IR 05000338/1993021
| ML20059D911 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/20/1993 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20059D898 | List: |
| References | |
| 50-338-93-21, 50-339-93-21, NUDOCS 9311030036 | |
| Download: ML20059D911 (16) | |
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UMTED STATES
/e aron NUCLEAR REGULATORY COMMISSION o
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REGloN 11
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S 101 MARIETTA STREET, N.W., sulTE 2900 7,,
- j ATL ANTA, GEORGIA 30323-0199 h4.....,o OCT 2 0 1993 Report Nos.
- 50-338/93-21 and 50-339/93-21 Licensee: Virginia Electric and Power Company Glen Allen, Virginia 23060 l-l Docket Nos.:
50-338 and 50-339 License Nos.:
NPF-4 and NPF-7 i-Facility.Name: North Anna 1 and 2
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Inspection Conducted:
September.20 - 24, 1993 Inspectork nw[
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R. P. Carrion, Radiation Specialist Date Signed
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c Approved by':- / nw [IfSM2r E/'e /24 T. R. Decker, Chief Date Signed Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This was a routine, announced inspection in the following areas: organization of the Chemistry Department and the units responsible for handling and shipping of radioactive material, plant water chemistry, the Radiological Environmental Monitoring Program (REMP), the Semi-Annual Effluent Release Report, processing and shipping of radiological materials, and decommissioning planning records.
Results:
The licensee's organization of its Chemistry Department and radioactive material processing and shipping units satisfied Technical Specification (TS)
and Updated Final Safety Analysis Report (UFSAR) requirements (Paragraph 2).
The licensee had implemented an effective Water Chemistry Program (Paragraph 3).
The licensee had effective programs in place to monitor releases of radiological effluents.
Plant operations caused minimum impact to the environment and virtually no dose to the general public from those effluents (Paragraph 4).
For the first half of 1993, liquid, gaseous, and particulate effluents were maintained well within TS,10 CFR 20, and 10 CFR 50 effluent limitations (Paragraph 5).
9311030036 931020 1-PDR ADOCK 05000338
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The licensee had good programs in place for_ the handling and shipping of radioactive material and they were effectively implemented (Paragraph 6).
The licensee is making progress in the area of decommissioning planning records (Paragraph 7).
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REPORT DETAILS 1.
Persons Contacted Licensee Employees J. Breeden, Supervisor, Radiological Analysis
- E. Dreyer, Supervisor, Radiation Protection L. Jones, Supervisor of Radiation Engineering
- G. Kane, Station Manager
- P. Kemp, Acting Assistant Station Manager NS&L
- J. Leberstein, Staff Engineer, Licensing
- J. Smith, Manager, Quality Assurance
- A. Stafford, Superintendent of Radiation Protection
- F. Thomasson, Corporate Health Physics and Chemistry Other licensee employees contacted during this inspection included engineers, technicians, and administrative personnel.
Nuclear Regulatory Commission
- D. Taylor, Resident Inspector J. York, Senior Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.
2.
Organization (84750 and 86750)
Technical Specification (TS) 6.2 describes the licensee's onsite and
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offsite organizations.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department, Radioactive Material Control Unit, and the Decontamination Waste Unit-to verify compliance with tha TS and Updated final Safety Analysis Report (UFSAR) requirements and to assure that adequate control of radioactive material to prevent / mitigate radiation exposures to the general public and plant personnel was maintained.
The inspector interviewed the Superintendent of Radiological Protection,
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who reported directly to the Station Manager. The Radiological i
Protection organization had recently been restructured into four (from five) departments: Health Physics (HP) Operations; HP Technical Services; Nuclear Chemistry; and Radiation Engineering.
Basically, the coordinators, supervisors, and technicians of the former department of Radwaste HP Operations had been shifted to the department of HP Operations. Units responsible for the handling and shipping of
radiological materials were now divided between HP Operations and HP Technical Services, with packaging activities being the responsibility
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of HP Operations and shipping activities being the responsibility of HP I
Technical Services.
