Test Reactor at Waltz Mill Site.Review of Insp Rept Raises Listed Concerns.Nrc Help in Matter Would Be Appreciated ML20205L1141999-03-12012 March 1999 Partially Deleted Ltr Establishing Irrevocable Standby Ltr of Credit in NRC Favor,At Request & for Account of W ML20207M5201999-03-0505 March 1999 Forwards Insp Rept 50-022/99-201 on 990201-03.No Violations Noted.Various Aspects of Reactor Operations,Maint,Safety & Emergency Preparedness Program Were Inspected ML20198L0781998-12-21021 December 1998 Forwards Environ Assessment & Finding of No Significant Impact Re 980928 & 1117 Applications for Amend to License TR-2 to Reflect Change in Legal Name of Licensee from CBS Corp Acting Through W Div to Simply CBS Corp RA-98-070, Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change1998-11-17017 November 1998 Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change ML20154G6871998-09-30030 September 1998 Forwards Amend 8 to License TR-2 & Se.Amend Approves Decommissioning Plan for Wtr,In Response to 980731 Submittal & Suppls & 0710.Amend Also Authorizes Approved Decommissioning Plan to Be Included as Suppl to Wtr SAR ML20154B0481998-09-28028 September 1998 Establishes Irrevocable Standby Ltr of Credit 1484 in NRC Favor,At Request & for Account of W,Up to Aggregate Amount of $11,098,000 Upon Presentation of Sight Draft & Signed Statement ML20236V8941998-07-31031 July 1998 Forwards Amend 7 to License TR-2 & Safety Evaluation.Amend Revises Facility License in Response to 971222 Application for Amend Suppl 980615 to Reflect Change in Legal Name for Wtr from Westinghouse Electric Corp to CBS Corp RA-98-038, Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified1998-07-10010 July 1998 Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified ML20236F7461998-06-26026 June 1998 Forwards Copy of EA & Fonsi Re Application for Amend Dated 971222.Proposed Amend Would Revise Possession Only License for Westinghouse Test Reactor at Waltz to Reflect Change in Legal Name from Westinghouse Electric Co to CBS Corp RA-98-033, Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl1998-06-15015 June 1998 Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl ML20216F2231998-04-13013 April 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety IA-98-100, Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety1998-04-13013 April 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety RA-98-021, Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept1998-03-20020 March 1998 Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept ML20199A2981998-01-21021 January 1998 Forwards Request for Addl Info Re Review of Westinghouse Test Reactor Decommissioning Plan Submitted by . Response to Encl RAI Should Be Submitted within 60 Days of Ltr Date ML20199G9611998-01-20020 January 1998 Permits Withdrawal of 970818 Application to Transfer & Amend License for Westinghouse Test Reactor Facility. Withdrawal Notice Encl RA-98-008, Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept1998-01-20020 January 1998 Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept RA-97-091, Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility1997-12-18018 December 1997 Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility ML20217F0181997-09-23023 September 1997 Forwards Notice of Consideration of Approval of Transfer of License & Issuance of Amend to Facility License,Proposed NSHC & Opportunity for Hearing. Notice Relates to 970818 Application Seeking Approval of Transfer of Authority ML20217E4181997-09-23023 September 1997 Forwards EA & Fonsi Re 970818 Application for Approval of Transfer of License for Waltz Mill Test Reactor from W to (1886) to (1997) & Issuance of Conforming Amend,Per 10CFR50.80 & 10CFR50.90 ML20141J8171997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr.All Activities Re Non-Power Reactors Including Licensing,Insp & Operator Licensing Will Be Responsibility of NRR RA-97-053, Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site1997-07-31031 