IR 05000220/1993017
| ML20046C906 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/03/1993 |
| From: | Joseph Furia, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20046C902 | List: |
| References | |
| 50-220-93-17, 50-410-93-17, NUDOCS 9308130010 | |
| Download: ML20046C906 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
i 50-220/93-17 Report Nos.
50-410/93-17 l
i; 50-220 i
Docket Nos.
DPR-63 License Nos.
NPF-54 t
Licensee:
Niacara Mohawk Power Corocration
300 Erie Boulevard West Syracuse. New York 13202 Facility Name:
Nine Mile Point Units 1 and 2 Inspection At:
Lycomine. New York i
Inspection Conducted:
July 26-30.1993 L
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h Inspectors:
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3-243
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J. Futi'a, Sen~ior Radiation Specialist, date Facilities Radiation Protection Section (FRPS),
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Facilities Radiological Safety and Safeguards t
Branch (FRSSB), Division of Radiation Safety and Safeguards (DRSS)
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Wd b'b Approved by:
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W. Pasciak, Chief, FRPS, FRSSB, DRSS date Areas Inspected: Inspection of the licensee's radwaste and transportation programs including: management organization, water processing, the Process Control Program (PCP),
transportation of radioactive materials, training, assurance of quality and implementation of the above programs.
Results: Continued strong performance in the area of radwaste processing and transportation
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of radioactive materials was noted. Training programs for radwaste and radiation protection personnel was also determined to be very good, while your program for the assurance of
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quality in the radwaste area remained excellent.
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9308130010 930804 PDR ADOCK 05000220 G
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DETAILS
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1. Personnel Contacted 1.1 Licensee Personnel
- D. Barcomb, Radiological Operations Supervisor, Unit 2
J. Burton, Manager Quality Assurance Operations
- R. Cole, General Supervisor - Radwaste, Unit 2
- K. Dahlberg, Plant Manager, Unit 1 A. DeSanto, Radiation Protection Supervisor - Transportation, Unit 1 A. Diana, Procurement Quality Assurance R. Passler, Supervisor - Procurement Quality Assurance
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T. Hogan, Supervisor - ALARA and Radiological Engineering, Unit 1
C. Gerber, Nuclear Technician
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A. Laratta, Procurement Quality Assurance
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- J. Lawton, Radiation Protection, Unit 1
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J. Maurice, Supervisor - Technical Training
- C. Merritt, Radwaste Supervisor, Unit 2 i
J. Mueller, Acting Plant Manager, Unit 2
- J. Pavel, Site Licensing
- N. Rademacher, Manager - Operations, Unit 1 W. Schultens, Radiation Protection Supervisor - Transportation, Unit 2
- P. Smalley, Radiation Protection Manager, Unit 1
- P. Swafford, Radiation Protection Manager, Unit 2
- B. Sylvia, Executive Vice President
- J. Torbitt, General Supervisor - Radwaste, Unit 1
- A. Zallnick, Supervisor Site Licensing 1.2 NRC Personnel W. Mattingly, Resident Inspector R. Plasse, Resident Inspector W. Schmidt, Senior Resident Inspector
- Denotes those present at the exit interview on July 30,1993.
2. Previous 1v Identified Items (Closed) Violation (50-220/92-044)l) Failure to wear dosimetry in the Radiologically Controlled Area (RCA). The licensee completed both short and long term corrective actions, including safety notices distributed throughout the plant, and the incorporation of lessons learned into the General Employee Training (GLT). A similar event did occur in mid-May, however the licensee identified this event, and its corrective actions reinforced actions taken for the March events. This item is close. _ _
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3. Radwaste and Transoortation - Unit 1 The licensee's management for this program area has remained the same since the last inspection in this area. At the time of this inspection, the General Supervisor -
radwaste reported through the Operations Manager to the Plant Manager. The licensee was examining the possibility of moving responsibility for this program from the Operations Department to the Radiation Protection Manager, but no action was
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anticipated before the start of 1994
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,I 3.1 Radwaste Processing Since the last inspection, the licensee has installed and begun operation of an
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Advanced Liquid Processing System (ALPS) from Chem-Nuclear Systems, l
Inc. (CNSI), in lieu of utilizing its waste evaporator, for the processing of j
floor drain liquids. Operation of the ALPS has resulted in a significant
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improvement in effluent water from the floor drain system, especially in the
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areas of Total Organic Carbon (TOC) and conductivity. The licensee's next
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significant effort in radwaste processing was scheduled to be the installation of i
a CNSI Rapid Dewatering System (RDS-1000) for_ spent resin dewatering and
drying. All other water processing systems remained the same sir.ce the last
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inspection in this area.
