IR 05000087/1986001
| ML20141D758 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 04/02/1986 |
| From: | Ridgway K, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20141D747 | List: |
| References | |
| 50-087-86-01, 50-87-86-1, NUDOCS 8604080263 | |
| Download: ML20141D758 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
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Report No. 50-87/86001(DRP) !
Docket No. 50-87 License No. R-119 f
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Licensee: Westinghouse Electric Corporation j Facility Name: Westinghouse Nuclear Training Reactor Inspection Conducted: March 12-14, 1986 Inspector: R R1 ah f/th4 Da'td r
I Approved By:
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E. R. Schweibinz, Chief IY[b Technical Support Staff Inspection Summary
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Inspection on March 12-14,1986 (Report No. 50-87/86001(ORM Areas Inspected: Routine, unannounced inspection of records, logs, and organization; review and audit functions; requalification training; procedures; surveillance and maintenance; fuel handling activities; radiation protection; radwaste management control; transportation activities; emergency !
I planning; and follow-up actions relative to an open inspection item. This inspection involved a total of 23 inspector-hours by one NRC inspecto Results: One violation, failure to submit an organization change (Paragraph 4), i and one deviation, late inspection reports (Paragraph 5), were identified. No significant safety issues were identified in the areas inspecte ,
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DETAIL S 1. Persons Contacted
- G. W. Scholand, Manager, Training and Operational Services
- N. T. Hamrick, Manager, Operations Training
- K. M. Rueter, Manager, Westinghouse Nuclear Training Reactor J. P. Kieffer, Lead Engineer C. C. Salvaglio, Radiation Safety and Security Coordinator P. P.. McWane, Senior Operator '
O. E. Van Beek, Senior Operator
" Indicates those present at the exit intervie . General This inspection, which began at 9:15 a.m. on March 12, 1986, was conducted to examine the training reactor program at the Westinghouse Electric Corporation Nuclear Training Center. The facility was toured shortly af ter arrival and the Reactor Room inspected on March 13. The inspector observed a reactor startup, a shutdown, and a safety channel surveillance during the inspection. The general housekeeping of the facility remains satisfactory, as was noted in the previous inspection (Inspection Report No. 50-87/84001(DRP)).
Amendment No. 8 of License No. R-119, dated November 27, 1984, renewed the license in it's entirety untti January 28, 200 The licensee had received the NRC show cause order, dated September 27, 1985, to reduce the amount of high enriched uranium fuel onsite to that necessary to maintain a normal schedule of operations. The renewed license limits the core configuration to one which requires less than 5 KGs of U-235. The excess irradiated fuel freed by the core rearrangement in 1981 was shipped to a Department of Energy facility during that year. The licensee has no unirradiated fuel on han . Licensee Action on Previous Inspection Findings (92701-92702)
(Closed) Open Item 087/84001-01: Some surveillance test records lack information. Surveillance procedures for daily and monthly surveillances have been revised. The procedures for quarterly, semiannual, annual, and biennial periods are being revised. The revisions, to be completed soon, will provide sufficient data tracking capabilit . Organization, Logs and Records (40750)
The facility organization was reviewed to verify its consistency with the Technical Specifications and/or Safety Analysis Report (SAR). The minimum staffing requirements were verified to be present during reactor operation, and fuel handling or refueling operation . ____ - - __ __ ____ - _ -__ ._ _-- _ _ _ - _ _ *
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- The reactor logs and records were reviewed to verify that
- Records were available for inspectio Required entries were made, Significant problems or incidents were documented.
l The facility was being maintained properl Through the review of records and interviews of personnsi, it was determined that the present organization at the Westinghouse Training Center is not that shown in the FSAR nor the Technical Specifications. A reorganization in late 1984 which changed upper management position titles and changed the lines of management above the Manager of the WNTR had not been submitted to the Office of Nuclear Reactor Regulation. This is considered to be a violation of the Technical Specifications (087/86001-01).
No other violations or deviations were identifie . Reviews and Audits (40750)
l l The licensee's review and audit program records were examined by the inspector to verify that: Reviews of facility changes, operating and maintenance procedures, design changes, and unreviewed experiments had been conducted by the Reactor Safeguards Committee (RSC) as required by Technical Specification That the review committee and/or subcommittees were composed of qualifiea members and that quorum requirements and frequency of meetings had been met.
- Required safety audits had been conducted in accordance with Technical l Specification requirements and that any identified problems were resolved.
i A review of the RSC meetings indicated the committee was meeting all
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requirements. Inspections of the facility are conducted quarterly by a member of the RSC. The written reports indicated that inspections were
! on schedule, thorough and technically adequate; however, the inspection l report for the third quarter inspection of 1985 had not yet been issue This 'is a deviation from Section 4.3.2 of the RSC Charter which requires
, written reports to be received by the RSC Chairman within 30 days of the inspection (087/86002-02).
l Through discussions with the licensee it was determined that the verbal
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j closeout for this inspection indicated no safety concerns l
No violations or other deviations were identifie L
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r I Requalification Training (40750)
The inspector reviewed procedures, logs, and training records; and interviewed personnel to verify that the requalification training program was being carried out in conformance with the facility's approved plan and NRC regulation Requalification examinations had been conducted in 1984. A review of individual training records indicated that 19 individuals are licensed as Senior Reactor Operators.
