IR 05000022/1999201
| ML20207M538 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 03/05/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207M525 | List: |
| References | |
| 50-022-99-201, 50-22-99-201, NUDOCS 9903190110 | |
| Download: ML20207M538 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION l OFFICE OF NUCLEAR REACTOR REGULATION
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Docket No: 50-22 License No: TR-2 Report No: 50-22/99-201 Licensee: CBS/ Westinghouse Electric Company Division ,
Facility: Westinghouse Test Reactor Location: Waltz Mill, Pennsylvania Dates: February 1-3,1999 Inspector: Stephen W. Holmes, Radiation Specialist j Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate i Division of Regulatory Improvement Programs /h1R
l 9903190110 990305 PDR ADOCK 05000022 g PDR
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EXECUTIVE SUMMARY l The reactor was being maintained as required by the possession only license inspections, surveys, records, and reports were as required by the License. The licensee had !
determined that the source of the water draining from the bottom of the reactor tank into !
the transfer canalin the Sub-Pile room was condensation and had taken appropriate l actions to channel the water directly into the canal. Oversight of the independent contractor operathg the counting lab was acceptably provided by the license Preplanning and coordination for decommissioning was being performe I
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Bgoort Details Summary of Plant Statug l
The reactor remains shut down with no fuel on site under a possession only licens Amendment No.8 to the license, authorizing decommissioning, had been issue Preplanning and coordination for the decommissioning was on goin Conduct of Operations 01.1 praanization and Operations Inspection Scone (Insoection Procedure 40755 and 690011 The inspector reviewed organization and staffing, administrative controls, annual reports, and reactor log entrie Observations and Findings Since the last inspection the site manager had changed. All other reactor related positions were the same. Interviews with site manager, operations, safety, and remediation and decommissioning staffs verify that their knowledge and experience is suitable to conduct the programs at the reacto Although not previously required, the Waltz Mill radiation safety committee (RSC)
had still provided administrative oversight, coordination, and assistance to the responsible staff. The inspector confirmed that the RSC, now required by Amendment No. 8, was being constituted and its charter drafte Log of entries into the reactor containment were clear, concise and indicated reason for entry and work performed. Access to the facility was controlle Conclusions Staffing, care taking, and preparations for decommissioning activities were acceptable and consistent with license requirements and licensee commitment Operational Status of Facilities and Equipment 92.1 Insoections and Survevs jnnection Scope (Inspection Procedure 40755 and 69001)
The inspector reviewed the annual report, survey procedures, survey results and analyses, Observations and Findinas Surveys and annual inspections of the retired facility, including contamination surseys, radiation area surveys, and liquid sample analyses, were completed at license required intervals. Survey results were evaluated by the radiation safety l
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officer (RSO). No anomalus results were noted. Procedures were used and provided adequate guidance for the surveys being, '*rformed, c. Conclusions l
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Inspections and surveys were completed as required and accurately reflect the conditions of the facilit Operations Procedures and Documentation a. Insoection Scope (Insnection Procedure 40755 and 69001)
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The inspector reviewed administrative cor.trols, operating procedures, and the electronic computer procedure file b. _Qbservetions and Findinag l l
Required procedures were available and used by the staff. Procedures had been updated and most placed on the licensees computer network. The procedures were cross indexed /hypertext linked with each other. The inspector confirmed that '
they were easy to access and use. Procedures not on the internal network were available in hard cop l c. Conclusions Facility procedures satisfied the License requirements and commitments of the final shutdown repor M1 Conduct of Maintenance a. Irisoection Scoce (Inspection Procedure 40755 and 69001 The inspector reviewed access log entries, annual reports, and interviewed staff on l maintenance. Tours were conduc+3d of the reactor containment and surrounding outside are b. Observations and Findinas Maintenance was focused towards maintaining equipment and facility integrity thereby preventing the spread of contamination and deterioration of the containment building. The containment was urioccupied and entered only when l required for inspections, surveys, or maintenance, as confirmed by iog entries.
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No water buildup or seepage was found. The licensee had determined that the i source of the water draining from the bottom of the reactor tank into the transfer ;
canal in the Sub-Pile room was condensation from the tank and had channeled the l water directly into the cana !
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' Conclusions
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Reactor containment was being maintained in an acceptable condition.
