IR 05000134/1998201
| ML20249A871 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 06/16/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249A869 | List: |
| References | |
| 50-134-98-201, NUDOCS 9806190027 | |
| Download: ML20249A871 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION Docket No:
50-134 l
l License No:
R 61 Report No:
98-201 Licensee:
Worcester Polytechnic Institute Facility:
Open Pool Training Reactor Location:
Worcester, Massachusetts Dates:
April 27-30,1998 Inspector:
Thomas F. Dragoun, Reactor inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate EXECUTIVE SUMMARY The licensee's programs were directed toward the protection of public health and safety and were found to be in compliance with NRC requirements. No safety concerns or violations were identified.
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.990 190027 990616 POR ADOCK'05000134
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i REPORT DETAILS Summarv of Plant Status The reactor was operated for a demonstration. The core was'off-loaded and fuel elements relocated to in-pool storage racks. Additional housekeeping improvements were noted.
The area radiation monitoring system was replaced.
1.0 Organization and Staffing.
a.
Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
organizational changes,
- staff qualifications, and a staffing levels.
b.
Observations and Findings The three licensed SROs and one RO on staff have~ current, unexpired operating licenses. Two graduate student SROs were licensed as undergraduates and have remained on staff for more than two years. Normally, student operators were available for less time. One student SRO, who was the Radiation Safety Officer, intended to remain another year. The availability of experienced staff allowed for improvements in programs and procedures. There were two reactor operator candidates in training.
. Conclusions Staffing requirements in technical specification (TS) 5.0 and 2.2(1) were satisfied.
2.0 Operation Logs and Records a.
Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
e reactor startup and shutdown checklists,
- . console operations log,.
e -~ maintenance report, and e records of a 50.59 review.
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b.
Observations and Findings Pre-critical and shutdown checklists were properly used during operation of the reactor. Console log entries included changes in reactor power, control rod positions, duty personnel, details of experiments, and conduct of training classes.
Unscheduled scrams were recorded in the back of console log with reference to the page number and reason for the scram. Alllog entries were neat, legible and in a bound book.
Periodic equipment checks and calibrations were recorded on " report forms" that were submitted to the RHSC for review. This well organized system facilitated record retrieval and schedule verification.
A maintenance log has been kept since 1994. However, the amount of required maintenance has been minimal.
A 50.59 evaluation for the lead shielding installed in the ceiling over the reactor pool to reduce radiation levels in the classroom above was completed. The evaluation properly addressed issues required by 10 CFR 50.59 and recorded the
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technical basis for each conclusion. Based on the satisfactory completion of the l
evaluation, inspector follow-up item 96-01-02 is closed.
c.
Conclusions Operating records were kept as required by TS 5.6.
3.0 Procedures a.
Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
- availability of procedures, e approval of procedures, and
- use of procedures.
b.
Observations and Findings Required procedures were available and approved by the RHSC. A periodic review by the Director in March 1998 resulted in approved changes to surveillance, operations, and administrative procedures. Two new procedures were developed. Reactor operators were informed of changes by memo.
In general, procedures had consistent format, were clear, detailed, and achieved the desired function.
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Conclusions Written procedures were provided as required by TS 5.5.
4.0 Operator Requalification a.
Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
records of console manipulations, e
e results of orals exams, and a written exams.
b.
Observations and Findings Requalification credit for reactivity manipulations and time spent supervising reactor operations were transferred from the console log to a computer database for ease in tracking. A sampling from the console log confirmed the assigned credit. An oral exam administered by the Facility Director covered seven areas.
The written exam was a fullinitial qualification exam used by the NRC. Exam content and scores were satisfactory.
c.
Conclusions The requalification program satisfied requirements in 10 CFR 55.
5.0 Surveillance and Limiting Conditions for Operation a.
Inspection Scope (inspection Procedure 40750)
The inspector reviewed:
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surveillance schedules, e
e surveillance procedures, e surveillance records, and e operating records.
b.
Observations and Findings During a previous inspection, the intpector noted that daily check of the console required by TS 3.1 did not specifically verify the visual alarms associated with the annunciator system. The Facility Director stated that a step was added to the checklist for visual alarm verification. This was confirmed by the inspector.
Inspector follow-up item 96-01-01 is closed.
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A review of records indicated that surveillance were scheduled and conducted at the required intervals using approved procedures. Surveillance data, like equipment calibrations, was recorded on " report forms" and submitted to the RHSC for review.
A review of Etrip chart recordings and parameter data indicated that the reactor was operated within the approved safety limits and operating restrictions.
c.
Conclusions TS 3.0 surveillance requirements were met.
6.0 Radiation Protection a.
Scoce (Inscection Procedure 40750)
The inspector reviewed:
e staffing, e routine surveys, e instrument calibrations, e personnel dosimetry, e effluent releases, radiological signs and postings, and e
e ALARA.
b.
Observations and Findinos The RSO for the reactor was a graduate student who also serves as the campus Assistant RSO. He was knowledgeable of the applicable regulatory requirements.
The size of the two programs allowed the RSO to fill both positions.
There are no high radiation or contaminated areas found in the facility. Gamma dose rates are surveyed weekly. Signs and postings were appropriate.
Vendor supplied whole body and finger ring TLDs are processed quarterly. Doses were well below NRC limits.
