IR 05000333/1988009
| ML20155D763 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/26/1988 |
| From: | Bicehouse H, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20155D761 | List: |
| References | |
| 50-333-88-09, 50-333-88-9, IEB-79-19, IEIN-87-007, IEIN-87-7, NUDOCS 8806150404 | |
| Download: ML20155D763 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-333/88-09 Docket No.
50-333-
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License No.
OPR-59
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Category C I Licensee:
Power Authority of the State of'New York P. O. Box 41 Lycoming, New York 13093 Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection At:
Scriba, New York Inspection Conducted:
May 2-6, 1988
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Inspector:
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a ff. Bicehutise, Radiation Specialist date M C~
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Approved by:
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W. PascTaT, Chief, Ef fluents Radiation-date Protection Section Inspection Summary:
Inspection on May 2-6, 1988 (Report No. 50-333/88-09)
Areas Inspected: Routine, unannounced safety inspection of the licensee's solid radioactive waste (radwaste) processing and preparation and radioactive materials packaging and shipping programs including previously identified items, management controls, quality assurance / quality control and implementa-tion of the programs.
Results: No violations or deviations were identified.
The licensee was implementing generally effective programs within the scope of the review.
8806150404 880607 PDR ADOCK 05000333 Q.
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DETAILS
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' Persons Contacted
' 1.- 1 Licensee Personnel
- R. Converse, Resident Manager
- W. Fernandez, Superintendent of Power
- D. Grodi, Quality Assurance (QA)_ Engineer
- D. Johnson,' Waste Management Supervisor
- D. Lindsey, Operations Superintendent A. McKeen, Assistant Superintendent, Radiological and Environmental Services (RES)
- E. Molcahey, Superintendent, RES.
R. Patch, General Supervisor, QA S. Smith, RES Technician
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J. Solini, Health Physics General Supervisor
- K. Szeluga, Radiation Protection Supervisor
- G. Vargo, Radiological Engineering General Supervisor
- V. Waltz, Technical Services Superintendent Other licensee personnel were contacted or interviewed.
l'. 2 Contractor Personnel J. Grey, Solidification Technician, LN Technologies Corporation 1.3 NRC Personnel-
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- A. Luptak, Senior Resident Inspector-R. Plasse, Resident Inspector
- Denotes those present at the exit interview on May 6, 1988.
2.
Scope of the Inspection This routine safety inspection reviewed the licensee's solid radioactive waste (radwaste) processing and preparation and radioactive materials packaging and shipping programs as implemented by the licensee from February 1, 1986 through May 6, 1988. During that period, the licensee niade 110 solid radwaste and other radioactive materials shipments. A sample of eleven radwaste shipments and another nonradwaste radioective materials shipment was selected and reviewed relative to criteria in the licensee's technical specifications, radwaste generation requirerr.ents (under 10 CFR 20.311 and 10 CFR 61.55-56), and radioactive materials requirements (under 10 CFR 71 and 49 CFR 170-189).
In addition, the licensee's actions regarding previously identified items were also reviewe,, _ _ - -. _ _
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During the period reviewed, the licensee shipped solid fadwaste materials typical of an operating boiling water reactor.(i.e., evaporator bottoms, bead and powder demineralizer resins, dry active waste, control rod drive filters and waste oils).
No rpecial radwaste shipments (e.g., control rod blades, decontamination resins, etc.) were made during the perlod reviewed although the licensee planned to ship control rod blades in the near future.
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Previously Identified Items 3.1 (Closed) Followup Item (50-333/85-30-02): Complete provisions for onsite low-level radwaste storage including safety evaluation review The licensee has not used the designated onsite low-level radwaste storage facility for-solid radwaste storage and has converted the building. to other uses (shop).
The licensee's Final Safety Analysis Report (FSAR, Volume 1, Section 2.4.3.7) showed the maximum probable flood elevation to be near,1y 12 feet below the level of the facility.
Evaluation of the potential for organic materials (e.g., resins) in radwaste containers in storage to provide pressure sufficient to breach the container and/or lead to flammable gas mixtures showed that the activity limits on potential storage minimized these risks.
In view of the circumstances, this item is closed.
3.2 (Cic3ed) Followup Item (50-333/86-03-02):
Increase QA/QC participation in radwaste solidification and shipping Quality Assurance / Quality Control (QA/QC) participation in audits, surveillances and process inspections was evident in the solidifi-cation and shipping of radwaste materials.
This item is closed (see related items in. Details 5 and 6).
3.3 (Closed) Followup Item (50-333/86-12-02):
Review RETS Appraisal Audit The results of the 1986 appraisal (JAF 86-01) were reviewed. The review showed that radiological environmental monitoring wr.s included and that all findings had been closed by the licensee. This item is closed.
