IR 05000087/1981002
| ML20004D501 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 05/22/1981 |
| From: | Boyd D, Janke R, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20004D494 | List: |
| References | |
| 50-087-81-02, 50-87-81-2, NUDOCS 8106090471 | |
| Download: ML20004D501 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION l
OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report No. 50-87/81-02 Docket No. 50-87 License No. R-119 Licensee: Westinghouse Electric Corporation 505 Shiloh Boulevard Zion, IL 60099 Facility Name: Westinghouse Nuclear Training Reactor Inspection Conducted: May 4-7, 1981 Inspectors:
K.
R., Ridgway 30- 25 E~d5 /
hb R. C. Janke ( ay 5-7, 1981)
C'-23-&/
g, Approved By:
D. C. Boyd,' Chief'
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Reactor Projects Section 1A
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Inspection Summary Insoection on May 4-7, 1981 (Report No. 50-87/81-02)
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Areas Inspected: Routine unannounced inspection of records, logs and organization; review and audit functions; requalification training; pro-cedures; surveillance and maintenance; refueling; experiments; radiation protection program; radwaste management program; transportation of radio-active materials; and followup action relative to IE Circulars and Open Inspection Items. This inspection involved a total of 46 inspector-hours onsite by two NRC inspectors including 0 inspector-hours onsite during off-shifts.
Results: No items of noncompliance were identified in the 10 areas inspected.
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DETAILS 1.
Persons Contacted
- J. M. Roth, WNTR Facility Manager
- C. W. Bach, Training Reactor Coordinator
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- F. E. Ellis, Radiation Systems Coordinator and Security Officer
- J. C. Snelson, Lead Engineer
- R. R. McWane, Senior Reactor Operator C. C. Ferguson, Senior Reactor Operator Denotes those present at the exit interview.
2.
General
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This inspection, which began at 9:00 a.m. on May 4, 1981 was carried out to determine that required radiation protection and operational safety measures were being carried out.
On May 5, the inspectors
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observed the Reactor Room and Reactor facilities during a down time
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between reactor runs. Safeguards Committee had reviewed and the WNTR i
Facility Manager had approved an experimental core' designed to reduce
the fuel possest ion to below 5 kilograns of U-235.
By adding a 21 element graphite v.flector ring around th-fuel periphery, the normal core of 28 fuel elements and 9 control rods with fuel followers was reduced to a core containing 20 fuel elements and 5 control rods with fuel followers. Later testing indicated the core could be further
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reduced by one fuel element. The new core configuration increased the worth o-f control rod No. 2 significantly which required a reduction
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in the rod drive speed to remain within the Technical Specification reactivity insertion rate limits.
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The licensee had submitted the required 60 day report for any new core to the Office of Nuclear Reactor Regulation (NRR) on March 19, 1981, testing of the new core started on January 19, 1981. Since the present license expires January 28, 1982, the licensee plans with NRR concurrence, to incorporate this core change into the Safety Analysis Report and the e
license renewal application to be submitted later this year.
3.
Organization, Logs and Records
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The facility organization was reviewed and verified to be consistent with the Technical Specifications and/or Hazards Summary Report. The
minimum staffing requirements were verified to be present during reactor
operation, and fuel handling or refueling operations.
The reactor logs and records were reviewed to verify that:
a.
Required entries were made.
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b.
Significant problems or incidents were documented.
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The facility was being maintained properly.
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Records were available for inspection.
Since the last inspection J. C. Snelson has replaced C. C. Ferguson as Lead Engineer and nine senior operators were licensed.
No items of noncompliance or deviations were identified.
4.
Reviews and Audits The licensee's review and audit program records were examined by the inspector to verify that:
a.
Reviews of facility changes, operating and maintenance procedures, design changes, and unreviewed experiments had been conducted by a
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safety review committee as required by Technical Specifications or Hazards Summary Report.
b.
That the review committee and/or subcommittees were composed of qualified members and that quorum requirements and frequency of meetings had been met.
c.
Required safety audits had been conducted in accordance with Technical Specification requirements and that any identified problems were resolved.
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No items of concompliance were identified.
5.
Rpqualification Training The inspector reviewed procedures, logs and training records; and itterviewed personnel to verify that the requalification training pr gram was being carried out in conformance with the facility's o
approved plan and NRC regulations. Six requalification examinations had been conducted in July 1980.
No items of noncompliance were identified.
6.
Procedures The inspector reviewed the licensee's procedures to determine if procedures were issued, reviewed, changed or updated, and approved in accordance with Technical Specifications and HSR requirements.
This review also verified:
a.
That procedure content was adequate to safely operate, reruel and maintain the facility.
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b.
That responsibilities were clearly defined.
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That required checklists and forms were used.
The inspector determined that the required procedures were available and the contents of the procedures were adequate.
The procedure manual had been revised in August 1980. Most revisions were editorial in nature.
No it' ens of nen:oapliance were identified.
7.
Surveillance The inspector reviewed procedures, surveillance test schedules and test records and discussed the surveillance program with responsible personnel to verify:
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That when necessary, procedures were available and adequate to a.
perform >he tests.
i b.
That tests were completed within the required time schedule.
c.
Test records were available.
No items of noncompliance were identified.
8.
Experiments
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i The inspector verified by reviewing experiment records and other
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reactor logs that:
a.
Experiments were conducted using approved procedures end under approved reactor conditions.
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b.
New experiments or changes in experiments were properly reviewed and approved.
c.
The experiments did not involve an unreviewed safety question, i.e., 10 CFR 50.59.
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Experiments involving potential hazstds or reactivity change were identified in procedures.
e.
Reactivity limits were not or could not have been exceeded during the experiment.
Me itema of noncompliance were identified.
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9.
Refuelina
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The facility fuel handling program was reviewed by the inspector. The review included the verification of approved procedures for fuel handling and the technical adequacy of them in the areas of radiation protection, criticality safety, Technical Specification and security plan requirements.
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The inspector determined by records review and discussions with personnel
that fuel handling operationa and startup tests were carried out in con-
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formance to the licensee's procedures.
No items of noncompliance were identified.
10.
IE Circular Followup
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For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular was applicable to the facility, appropriate corrective actions were taken or were
scheduled to be taken.
a.
IE Circular 79-08, Attempted Extortion - Low Enriched Uranium.
b.
IE Circular 80-02, Nuclear Power Plant Staff Work Hours.
c.
IE Circular 80-14, Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel, d,'
IE Circular 81-02, Performance of NRC-Licensed individuals while o
on duty.
11.
Review of Periodic and Special Reports
The inspector reviewed the following reports for timeliness of submittal and adequacy of information submitted:
a.
Annual operating report for license R-119, CY 1980.
b.
Safety considerations for the 24 element reflected core, December 3,1980 12.
Radiation Protection The inspectors reviewed records and interviewed personnel to determine l
that the surveillance requirements in the area of radiation protection
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had been carried out and no adverse conditions were noted.
13. Radioactive Effluents
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The inspectors reviewed records of gasecus, liquid and byproduct releases since the last inspection.
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No itema of noncompliance were identified.
14. Material control and Accountability (MCA)
i There had been no receipts or shipments since the last MCA inspection.
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i 15. Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on May 7,1981, and sumusarized the
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scope and findings of the inspection.
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