IR 05000244/1989026
| ML17250B049 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/30/1989 |
| From: | Bores R, Joseph Furia NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17250B048 | List: |
| References | |
| 50-244-89-26, NUDOCS 8911140102 | |
| Download: ML17250B049 (10) | |
Text
NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos.
50-244 89-26 Docket Nos.
50-244 License Nos.
DPR-18 Priority Category C
Licensee:
Rochester Gas and Electric Com an as venue Y
k ll649-0 Facility Name:
R.
E. Ginna Nuclear Power Plant Inspection At:
Ontario New York Inspection Conducted:
October 23-27 1989 Inspectors:
uria, a ia ion pec>a
>s
,
j./sdPf Approved by:
ores, se
,
uen a ia ion Protection Section, FRSSB 8a A9 Inspection Summary:
Ins ection on October 23-27 1989 Ins ection Re ort No.
50-244 89-26 Areas Ins ected:
Routine, unannounced inspection of the solid radioactive waste sys ems an ransportation programs including:
Management controls, audits, quality assurance, and implementation of the above programs.
Results:
Within the areas inspected, no violations or deviations were noted.
8911140102 891101 PDR ADOCK 05000244
>hllj
1.0 Personnel Contacted 1. 1 Licensee Personnel DETAILS S. Spector, Plant Manager
- A. Herman Health Physicist
- D. Kotarski, Radiation Protection E Shift Technician
~ F. Mis, Health Physicist
- A. Jones, Corrective Actions Coordinator M. Klueber, Radiation Protection Technician K. Easterbrook, guality Assurance Engineer
- W. Goodman, Health Physics Foreman
~ D. Filkins, Health Physics"and Chemistry Manager
- R. Maichionda,- Director, Outage Planning
- J.
Germain, guality Control Foreman
- R. Ploof, Technical Engineer
- T, Schuler, Operations Manager 1.2 NRC Personnel
" N, Perry; Resident Inspector
- Denotes those present at the exit meeting on October 27, 1989.
2.0
~Pur ose The purpose of this routine inspection was to review the licensee's program to properly prepare, package and ship licensed radioactive materials for transport and disposal.
3.0 Trans ortation and Solid Radwaste Processin In accordance with plant procedures, preparation, packaging and transportation of wastes were the responsibility of the Radwaste Section of the Health Physics and Chemistry Department.
A Health Phy'sicist was assigned principle responsibility in this'area.
He reported directly to the Health Physics and Chemistry Manager, who in turn reported to the Plant Manager.
Wastes included evaporator bottoms, spent resins, filters and Dry Active Wastes (DAW).
3.1
~ualit Assurance ualit Control The guality Assurance/guality Control program at Ginna involved guality Assurance audits of inplant and principle vendor activities, guality Control reports of selected radwaste activities, and 0uality Control hold points and checklists to examine each shipment and major radwaste evolutions.
Audit 89-20:BS, dated August 16, 1989 was an evaluation of the licensee's Radwaste Packaging and Transportation
3.2 Program.
Three findings were identified in this audit, none with direct safety significance.
All findings were promptly addressed by the licensee, and corrective actions were verified by Quality Assurance.
Audit TE56640-K001, dated August 1,
1989 was conducted to evaluate Chem-Nuclear Systems, Inc.
(CNSI), which provided waste liners, shipping casks and disposal services for various licensees, including Ginna.
Seven Areas" of Concern (AOC) were identified, none of which involved significant safety issues.
This audit was conducted under the auspices of the Nuclear Procurement Issues Council
$ NUPIC), of which the licensee is a member.
The scope and technical depth of these audits were determined to be good.
Quality Control (QC) conducted periodic surveillances of radwaste activities, and sn addition had mandatory radioactive material shipment hold points.
Eighteen QC reports had been issued durina 1989 in the radwaste area.
These reports were found to adequate'fy meet the commitments made by the licensee in its Quality Assurance Manual.
Hold points for QC review were documented for each shipment of radwaste, in accordance with the following procedures.
QCIP-21,
" Inspection of Shipping Packages (Casks) for Radioactive NaterIal" This program of Quality Control activities was determined to be excellent.
The inspector had no further questions in this area.
~V As part of this inspection, the inspector reviewed the records of the 14 radioactive material shipments listed below.