July 1997 Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site ML20147H8931997-04-0707 April 1997 Forwards W Repts Conceptual Remediation Plan & Conceptual Decommissioning Plan, Which Provides Time Schedule for Radiological Remediation of Wtr Facility & Objectives, Priorities,Schedule & Remediation Approaches IR 05000022/19970011997-03-0606 March 1997 Forwards Insp Rept 50-022/97-01 on 970203-05.No Noncompliance Noted ML20057F3401993-10-0404 October 1993 Forwards Insp Rept 50-022/93-01 on 930913.No Safety Concerns or Violations Noted RS-93-008, Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities1993-02-0505 February 1993 Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities ML20126D3651992-12-21021 December 1992 Forwards Annual Rept of Insp of Retired Westinghouse Test Reactor for 1992 ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20215C4061987-05-29029 May 1987 Informs of Recent Reorganization of Nrr.T Michaels Assigned as Project Manager for Facility ML20210F7271987-02-0505 February 1987 Forwards Addendum to Annual Insp Rept for Retired Westinghouse Testing Reactor for 1986, Per J Dosa 870128 Telcon W/Author.Addendum Provides Clarification & Addl Info ML20207C4801986-12-22022 December 1986 Forwards Annual Insp of Retired Westinghouse Testing Reactor Per License TR-2 for 1986 ML20138P8891985-12-16016 December 1985 Forwards Annual Insp of Retired Westinghouse Test Reactor (License TR-2) for 1985.Status of Retired Facility Remains Same as Last Rept ML20216F7431969-05-19019 May 1969 Forwards Order Authorizing Partial Dismantle of Wtr to Extent Described in 690429 Application & Suppl, . Notice of Issuance of Order Also Encl ML20216F7351967-06-28028 June 1967 Discusses Re Request for Renewal of License TR-2 ML20216F7181963-03-25025 March 1963 Forwards Amend 2 to License TR-2,authorizing W to Possess, But Not to Operate Wtr.Also Encl Are Notice of Amend & Hazards Analysis Rept ML20216F6401962-03-0202 March 1962 Forwards Analysis of Safety Operation of Wta.Authorization Granted to W to Transfer Sf Elements to Pool in Decontamination Bldg for Storage Prior to Shipment Off Site ML20216F5041960-07-28028 July 1960 Forwards Rept Re Release of Contaminated Water to Storm Sewers on Wtr Site.Prevention of Further Releases of This Type Are Listed ML20216F5401960-07-18018 July 1960 Submits Table Giving Suitable Operating Conditions Which Will Be Observed During Escalation Program.Wtr Operating Procedures P-107 Detailing Action to Be Taken by Reactor Operating Staff in Event of Reactivity Changes Encl ML20216F2411960-06-30030 June 1960 Forwards Order issued,600630,respecting Operation of Westinghouse Testing Reactor ML20216F4091960-04-0404 April 1960 Forwards Rept Dealing W/Incident Involving Release of Radioactivity at Wtr Site,Per Requirements of Wtr Emergency Procedures 1999-06-14
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D0681999-10-0707 October 1999 Forwards First of Planned Series of Progress Repts Re Status of Remediation & Decommissioning Work Underway at W Waltz Mill Site Near Madison,Pa ML20216K0441999-10-0404 October 1999 Forwards Proposed Replacement Pages to TR-2 Ts,In Order to Provide Addl Clarifications & to Accommodate Minor Editorial Changes.Ts Amend Would Clarify Facility Boundaries ML20216J7501999-10-0101 October 1999 Forwards Proposed Replacement Pages to Decommissioning Plan & for Ts.Pages Are Being Submitted to Replace Similar Pages Previously Transmitted in ML20195H4271999-06-14014 June 1999 Forwards Annual Insp of Retired Wtr Per License TR-2 for 1998.Physical Status of Retired Facility Remains Same as It Was at Time of Last Rept ML20204F6351999-03-18018 March 1999 Expresses Appreciation to NRC for Forwarding Copy of Insp Rept 50-022/99-201 Reflecting Results of 990203 Insp of W Test Reactor at Waltz Mill Site.Review of Insp Rept Raises Listed Concerns.Nrc Help in Matter Would Be Appreciated ML20205L1141999-03-12012 March 1999 Partially Deleted Ltr Establishing Irrevocable Standby