Portable gamma and neutron survey meters are calibrated annually by a vendor using appropriate technique. Staggered shipments ensure an adequate supply of instruments on hand. The area radiation monitors were calibrated quarterly by the RSO. The inspector noted that the calibration procedure did not take advantage of the microprocessor controlled features of the new system to reduce dose to the RSO. The licensee stated that this matter would be reviewed.
Liquid waste was collected in a holdup tank for analysis prior to release.
Laboratory analysis of samples by the RSO were appropriate and the results were i
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1 within NRC limits. Waste was discharged after a review of the analytical data by
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the Facility Director. Use of the COMPLY computer program indicated that the
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gaseous releases of Ar-41 were within the NRC constraint limit. No solid waste was generated. Irradiated samples are stored for decay, surveyed, and released.
The ALARA policy was contained within Radiation Regulations issued by the RHSC. The RSO did quarterly audits of doses and reported results to the RHSC.
c.
Conclusions The radiation protection program has been maintained in accordance with regulatory requirements and licensee commitments.
7.0 Committee Oversight a. ~ Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
e RHSC membership, and e RHSC reviews b.
Observations and Findings
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Membership losses through retirements have been replaced with qualified personnel. Recent procedure changes were approved during the quarterly meeting held in April 1998. Report forms" were reviewed as required by licensee procedures.
c.
Conclusions Requirements in TS 5.2 were met.
8.0 Emergency Preparedness a.
Inspection Scope (Inspection Procedure 40750)
The inspector reviewed:
e status of off-site support agreements, e emergency procedures, and e conduct of drills b.
Observations and Findings Letters of agreement for off-site support had been signed by the required agencies. However, most were signed in 1996 and needed to be updated.
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Emergency procedures conformed to the emergency plan and were concise.
Required logs and records were maintained. The emergency response kit kept at the campus police station was properly maintained.
Semiannual building evacuation drills were conducted on schedule with multiple-observers. Observer comments and suggestions for improvement were documented and resolved.
c.
Conclusions
' The Emergency Preparedness Plan was properly implemented.
9.0 Material Control and Accounting a. insoection Scone (Insoection Procedure 851021 The inspector reviewed:
e procedures, e assignment of responsibilities, e material balance reports, and e annualinventory results.
b. Observations and Findinas The inspector verified through a review of records that the licensee was maintaining and implementing nuclear material control procedures. Responsibility and authority for material control were assigned to the Facility Director by procedure AP-01.
There were no receipts of SNM or shipments between September 30,1993 and March 31,1998.
Physicalinventories were conducted annually as required by 10 CFR 70.51(d). The licensee's last inventory was performed in July 1997. On April 27,1998, the inspector conducted a piece count of the SNM at the facility. The following material was accounted for:
Plutonium Bervilium Sources one in the reactor pool (sealed source serial no.M615)
Fuel Assemblies twenty-one fixed plate fuel assemblies in the reactor core one six plate fuel assembly in the reactor core one complete eighteen plate removable fuel assernbly in storage four fixed plate fuel elements in storage six loose fuel plates in storage
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All Material Balan'ce Reports (DOE /NRC Form-742) submitted by the licensee for the period September 30,1993 through March 31,1998, satisfied tSe requirements specified in 10 CFR 70.53.
c. Conclusions No deficiencies were identified in the licensee's Material Control and Accounting program.
10.0 General Physical Security Requirements For Special Nuclear Material Of Low Strategic Significance a. Insoection Scone (Insoection Procedure 814311 The inspector reviewed:
o records,and reports, e security organization, o key control, e detection aids, e physical barriers, e screening and access controls, e provisions for contingencies, and
- written procedures.
b. Observations and Findinas Reactor staff tests the security system semiannually and reports the results to the RHSC. Facility locks and keys were replaced in early 1998. The inspector verified that the replacements met criteria specified in the NRC-approved security plan.
The licensee's physical protection program was found to conform to NRC requirements and the licensee's implementing procedures.
c. Conclusions The NRC-approved security program was acceptably implemented.
X1 Exit Meeting Summary (Inspection Procedure 30703)
i The inspector presented the inspection results to members of licensee management at
.the conclusion of the inspection on April 30,1998. The licensee acknowledged the l
. findings presented.
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PARTIAL LIST OF PERSONS CONTACTED Licensae L. Bobek, Nuclear Reactor Facility Director
' R.' Borrelli, Radiation Safety Officer
'T. Boulette, Director, Nuclear Engineering Program-Sgt. ' S. Desy, Campus Police
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INSPECTION PROCEDURES USED IP 30703:
ENTRANCE AND EXIT INTERVIEWS IP 40750:
CLASS ll NON-POWER REACTORS IP 81431 FlXED SITE PHYSICAL PROTECTION OF SPECIAL NUCLEAR MATERIAL OF LOW STRATEGIC SIGNIFICANCE IP 85102 MATERIAL CONTROL AND ACCOUNTING - REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened none Closed 50-134/96-01-01 IFl Verify visual alarrns during annunciator system checkout 50 134/96-01-02 IFl Conduct 50.59 evaluation of lead shield.
LIST OF ACRONYMS USED
.. CFR Code of Federal Regulations NRC Nuclear Regulatory Commission RHSC-Radiation, Health, and Safeguards Committee-RO Reactor Operator
.RSO Radiation Safety Officer SRO Senior Reactor Operator TLD-Thermoluminescent dosimeter -
TS Technical Specifications
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