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Of significant note was the licensee's extensive efforts to decontaminate and
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repair both systems and facilities in the old and new Radwaste Buildings.
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Previous inspection reports have highlighted deficiencies in these facilities i
including a backlog of work orders to correct packing leaks in pumps, and
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extensive contamination of the lower elevations of these facilities. Included in
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this effort was the decontamination and final clean-up (until decommissioning)
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of the 225' elevation of the Old Radwaste Building.
i The licensee submitted representative plant samples on an annual basis to l
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Teledyne Isotopes, Inc. for the purpose of quantifying hard to measure l
radionuclides. A weakness noted in the licensee's program was the lack of formal procedures for the monitoring of plant conditions to demonstrate tl at i
the annual samples continued to be representative of the plant waste streams in j
accordance with Title 10, Code of Federal Regulations (CFR), Part 61.55.
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Although the licensee's Shipping Supervisor monitored both plant primary i
water cobalt-60 to cesium-137 ratio on a weekly basis, no criteria were
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established for deciding when new samples needed to be obtained for updating
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scaling factors.
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1 The licensee was close to completing modifications to the Stock Cement System storage area for the purposes of allowing it to store processed resm and filter liners from both Units 1 and 2, as part of the licensee's interim radwaste storage plan. This facility was built in the early 1980's as part of the Stock cement waste processing system installed at Unit 1. Although this waste system was never made fully operational, the large, shielded storage pit that
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was built as part of the system lended itself to being converted for use as a
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liner storage area. Capacity (by volume) in the pit is more than adequate to
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store five years worth of plaut generated resins and filters from both units.
l 3.2 Transoortation
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Responsibility for preparation of documentation and surveys of outgoing e
radioactive materials shipments belonged to the Radiation Protection Supervisor for Transportation, who reported to the Radiation Protection i
Manager. As part of this inspection, records of the following shipments were reviewed:
Shipment #
Activity (Ci)
Volume (cu ft)
Tvoe
i 0593-010 4.24E+01 205.8 Resin
0593-068 8.78E+00 205.8 Resin
0593-069 9.96E+01 194.1 Filter Media
0693-134 9.54E+00 205.8 Resin
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0693-230 1.16E+01 205.8 Resin.
0693-316 5.46E+01 194.1 Filter Media 0793-378 6.06E+00 205.8 Resin
All shipments were determined to be in full compliance with all applicable provisions of Title 49, CFR, Parts 100-177 and Title 10, CFR, Parts 20, 61 and 71. Copies of shipping cask Certificates of Compliance (C of C), cask j
handling procedures, user registrations and consignee's licenses were all
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maintained as required.
t 4. Radwaste and Transoortation - Unit 2
i Since the last inspection in this area, the licensee reorganized its management
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structure for this program area, placing the General Supervisor - Radwaste under the i
Radiation Protection Manager. In addition, during the upcoming refueling outage, the
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General Supervisor - Radwaste has been given responsibility and manpower for plant decontamination.
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4.1 Radwaste Processirtg i
The licensee successfully installed an ALPS late in 1992, as a temporary modification to the plant water treatment system. Specifically this system replaces the flatbed demineralizers (diatomaccous earth filters) in the floor drain system. The ALPS was physically located outside the i
extruder / evaporator area, with temporary hose connections made at the flatbed j
filter. Since this system has been successfully nm by the licensee, a
permanent plant modification for 1994 has been scheduled, which will remove the flatbed filter and place the ALPS into the flatbed filter room with j
permanent plant piping connections.
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The licensee has made a considerable effort to decontaminate the radwaste facility so as to allow operators to conduct their rounds without using
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protective clothing. A tour of the Radwaste Building was conducted by the inspector. All areas were accessible without protective clothing, although some did require entering high radiation areas.
The licensee submitted representative plant samples on a biannual basis to l
Teledyne Isotopes, Inc. for determL uon of waste stream specific isotopic
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distributions. Waste streams sampled included Dry Active Wastes (DAW),
i spent resins and filter resins. The licensee utilized weighted averaging
algorithms for the final determination of scaling factors, in accordance with Title 10, CFR, Part 61.55.
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The licensee developed an unused area under the Radwaste Building truck bay
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for the storage of processed DAW from both Units 1 and 2. This area on the 250' elevation has been upgraded to include lighting, fire detection and radiation monitoring, in anticipation of the need for on-site storage of radwaste beginning no later than July 1,1994, when the current Low-Level Waste Disposal Site at Bamwell, South Carolina is no longer available.