Ltr of Credit in NRC Favor,At Request & for Account of W RA-98-070, Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change1998-11-17017 November 1998 Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change ML20154B0481998-09-28028 September 1998 Establishes Irrevocable Standby Ltr of Credit 1484 in NRC Favor,At Request & for Account of W,Up to Aggregate Amount of $11,098,000 Upon Presentation of Sight Draft & Signed Statement RA-98-038, Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified1998-07-10010 July 1998 Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified RA-98-033, Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl1998-06-15015 June 1998 Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl RA-98-021, Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept1998-03-20020 March 1998 Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept RA-98-008, Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept1998-01-20020 January 1998 Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept RA-97-091, Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility1997-12-18018 December 1997 Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility RA-97-053, Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site1997-07-31031 July 1997 Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site ML20147H8931997-04-0707 April 1997 Forwards W Repts Conceptual Remediation Plan & Conceptual Decommissioning Plan, Which Provides Time Schedule for Radiological Remediation of Wtr Facility & Objectives, Priorities,Schedule & Remediation Approaches RS-93-008, Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities1993-02-0505 February 1993 Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities ML20126D3651992-12-21021 December 1992 Forwards Annual Rept of Insp of Retired Westinghouse Test Reactor for 1992 ML20210F7271987-02-0505 February 1987 Forwards Addendum to Annual Insp Rept for Retired Westinghouse Testing Reactor for 1986, Per J Dosa 870128 Telcon W/Author.Addendum Provides Clarification & Addl Info ML20207C4801986-12-22022 December 1986 Forwards Annual Insp of Retired Westinghouse Testing Reactor Per License TR-2 for 1986 ML20138P8891985-12-16016 December 1985 Forwards Annual Insp of Retired Westinghouse Test Reactor (License TR-2) for 1985.Status of Retired Facility Remains Same as Last Rept ML20216F5041960-07-28028 July 1960 Forwards Rept Re Release of Contaminated Water to Storm Sewers on Wtr Site.Prevention of Further Releases of This Type Are Listed ML20216F5401960-07-18018 July 1960 Submits Table Giving Suitable Operating Conditions Which Will Be Observed During Escalation Program.Wtr Operating Procedures P-107 Detailing Action to Be Taken by Reactor Operating Staff in Event of Reactivity Changes Encl ML20216F4091960-04-0404 April 1960 Forwards Rept Dealing W/Incident Involving Release of Radioactivity at Wtr Site,Per Requirements of Wtr Emergency Procedures 1999-06-14
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CBS Corporation 11 stanwix street j Room 383 Pittsburgh. PA 15222 June 14,1999 Teiephone: (412) 642-3285 i
Fax:(412) 642 3957 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 -
Attention: Document Control Desk l
Reference:
Annual Report - License No. TR-2, Docket 50-22 Transmitted herewith is the attached " Annual inspection of Retired WTR per License TR-2" for 1998. This report has been prepared in compliance with the requirements of Facility License l No. TR-2, Docket 50-22 (Technical Specificatior Number 6.6.1, Annual Report). l The physical status of the retired facility remains the same as it was at the time of the last report. As noted in the report, the WTR Decommissioning Plan was approved with the issuance of Amendment Number 7 to the license, dated September 30,1998. Activities are underway to implement that plan in order to terminate this license.
If you have any questions regarding this matter, please write me at the above address or telephone me at (412) 642-3285.