There was one vacancy; for a decontamination technician in HP Operations. There had been one change in the Nuclear Chemistry Department since the last inspection. The supervisor had been temporarily re-assigned to another group and an acting supervisor had been named.
The inspector concluded that TS and UFSAR requirements had been satisfied.
No violations or deviations were identified.
3.
Plant Water Chemistry (84750)
During this inspection, Unit I was in its tenth fuel cycle, producing power at 100 percent of capacity. Unit 2 was in its ninth refueling outage, a.
Primary Water Chemistry (1)
TS Parameters TS 3.4.7 specifies that the concentrations of dissolved oxygen (D0), chloride, and fluoride in the Reactor Coolant System (RCS) be maintained below 0.10 parts per million (ppm), 0.15 ppm, and 0.15 ppm, respectively, during steady state operation. TS 3.4.8 specifies that the specific activity of the primary coolant be limited to less than or
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equal to 1.0 microcuries/ gram (uCi/g) dose equivalent iodine (DEI).
These parameters are related to corrosion resistance and fuel integrity.
The oxygen parameter is based on maintaining levels sufficiently low to prevent general and localized corrosion. The chloride and fluoride parameters are based on providing protection from halide stress corrosion.
The specific activity parameter is based on minimizing personnel radiation exposure during operation and maintenance.
Pursuant to these requirements, the inspector reviewed daily summaries for Units 1 and 2 which correlated reactor power output to chloride, fluoride, and dissolved oxygen concentrations, and specific activity of the reactor coolant for the period of July 29 through September 21, 1993 and determined that the parameters were maintained well below TS limits.
Typical values for D0, chloride, and fluoride for Unit I were less than five parts per billion (ppb), less than three ppb, and less than three ppb, respectively.
For Unit 2 the values were less than five ppb, three ppb, and three ppb, respectively, during steady-state conditions before beginning the current refueling outage (on September 7).
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Unit 1 DEI values at steady-state conditions ranged from 6.68E-3 pCi/g to 5.32E-3 pCi/g, a typical value being 5.9E-3 pCi/g. Corresponding Unit 2 DEI values ranged from 2.99E-2 pCi/g to 1.38E-2 pCi/g, a typical value being 1.8E-2 pCi/g.
(2)
Leaking Fuel Unit I had shown no evidence of any leaking fuel since the previous refueling outage last spring when two defective fuel rods were removed.
Unit 2 had shown evidence of a fuel defect event near the end of December 1992 by a small spike in the DEI values. At that time, one fuel rod was estimated to have one small defect. The licensee had initiated an action plan which included the following: monitoring and trending the primary coolant radiochemistry for any additional anomalies; reviewing power history data prior to the time of apparent fuel failure; planning for fuel examinations during the current refueling outage to identify any defective fuel rods and, following the examinations, investigating potential failure mechanisms; and redesigning the core of the next fuel cycle to ensure that no defective fuel assemblies are reused.
In April of 1993, the unit experienced reactor trips and shortly thereafter (in May),
I-131 concentrations increased to approximately 1.0E-2 pCi/g.
Licensee evaluations at the time indicated one to three defective fuel rods.
During the process of transferring the fuel from the reactor core to the Spent Fuel Pool (SFP), a visual inspection of fuel assembly Y-48 on September 21 noted a gap of approximately three to four inches in length in rod 3, face 3, span 6, an exterior rod of the assembly.
(The core location of the assembly had been J-6.)
It was noted that during the transfer, face 3 had been face down, thereby allowing the degraded section to fall away from the main part of the assembly. A later inspection of the rod using a remote video camera found evidence of hydriding at the top.
of the missing section.
A fuel pellet was visible above the gap.
(Therefore, fuel pellets had not fallen out of the upper section.) The bottom of the missing section was cleanly broken, indicating possible debris-induced f retting.
Additional hydriding blistering of the fuel rod was observed at various points both above and below the missing section.
It was noted that this fuel assembly contained twice-burned fuel and was scheduled to be discharged during the current refueling outage.
On September 24, a cylindrical object and another smaller object were observed on the bottom of Unit 2 Fuel Building transfer canal, near the up-ender.
