IR 05000317/1993015
| ML20044H302 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/27/1993 |
| From: | Joseph Furia, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20044H298 | List: |
| References | |
| 50-317-93-15, 50-318-93-15, NUDOCS 9306080159 | |
| Download: ML20044H302 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-317/93-15
Report Nos.
50-318/93-15
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50-317 Docket Nos.
50-318
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DPR-53 License Nos.
DPR-69 Licensee:
Baltimore Gas and Electric Company Post Office Box 1475
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Baltimore. Maryland 21203
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Facility Name:
Calvert Cliffs Nuclear Power Plant. Units 1 and 2 Inspection At:
Lusbv. Maryland Inspection Conducted:
May 18-21.1993 Inspector:
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J. ft)nr'a, S'enior Radiation Specialist, date tj Frilities Radiation Protection Section (FRPS),
Facilities Radiological Safety and Safeguards Branch (FRSSB), Division of Radiation Safety
and Safeguards (DRSS)
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4.f 6 4,7-43 Approved by:
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W. Pasciak, Chief, FRPS, FRSSB, DRSS date Areas Inspected: Announced inspection of the radiation protection program including:
management organization, assurance of quality, radiation control during outage operations, ALARA, and implementation of the above programs.
Results: Strong performance in the area of radwaste and transportation was noted. ALARA I
deficiencies, identified in previous inspections, have been addressed by your staff, including the creation of an ALARA management committee and the placement of an ALARA technician into the Unit I refueling outage planning group.
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9306080159 930528 PDR ADOCK 05000317 G
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O DETAILS 1. Personnel Conta_qtsd 1.1 Licensee Personnel
- A. Anuje, Quality Assurance Manager P. Chabot, Superintendent, Technical Support
- S. Hutson, Supervisor, Radiation Control - Operations
- J. I2nhart, Supervisor, Materials Processing
- W. Maki, Compliance Engineer
- G. Phair, Assistant General Supervisor, Radiation Control and Support
- C. Sly, Compliance Engineer L. Smailek, Health Physicist W. Sullivan, Quality Assurance Unit
- B. Watson, General Supervisor - Radiation Safety
- R. Wyvill, Supervisor, Radiation Control - ALARA 1.2 NRC Personnel
- K. Lathrop, Resident Inspector i
- P. Wilson, Senior Resident Inspector
- Denotes those present at the exit interview on May 21,1993.
2. Transportation and Radwaste The licensee's program for transportation of radioactive materials and the processing of radwaste remained unchanged since the last inspection in this area. Shipment of radioactive materials was the responsibility of the Materials Processing unit of the
Radiation Safety Department, as was responsibility for the Process Control Program (PCP) for radwaste. The Chemistry Department maintained responsibility for Title 10, Code of Federal Regulations, Part 61 (10 CFR 61) scaling factor analysis, while processing of plant liquids remained the responsibility of the Operations Department.
2.1 Transportation
The licensee's Materials Processing unit controls the shipment of radioactive material. The licensee utilizes the RADMAN computer program (WMG, Inc.)
to prepare its shipping manifests and associated documentation. Transportation casks, when needed, were supplied by Chem-Nuclear Systems, Inc. (CNSI).
The licensee had on file all appropriate documentation for the utilization of these NRC approved shipping containers, including the Cask Certificates of Compliance, Safety Analysis Reports, and were registered as users with the NRC. As part of this inspection, the following radioactive material shipping records were examined:
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Shioment #
Activity (Ci)
Volume (cu ft)
Type 93-068 6.07E-02
'2080.0 DAW 93-069 3.96E-02 990.0 Laundry 93-070 1.00E+01 120.3 Resin 93-071 3.96E-02 990.0 Laundry 93-072 3.33E-02 2080.0 DAW 93-073 3.66E-02 900.0 Laundry 93-074 2.49E-02 560.0 Laundry 93-075 2.54E-02 906.0 DAW 93-076 9.63E-05 4.0 Samples93-077 2.47E-05 1.5 Samples
'93-078 3.41E-02 810.0 Laundry l
These shipments were determined to be in compliance with the applicable
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provisions of 49 CFR Parts 100-177 and 10 CFR Parts 20, 61 and 71.
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2.2 Radwaste Radioactive water systems were processed by plant operations through mechanical filters and demineralizer beds, with the filters collected in a liner, and the spent demineralizer beds sent to the resin storage tank, located on the 45' elevation of the Auxiliary Building, Spent resins were dewatered by the materials processing group into liners which were then dewatered and shipped to a licensed disposal site. Dry active wastes'(DAW) were collected throughout the radiation controlled areas of the plant by nuclear plant support personnel, stored temporarily in the truck lock on the 45' elevation of the Auxiliary Building, then transferred to the Materials Processing facility, where it was bulk loaded in SeaVans, and shipped to SEG (a Westinghouse
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Company) for sorting, reclamation, incineration and/or disposal.