~tl i V
Ylllft t t. it ti
~Te QCIP-21.6,
"Inspection of Exclusive Use Radioactive Material Transport Vehicles" 89-30 89-31 89-32 89-33 89-34 89-35 89-37 89-38 89-39 89-40 89-41
'89-42 89-43 89-44 120.4 2560 4.7 4.7 4.7 154 4.1 405 405 405 2590 405 405 405 3. 58E+1 3.64E-1 1.80E-6 1.80E-6 1.70E-2 3.69E-7 2.44E-4 1.59E+0 2.38E+0 2. 15E+0 8.95E-1 1.68E+0 1.78E+0 1.27E+0 resin DAW liquid samples liquid samples waste samples outage equipment outage equipment evap bottoms evap bottoms evap bottoms DAW evap bottoms evap bottoms evap bottoms
U i
All records were found to be complete, and to accurately classify the material in accordance with 10 CFR
and
CFR Parts 100-179.
In addition, the inspector reviewed the following transportation procedures'.
RD-10.0, Rev 17, "Preparing Radioactive Material for Shipment or Storage" RD-10.2, Rev 5,
"Radwaste Shipping to CNSI at the Barnwell, SC Site, Type A guantIties" RD-10.4. 1, Rev 8,
"US Ecology Radioactive Shipment Record (RSR) for Use at Beatty, Nevada and Richland, Washington" RD-10.6, Rev 23,
"Shipping of Low Level Radioactive Waste" RD-10. 14, Rev
"Handling, Loading and Unloading of the Chem-Nuclear 8-120A or B(U Transport Cask" RD-11, Rev 9, "Receipt of Radioactive Material"
/
These rocedures were determined to be complete and to accurately current transportation operations.
P reflect 3.3 Radwaste In accordance with plant procedures, liquids were processed through the plant evaporator, and the evaporator bottoms were then solidified utilizing plant procedures and equipment.
Due to the reduced
.efficiency of the evaporator, the licensee was considering the use of a vendor supplied mobile demineralization system.
Spent resins are sluiced to a High Integrity Container and dewatered by the licensee.
Spent filters were stored on site in shielded containers.
DAW was bulk loaded in SeaVans for shipment to Scientific Ecology Group (SEG)
or guadrex.
Laundry was processed on site.
The inspector reviewed the following procedures related to radwaste.
RD-10. 17, Rev 0, "Transfer of a Filled Resin Liner From a Process Shield or Cask to a Shipping Cask" RD-16.0, Rev 2,
"Process Control Program" RD-16. 1, Rev 3, "Demonstration of Solidification of Waste Stream" RD-10.5, Rev 9, "Radioactive Waste Containers Storage Area Inventory" RD-10.7, Rev 12,
"Methods for the Segregation, Sorting and Handling of Radioactive Waste"
,
3.4 3.5 4.0 Exit RD-16.2, Rev 1,
"Drumming of Waste Evaporator Bottoms and Miscellaneous Waste" These procedures were determined to be complete and to accurately reflect current transportation operations.
Scaling factors for plant wastes were evaluated on an annual basis by SAI Corporation for all waste streams, in accordance with plant procedure RD-10.8, Rev 4,
"IOCFR61 Compliance".
This met the sampling criteria set forth in the NRC Branch Technical Position for Waste Classification.
The licensee continued to perform most calculations for waste classification and manifesting by hand calculations.
No errors were found in the paperwork associated with the licensee's shipping activities, and this could be attributed to the professionalism of the radwaste staff, and the strength of the guality Control program in this area.
The inspector had no further questions in this ar'ea.
~Trainin Training in the areas of transportation and radwaste was presented to guality Assurance, gC, and Health Physics personnel on a biennial basis.
This training program, last presented in November and December, 1988, consisted of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of classroom training, followed by a comprehensive examination.
This program was determined to meet the requirements of NRC IE Bulletin 79-19 for the training of radwaste workers.
Interim Radwaste Stora e
The licensee had limited onsite storage capacity, and it is unlikely that this capacity can be significantly enlarged due to the space limitations of the plant site.
Licensee plans, which were in a
preliminary state at the time of this inspection, included the purchase of a limited number of process shields for the storage of spent resin liners (assuming that the evaporator system is replaced by a mobile demineralization system),
and the continued access to either SEG or guadrex for most DAW.
Interview The inspector met the licensee representatives (denoted in Section 1) at the conclusion of the inspection on October 27, 1989.
The inspector summarized the purpose, scope, and findings of the inspection.
At no time during the inspection did the inspector provide any written information to the licensee.