Sincerely,
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Richard K. Smith i Director - Environmental Remediation I i
t Attachment cc:
Mr. Theodore S. Michaels, Senior Project Manager Non-Power Reactors & Decommissioning Project Directorate Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
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Washington, DC 20555-0001 l
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9906170047 990614
.PDR ADOCK 05000022 ~
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' Regional Administrator, l
U.S. Nuclear Regulatory Commission, Region I
-475 Allendale Road l King of Prussia, PA 19406-1415 James Yusko, Regional Manager, Radiation Protection i
Commonwealth of Pennsylvania Department of Environmental Protection Field Operations 400 Waterfront Drive Pittsburgh, Pennsylvania 15222-4745 l A. Joseph Nardi, Supervisory Engineer
- l. Westinghouse Electric Company- l Copies transmitted: 3 notarized and 5 conformed i
COMMONWEALTH OF PENNSYLVANIA )
) SS:
COUNTY OF ALLEGHENY )
l ..
l Before me, the undersigned notary public, this day personally appeared Richard K.
Smith, CBS Corporation,11 Stanwix Street, Pittsburgh, PA 15222, to me known, who being l duly sworn according to law, deposes and says: that the statements sworn to in this letter and l attachment are correct and accurate to the best of his knowledge. ;
l Signature of affiant Subscriped and sworn to before me this / V day of June,1999 l
J A ttAs)
NotGPublic /
Notarialseal Mary Colleen GaMn. Notary Pubhc PmsburDh, Allegheny County My Commission Expires Nov. 22,1999 i ;
j ~ Member Pennsylvania Association of Nciaries
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,1998 ANNUAL INSPFCTION REPORT FOR RETIRED WESTINGilOUSE TEST REACTOR U.S.N.H.C. I.lCENSE TR-2 DOCKET 50-22
SUMMARY
OF FACILITY ACTIVITIES During 1998, the facilities of the retired Westinghouse Test Reactor (WTR), retained under NRC License TR-2, were entered for the purpose of conducting the annual radiological survey, inspections, and for performing any preventive maintenance required. Those personnel entering the facilities to conduct the inspections were: R.G.
Cline, Manager, Industrial flygiene, Safety, and Environmental Compliance, M. Brandonio, Facilities Sernees; W.D. Vogel, Radiation Safety Officer; M. Ferguson, Safety Engineer, and I. Seybold, Ilealth Physics Engineer.
The findings and actions taken are summarized below:
- 1) During the past year, several entries were made into the vapor containment for general inspections and to determine if significant wall condensation or water was accumulating on the floor. Actions were previously taken to reduce humidity and water accumulation including covering the canal with plastic sheeting and polyurethane boards; installing two (2) dehumidifiers - replaced in 1994; and installing a sump pump in a small hole (sump) in a low area of the floor. These actions continue to prove effective, and the humidity within the vapor container is being maintained at a very low level, and essentially no accumulation of water has been observed on the floor during the various inspections.
- 2) The general condition of the vapor container was good, and no significant moisture was obsen ed on any interior walls, either above or below ground level. Visual inspection of the interior surface showed little or no increased deterioration of the surface coating. Some rusting was observed on the interio- bottom portion of the vapor shell skin, but this condition was essentially unchanged fiom the last several years.
Therefore, no action is deemed necessary concerning the structural stability of the vapor container. The exterior surface of the vapor container was repainted in July 1992, and its overall condition remains generally good.
- 3) The water level in the canal was measured and found essentially the same as that observed during the previous annual inspection (1997). The canal low-level water alarm annunciator system was replaced in 1995. The canal low-level water alarm was manually activated, and the alarm responded properly, i.e.,
audible alarm and printout in the Security Control Center and audible and visual alarm in the IIcalth Physics office.
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' No work was done under the water in the vapor container canal since the last annual inspection so the conditions remain unchanged. As previously reported, a system was installed in September 1986 to permit the ion exchange processing of the canal water and return of the processed water to the canal. The processing system continues to work well, and approximately 82109 gallons was processed and recycled in 1998.
