IR 05000244/1990020
| ML17262A241 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/30/1990 |
| From: | Joseph Furia NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17262A240 | List: |
| References | |
| 50-244-90-20, NUDOCS 9011150067 | |
| Download: ML17262A241 (6) | |
Text
'U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
0 0 5 0
.
~522244 00-20 Docket No.
50-244 License No.
DPR-18 Licensee:
Rochester Gas and Electric Com an 49 East Avenue Rochester New York 14649 Facility Name:
Robert E. Ginna Nuclear Power Plant Inspection At:
Ontario New York Inspection Conducted:
October 15-18 1990 Inspector:
J. Furia, Radiation Specia st, Effluents Radiation Protection Section (ERPS), Facilities Radiological Safety and Safeguards Branch (FRSSB),
Division of Radiation Safety and Safeguards (DRSS)
'go date Approved by:
R.
Bore Chief, ERPS, FRSSB, DRSS i~a/e date Inspection Summary:
Ins ection on October 15-18 1990 Ins ection Re ort No.
4/49-2 0 Areas Ins ected:
Routine, unannounced inspection of the transportation and solid radioactive waste programs including:
management controls, audits, quality assurance, and implementation of the above programs.
Results:
Within the areas inspected, no violations or deviations were noted.
90111 iOA67 903.0
DETAILS 1.0 Personnel Contacted 1.1 Licensee Personnel K. Easterbrook, guality Assurance Engineer
- D. Filkins, Manager, Health Physics'nd Chemistry
- A. Herman, Health Physicist N. Kiedrowski, Training Instructor G. Snajder, guality Management
& Support Services, Inc.
- S. Spector, Plant Manager
- J.
Widay, Superintendent
- Ginna Production le2 NRC Personnel
- T. Moslak, Senior Resident Inspector
- N. Perry, Resident Inspector
- Denotes those present at the exit interview on October 18, 1990.
2.0
~Por ose The purpose of this routine inspection was to review the licensee's program for the preparation, packaging and transportation of.radioactive materials.
3.0 Trans ortation and Radwaste Processing, packaging and transportation of radwaste and other radioactive materials were the responsibility of the Health Physics and Chemistry Department, whose manager reports to the Plant Superintendent.
Within the Health Physics and Chemistry Department, one health physicist was given responsibility for the management of the radwaste and transportation program.
3.1 Radwaste The plant processed waste water through a
Chem Nuclear Systems, Inc.
(CNSI)
demineralization system; primary plant water through the Chemical Volume Control System (CVCS);
and collected Dry Active Waste (DAW) for disposal.
Spent resins were dewatered with low activity anion resins from the waste water system and shipped to Scientific Ecology Group (SEG), while the remainder of the spent resins was shipped to the Barnwell Low-Level Disposal Facility.
Since the last inspection in this area, the licensee has suspended operation of the waste evaporator, in an effort to reduce waste generation volume.
In addition, the licensee has expended great effort to remove all non-essential contaminated materials from the site, in order to reduce the amount of material which would have to be placed in an Interim Radwaste Storage Facilit As part of this inspection, the inspector reviewed the following procedures utilized in the processing, packaging and shipment of radwaste and radioactive material.
RD-10.0, Rev 18, "Preparing Radioactive Material for Shipment or Storage" RD-10.2, Rev 6,
"Radwaste Shipping to CNSI at the Barnwell, South Carolina Site" RD-10.6, Rev 24,
"Shipment of Low Level Radioactive Waste" RD-10.8, Rev 4,
"10CFR61 Compliance" RD-11, Rev 9, "Receipt of Radioactive Haterials" RD-16.0, Rev 3, "Process Control Program" S-4. 1.27, Rev 3,
"Temporary Chem Nuclear Waste System Operation" These procedures were determined to be complete and to accurately reflect plant operations in this area.
Scaling factors for hard to detect isotopes were typically determined annually based on representative composite samples provided to Scientific Applications International Corporation (SAIC) for analysis.
