ML20058F324
| ML20058F324 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/02/1990 |
| From: | Bores R, Joseph Furia, Peluso L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20058F322 | List: |
| References | |
| 50-219-90-17, NUDOCS 9011080209 | |
| Download: ML20058F324 (6) | |
See also: IR 05000219/1990017
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50 219/90-17
Docket No.
50 219
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License No. DPR-16
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Licensee: GPU Nuclear Corooration
P. O. Box 388
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Forked River. New Jersev 08731
Facility Name: Qylter Creek Nuclear Generatina Station
Inspection At:
Forked River. New Jersey
inspection Conducted:
Seotember 18-21. 1990
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Inspectors:
T. Furia, Radiation Specialist, Ef fluents
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Ra'iation Protection Section (ERPS), facilities
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Radiological Safety and Safeguards Branch (FRSSB),
Division of Radiation Safety and Safeguards (DRSS)
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L. 'Peluso, Radiati n Specialist, ERPS, FRSSB, DRSS
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Approved by:
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(n R. Bores, Chief, ERPS, FRSSB, DRSS
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Inspection S
ary:
Inspection on September 18-21. 1990 (Inspection Report'
No.-50-219/90 171
Areas Inspected:
Routine unannounced inspection of the transportation and
solid radioactive waste programs including: management controls, audits,
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quality assurance, and implementation of the above programs,
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Results: Within the areas inspected, no violations or deviations were noted.
The licensee committed to providing a schedule for the identification and
dis)osal of the contents of five tanks located in the old radwaste building
wit 11n 45 days of the date of the letter which transmits the inspection
findings (Section3.1).
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9011080207 901003
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DETAILS
1.
Personnel Contacted
1.1 Licensee Personnel
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- J. Barton, Deputy Director
K. Brown, Operations Quality Assurance Engineer
- R. Brown, Manager, Radwaste Operations
W. Collier, Radwas'e Shipping
- B. DeMerchant, Lir .ising Engineer
M. Douches, Qualicy Assurance Auditor
D. Robillard, Quality Assurance Lead Auditor
D. Rogers, Training Coordinator
- P. Thompson, Quality Assurance Audits
- A. Wacha, Radwaste Programs Manager
1.2 NRC Personnel
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- E. Collins, Senior Resident inspector
M. Banerjee, Resident Inspector
- Denotes those present at the exit interview on September 21, 1990.
2.
Purpose
The purpose of this routine inspection was to review the licensee's
program for the preparation, packaging and transportation of radioactive
materials.
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3.
Transoortation'and Radwaste
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Processing, packaging and transportation of radwaste and other
radioactive materials were the responsibility of the Radwaste Operations
Section of the Operations Department.
The Radwaste Operations Section
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was divided into the Operations and Shipping Sections, with the former
responsible for processing radwaste liquids and the latter responsible
for the processing of generated wastes and their shipment for disposal.
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3.1 Radwaste
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Radwaste systems for the plant were located in two buildings, the
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old and new radwaste buildings.
In the old radwaste building, a
few tanks and pumps were still in use for the collection of spent
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resins and sludges from the reactor water clean-up and spent fuel
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3001 clean-up systems, and their transfer to the new radwaste
auilding. Additionally, the east portion of the old radwaste
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building was utilized for the collection and segregation of Dry
Active Wastes (DAW). The new radwaste building contained all
radwaste system filters and demineralizers, evaporators, and
processing equipment for the solidification or dewatering of'
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generated wastes.
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The licensee had been running two waste evaporators as part of its
high conductivity liquids processing system until the Spring of
1990. At that time, due in part to the leakage from one of the
evaporators' tube sheets, the licensee contracted with Chem-
Nuclear Systems, Inc. for the installation and operation of an
Advanced Liquid Processing System (ALPS).
Spent resins from this
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and other in-plant demineralization systems were dewatered in
Polyethylene High Integrity Containsrs (Poly HICs) in preparation
for disposal. Wastes from the precoat filter systems were
solidified in steel liners in preparation for disposal. DAW was
collected and segregated, with the majority of the materials being
bulk loaded in SeaVans for shipment to Westinghouse-SEG.
During this inspection, it was determined that five holding tanks
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in the old radwaste building contained unidentified liquids which
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should be disposed of as radioactive wastes.
These tanks have not
been used as part of the plant radwaste processing system for
twelve years.
The tanks are the floor drain collector tank, waste
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neutralization tanks NV05A and NV05B, concentrated waste tank and
spent resin tank. The licensee committed at the exit meeting to
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provide to the NRC a schedule for the identification and disposal
of the contents of.these five tanks within 45 days of the date of
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the letter which transmitted this inspection report.
As part of this inspection, the inspectors reviewed the following
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procedures utilized in the processing, packaging and shipment of
radwaste and radioactive material.
