IR 05000097/1979001
| ML19270H760 | |
| Person / Time | |
|---|---|
| Site: | 05000097, 05000157 |
| Issue date: | 10/18/1979 |
| From: | Briggs L, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270H749 | List: |
| References | |
| 50-097-79-01, 50-157-79-02, 50-157-79-2, 50-97-79-1, NUDOCS 8001030082 | |
| Download: ML19270H760 (6) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-157/79-02 Report No. 50-97/79-01 50-157 Docket No. 50-97 R-80 G
--
License No. R-89 Priority
--
Category H
Licensee:
Cornell University Ithaca, New York 14850 Facility Name:
Ward Laboratory of Nuclear Enaineering Inspection at:
Ithaca, New York Inspection conducted:
September '.o-27,1979 Inspectors: f $. k,6,-/>
/s//7/79 L. E. Brigg @ Reactor Inspector date signed date signed date signed Approved by:
bC U.b 10!IB M E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2, R0&NS Branch Inspection Summary:
Inspection on September 25-27, 1979 (Report Nos. 50-157/79-02 and 50-97/79-01)
Areas Inspected:
P.outine, onsite, unannounced inspection by one region-based inspector (17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />) of seven inspection areas:
organization, logs and records; review and audit; requalification training; procedures; surveillance; experi-ments; and class H reactor inspection.
Results: Noncompliances:
(2) (Infraction - failure to conduct the required number of Safety Committee meetings in 1977 and 1978, paragraph 3; Infraction -
failure to perform required fuel inspections within TS required time frame, paragraph 6.c).
1678 132 Region I Form 12 (Rev. April 77)
8001030 h
.
.
.
DETAILS 1.
Persons Contacted
- H. Aderhold, Reactor Supervisor, Ward Laboratory
- Professor D. Clark, Director of Ward Laboratory of Nuclear Engineering P. Craven, Reactor Operator
- Present at exit interview.
2.
Organization Logs and Records a.
Organization Facility organization was reviewed to compare composition and structure to facility Technical Specifications (TS).
The Cornell TRIGA and ZPR reactors are no longer a part of the School of Applied and Engineering Physics.
The reactor complex is now under the Nuclear Science and Engineering Program and reports directly to the Dean, College of Engineering until a director is selected to head the Nuclear Science and Engineering Program.
This change was reported by letter dated October 31, 1978.
No inadequacies were identified in this area.
b.
Logs and Records The inspector reviewed log books and checklists to ensure that they are being used and filled out as required.
This review included requirements for signatures, dates, initials, etc.
Emphasis was placed on the Operator's Console Log Book used to document reactor operations.
This log was found to be complete and neatly filled out on numbered pages.
The period selected for this review was January 1, 1979 to September 26, 1979 for the TRIGA reactor and June 9, 1978 to September 26, 1979, for the ZPR facility.
The log review also indicated that the TRIGA facility has been used for three basic purposes:
1) Training; 2) Activation Analysis; 3) Nuclear Research.
The ZPR facility was used only as a training facility for students at power ievels of 10 watts thermal or less.
No unacceptable conditions were identified.
1678 133
.
.
.
.
.
3.
Review and Audit A review of the Ward Laboratory Safety Committee (WLSC) minutes was conducted, emphasizing committee composition, meeting frequency and required topics.
Records from March 26, 1976 (meeting No. 49) through August 10, 1979 (meeting No. 60) were reviewed.
-
The inspector noted that all requirements were being met with the
.
exception of meeting frequency.
Meetings are required a minimum of four (4) times a year.
During 1977 only two (2) meetings (No's 54 and 55) were conducted.
In 1978 only three (3) meetings (No's 56, 57 and 58)were held, This is an item of noncompliance (157/79-02-01).
4.
Requalification Training The inspector determined that four (4) individuals currently hold SR0 licenses at the facility.
Two (2) individuals hold an SR0 license on both the ZPR and TRIGA reactors with each of the two remaining operators holding a single license, one on the ZPR the other on the TRIGA.
During discussions with the licensee and requalification test reviews, it was determined that two operators, one with a double SR0 license and the ZPR SRO were in a training status because of a sabbatical leave period.
All operators are scheduled to take the annual requalifi-cation test this fall.
The inspector also noted that requalification tests sometimes slipped beyond the established annual schedule because of reactor operations.