It was assumed to be the missing piece of fuel rod cladding and a fuel pellet.
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4 was noted the length of cladding could house four fuel pellets.
It was unknown at the time of the inspection if additional pellets were inside the cladding or were elsewhere in the Transfer Canal. Using a R0-7 meter eight inches from the cylinder (under water), the licensee measured 10200 Rads per hour. The licensee had not yet developed a recovery plan. The location of the material did not pose a radiological hazard to personnel or to plant operations.
It was located in a "no flow" area of the transfer canal and was well-contained.
Retrieval would be considered but would not have a high priority.
Industry experience would be reviewed as would reportability issues.
Meanwhile, meeting the refueling date of October 2 remained the highest priority. The SFP would be monitored for increased activity concentration levels and the reactor core barrel would be closely inspected (via underwater camera)-
for debris.
Ultrasonic testing of fuel assemblies for re-use had been completed. Two additional defective fuel rods had been found.
(3)
Record Retention The inspector requested records for the TS-required parameters of Units 1 and 2 for the arbitrarily-chosen period of May 1 through June 30, 1981. The information was produced (via microfiche) for the inspector's review in a
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timely manner. The records were complete.
The inspector concluded that the Primary Water Chemistry was maintained well within the TS requirements, b.
Secondary Water Chemistry (1)
General Program TS 6.8.4.c requires the licensee to establish, implement, maintain, and audit a Secondary Water Chemistry Program to inhibit steam generator tube degradation.
The inspector reviewed the licensee's program.
The sampling schedule for critical variables and the control points for the variables was identified in the Nuclear Operations:
Nuclear Plant Chemistry Manual, Section 5.2, " Secondary Sample Scheduling and Specifications." The procedures to measure the value of the critical variables were made available to the inspector, who reviewed selected portions of several including: CH-72.P01, "pH: Measuring Using pH Meter;" CP-77.1, " Soluble Silica Colorimetric;" and CH-72.C01, " Conductivity:
Specific or Cation." The identification of process sampling points was done in
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Chemistry Procedures specific to the sample to be taken.
The inspector reviewed selected portions of several including:
CH-51.230, "On-Line Chemistry Monitor System (0LCMS):
Sampling Feedwater;" CH-51.220, "0LCMS:
Sampling Condensate Pump Discharge;" and CH-51.260, "0LCMS:
Sampling Steam Generator Blowdown." Procedures for the recording and management of data included CH-97.100, " Sampling Data Evaluation, Tracking and Trending" and Section 8.0,
" Guidelines for Data Management" of the Nuclear Operations:
Nuclear Plant Chemistry Manual.
The Manual also defined action levels, and specified actions to be taken with respect to given action levels to remedy the adverse condition in Section 5.4.1, " Secondary Chemistry Action 5'atements." Administrative Procedure ADM-19.22, " Secondary Chemistry identified the authority responsible for the interpretation of the data and sequence and timing of administrative events required to initiate corrective action.
(2)
Records Review The inspector reviewed records of the steam generators of both units for the period of July 29 through September 21, 1993, and determined that the required parameters were maintained within their respective limits.
Unit 1 operated at 100 percent of capacity for the period reviewed. Unit 2 operated at 89 percent of capacity in late July and " coasted down" to 69 percent of capacity on September 6, when the current refueling outage began.
TS 6.10.2.0 requires that the licensee retain records of secondary water sampling and water quality "for the duration of the Facility Operating License." The inspector requested records for the steam generators of Units 1 and 2 for the arbitrarily-chosen period of May 1 through June 30, 1981.
The information was produced (via microfiche) for the inspector's review in a timely manner.
The records were complete, satisfying regulatory requirements.
i The inspector concluded that the licensee had implemented a Chemistry Program capable of detecting both Primary and Secondary Side chemistry parameters to ensure safe and reliable plant operation and that it was well-maintained and satisfied TS requirements.
No violations or deviations were identified.
4.