SAIC also performed the scaling factor determinations for the licensee.
3.2 TTitive Packaging and shipping of all radioactive materials, including radwaste were the responsibility of the Health Physics and Chemistry Department.
As part of this inspection, the following 20 shipping records for materials shipped in 1990 were reviewed.
~Shi ment 2~iit
~32
~T 90-01 90-02 90-03 90-04 90-05 90-06 90-07 90-08 90-09 90-10 90-11 90-12 90-13 5.36E-06 4.89E-01 1.50E+00 2.24E+00 1.62E-08 1.34E-Ol 1.79E+01 3.66E-02 7.50E-05 2.65E-05 4.95E-05 1.10E-04 5.50E-03 127.5 2560.0 405.0 405.0
<1.0 412.2 120.3 2560.0 90.0
<1.0 222.0 90.0 1130.4 Laundry DAW Evap Bottoms Evap Bottoms Samples Resin Resin DAW Laundry Samples Equipment Laundry Equipment
~Shi ment
~ti it ti UIflt
~Y 90-14 90-15 90-16 90-17 90-18 90-19 90-20 All records were in Titles 10 and
'.69E'-04 3.13E-Ol 5.70E-01 2.42E+00 1.11E-04 5.86E-07 4.25E-02 determined to.meet the regulatory 49, Code of Federal Regulations.
Laundry Hetals DAW Equipment Laundry Equipment Equipment requirements as set forth 3.3 Interim Radwaste Stora e
In preparation for possible exclusion from the existing burial sites in 1993, as allowed under the Low-Level Waste Policy Act of 1980 and the Low-Level Waste Policy Amendments Act of 1985, the licensee has developed preliminary plans for the utilization of the existing Radwaste Storage Building as an Interim Radwaste Storage Facility.
Due to the licensee's efforts to reduce radwaste at the plant site during the past year (Section 3. 1), the volume of waste which would require storage has been greatly reduced.
In addition, the licensee has processed out all spent primary plant resins, and thus would be expected not to have a need to process this type of material for another 15-18 months.
On October 1,
1990, the State of New York was notified by representatives of the States of Nevada, South Carolina and Washington that waste generated in New York may be excluded from the existing burial sites as early as December 7,
1990.
At the time of this inspection, the licensee was accelerating its plans for interim on-site storage.
t.t ~ti t<<
The licensee's program for the assurance of quality in the radwaste and transportation areas involved evaluating principle vendors supporting this area, plant audits of this area, and quality control review of all shipments of radwaste and principle r adwaste evolutions.
Vendor evaluations were conducted by the licensee's corporate offices.
The evaluation of CNSI, which supplies liners and shipping casks to the licensee was conducted by representatives of the Wolf Creek Nuclear Generating Station, on behalf on the Nuclear Procurement Issues Council (NUPIC), of which the licensee was a member.
All pertinent records related to this audit were maintained by the licensee.
Audits of the plant radwaste and transportation program were conducted on an annual basis.
Audit 90-19:GFS, dated June 20, 1990, was the most recently completed audit in this area.
There were no findings requiring followup or deficiencies identified in this audit related to the radwaste program.
The inspector had no further questions in this are A l
guality Control (gC) evaluated all radwaste shipments and major evolutions, and documented these reviews 'in Surveillance Reports.
Surveillance Reports for 1990 were reviewed and determined to provide comprehensive coverage of the radwaste program.
3.5
~Trainin Training of Radwaste Operations personnel to meet the requirements of NRC IE Bulletin 79-19 was established to present new radwaste employee training, and subsequent biennial retraining.
Retraining for the current cycle was scheduled to commence in early December, 1990, utilizing a SEG provided training program.
Four days of training were scheduled for those Health Physics personnel directly involved in the radwaste shipping program.
The inspector had no further questions in this area.
4.
Exit Interview The inspector met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on October 18, 1990.
The inspector summarized the purpose, scope and findings of the inspection.