IR 05000333/1990018
| ML20044A781 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/25/1990 |
| From: | Bores R, Joseph Furia, Person R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20044A780 | List: |
| References | |
| 50-333-90-18, NUDOCS 9007020247 | |
| Download: ML20044A781 (6) | |
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U.S. NUCLEAR REGULATORY COMMISDION
REGION I
Report No.
$0-333/90-18 Docket No.
50-333 License No.
DPR-59 Licensee New York Power Authority P.
O.
Bom 41 Lycomino. New York 13093 Facility Names James A. FittPatrick Nuclear Power P1,gnt Inspection Att Lveomino. New York Inspection Conducted:
June 4-8, 1990 Inspectors h-d f
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6)Furia,"Aadiatiop Specialist, Effluents date
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\\ Radiation Protec' tion ',ection (ERPS), Facilities Radiological Safety and Safeguards Branch (FRSSB),
Divisica of Radiation Safety and Safeguards (DRSS)
f L)a::d, ~
Jer iu<js
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f R[WLateandDecommissioninglers'on,' Project M anagdr, Divisica of Low
/ dat'e
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, Of fic's of Nuclear Materials safety and Safeguards Approved by:
MOfh E. Bores,[/hief, ERPS, FRSS3, DRSS date Inspection Summary:
Innnection on June 4-8, 1990 (Inspection ReDort No. 50-2E /90-181 hr.gjts Inspected:
Routine unanounced inspection of the transportation and sol:.d radioactive waste programs including:
management controls, audits, qua.ity assurance, and implementation of the above programs.
Enfalt.g: Within the areas instected, one non-citad tiolation in the transportation area (Section 3 2) was noted.
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DETAILB 1.
Zumponel contacted 1.1 Licensen Personnel P. Brosenich, Waste Management General Supervisor
- W. Fernandet, Resident Manager
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R. Liseno, Superintendent.of Power
R. Locy, Operations Superintendent l
D. Simpson, Training Superintendent
t J. Solini, Health Physics General Supervisor
K. Steluga, Madiation Protection Supervisor 0. Tasick, Superintendent, Quality Assurance j
- G. Vergo, Radiological and Environmental Services Superintendent A. Young, Decontamination and Shipping Manager 1.2 NRc Personngl
- R. Plasse, Resident Inspector W. Schmidt, Senior Resident Inspector i
Denotes those present at the exit interview on June 8, 1990.
- 2.
Puroome The purpose of this routine inspection was to review the licensee's program for the preparation, packaging and transportation of radio-active materials.
3.
Iranpoortation and Radwaste The licensee's program for the packaging and traraportation of z3dioactive materials, including solid radwaste, was conducted jointly by *.he operations and Radiological and Environmental Services (RES)
Depattments. Radwante was processed, packaged and shipped by the Waste j
Manageaent section of the Operations Department.
Shipping paper preparation, analysis for scaling factors and the shipment of j
f radioactive materials, were the responsibilities of the RES Department.
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3.1 Radwaste
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The licensee produced four waste streams of solid radwaste, including evaporator bottoms, powder resin, bead resin and Dry Active Waste (DAW). Evaporator bottoms were typically solidified utilizing a LN Technology (now SEG, a Division of Westinghouse)
l waste cementation system. Resins were typically dswatered in High l
Integrity Containers (HICs), also utiliaing an LN Technology
.i system.
DAW was segregated into compactable and noncompactable I
wastes, with the former compacted on site, and the latter either
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packaged for disposal, or. shipped for possible decontamination.
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As part of this inspection, the following 11 waste shipment I
records were reviewed.
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j Shinment No.
hetlvity (Cil Volume feu fti Iggg j
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01-90-010 1.66E+01 158.1 Rosin 03-90-083 1.20E+00 181.7 Evap
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3-90-084 4.94E+01 181.7_
Evap-03-90-085 3.30E+01 181.7 Evap 04-90-087 2.59E+01 181.7 Evap 05-90-042 1.62E+02 134.6 Resin l
90-001 4.97E-01 920.0 DAW J
90-002 2.15E-01 920.0 DAW j
05-90-045 5.775+00 105.0 DAW 06-90-044 2.91E+01 181.7 Evap
'l 05-90-046 3.34E+02 134.6 Resin
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All shipments were determined to meet the requirements of 10 CFR and 49 CFR.
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l The licensee, through its RES Department, had 3-month composited
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j plant samples taken from the evaporator bottoms, spent bead resin j
and spent powder resin storage tanks analysed for 10 CFR Part 61
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compliance every six months.
The results of these analyses were j
i entered into the WMG, Inc. RADMAN data base, and new plant scaling
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factors were determined annually. This program exceeds the recommendations contained in the USNRC Bran h Technical Position.
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3.2 Transoortati2D Shipment of radioactive materials wea the responsibility of the l
Waste Management Section and the RES Department.
For shipments of radwaste, the Waste Management Section packaged the material and I
arranged for transport.
The RES Department prepared all shipping
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manifests through the utilisation of the WMG, Inc. RADMAN contputer code. As part of this inspection, the following procedures were
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reviewed.
