IR 05000223/1978003
| ML20062B919 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 09/15/1978 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062B895 | List: |
| References | |
| 50-223-78-03, 50-223-78-3, NUDOCS 7811020186 | |
| Download: ML20062B919 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSI0l
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0FFICE OF INSPECTION AND ENFORCEMhNT Region I Report No. 50-223/78-03 Docket No. 50-223
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License No.
R-125 Priority Category F
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Licensee:
University of Lowell 1 University Avenue
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Lowell, Massachusetts 01854 Facility Name:
University of Lowell gv.
Inspection at:
Lowell, Massachusetts Inspection conducted: August 17-18, 1978 Inspectors:
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Edward G. Greenman, Reactor Inspector date signed
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date signed date signed Approved by:
8 6 AM f f / 'l /71
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E. C. McCabe, Jr., Chief, Reactor Projects cate signed Section No. 2, RO&NS Branch l
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Insoection Summary:
l Inscection on Aucust 17-18, 1978 (Recort No. 50-223/78-03)
l Areas Inscected:
Routine, unanncunced inspection by a regional based inspector of preceoures, surveillance, exceriments, follcwup on prior items of nonccmpliance, cmergency plans (drill verification), licensee event report review (in-office and on site review), independent effort and 10 CFR 21 implementation.
The inspection involved 9 inspector hcurs on site by one regional based inspector.
l Resul ts:
Of the eight areas inspected, no items of noncemoliance were identified I
in seven areas.
One item of ncncompliance was identified in one arcs related to a failure to comply with posting requirements of 10 CFR 21 (Deficienc/ - Detail 9).
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l Regien I For:: 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Princioal Licensee Emolayees
- Dr. L. Begbian, Associate Vice President for Academic Services
- Mr. G. Chabot, Radiation Safety Officer
- Dr. J. Phelps, Professor in Charge of Nuclear Reactor
- Mr. T. Wallace, Reactor Supervisor The inspector also talked with and interviewed several other licensee employees during the inspection.
They included reactor operators and security personnel.
- denotes those present at the exit interview.
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- denotes those present part-time at the exit interview.
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2.
Licensee Action On Previous Inscection Items (Closed) Noncompliance (223/78-02-01) Failure to calibrate two high range gama survey instruments quarterly.
The inspector confirmed that the two instruments in question had been removed from the Emergency Equipment List and verified that they were not in the approach closet.
Corrective action was as described in the licensee's letter to RI dated March 20, 1978.
The inspector had no further questions regarding this item.
(Closed) Nonccmpliance (223/78-02-02) Failure to hold a semi-annual drill during the second half of 1977.
The inspector confirmed that an emergency drill was conducted in the first half of 1978.
Corrective action was as described in the licensee's letter to RI dated March 20, 1978.
The inspector had no further questions concerning this item.
(Closed) Inspector Followup Item (74-05-01) Action Levels in Procedures.
Review of licensee's procedures for evacuation of building indicate that coverage has been provided to assure cause is determined when a radiation monitor alar ns and that initiation of the reactor area (or general area) evacuation is acccmplished when a LREA or GREA alara cccurs, unless the alarm is an:icipated due to work involved not warranting evacuation.
The inspector had no further questions regarding this matter.
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3.
Logs and Records
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The folicwing logs and records were reviewed for the periods as indicated.
No unacceptable conditions were identified, a.
Reactor Log - July-August 18, 1978 b.
Shift Record Data Sheets - August 18, 1978 c.
Daily Checklist - August 18, 1978 (],
d.
Reactor Checkout List - August 18, 1978 e.
Reactor Safety Subc:mmittee Meeting Minutes - March 8-July 13, 1978 f.
Surveillance Test Records - as stated in this report t
4.
Facility Tour The inspector examined various areas of the facility including the pump room and the control rocm, to inspect the general state of cleanliness, housekeeping and adherence to fire protection guide-lines.
The inspector verified equipment status and operability and confirmed by comparison of selected control room instrumentation that selected Technical Specification parameters were adhered to.
Status of locked valves in the pump room was verified.
The inspector observed that cable penetrations to the control recm were not sealed from the control recm to the level below.
No requirements were identified to require sealing.
The licensee was requested to provide an engineering review regarding this matter.
This item (223/78-03-01) will be further reviewed during a subsequent inspecticn.