Radiological Environmental Mor,1toring Program (84750)
TS 6.8.4.f specifies that the licensee shall conduct a Radiological Environmental Monitoring Program (REMP) to monitor radiation and radionuclides in the environs of the plant and defines how the program shall be conducted. The REMP shall provide representative measurements
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of radioactivity in the highest potential exposure pathways and.
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verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.. Accumulation of radioactivity in the environment can thereby be measured and' trends assessed; to determine whether the radioactivity resulted from plant
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operations, to project the potential dose to off-site populations based on the cumulative measurements of any plant-originated radioactivity,
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and to detect unanticipated pathways for the transport o' radionuclides-through the environment.
a.
Annual Radiological Environmental Operating Report TS 6.9.1.8 requires that the Annual Radiological Environmental i
Operating Report be submitted prior to May 1 of the following year. It also includes format and content requirements for the report.
The inspector reviewed the report for calendar year 1992 to verify compliance with the.TSs. The report had been submitted-in compliance with TS 6.9.1.8 on April 22, 1993, and the format and
contents were as prescribed by the TS. The inspectors determined that the report was in compliance with the TSs.
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The inspector reviewed the Radiological Environmental Operating Report for 1992. Analytical results were divided into five i
categories based on exposure pathways: Airborne, waterborne,
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aquatic, ingestion, and direct radiation.
Each of the pathways was described as follows:
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The airborne exposure included airborne iodine, airborne
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particulate, precipitation, and soil samples. No fission products or other man-made. isotopes in the airborne particulate media were detected in 1992. Overall 1992
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airborne results were very similar to those of previous years and preoperational levels.
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The waterborne exposure pathway included ground /well water, j
river water, and surface water samples.
No man-made or
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natural isotopes were detected in Lake Anna surface water, except for tritium. The average tritium-activity in 1992 l
was_approximately 20 percent of the NRC reporting: limit, which represented an increase from preoperational levels as
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well as from leveh, of previous years.
The aquatic exposure pathway included-sediment / silt and
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shoreline samples.
During the preoperational-period,
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cesium-137 had been detected in sediment.
In 1992, Cs-137 was detected in four samples (of six collected _- three stations, collected semiannually), at a maximum concentration of 524 pCi/kg.
(It was noted that Cs-137 was also identified in samples of aquatic sediment during the
preoperational period.) Also in 1992, Mn-54 was identified
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at a concentration of 24.5 pCi/kg in one (of six) sample.
Additional man-made isotopes appear to have accumulated since that period. One shoreline soil sample contained detectable levels of cesium-134 at a concentration of 114 pCi/kg.
Both shoreline samples contained cesium-137, at an average concentration of 532 pCi/kg, which continued an increasing trend from 1989, when a concentration of 378 pCi/kg was reported, through 1992, when a concentration of 534 pCi/kg was reported.
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The ingestion exposure pathway included milk, fish, and food / vegetation samples.
Neither iodine-131 nor cesium-137 were detected in any 1992 milk sample.
Strontium-90 was detected at concentrations comparable to those of recent years, i.e. lower than those of preoperational years.
Naturally-occurring potassium-40 was detected at normal environmental levels. One (of four) fish samples contained cesium-137 at a concentration comparable to that of preoperational years.
The other three fish samples did not contain cesium-137 at detectable levels.
Vegetation samples yielded concentrations of radioisotopes which were similar to those of the control sampling stations and of the preoperational period.
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The direct radiation exposure pathway measured environmental exposure by use of thermoluminescent dosimeters (TLDs). TLD results for 1992 remained consistent with those of previous
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years, i.e. essentially unchanged since the preoperational
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period.
i The radiological environmental data indicated that plant operations had no significant impact on the environment or public health and safety.
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Ccmparison of Results of Commonwealth of Virginia vs North Anna The Virginia Department of Health entered into a contractual j
agreement with the NRC to perform independent environmental sampling and radiological analyses of samples at designated locations around nuclear facilities licensed by the NRC within the
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state, including North Anna.
The principal objective of the contract is to provide reasonable assurance that environmental measurements made by NRC licensees are valid.