4.2 Transportation J
Responsibility for preparation of documentation and surveys of outgoing radioactive materials shipments belonged to the Radiation Protection Supervisor for Transportation, who reported to the Radiation Protection Manager. As part of this inspection, records of the following shipments were reviewed:
Shipment #
Activity (Ci)
Volume (cu ft)
Iyp_c 0493-169 2.38E+01 205.8 Resin 0593-070 1.53E+02 83.4 Resin 0593-109 9.58E+00 205.8 Resin 0593-137 1.38E+02 83.4 Resin 0693-172 1.98E+00 205.8 Resin 0693-193 8.17E+00 205.8 Resin 0693-252 9.67E+00 205.8 Resin 0693-293 4.52E+00 205.8 Resin 0693-335 3.01E+00 314.2 Resin 0793-426 3.34E+02 83.4 Resin All shipments were determined to be in full compliance with all applicable-provisions of Title 49, CFR, Parts 100-177 and Title 10, CFR, Parts 20,61 and 71, except as noted below. Copies of shipping cask Certificates of Compliance (C of C), cask handling procedures, user registrations and -
consignee's licenses were all maintained as required. In addition, on July 28, the inspector observed the shipment of a CNSI 14-215H cask containing
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9 dewatered resins. The shipment was made in a professional manner by members of the Radwaste and Radiation Protection staffs.
On July 16, 1993, the licensee shipped four boxes of contaminated laundry to
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Interstate Nuclear Services (INS) for laundry processing, with a shipment manifest improperly listing the proper shipping name as Radioactive Material,
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Limited Quantity inswad of the appropriate Radioactive Material, Low Specific l
Activity. Title 49, CFR, Part 172.202(a)(1) requires that the appropriate
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proper shipping name be placed on the shipping manifest. Upon discovery of the error on July 19,1993, the licensee immediately notified INS of the error,
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and prepared and sent to INS a corrected shipping manifest. Additional long and short term corrective actions were taken based upon the root cause
analysis conducted by the licensee in response to this error. This apparent violaticn is not being cited in accordance with Title 10, CFR, Part 2,
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Appendix C,Section VII.B.(2)in that: the licensee identified the violation; it would normally be classified at severity Level IV or V; and the licensee took i
prompt and appropriate corrective actions.
5. Training
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The licensee continued to maintain a highly effective training program for radwaste and transportation personnel. Responsibility for this training area rested with the
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Technical Training section of the Training Department. Recently the supervisor of this section was replaced, when the former supervisor accepted a new position within the company. The new supervisor had previously served as a technical trainer,
especially in the area of chemistry.
Training of licensee personnel in order to meet the licensee's commitment in response to NRC IE Bulletin 79-19, included initial qualification training of radwaste operators,
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and periodic retraining, of several weeks each year. The retraining program was
based on a two to three year training cycle, and included both refresher courses in basic sciences, and current industry events. Augmenting this training was the use of
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vendor-supplied specialist training in radwaste and transportation, given to the Radwaste Supervisors and the Shipping Supervisors.
6. Assurance of Ouality The licensee's program for assurance of quality in the radwaste and transportation
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area includedp657Xa:rflits-plant activities, audits of principle vendors, Quality Surveillance Reports (QCRs) of plant activities, and Quality Inspection Reports.
j Audits of in-plant activities were conducted at least as frequently as required by plant j
Technical Specifications, with the most recent audit involving radwaste and
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transportation having been conducted in 1992. In addition, the licensee utilized its
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Procurement Quality Assurance program extensively in support of plant activities, including maintaining copies of all relevant documents pertaining to the most recent Nuclear Utilities Procure. ment Issues Council (NUPIC) audit of Chem-Nuclear
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Systems, Inc., dated August 7,1992 (Audit QAA/0030-92-07). Six QSRs were
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conducted by the licensee since March of 1993 in the radwaste area, plus several-
other QSRs touched on waste minimization during maintenance and operations activities. In addition, all shipments of radwaste were examined by the Quality Assurance Department and documented in Quality Inspection Reports. This extensive
program of quality assurance / quality control continued to be a notable licensee
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strength.
5. Exit Interview
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The inspector met with the licensee representatives denoted in Section 1 at the l
conclusion of the inspection on July 30,1993. The inspector summarized the
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purpose, scope and findings of the inspection. The licensee acknowledged the
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findings of the inspection.
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