101.3, Rev 28, " Shipment of Radioactive Materials"
351.21,Rev6,"RadioactiveWaste/Non-WasteContainerControl'
351.23, Rev 7, " Shipment of Type A, LSA Radioactive Material"
351.31, Rev 3, "Off Site Shipments of Non Waste Radioactive
Material"
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351.35, Rev 10 " Packaging Radioactive Waste in Chem H iear
(CNSI)14-195 Type A Radwaste Shipping Cask"
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351.36. Rev 11. " Process Control Plan for Transfer and
Solidification of Solid Wet Waste via CNSI Cement Solidification
System"
351.47, Rev 3 " Radioactive Waste Sampling Program for Waste
Classification"
351.50, Rev 3, " Packaging and Shipn.'nt of Contaminated Protective
Clothing (Laundry)"
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351.57, Rev 2, " Operation Instruction for the RADMAN Computer Code
on the IBM PC"
351.59, Rev 1, " Packaging Radioactive Waste Within a Chem Nuclear
(CNSI) 14-215H Type A Radwaste Shipping Cask"
352.0, Rev 12, " Process Control Plan for Processing Resin into a
CNSI High Integrity Container"
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 on an annual basis by the submission of representative
composite samples to Scientific Applications International
Corporation (SAIC). Results from these analyses were then
reviewed and entered into the WMG, Inc. RADMAN computer code for
the generation of plant scaling factors.
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3.2 Transoortation
Packaging and shipping of all radioactive materials, including
radwaste, were the res)onsibility of the Radwaste Shipping
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Section. As part of 111s inspection, the following 26 shipping
records for materials shipped since June 1, 1990 were reviewed.
Shioment
Activity (Ci)
Volume (cu fti
lyng
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3012 90
4.69E+00
180.1
Sludge
0310-90
1.59E-06
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Samples
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0311 90
2.00E-03
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Samples
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4006 90
1.26E+01
205.8
Resin
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3013 90
2.62E401
180.1
Sludge
7002-90
4.52E+00
84.0
Filters
6001 90
3.19E+00
180.1
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0206 90
1.88E 07
7.5
Valves
0207-90
2.67E-03
180.0
Equipment
0208 90
2.27E-02
270,0
Equipment
0109 90_
8.02E-02
960.0
Laundry
1005-90
7.39E 01
2560.0
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1004 90
8.21E-Ol
'2560.0
0209 90
1.10E 02
300.0
Valves
6002-90
2.29E+00
180.1
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7001-90
5.57E+00
114.9
Filters
3016 90
9.72E+00
180.1
Sludge
3015-90
3.llE+01
180.1
Sludge
3014 90
5.98E+01
180.1
Sludge
4009-90
3.64E400
205.8
Resin
4008 90
3.85E+00
205.8
Resin
4007-90
2.99E+01
120.3
Resin.
5005-90
9.20E+00
180.1
Concentrates
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5004-90
8.13E+00
180.1
Concentrates
0313-90
2.16E-06
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Samples
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0312-90
5.92E 05
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Samples
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All records were determined to meet the regulatory requirements as
set forth in Titles 10 and 49, Code of Federal Regulations.
On September 21, 1990, the inspectors observed the loading of a
CNSI 14-195H shipping cask with a liner containing solidified
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sludge, known as shipment 3017-90. Also observing this evolution
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was an auditor from the plants Quality Assurance Department as
part of the current audit of the radwaste program (see Section
3.4). This shipment was made in a professional manner with
knowledgeable plant and contractor personnel.
The inspectors had
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no further questions in this area.
3.3 Ir,terim Radwaste Storaae
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in preparation for possible exclusion from the existing burial
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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 constructed an Interim Low-level Radwaste Storage
facility. This facility was designed to store up to five years of
plant generated low-level waste in packages ready for disposal.
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Due to efforts at waste volume reduction within the plant, this
facility now has an available capacity of more than five years'
worth of plant generated wastes.
The inspectors had no further
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questions in this area.
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3.4 Ouality Assurance
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The licensee's program for the assurance of quality in the
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radwaste and transportation areas involved the auditing of
principle vendors supporting this area, plant audits of this area,
and periodic surveillances,
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Vendor audits were conducted by the GPU Nuclear corporate offices.
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The audit of CNSI, which supplies liners, shipping casks,
dewatering, solidification and demineralization services to the
licensee was conducted in 1988 by the Nuclear Utilities
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Procurement Issues Council (NVPIC). The licensee maintained all
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ap3ropriate documentation related to this audit, including
su> sequent correspondence between CNSI and the lead auditor for
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NVPIC.
Auditt of the plant radwaste and transportation program were
conducted on an annual basis. Audit S-0C-89-ll, dated March 1,
1990, was the most recently completed audit in this area.
There
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were no findings or deficiencies identified in this audit which
required licensee followu). At the time of this inspection, the
licensee was conducting tie 1990 audit in this area. The
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inspectors reviewed the audit plan and held discussions with both
of the audit team members. The scope and technical depth of this
audit was determined to be good.
Surveillances of the radwaste and transportation program were
conducted periodically by the Operations Quality Assurance Group.
Eighteen Monitoring Reports, which document the surveillances
conducted in 1990 were reviewed and determined to be of a very
high quality. The inspectors had no further questions in this
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area.
3.5 Trainina
Training of Radwaste Operations personnel to meet the requirements
of NRC IE Bulletin 79-19 was divided into two distinct programs.
The first program was outlined in Program 6231-PGD-2617, Rev 0,
"Radwaste Operator recualification", and was presented to Radwaste
Operators.
The seconc program consisted of attendance at vendor
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supplied training programs, and was utilized to train the Radwaste
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Shipping and Operations Quality Assurance personnel. These two
t aining programs were determined to be excellent.
5.
Exit Interview
The inspectors met with the licensee representatives denoted in Section
1 at the conclusion of the inspection on September 21, 1990. The
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inspectors summarized the purpose, scope and findings of the inspection,
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