3.4 (Closed) Followup Item (50-333/86-12-03):
Revise procedures and perform study Review of three procedures (i.e., ESP-5, ESP-11 and ESP-12) showed that appropriate corrections were made to them by the licensee.
The licensee performed a study to determine the optimum use of the four-liter Marinelli beaker for gamma spectroscopy of water and modified procedures in accordance with the results of that study.
This item is close.
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3.5 (Closed) Followup Item (50-333/86-21-01):
Perform audit of vendor performing analyses of composited samples of radioactive effluents in 1987 Comprehensive reviews of the vendor laboratory (i.e., Teledyne Isotopes, Inc.) were conducted by technically qualified licensee representatives in 1987.
This item is closed.
4.
Management Controls The licensee's management controls were reviewed to determine if clear designations of responsibilities had been made, controlled procedures were in place, training / retraining programs were being implemented and vendor-supplied solidification / dewatering ac'.1vities were controlled (NRC Information Notice No. 87-07).
4.1 Organization / Responsibilities Solid radwaste processing and preparation activities are the responsibility of the licensee's Operations Department. Within the Operations Department, the Waste Management General Supervisor manages the solid radwaste program including onsite vendor provided solidification and dewatering activities.
Solid radwaste packaging and shipping activities are shared by the Operations and Radiological and Environmental Services (RES) organizations. Within the RES Department, the Radiation Protection Supervisor provides supporting surveys, maintains records and conducts calculations using the RADMAN computer program.
Supporting analyses for hard-to-identify radio-nuclides are provided by contracted vendors and evaluated / incorporated into the RADMAN program by the Radiation Protection Supervisor.
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Quality Assurance organization provides quality control inspections, quality a:;surance surveillances and audits of all aspects of the
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l processing, preparation, packaging and shipping activities. Within the scope of this review, the licensee had clearly defined responsi-
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bilities including interfaces between departments and oversight of vendor activities.
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4.2 Procedures
i The inspector reviewed nine operations (i.e., OP-48 series) and two RES (i.e., PSP-8 and RPOP-3) procedures to determine if adequate
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instructions to process and prepare solid radwaste materials and package and snip radioactive materials had been provided.
In addi-tion, vendor solidification and dewatering procedures were reviewed.
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I Within the scope of this review, no weaknesses relative to regulatory l
requirements were noted.
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The licensee uses the RADMAN computer code to support solid radwaste classifications, prepare waste manifests and maintain the waste stream specific database.
The computer code relies on a waste-specific database to characterize and classify packaged solid radwaste. materials.
The licensee routinely obtained waste stream samples for inhouse gamma spectroscopy and more detailed radiochemical analyses by a vendor laboratory. The data were reviewed and incorporated to update the scaling factors for hard-to-identify radionuclides by the licensee.
Licensee supervisory personnel reviewed all data inputs and computer outputs routinely before shipment.
Review of database and radionuclide library showed them to be current and complete. Within the scope of this review of the licensee's computer program management, no weaknesses relative to regulatory requiremerts were identified.
4.3 Training / Retraining In response to NRC IE Bulletin No. 79-19, the licensee committed to initial training and periodic retraining for personnel involved in solid radwaste packaging and shipping activities.
The-inspector interviewed selected supervisory, RES technician and operators to
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determine if. training and retraining had been completed.
Within the scope of this review, no deviations were noted.
5, Radwaste Generator Quality Control Specific quality control (QC) requirements are specified in 10 CFR 20.311 to assure compliance with.10 CFR 61.55-56. A process control program for so1 Mification and dewatering activities is required by the licensee's Te -nical Specifications.
The licensee's radwaste gerarator QC program was reviewed and discussed with cognizant quality asst nce personnel and its implementation during eleven solid radwaste shipments was verified. The licensee established a matrix for radwaste shipments in Quality Assurance Instruction (QAI) 11.0, "Quality Assurance Program for Radioactive Waste Shipments." (Revision 2, March 27, 1987), which described implementation of each of 10 CFR 50, Appendix a criteria to these licensed activities. - QC requirements in the QAI included 10 CFR 20.311 radwaste generator requirements including (but not limited to):
establishment and verification of witness points in procedures for
solidification and dewatering; independent determinations of waste class under 10 CFR 61.55;
audits of requirements by technically qualified QA personnel
(including the Process Control Program) and management review of those audits; vendor evaluations (audits) for radioanalytical and solidification /
dewatering services; and receipt inspections of high integrity containers (HICs).
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Within the scope of.this review, the licensee had established and implemented an effective QC program under 10 CFR 20.311.
6.
Radioactive Materials Shipper-Ouality As.surance/Ouality Control The provisions of 10 CFR 71, Subpart H, require the establishment of a quality assurance program for the, sckaging and transportation of radio-active materials. A Commission-approved quality assurance program which satisfies the applicable criteria of 10 CFR 50, Appendix B and which is established, maintained and executed for. transport packages is acceptable to meet the requirements of 10 CFR 71, Subpart H.
