IR 05000223/1979001
| ML19242C057 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 06/21/1979 |
| From: | Mccabe E, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19242C056 | List: |
| References | |
| 50-223-79-01, 50-223-79-1, NUDOCS 7908090694 | |
| Download: ML19242C057 (6) | |
Text
-
-
-
..
"
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
'
REGION I
Report No. 50-223/79-01 Docket No. 50-223 License No. R-125 Priority --
Category F Licensee: University of Lowell 1 University Avenue Lowell, Massachusetts 01854 Facility Name: University of Lowell Inspection At:
Lowell, Massachusetts Inspection Conducted:
April 18-20, 1979 Inspector:
6h/b9 T. Y. ~Stetka, Reactor Inspec tor dat6 si$ned'
d f/[77 Approved By:
//MJ/
,M
/-,
,
'E. C gic Cab e, Jr d,4 Chief, ' Reac to r datd signed Projects Section No. 2, RO&NS Branch Inspection Summary:
Inspection on April 18-20, 1979 (Report No. 50-223/79-01)
Areas Inspected:
Routine, unannounced inspection of logs and records,
.
operator licenses, organization and administration, operator requali-fication program, IE Bulletin and Circular responses, and licensee action on previous inspection findings.
Facility tours were conducted.
The inspection involved 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> on site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
.5T D b 790800067p
.
'
.
DETAILS 1.
Persons Contacted
- L. Beghian, Associate Vice President for Academic Services G. Chabot, Radiation Safety Officer M. Evans, Chief Reactor Operator
- J. Phelps, Professor-in-Charge of Nuclear Reactor
- T. Wallace, Reactor Supervisor The inspector also interviewed other licensee representatives including operations and office staff personnel.
- Denotes those present at the exit interview.
2.
Licensee A'ction on Previous Inspection Items (Closed) Followup Item (223/78-01-01):
Review of licensed operator exami-nations.
The licensee conducted examinations on January 31, 1978 and all operators tested satisfactorily passed the examinations.
(Closed) Noncompliance (223/78-03-04):
The inspector examined bulletin boards throughout the facility and verified that required posting was accomplished.
(Closed) Followup Item (223/78-03-01):
The licensee performed an engineering review of cable penetration sealing and determined that such sealing is not necessary.
The inspector reviewed the engineering evaluation, discussed this issue with cognizant licensee personnel, and concurred with the li-censee's conclusions.
(Closed) Unresolved Item (223/78-03-02):
The licensee has revised proce-dure S.P.16, Rod Drop and Drive Measurements, as Revision 3 dated August 28, 1978 to include requirements to assure that operating magnet currents are less than the magnet currents used to perform the rod drop measure-mente.
(0 pen) Followup Item (223/78-03-03): The September 28, 1978 meeting of the Reactor Safety Subcocuittee reviewed this item; however, no new experiments requiring subcommittee review have been initiated since this item was identified.
This item will be reviewed during subsequent inspections.
590220
3.
Logs and Records The following logs and records were reviewed for the periods as indicated.
No unacceptable conditions were identified within the scope of this in-specticn.
a.
Reactcr Log Book No. 6 for the period January 2,1979 through March 23, 1979.
b.
Daily Routine Check Sheets for March 1979, c.
Pre-Startup Check Sheets for March 1979 d.
Reactor Shutdown Check Sheets for March 1979.
e.
Reactor Checkout Instruction Sheets for March 1979.
f.
Shift Record Data Sheets for March 1979.
g.
Unscheduled Routine Maintenance forms for 1979.
h.
Core a T Recorder Chart for January 1979.
i.
Primary Coolant Flow Chart for January 1979.
J.
Linear Power Level Chart for February - March 1979.
No inadequacies were identified.
4.
Facility Tours a.
The inspector toured various areas of the facility including the control room, rear panel areas, reactor building, emergency generator room, pump room, and waste storage area to determine the general state of cleanliness, housekeeping and adherence to fire protection guide-lines.
The inspector checked equipment status and operability and verified by comparison of control room indications that limits for power, flow and nuclear channel operability were being adhered to.
Coolant conductivity and temperature parameters were also examined.
The inspector also verified that the minimum licensed operator com-plement required by Technical Specifications was satisfied and that specific licence restrictions if applicable were adhered to.
590221
.
.