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No violations or deviations were identified, i Procedures (40750)
The inspector reviewed the licensee's procedures to determine if procedures l were issued, reviewed, changed or updated, and approved in accordance with Technical Specifications and SAR requirements. This review also verified:
. That procedure content was adequate to safely operate, refuel and maintain the facilit .
, That responsibilities were clearly defined.
i l That required checklists and forms were use .The inspector determined that the required procedures were available; however, the Operating and Experiment Manuals still contained references to obsolete Technical Specification paragraph numbers and surveillance l
frequencies. The updating of surveillance procedures and check sheets to the new Technical Specifications is almost complete. Updating of procedures is considered to be an open inspection item (087/86001-03).
l No violations or deviations were identifie . Surveillance (40750)
The inspector reviewed procedures, surveillance test schedules and test records and discussed the surveillance program with responsible personnel to verify:
1- That, when necessary, procedures were available and adequate to perform tests, That tests were completed within the required time schedule,
.. Test records were availabl The licensee's surveillance program appeared to be satisfactor No violations or deviations were identified.
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. Experiments (40750)
The inspector verified by reviewing experiment records and other reactor logs that: Experiments were conducted using approved procedures and under approved reactor condition New experiments or changes in experiments were properly reviewed and approve The experiments did not involve an unreviewed safety question, i.e.,10 CFR 50.59 requirements regarding experiments were me . Exportments involving potential hazards or reactivity changes were identified in procedures, Reactivity limits were not or could not have been exceeded during an experimen The inspector reviewed the one experiment approved since the last inspectio No violations or deviations were identifie . Fuel Handling (40750)
The facility fuel handling program was reviewed by the inspector. The review included the verification of approved procedures for fuel handling and their technical adequacy in the areas of radiation protection, criticality safety, Technical Specification and security plan requirement The inspector deternined by records review and discussions with personnel that fuel handling operations were carried out in conformance of the licensee's procedure No violations or deviations were identifie . Transportation Activities (86740)
There has been no transportation activity since the last inspectio . Radiation Control (40750)
The inspector reviewed the radiation protection activities since the last inspectio Records were reviewed, personnel were interviewed, and observations were made to verify that radiation controls were being carried out in accordance with license and NRC regulations. The areas covered were: Posting and labeling of restricted areas and radioactive material Control of irradiated sample L -
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. * Calibration of radiation detection instruments, Required periodic dose rate and contamination surveys, Exposure records of personne Posted areas of the facilit Personnel trainin The licensee's program includes the routine use of direct self-reading dosimeters, TLD badges, and TLD finger ring The TLD badges contain both beta gamma and neutron sensitive chip Records of personnel dosimetry results were reviewed for 1984 and 198 The highest whole body dose was 74 mrem in 1984 and 42 mrem in 198 The reduction in dose was attributed to the use of a new shielded fuel and control rod examination tabl No violations or deviations were identifie . RadwasteManagement(40750) Gaseous Radwaste Monthly particulate air samples taken in the facility during reactor operations show activities generally less than 10E-11 microcuries per milliliter which is essentially background, Liquid Wastes Potentially contaminated water is collected and stored in a 55 gallon drum, a laboratory waste tank, and the dump tank holdup tank where it is sampled prior to release to the sanitary sewer. In 1984, less than 0.02 microcuries were released in 87 gallons of liquid radwast There were no liquid waste releases in 198 Solid Wastes There have been no solid waste shipment No violations or deviations were identifie . Emergency _ Planning _(40750)
The inspector reviewed records and interviewed personnel to determine that the approved emergency plan was being carried out by verifying: That procedures were in place and required records were being kept, That required drills were conducted and evaluated.
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..o That required training had been conducte That required emergency equipment was in place and being maintaine ;
The emergency plan, submitted July 13, 1933 was determined to be acceptable by the Office of Nuclear Reactor Regulation or May 18, 1984 and was then implemented by the license No violations or deviations were identifie . Review of Periodic and Special Reports (90713)
The inspector reviewed the following reports for timeliness of submittal and adequacy of information submitted: l Annual Report for calendar year 1984 Annaal Report for calendar year 1985 No violations or deviations were identifie . Exit Interview (30703)
The inspector met with the licensee representatives (listed in Paragraph 1)
at the conclusion of the inspection on March 14, 1986 and sumnarized the scope and findings of the inspectio The inspector also discussed the l likely informational content of the inspection report with regard to
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j documents or processes reviewed by the inspector during the inspection, l The licensee did not identify any documents or processes as proprietar The licensee acknowledged the following remarks by the inspector at the i meeting and by telecon following the meeting: j i The failure to submit a Technical Specification amendment for the l 1984 organizational change (Paragraph 4). j 4 The failure to submit RSC inspection reports in a timely manner I (Paragraph 5). The need to update the Operation and Experiment Manuals to include the new Technical Srecification references and requirement l l
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