The licensee established a goal of not more than 40,000 cubic feet of DAW to
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be generated for 1993, and through May 21,1993, had shipped to SEG approximately 20,000 cubic feet. Since the Unit 2 refueling outage was more than 80% complete at the time of this inspection, and represented the most significant challenge this year to the licensee's goal, it appears that the licensee will f' ish 1993 at less than 40,000 cubic feet shipped. In part to aid in waste m
disposed, the licensee has also changed over most of its non-reusable supplies for the radiologically controlled area (RCA) to incinerable materials. Through May 21,1993 the licensee had shipped 32,000 cubic feet of DAW to SEG in i
1993 (including 12,000 cubic feet left over from the end of 1992) and SEG processed this waste volume down to some 7000 cubic feet for burial.
Since the last inspection in this area, the licensee had made several notable
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improvements to its waste resin handling and processing system. Included in these improvements has been: installation of a new spent resin system control panel; installation of new level instrumentation in the spent resin metering tank; rental of a new resin liner fill head, including quick disconnect couplings for reduced dose to materials processing personnel, and liner overflow protection; and replacement of the liner cart hydraulic system with electrical motors, which significantly improves liner fill operations from the industrial safety aspect.
The licensee submits plant smear samples on a biannual basis for the determination of DAW scaling factors, in accordance with 10 CFR Part 61.
Resin samples were collected from each liner processed, via a new in-line sampling mechanism, composited and submitted on an annual basis for analysis. All analyses were performed by the licensee's primary laboratory, i
TMA Norcal, under contract to the licensee. An initiative undertaken by the licensee in 1992 was to have the National Institute for Standards and Technology (NIST) certified samples sent to this laboratory together with samples sent to the licensee's secondary laboratory, Scientech, for analysis.
Results indicated generally good agreement between the laboratory's results and the actual values provided by NIST. The licensee was, at the time of this inspection, collecting cuttings from its Chemistry and Volume Control System
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(CVCS) letdown filters for scaling factor analysis. Preliminary analysis, performed using smear samples from the filters indicated that some of the spent filters currently stored in a shielded liner were beyond class C wastes, based on plutonium-241. The results of these new analyses will be reviewed by the inspector during a future inspection.
The licensee's program for potential interim radwaste storage includes utilization of areas along the West Road of the protected area and the Lake Davies area for spent resins and filters, and the DAW storage area of the Materials Processing Facility (MPF) for processed DAW. At the time of this inspection, the safety analysis for the use of the 12ke Davies site required under 10 CFR 50.59 was being conducted by the licensee.
2.3 Assurance of Ouality The licensee conducted biennial audits of its Process Control Program in accordance with plant technical specifications. At the time of this inspection, the licensee was conducting its audit, with the audit scheduled for completion by June 25,1993. The inspector met with the lead auditor and examined the audit scope and plan. In addition to the lead auditor, a contracted technical expert in radwaste and transportation was part of the audit team. The results of this audit will be examined during a future inspectio,
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I The licensee has significantly increased its utilization of Quality Surveillance activities in the radwaste and transportation area. Since October 1992, three surveillances of radwaste activities have been conducted. No findings of safety significance were noted in these surveillances. The licensee continued to utilize Nuclear Procurement Issues Committee (NUPIC) audits in order to qualify its shipping cask supplier, CNSI. The licensee had on file a copy of the most recent NUPIC audit of CNSI, conducted by Carolina Power and Light (audit QAA/0030-92-07), together with the CNSI response to two i
identified findings from the report.
3. Radiation Safety As part of this inspection, a review of the licensee's Unit 2 refueling outage was conducted. This outage commenced on February 19,1992 and was expected to last through the first week of June. Prior to the outage an ALARA goal of not more than 225 Person-Rem was established. At the time of this inspection, total dose for this outage was 268 Person-Rem, with approximately 20 days remaining in the outage, and all higher dose jobs, except reactor re-assembly completed.
The most significant challenge to the licensee during the outage was the discovery
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after shutdown that 7 of the 8 In-Core Instrumentation (ICI) flanges were leaking.
This, compounded with rust particles from the containment air coolers, led to high levels of contamination throughout the containment, and a high expenditure of Person-
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Rem for the clean-up of the ICI flanges. Preliminary estimates made by the ALARA supervisor indicated that 40-50 Person-Rem of dose had been expended cleaning up
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the flanges, this representing most of the dose beyond the licensee's pre-outage ALARA goal.
Additional challenges during the outage included the presence of fixed contamination in parts of the turbine system, especially on some of the turbine blades. Licensee actions, included the establishment of a radiologically controlled area on the turbine deck, the assignment of a senior radiological controls technician to provide support for work in the turbine area, and the control of materials and tools entering this area.
As part of its program for improving plant ALARA performance, the licensee
recently established an ALARA Management Committee which included the i
Superintendents for Operations, Maintenance and Technical Support. The committee conducted in-process ALARA job reviews during the outage, and was in the process of writing an outage ALARA report. The impact of these initiatives on the ALARA program will be reviewed during a future inspection.
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4. Exit Interview The inspector met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on May 21,1993. The inspector summarized the purpose, scope and findings of the inspection.
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