During these tours, the inspector observed personnel exiting the reactor building and not utilizing the hand and foot monitors located at the exits.
The inspector discussed monitor use with a licensee reprocantative who stated that while the monitors should be used, the poi slity of beccming contaminated was very remote due to separate barr.cading and posting of potentially contaminated areas.. The in-spector observed the effectiveness of the licensee's contamination controls during the tour and agreed with the licensee's assessment.
However, the inspector stated that these monitors should be utilized to insure that contamination control remains effective.
The licensee acknowlodged the inspector's comments and stated that action would be taken to insure personnel use of hand and foot monitors.
This item (223/79-01-01) is unresolved.
b.
During these tours the inspector witnessed the startup and shutdown of the reactor.
Prior to these observations, the inspector reviewed the following procedures to verify licensee adherence to procedures during these evolutions:
- R.0. 5, Routine Startup, Rev. 1;
- R.0. 6, Operation At Power and Adjustments in Power Level, Rev.1; and,
- R.0. 7, Reactor Shutdown, Rev. 1 No inadequacies were identified.
5.
Operator License Review The facility is now staffed with four licensed senior reactor operators and three licensed reactor operators.
The licensen for all of these individuals were reviewed by the inspector to verify that the licenses were current and that assigned duties were in accordance with license requirements.
The Reactor Supervisor's license, which is current, was unavailable for the inspector's review.
This license will be examined during a subsequent inspection and is considered to be an open item (223/79-01-02).
6.
Organization and Administration The inspector was apprised that Mr. M. Evans was appointed Chief Reactor Operator in August 1978.
This individual holds a Senior Reactor Operator License.
This position is not identified in the facility Technical Speci-fications.
5CJON2
The Director of the Nuclear Center position is still vacant (see NRC:RI Report 50-223/78-01) with the responsibilities for this position still assumed by the Assistant Vice President for Academic Stsdies.
It is ex-pected that this position will be filled this summer.
This item (223/79-01-03) is open.
With the exception of the vacancy noted above, the facility organization remains as described in the Technical Specifications and no inadequacies were identified.
7.
Requalification Program The licensee's Requalification Program for Licensed Reactor Operators and Licensed Senior Reactor Operators, dated June 22, 1978, is a revised version of the initial requalification program dated June 19, 1974.
The revised program changed the operatc;'s examination frequency from annual to biennially and lowered the passing grade to 70%.
These changes were re-viewed and approved by the NRC Operator Licensing Branch (OLB).
The new requalification program credits the Reactor Supervisor and Chief Reactor Operator with participation based on their direct responsibility in conducting the program.
A review of operating records identified no failure of licensed operators to conduct required reactivity control manipulations at the console.
No unacceptable conditions were identified with respect to 10 CFR 55.31(e) and 55.33(c)(2)(i).
The inspector verified that the methods identified in the requalification program have been implemented and that lectures are conducted, drills are completed, and abnormal, emergency, and operation procedures and their changes have been reviewed and covered in the program.
The inspector also verified that the licensee is conducting a formal lecture program.
During review of the requalification program, it was noted that the operators were not completing the sign-offs for procedure review on a timely basis.
This item (223/79-01-04) will be reviewed during subsequent inspections.
8.
Bulletin / Circular Review a.
The inspector reviewed the licensee's action with respect to Bulletin IEB 78-07, Protection Afforded by Air-Line Respirators and Supplied-Air Hoods.
The bulletin was reviewed by the Radiation Safety Officer who determined that the facility does not use the type of respirMory equipment identified.
No inadequacies were identified.
590223
.
/
b.
The licensee's actions with respect to Circular 77-14, Separation of Contaminated Water Systems from Noncontaminated Plant Systems, were reviewed. The licensee has backflow preventer valves installed in the two connectors to the city water supply.
The inspector examined the installation of these valves during the plant tour and discussed the use of these valves with cognizant licensee personnel.
These valves were installed prior to the issuance of the circular and the licensee determined that no addiulanal action was necessary.
No inadequacies were identified.
9.
Unresolved Items Unresolved items are those items for which more information is required to determine whether they are acceptable items or items of noncompliance.
An unresolved item is contained in paragraphs 4.a and 5.
]0.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on April 20, 1979.
The inspector summarizea the scope and findings of the inspection as they were detailed in this report.
During this meeting, the unresolved items were identified.
-
%
590Z24