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5.
Review of Nonroutine Event Recorted by the Licensee Licensee even: report inscection included the licensee's action with respect to a failure of the evacuation horns in the nuclear center to alarm, when a test was initiated, and as reported by licensee's letter to RI, dated March 9,1978.
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The inspector verified that the event had been reviewed as required j
by the Technical Specifications and that corrective action had been
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taken.
The inspector also confirmed that the operators are requirtd
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by checklist to visually check the power on light that has been installed in the circuitry to detect malfunctions, e.g. blown fuses.
6.
Procedures The inspector reviewed the licensee's administrative guidance and verified that responsibilities of operators and senior ocerators were established via procedures including changes, apprcvals and
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levels of subsequent review.
The inspector reviewed the following ('
procedu ts for technical adequacy and conformance with Technical Specification requirements.
a.
Containment Isolation and Closure b.
Emergency Generator Load Test i
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Routine Startup
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The inspector also observed completion of startup checklists and a facility startup and operation on August 18, 1978, and confirmed step by step that the procedure accomplished its intended purpose, was available and utilized by the console operator, had been reviewed and approved and was the latest revision.
Specific operations reviewed included console checkout, approach to criticality, criti-cality and low power operation.
,,C The inspector noted that magnet currents for control rods were reading in excess of values recorded for the most recent control rod testing results. The inspector apprised the licensee that existing settings were non-conservative.
The licensee concurred with the inspector's position and agreed to reduce the magnet current settings following completion of the run that was in oro-gress.
This item (223/78-03-02) is unresolved pending revie, of the licensee's action in this area.
7.
Surveillance The following surveillance test records were reviewed for the periods as indicated.
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a.
Annual Control Blade Inspection - June 28, 1977-June 2, 1978
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Safety Channel Calibrations - October 21,1977-April 20,1978 c.
Pool Level Calibrations - January 13-May 26,1978 d.
Ventilation System Surveillance - March 12, 1976-June 12, 1978 e.
Emergency Ventilation. - July 11, 1977-June 12, 1978 f.
Rod Drop Time Measurements - June 1978 The inspector also verified selected parameters identified in the
{>3 Technical Specifications and verified based uoan the startup as observed that equipment was operable as required and that limiting conditions for aperation were being satisfied.
No unacceptable conditions were identified.
8.
Exoeriments
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The inspector reviewed minutes of the Reactor Safety Subcommittee (RSSC) for July 13, 1978, to determine that the comittee was dis-charging its responsibilities for experimental reviews specifically reagrding a proposal under consideration involving Na24.
No inadequacies were identified.
The inspector noted that documentation concerning such approvals is unclear, in writing, for the comittee's deternination that pursuant to 10 CFR 50.59, no unreviewed safety questions are involved.
A responsible licensee representative stated that such documentation would be provided.
This item (223-f 78-03-03) will be reviewed further during a subsequent inspection.
The inspector also audited a sampling of the licensee's Reactor
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Irradiation Request Forms, and verified that appropriate shielding i
for experimental facilities was in place.
The licensee's adherence to protective clothing requirements was also confirmed.
No unaccep-table conditions were identified.
l 9.
Establishment and Imolementation of 10 CFR Part 21 Recuirements
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An in-office review was conducted of the licensee's draft procedures and controls established to comply with the requirements of 10 CFR l
21.
No items of nonccmpliance were identified in this area of
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review. The inspector also observed the licensee's Sulletin Soards
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to confirm the adequacy of 10 CFR 21 required documents for posting.
i Contrary to 10 CFR 21.6, Section 206 of the Energy Reorganization l
Act of 1974, nor 10 CFR 21, or alternate notices had been posted
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by the licensee as of Augu t 17, 1978.
This failure to post items i
as required constitutes a Deficiency level item of noncompliance.
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(223/78-03-04)
10.
Unresolved Items Unresolved items are those items for which further infomation is required to determine whether they are acceptable or items of non-compliance.
An unresolved item is contained in paragraph 6 of this report.
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11.
Exit Interview
/\\kl An exit interview was conducted on August 18, 1978, with licensee representatives *(denoted in paragraph 1) at the conclusion of the inspection.
The inspector sunnarized the purpose and scope of the inspection and the findings.
Licensee representatives acknowledged the inspection findings.
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