R1 Radiological Protection and Chemistry Controls l 1 R1.1 Radiation Protection I l
, Scoce (Insoection Procedure 40755 and 69001) ;
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The inspector reviewed radiological signs and postings, routine radiation survey l results, and dosimetry records, l Observations and Findinas l
Posting and labeling of the reactor was appropriate for the hazards involved. All signs and postings were visible and legibl Surveys of radiation and contamination areas were acceptabl NRC Forrn 3's were posted as require Personnel exposures were well under regulatory requirements. The processor was National Voluntary Laboratory Accreditation Program certified in the appropriate areas as required. In addition to the monthly badges, self reading dosimeters were used to track short term doses during entry into the containment. Procedures and programs were in place for declared pregnant workers, lost badges, and for investigation of abnormal exposure results, Conclusions The facility radiation protection program has been maintained in accordance with regulatory requirements and licensee commitment R1.2 Effluent Monitorina Scoce (Insoection Procedure 40715 and 69001)
The inspector reviewed annual reports and interviewed staff on effluent release Observations and Findinas l Effluent releases from the reactor are extremely infrequent and normally consist of l
water in leakage into the primary coolant tunnel. Water accumulation in the tunnel l
has also stayed constant over the last 2 years with low gross activity. The
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licensee had acquired a water processing system and will process / treat the primary
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coolant and transfer canal water during the planned decommissioning in compliance with state discharge requirement c. Conclusions l Effluent monitoring satisfied License requirement R2 Status of RP&C Facilities and Eauipment a. Scope (Insoection Procedure 40755 and 69001)
The inspector reviewed counting lab equipment calibrations, analysis procedures, and interviewed licensee and lab contract staff in this are b. Observations and Findinos Counting equipment was calibrated as recommended by the manufacture or industry standards and was suitable for the surveys and analyses performe Periodic system checks were being made, tracked, and charted on compute Cahbration sources were NationalInstitute of Standards and Technology traceable ,
and conformed to thts geometry of the sarnples being analyze ,
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The lab operations had been contracted to an outside firm. The lab facility and equipment were still owned by the licensee a:J the same procedures and I equipment was being used. The licensee continued to provide oversight to the operation c. Conclusions RP&C equipment was being maintained and operated according to industry and equipment manufacturer standards. License requirements were satisfie R3 RP&C Procedures and Documentation )
a. Scope (Inspection Procedure 40755 and 69001)
The inspector reviewed the Waltz Mill radiation safety program documentation, i various individual procedures, and interviewed the RSO and other personnel in this !
area, b. Observations and Findinas The written radiation safety program covered the whole Waltz Mill site. Individual proceduras were understandabic and straight forwar ;
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The procedures manual had been updated as part of the process of incorporating the manualin the site computer network. The procedures were cross i indexed /hypertext linked with each other. The inspector confirmed that they were easy to access and use. Procedures not on the internal network were available in hard copy.
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l The radiation safety pro 3 ram documentation satisfied the requirements of 10 CFR l 20.110 ]
l R6 RP&C Orocnization and Administrati_ Scope (Insoection Procedure 40755 and 69001)
The inspector interviewed the RSO and other health physics staf l l
i Observ_ations and Findinos j i
-- The operations staff consisted of six technicians, one enginoct, four contractors, three administrative personnel and the RSO. One technician, who has twenty years experience at the facility, is normally assigned to those operations involving the reacto The Waltz Mill RSC also provided administrative oversight, coordination, and assistance to the radiation safety staf Conclusions Health physics staffing meets regulatory requirements and licensee commitment P8 Miscellaneous EP issues, Medical and Fire Scope (Insoection Procedure 40755 and 69001)
The inspector reviewed training records, procedures, and interviewed staff in this l are Observations and Findinas ;
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Although an Nuclear Regulatory. Commission approved emergency plan was not required, the Waltz Mill site maintains it own certified fire brigade and separate medical clinic. Training and tours of the facility was provided yearly to the ctaf l Interviews with staff, and review of training records indicate that they are !
knowledgeable of the hazards involved in responding to emergencies at the reactor.
l Emergency calllists at the guard station were available and accurat l
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l l- Conclusions Eme gency response staffing was sufficient for the radiological hazards involved in a fire or injury involving the reactor facility.
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X1 Exit Meeting Summery (Inspection Procedure 30703) j i
. The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on February 3,1999. The license acknowledged the findings presen ed, j l
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l PARTIAL LIST OF PERSONS CONTACTED Licensee
'B. Bevilacqua Manager, Waltz Mill Site
'R. Cline Manager, industrial Hygiene, Safety & Environmental Compliance E. Darragh Dosimetry Technician J. Dinicola Senior Health Pl.ysics Technician L. Foglia Dosimetry Technician E. Grohregin Radiochemistry Supervisor i
- D. Vogel Waltz Mill Radiation Safety Officer
' Attended Outbriefing INSPECTION PROCEDURES USED
IP 40755: CLASS lil NON-POWER REACTORS :
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IP 69001: CLASS 11 NON POWER REACTORS ,
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ITEMS OPENED, CLOSED, AND DISCUSSED Opened
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None Closed None LIST OF ACRONYMS USED EP Emergency Plan HP Health Physics RSC Radiation Safety Committee RSO Radiation Safety Officer RP&C Radiation Protection and Chemistry Controls