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As noted in Table 1 of this report, the canal water was sampled and found to have a gross beta-gamma activity of 1.6 X 10' pCi/ml. The canal water sample was analyzed for specific radionuclides and gave the following results:
l Nuclide 1998 1997 1996 1995 1994 l pCi/ml pCi/mi pCi/ml pCi/ml pCi/ml l
l Cobalt-60 13 x 10 4
1.4 x 10 2.0 x 10' l.8 x 10 3 1.4 x 10 4
l 4 3 Cesium-137 1.3 x 10' 4.7 x 10" 4.1 x 10 1.6 x 10' 8.4 x 10 Cesium-134 Not Detected Not Detected Not Detected Not Detected Not Detected l 4 i Strontium-90 1.1 x 10* 3.3 x 10* 1.4 x 10' 5.2 x 10* 3.6 x 10 ,
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- 4) Overall housekeeping within the vapor container remains satisfactory. All loose floor tiles have been removed and very little debris was obsers ed on the floor.
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- 5) The personnel entry doors on the east and west sides of the vapor container were found locked at the time of entry, as w ere the doors leading into the Rabbit Pump room, the Sub-Pile room, at.d the cover over the primary coolant pipe tunnel. These areas were unlocked to permit access for this inspection but were again locked w hen the inspection was completed.
- 6) The valve on the drainline on the bottom of the reactor (inside the Sub-Pile room) was inspected. While the valve was temoved during the 1993 characterization to allow access to the interior of the vessel, the remaining piping was verified to be open to the interior of the vessel thus assuring venting of the vessel. A channel was installed to divert condensation from within the vessel to the canal. The butterfly valve in the ventilaten ducts in the Truck Lock Area was inspected and found in the CLOSED position.
- 7) The absolute filter through which the reactoi primary coolant system breathes into the Annex area was j inspected and found in good condition. The filter was replaced in March 1996.
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+8) . As previously noted, several entries were made into the vapor container during the year. The key for the area is maintained by the Site Security Guards, and records of all entries, indicating date and the Radiation l Safety Officer maintains time, purpose and names.
- 9) No changes were made in Westinghouse management relative to the administration of License TR-2 since the submission of the 1997 annual report.
- Bruce Bevilacqua remains as the Manager Resources and Support Operations. Mr. Bevilacqua is the senior site manager having responsibility for the retired WTR facilities, e Russell G. Cline remains as the Manager, Industrial liygiene, Safety, and Environmental Compliance (IllSEC). Mr. Cline reports directly to Mr. Bevilacqua.
e Wayne .D. Vogel, Radiation Safety Officer, reports directly to Mr. Cline.
- 10) The inspection of the primary coolant tunnel (snakepit) surrounding the vapor container indicated that 4
approximately 17360 gallons of water, with a gross beta activity of 2.1 x 10 pCi/m!.
- 11) The cover for the East Test Loop Dump Tank was removed in February 1998 to ing the condition of the pit and obtain a water sample. Approximately 4500 to 6000 gallons of water wt. stimated to be in the d
pit. The activity level was determined to be 4 x 10 Ci/ml with the principle nuclide being Cs-137.
l M AJOR PREVENTATIVE AND CORRECTIVE MAINTENANCE OPERATIONS There were no major preventative maintenance or correctin operations having safety significance performed in 1998.
MAJOR CllANGES IN REACTOR FACILITY AND PROCEDURES l
. The Waltz Mill Decommissioning Plan was approved for implementation on September 30,1998.
During the period from October 1,1998 to December 31,1998, preparations were being made to implement the TR-2 Decommissioning Plan in accordance with Amendment 8 of the TR-2 License. No major changes .in the reactor facility, procedures and activities significantly different from those previously described in the safety analysis report were made to the WTR or the Facility License number TR-2 during this time.
Only project control procedures supporting the license amendment and the decommissioning project were developed and general facility inspections were conducted.
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RADIOACTIVE EFFLUENTS RELEASED OR DISCil ARGED TO Tile ENVIRONS No liquid or air effluents were made to the environs from the facility in 1998. No radioactive waste was generated or shipped from the facility in 1998.