The licensee elected to apply the currently established 10 CFR 50, Appendix B quality assurance program to the' packaging and shipment of radioactive materials. As noted in Detail 5, the licensee had developed a matrix to address each 10 CFR 50, Appendix B criterion. Twelve radioactive materials shipment records were reviewed and discussed with licensee personnel to determine if the licen-tee had implemented the matrix requirements of the QAI. The inspector reviewed receipt of shipping containers, vehicle and package inspections, assurance of vendor-supplied package maintenance, tests and inspections, audits and other aspects of the application of the quality assur o
program.
Within the scope of the review, the licensee was implementing an etfective quality assurance program for radioactive materials packaging.and shipping activities.
7.
Radiochemistry The inspector reviewed recent fuel performance, activation product behavior and general demineralizer management to determine the general adequacy of the licensee's sampling and vendor analysis program for difficult-to-identify radionuclides. The inspector noted that recent fuel performance was excellent, significant changes in activation i
products weren't evident and demineralizer resins weren't regenerated.
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In addition, the licensee samples each waste stream for each batch and composites the samples on a continuous quarterly basis for vendor analyses.
Since only Class A radwaste materials had been shipped by the licensee, sampling an6 vendor analyses were more frequent than suggested by guidance provided in the Low-Level Waste Branch Technical Position on
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Waste Classification.
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Solid Radwaste Processino The licensee's solid radwaste processes were reviewed and discussed with the licensee. The licensee's solid radraste processing equi (including vendor-supplied solidification / dewatering operations) pment are cleanup phase separator tanks (in the Reactor Building)ption of the located in the Radioactive Waste Building with the exce Licensee proc-
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esses for evaporator bottoms, bead and powdered demineralizer resins, compacted and uncompacted dry active wastes and waste oils were reviewed and discussed with the iicensee's operations and solidification vendor
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personnel and work areas were toured. The following aspects of the operations were reviewed:
valve operation for resin transfer from holding tanks to the
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contracted vendor solidification / dewatering operation; sorting and compacting dry active waste; a
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communications, ventilation, radiological controls and spill continement during resin transfer operations;
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Vendor process control program parameter measurement; waste stream' sampling and compositing;
sample calculations for four solidified shipments; and a
quality assurance involvement in the processes.
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Within the scope of this review, no violations were noted.
9.
Radwaste Generator Requirements The eleven solid radwaste shipments were reviewed against each of the following requirements:
waste manifests under 10 CFR 20.311(d)(4) and 20,311(b) and (c);
waste classification under 10 CFR 20.311(d)(3) and 10 CFR 61.55;
waste-form and characterization under 10 CFR 20,311(d)(3) and 10 CFR
61.55; waste shipment labeling under 10 CFR 20.311(d)(2) and 10 CFR 61.55;
tracking of shipments under 10 CFR 20,311(d), (e), (f) and'(h); and
adherence to disposal site license conditions for Agreement State
licensees under 10 CFR 30.41.
The basis for determination of waste class, (e.g., sampling, inhouse and vendor radiochemical analyses, scaling for dif ficult-to-identify radio-nuclides, dose-rate-to-curie calculations and RADMAN data input / output)
was also reviewed for each shipment relative to the guidance in the Low-Level Waste Licensing Branch lechnical Position.
Within the scope of this review, no violations were noted. Adequate technical bases were noted for the shipments reviewea. Waste manifest,
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l classification, form, labeling c i tracking and adherence to disposal site license conditions were evident for each shipment reviewed.
10.
Radioactive Materials Shipping Requirements Twelve radioactive materials shipments were reviewed relative to criteria in 10 CFR 71 and 49 CFR 173-189 to determine if transportation require-ments had been met.
10.. Selection of Packar
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Proper-shipping documentation was.provided and maintained by
l the. licensee (49 CFR 173.444(c) and 173.425(b)(9).
l Within the scope of the review, no violations were identified.. The license'e had established and implemented an adequate program in
tiiese areas.
10.4 Transrs-+,ation Incidents The licensee reported that no violations or warnings from the Agreement States had been received-during the period covered by this inspection. NRC Region I hadn't received any indication of problems with the licensee's shipments.
11.
Exit Interview The inspector met with the licensee's representatives (denoted in Detail 1) at the conclusion of the inspection on May 6, 1968.
The inspector summarized the scope and findings of the inspection as described in this report and discussed the upcoming special shipments and previous regulatory problems associated with other licensees'
shipments of similar materials.
At no time during the inspection was written material provided to the.
licencee by the inspector.
No information exem.)t from disclosure under 10 CFR 2.790 is discussed in this report.
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