F-OP-30, Rev 17, " Fuel Pool Cooling and Clear.-Up System" F-OP-34, Rev 11, "Recin Transfer, Regeneration and Cleaning" F-OP-48, Rev 16, " Solid Radwaste System"
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F-OP-48A, Rev 20, " Documentation of Radwaste Shipments" I
F-OP-48B, Rev 14, " Waste Packaging and Handling" (
F-OP-480-09, Rev 8, " Handling Prc<edure for the LN-170 cask"
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F-OP-48C-10, Rev 6, "'landling Procedure for the LN-142 Cask" F-OP-48C-11, Rev 4,
'High Integrity Container Handling Procedure" l
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All procedures were found to be complete and to accurately reflect I
existing plant processes, with the exception noted below, i
on April 3, 1990, the licensee received a LN-170 shipping cask on site, which was intended for use in the shipment of dowatered l
powder resin. Upon receipt, in accordance with Procedure F-OP-l 48C-09, Rev 8, the primary and secondary lid gaskets for this cask i
were visually examined and the dates of the last gasket changes
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were noted. Under Condition 7a of the Certificate of Compliance
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issued for this cask, both gaskets must be changed at least once every year. At the time of the receipt inspection, the secondary i
lid gasket had last been changed on May 4, 1989.
Due to higher
than anticipated dose rates on the liner containing the powder resin, the licensee determined that a different shipping cask was
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required, and the LN-170 cask was placed in storage on site to be used for a later shipment. On May 29, 1990, the LN-170 cask was
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loaded with a liner containing solidified evaporator bottoms, and
the cask was shipped on May 30, 1990 to the Barnwell, South I
Carolina Waste Disposal Site.
Since the cask had previously been
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accepted by the licensee on site, the date of last gasket change wan not reviewed prior to use on May 29, 1990. Upon receipt in
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Barnwell, the licensee was notified by the Disposal site Operator,
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Chem-Nuclear Systems, Inc. (CNs!), of the expired lid gasket.
Although the gasket was past its expiration date, no degradation
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of the gasket was observed by the CNSI staff.
The licensee
immediately initiated a temporary modification to Procedure
F-OP-48C-09 to preclude a re9etition of this event, and a l
l permanent revision to this procedure was approved by the licensee
on June 6, 1990. Due to the prompt corrective actions taken by l
the licensee, and the low safety significance of this violation,
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in accordance with 10 CFR 2, Apper. dix C, the NRC will exercise its
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discretionary authority and clastify this event as a non-cited i
violation (50-333/90-18-01).
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3.3
_$nterim Radwaste Storaos
- i As part of this inspection, a review of the licensee's plans and available facilities for the storage of low-level radwaste was
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conducted. At the present' time, New York state has not-selected l
L or built a low-level waste.s.te, and as such the licensee may be l
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subject to exclusion from the existing low-level waste disposal
l sites by January 1, 1993.
In anticipation of this possibility, I
the licensee constructed an Irterim Storage' Facility, with an l
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originally designed capacity of 18 months' worth of generated low-level radwaste. _ currently the facility is utilised as a contractor staging arma and warehouse, however, the licensee anticipates that this facility can be returned to service for radweste storage within approximately one month.
In addition, based upon new waste minimisation techniques available to the licensee, the capacity of the Interim Radweste Storage Building may be up to 5 years' worth of plant generated low-level waste.
3.4 ouality Assurance The licensee's program for the assurance of quality in the radwaste program included the use of periodic surveillances, biennial audits of the Process Control Program (PCP), and triennial audits of principle vendors.
The licensee's Quality Assurance Department was tasked with performing these tasks.
Surveillances of radwaste evolutions were conducted on approximately 20% of the radwaste shipments. The Quality j
Assurance surveillance Reports (QA8Rs) for 1990 were reviewed as f
part of this inspection and determined to be of a high quality with appropriate technical depth.
Audits of the PCP were conducted biennially, in accordance with plant Technical specifications. Audit 1314, dated May 2, 1990, was the most recent audit conducted in this area, and was reviewed as part of this inspection. Three findings and six
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recommendations were' identified as a result of this audit, none of which involved a significant safety issue. All findings were corrected in a timely manner.
Audits of principle vendors supplying radwaste materials or services were conducted on a triennial basis. Audit 634, dated November 30, 1987, was conducted to evaluate The LN Technologies l
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Corporation, now a part of SEG, a Westinghouse subsidiary.
LN Technologies supplied processing equipment, disposal' liners and shipping casks to the licensee. All findings in this audit were
corrected during the audit, and thus no further action was
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required.
3.5 Trainino The licensee has developed training programs for both the operations and RES Department personnel involved in the
processing, packaging and shipment of radwaste. Personnel were provided initial training under lesson plans RES-3021 and DRW-1005, respectively.
RES-3021 was a vendor (WMG, Inc.) developed program which involved 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of classroom training.
In addition, RES personnel involved in radweste had requirements as
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I part of their qualification card to perform radwaste specific
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tasks. DRW-1005 was a two and one-half hour long training program i
developed by the licensee, and was also used in conjunction with a j
qualification card for Waste Management personnel. Retraining for i
personnel involved retaking these courses on an annual basis.
It
was noted by the inspectors that copies of procedures in the
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instructors manual for lesson plan DRW-1005 included procedures that were outdated or no-longer in use at the facility.
In addition the licensee did not have a formal program of lesson plan
review that included periodic review by supervisory personnel from i
the RES or Operations Departments. The licensee stated that these
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areas would be reviewed, and appropriate corrective actions taken.
I 4.
Exit Intervieg i
The inspectors met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on June 8, 1990. The inspectors
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summarized the purpose, scope and findings of the inspection.
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