ML19323H842
| ML19323H842 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 04/30/1980 |
| From: | Fisher W, Peck C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323H841 | List: |
| References | |
| 70-1308-80-02, 70-1308-80-2, NUDOCS 8006170064 | |
| Download: ML19323H842 (4) | |
Text
.
.. ?7 U
V U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III Report No. 70-1308/80-02 Docket No. 70-1308 License No. SNM-1265 Licensee: General Electric Company 175 Curtner Avenue San Jose, CA 95125 Facility Name: Morris Operation
. Inspection At: Morris Operation, Morris, IL Inspection Conducted: March 21, 26, and 27, 1980
-t Inspector:
. C. Peck N 3C[PC U4 C94 Approved'By:
W. L. Fisher, Chief M_?d/h d Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on March 21, 26,-27, 1980 (Report No. 70-1308/80-02)
Areas Inspected: Routine, announced health and safety inspection, in-cluding: organization, fuel storage and handling, facility changes and modifications, surveillance testing, internal exposure control, external exposure control, and a followup of IE Bulletin 79-19.
The inspection involved 18 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance were identified in the seven areas inspected.
800 617 0 C)%
DETAILS 1.
Persons Contacted
- E. E. Voiland, Plant Manager
- T. E. Ingels, Manager, Quality Assurance and Safeguards
- K. J. Eger, Senior Engineer, Licensing and Radiological Safety
- H. R. Strickler, Operations Manager
- J. P. Kesman, Plant Engineering and Maintenance Manager J. E. McGrath, Plant Safety Supervisor N. P. Shaikh, Operations Engineer K. A. Astrom, Specialist, Field Services
- Denotes those present at the e. cit interview.
2.
General The inspection began at 12:00 p.m. on March 21, 1980, with observa-tion of the receipt and unloading of the twelfth in a series of spent fuel shipments from the San Onofre reactor. The remainder of the inspection was conducted on March 26 and 27.
3.
Organization Mr. J. E. Van Hoomissen has replaced Mr. L. L. Zahn, Jr. as Manager of Spent Fuel Services Operations.
4.
Fuel Receipt and Storage A series of spent fuel shipments from the San Onofre reactor began in January 1980. The shipments were to have begun in mid-1979 but were delayed because certification of NFS-4 type casks was suspend-ed temporarily pending a study and testing of some changes that were made to some of the casks.
In early 1980, use of the casks for dry shipments was approved, by which time the San Onofre fuel had cooled sufficiently to permit dry shipments.
Shipments have been accomplished without incident. The inspector examined radiation and contamination survey records for each of the shipments and found that there had been no measurements exceed-ing DOT limits. The receipt and a portion of the unloading of the twelfth shipment was observed during the inspection. The maximum radiation level found on the cask surface was 90 mR/hr at the impact limiter, and tge maximum smearable contamination found was gbout 6000 dpm/100cm. Limits are 200 mR/hr and 22,000 dpm/100cm,
respectively.
No items of noncompliance were identified. i
L 5.
Radiation Protection a.
External Exposure Control Monthly-film badge records were examined but not in detail.
No problems were identified.
b.
Internal Exposure Control The March 1979 urinalysis for one individual disclosed a cesium-137 concentration that could possibly represent a dose greater than 40 MPC-hours (Report No. 79-03). A subsequent urinalysis showed a reduction in cesium-137 from 1.2 E-06
,uCi/ml to 3.6 E-07.pCi/ml, and quarterly samples have since indicated concentrations of gamma emitters less than IE-07
,uCi/ml. A whole body count in April 1979 indicated 1.1% of MPBB for cobalt-60 and smaller percentages for the other gamma emitters. Efforts to determine the cause of the high original urinalysis disclosed that the uptake probably occurred during work in the sample cell in the laboratory. The ratio of cesium isotopes in the sample from the sample cell was about the same as that in the urine sample. As a result of this finding, an SWP which includes respiratory protection is now required for work in the cell.
Quarterly urinalyses for all workers since May 1979 and whole body counts in November 1979 indicated no significant exposures.
No items of noncompliance were identified.
6.
Surveillance Tests Records of routine compliance and operability tests conducted since June 1979 were examined. All tests have been conducted at their required frequencies. The tests have disclosed no unsafe conditions or trends.
Fuel basin water quality remains within operating specifications in both chemical and radioactivity content. The water activity was about 2 E-04,uci/ml at the time of the inspection.
No items of noncompliance were identified.
7.
IE.Bulletin 79-19 Actions taken by the licensee in response to IE Bulletin 79-19 were examined. The program for transfer, packaging, and shipping of waste materials was reviewed. Findings are summarized below:.
The licensee maintains current DOT and NRC regulations Copies of burial site require =ents are maintained.
Management approved procedures in the form of SOP's covering handli..g, transfer, storage, packaging, and package surveys are maintained.
Training for persons involved in the transfer, packaging, and transport of low-level waste has been implemented. A manual entitled "LSA Management at M0" was prepared and used for the training of involved workers. Written quizzes were used to test employee knowledge of the subject matter. Training re-cords are maintained.
In addition, a videotape was prepared to instruct employees in correct waste handling and packaging techniques. Retraining will be scheduled periodically, at least biennially.
The licensee has a management-approved audit program which includes examination of low-level waste management. The in-spector reviewed an audit of the waste system conducted by personnel from the company's San Jose office within 60 days after issuance of IE Bulletin 79-19.
Increased emphasis in the training program described in the preceding paragraph resulted from the audit.
Waste packages on hand were inspected. There were no apparent problems. Because the facility does not normally have problems of liquid waste solidification and absorption, no packages were opened.
l 8.
Exit Interview j
The inspector met with licensee representatives identified in Paragraph lat the conclusion of the inspection. The inspector re-viewed the scope of the inspection and stated that no items of non-compliance had been identified.
I Comtemplated future facility changes and improvements were discussed.
4 I
l l
t I '