To this end, the Commonwealth of Virginia:
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Detects and measures radioactive releases during routine plant operation.
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Detects and measures radioactive releases during abnormal operation events.
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Heasures reconcentration of radioactive effluents in the environment, especially in human exposure pathways.
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Provides an independent means of verification of release reports.
These objectives are achieved through continuous sampling of air and ambient radiation, as well as, periodic sampling of water, milk, vegetation, fish, etc.
The inspector compared several air particulate, air cartridge, milk, fish, and surface water (for tritium and gamma isotopics)
results as reported by the licensee to those listed in the
" Environmental Radiation Program,1992 Comparative Report,"
submitted by the Virginia Department of Health, Bureau of Radiological Health. The results compared favorably. The inspector discussed the comparison with the Superintendent of
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Radiological Protection and the Supervisor of HP Technical Services.
c.
Observation of Sample Collection The inspector accompanied a team of technicians on their normal weekly rounds to collect samples to observe collection technique and to check the physical condition and operability of the sampling stations. Samples were taken at four indicator stations, including:
Nos. lA, 2, 3, 4, 5, 5A, 6, 7, 22, and 23, which included various combinations of media (air or water, plus a TLD).
Some of the stations were co-located with sampling stations of the Commonwealth of Virginia.
NRC TLDs were observed at Station Nos. 4, 6, and 22. Virginia TLDs were observed at Station Nos. 4, 6, 7, 22, and 23. The inspector noted that the TLDs were properly located and there was no evidence of vandalism. The air sampling tations were located well above ground level, on poles or on roofs of buildings, to assure that there would be no interference from tall weeds / vegetation in taking representative samples.
The inspector noted that all of the sampling units were well maintained and operating. Three air sampling units were noted to
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be operating beyond the date by which their calibration was due.
Discussions about this point with the Supervisor of Radiological Analysis determined that the licensee was aware of the condition and had planned to calibrate the units within the near future.
It had not been done earlier due to the manpower requirements of the Unit 2 outage.
(The inspector noted that the grace period allowed by the TSs had not expired for their calibration.) The' inspector also observed that the technicians used good HP techniques to avoid sample contamination and conducted their work in an efficient, competent manner.
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The inspector concluded that the licensee had effective programs il place to monitor releases of radiological effluents.
Plant operations j
caused minimum impact to the environment and virtually no dose to the general public from those effluents.
No violations or deviations were identified.
5.
Semiannual Radioactive Effluent Release Report (84750).
TS 6.9.1.9 requires the licensee to submit a Semiannual Radiological Effluent Release Report within specified time periods covering the operation of the facility during the previous six months of operation.
The inspector reviewed the semiannual radioactive effluent release report for the second half of 1992, issued February 24, 1993. This review included an examination of the liquid and gaseous effluent results for the second half of 1992 and dose estimates for the entire calendar year of 1992.
Full year totals for 1990, 1991, and 1992 were compared. The data are summarized on the following page:
North Anna Units 1 and 2 Radioactive Effluent Summarv
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Unplanned Releases a.
Liquid
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Activity Released (Curies)
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Gaseous 1.
Fission and 2.24E+3 1.23E+3 1.42E+2 Activation Gases 2.
Iodines 2.55E-3 1.34E-2 1.02E-3 3.
Particulates 1.46E-4 1.00E-4 3.86E-4 4.
Tritium 4.90E+1 4.94E+1 1.04E+1 b.
Liquid 1.
Fission and 3.20E-1 3.21E-1 2.52E-1
Activation Products 2.
Tritium 1.16E+3 9.29E+2 3.25E+2 3.
Gross Alpha 2.18E-4 4.73E-4 3.68E-4 Volume of Liquid Wastes Released 3.17E+8 2.68E+8 1.28E+8 Prior to Dilution
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(liters)
- First half of 1993 only
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No unplanned releases, as defined by the criteria presented in
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Section 6.6.2 of the ODCM, were reported in 1993 through the date of this inspection.