ENVIRONMENTAL SURVEY Since there were no discharges made from the facility to the environs in 1998, there is no relevant environmental i
surveillance data to report. j I
ANNUAL RADIATION SURVEY l The results of the radiological survey are shown in Table I, attached. A review of the survey data obtained since 1963 indicate that the accessible radiation and contamination levels are very low and relatively stable. Frequently, some scatter is seen in the data that is attributed to sampling techniques, locations, sensitivity of the counting instrumentation, radioactive decay, and relatively low levels of activity present. Any slight changes in a specific set of data from year-to-year are not considered significant. Inaccessible locations inside the reactor vessel, and hardware in the canal have higher radiation levels, principally from metal activation of reactor components and surface contamination. 1 The sampling techniques, equipment, and instrumentation used during this inspection were as follows:
I Water samr% were taken in clean polyethylene botdes at the inlet to t!." canal La exchange processing !
a) system or as '* grab" samples in non-flowing systems. An aliquot of the sample was evaporated to dryness in a two-inch stainless steel planchet and counted in an automatic, thin-window gas proponional, alpha-beta anti; coincidence counter. The counting efficiency for beta-gamma activity was 39 % and the backgrourad was 1.62 cpm.
For specific radionuclide determinations, an aliquot of the untreated sample was analyzed by gamma-ray
, spectrometry using a high-resolution germanium detector. The strontium-90 activity was determined by performing a chemical sepamtion on a portion of the sample and then counting the separated strontium-90 fraction in the counter described above.
2 b) Contamination surveys were performed by taking random smears of approximately 100 cm using 3 cm filter paper (Whatman 5 or equivalent). The filter paper was then counted in the gas proportional counter r ., -
described in (a), above. A varying number of smears were taken for each area listed in Table 1, and the
' average value was reported.
c) Air samples were collected using a Radeco high volume sampler with a flow rate of 4.5 to 5.5 cfm and collected on a GF47.GA glass fibe, filter paper with a collection efficiency of 95%. The sampling time was 20 minutes. After sampling, the filter paper was counted in the gas proportional counter described in (a),above, d) Radiation surveys were made at random locations within each area shown in Table 1. Measurements were 2
made at waist height using an Eberline Model E-520 with a G-M detector with a 30 mg/cm window, and a Ludlum Model 19 Micro-R meter with a Nai crystal. The average radiation level for each area was determined and reported in Table 1.
,.4 TABLE 1
Reference:
WTR-172. Appendix A RADIATION AND CONTAMINATION AREAS SURVEY REPORT Retired WTR Facility License TR-2 Survey Dates: July - August '1998 IIcalth Physics Procedure No. 29 LOCATIONS Radiation b-g Contamination Levels
- Levels mr/hr Surface Air Water dpm/100 cm 2 mci /mi mci /mi
- 1. Reactor Building
- 1. 16 ft Elevation - <1 321 1.4 x 10d ' N.A.
General Background
- 2. Rabbit Pump Room - 1.8 < 200 7.7 x 10 N.A.
General Background
- 3. Sub-Pile Room - 0.6 2080 2.2 x 10"' N.A.
I General Background
- 4. Reactor Top - <1 < 200 4.4 x 10a2 N.A.
I General Background
- 5. Reactor Top - <1 < 200 3.1 x 10 42 N.A.
l Over Closed Vessel-l General Background
- 6. Reactor Top - <1 < 200 2.7 x 10a2 N.A.
Around Trench -
General Background
- 7. Canal Wall Top <1 N.A. N.A. N.A.
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- 8. Canal Water <1 N.A. N.A. l.6 x 10
- 9. Pit - <1 205 2 8 x 10a2 2.1 x 10*
PC Pipe -
l Tunnel 16 ft Elevation l
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- N.A. Not Applicable l
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