The licensee stated that, in the future, the test will be given each fall and that all operators will adhere to testing schedules.
This item is unresolved pending licensee action and subsequent NRC inspection.
(157/ 79-02-02).
5.
Procedures Facility operations and surveillance procedures were reviewed for the TRIGA and ZPR reactors.
The content and format were discussed with the licensee.
All safety-related procedures were approved by the WLSC.
The licensee has one procedure for each facility (TRIGA operations, July 24, 1972 and ZPR operations, April 29, 1963) that encompasses reactor startup, shutdown, steady state power operation, pulse operation (TRIGA only), maintenance guidance, special operations, Reactor Log format, and startup and shutdown checks.
1678 134
.
.
.
.
The inspector, accompanied by a licensee representative, walked through the TRIGA Reactor Daily Startup Checklist and the TRIGA Shutdown Checklist.
No unacceptable conditions were identified.
6.
Surveillance a.
TRIGA Technical Specifications Operating Limits The following Technical Specification (TS) operating limits were reviewed to verify compliance.
TS Requirement Setting Observation 2.2 Fuel Temperature 800 C (B Ring)
90 C (IO)
3.10.a)
Water Temperature 130 F 82 F (10)
3.10.b)
Pool Level
>18 1/2 feet 23' 2 1/2" (IO)
above Core 3.2 Transient Rod Fullout Fullout indicator at 938 (IO)
b.
ZPR TS Operating Limits TS Requirement Setting Observation C
Control Rods 3 rods clusters operable 3 operable (IO)
E Moderator Full height when full height (RR)
critical (IO) - Verified by inspector observation.
(RR) - Verified by recor/ review.
c.
Technical Specification Surveillances The following TRIGA surveillances were reviewed to verify compliance with TS requirements. No surveillance is required by ZPR TS.
1678 135
,
.
.
Control Rod Drop Times, data reviewed for August 26, 1977,
--
September 12, 1978, and September 2,1979; Visual Control Rod Inspection, data reviewed for August 25,
--
1977, September 18, 1978, and September 1,1979; Temperature Channel Calibration, data reviewed for April 28,
--
1978, October 2,1978, March 2,1979, and September 21, 1979;
--
Control Rod Worths, data reviewed for September 2,1977 and August 22,1978; and, Fuel Element Inspection, data reviewed for inspection No's 14,
--
15,16 and 17, completed on November 4,1975, January 3,1977, March 29,1978, and February 1,1979 respectively.
The above review disclosed that fuel element inspection No.16 had not been conducted within the TS required time frame of 14 months. This is an item of noncompliance (157/79-02-03).
7.
Experiments A review of experiments numbered 249 through 270 covering a period of January 5, 1976 through September ll, 1979, indicated that no experiments were without required TS review and approval. A comparison of Reactor Logs and approved experiments verified that the reactor was being used for the three basic purposes noted in paragraph 2.b of this report.
No unacceptable conditions were identified.
8.
Facility Tour The inspector, accompanied by a licensee representative, toured the facility.
Areas observed included housekeeping, fire hazards, radiation posting and reactor operations within TS limits (paragraph 6.a).
The inspector witnessed a reactor startup, steady state operation and reactor shutdown.
Independent radiation readings were taken by the inspector during operation in various areas. Appropriate procedures were adhered to during reactor operation and area radiation readings were consistent with postings. The tour included the ZPR facility.
In addition, the inspector reviewed the portable radiation survey instrument calibration program. During that review, it was noted that, for a period of over ten (10) years, instruments had been cMibrated on an 1678 136
.
.
.
.
'
annual basis with the exception of the past year (last calibration was May 1978). A review of the radiation survey instrument calibration procedure and other associated documents did not disclose a required frequency of calibration. The licensee agreed that instruments should be calibrated on an annual basis and that the associated procedure will be changed to require annual calibration.
The licensee also stated that, last year, responsibility for calibration had been given to a different person but that responsibility would now be returned to the originial party.
This item is unresolved pending licensee procedure revision and subsequent NRC inspection of the reestablished calibration program (157//79-02-04).
9.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable, an item of noncompliance, or a deviation.
Unresolved items identified during this inspection are discussed in paragraphs 4 and 8.
10.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on September 27, 1979.
The findings, scope and purpose of the inspection were summarized at that time.
The licensee acknowledged the inspector's findings.
167g 137 J