A comparison of the activity released from liquid fission and activation products and gaseous iodines, particulates, and tritium data for 1991, 1992, and the first half of 1993 (extrapolated assuming the same rate for the second half of the year), showed no significant changes. A slight increase in liquid gross alpha, as well as a decrease in gaseous fission and activation products and liquid tritium was similarly noted.
For the first half of 1993, North Anna liquid, gaseous, and particulate effluents were maintained well within TS,10 CFR 20, and 10 CFR 50 effluent limitations.
During this reporting period, no changes to the ODCM had been made.
During this reporting pericd, no extended periods of inoperability occurred with any liquid o. gaseous effluent monitoring instrumentation specified in the ODCM.
Evaluation of the land use census conducted in 1993 identified no change in sample locations for the REMP.
No major changes to the Radioactive Gaseous and Solid Waste Treatment Systems were made during the reporting period.
The report also included the results of solid radwaste shipments.
The following table summarizes those shipments for the previous two and a half years. The shipments typically included spent resins, filter sludge, dry compressible waste, and contaminated equipment.
North Anna Solid Radwaste Shioments 119.1 19_91
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Volume (cubic meters)
234.6 386.6 155.9 Activity (curies)
301.2 136.6 523.6
- First half of 1993 only for solid radwaste, the inspector noted that no trends were evident for the period reviewed. The apparently high value for activity was roughly in line with that of 1990 (724.1 curies).
The inspector concluded that the Semiannual Radioactive Effluent Release Report was complete and satisfied TS requirements.
No violations or deviations were identifie,
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6.
Radwaste Processing and Transportation (86750)
10 CFR 71.5 (a) requires that each licensee who transfers licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation (DOT) in 49 CFR, Parts 170 through 189.
Pursuant to these requirements, the inspector reviewed the licensee's activities affiliated with these requirements to determine whether the licensee effectively processes, packages, stores, and ships radioactive materials.
The licensee's program for the processing (including separation and compaction) and packaging of radioactive materials, including solid radwaste, was conducted by the Decontamination Unit within the HP Operations Department. The licensee's program for the transportation of-radioactive material was conducted by the Radioactive Material Control Unit within the HP Technical Services Unit and was responsible for loading shipments and preparing shipping documentation.
a.
Observation of a Shipment The inspector observed Shipment No. 93-SEG-05, one Powdex resin liner and eight B-25 boxes of Low Specific Activity (LSA)
material, Dry Active Waste (DAW), destined for Quadrex for processing.
The inspector reviewed the records of the shipment prior to its leaving the site. The radiation and contamination survey results were well within regulatory limits for highway
transport. The shipping manifest examined was consistent with the DOT requirements, including the 24-hour emergency telephone number as specified in 49 CFR 172.201(d). 1he inspector surveyed the shipment before it left the site to verify the licensee's survey and determined that it was accurate.
Based on this review, the inspector concluded that the shipment was handled according to the licensee's procedures and was properly documented.
b.
Radwaste Shipping Documentation The inspector reviewed shipping logs for 1993. The licensee classified shipments into three categories:
Radiological Material Receipts; Radiological Material Shipments; and Radwaste Shipments, which were further identified as shipments to the disposal facility, Scientific Ecology Group, Inc. (SEG), and Quadrex.
Radiological Material Receipts included items such as decontaminated outage and refueling equipment, empty Sea-Land containers, and laundered protective clothing and modesty garments.
Radiological Material Shipments included items such as contaminated outage equipment, radioactive material samples, and
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Radwaste Shipments included radioactive material ultimately destined for disposal. The logs showed that for the
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1993 calendar year to date (September 22), there had been 149 Radiological Material Receipts,156 Radiological Material Shipments, and 53 Radwaste Shipments (16 directly to the disposal i
facility, four to SEG, and 33 to Quadrex).
The inspector reviewed i
three radwaste shipment documentation packages (93-14, 93-16, and i
93-SEG-04) for completeness and compliance with the regulations.
The packages documented the shipments and included items such as unique shipment and shipping container numbers, waste content and volume, total activity, analytical summary and breakdown of isotopes with a half-life greater than five years. The radiation
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and contamination survey results were within the limits specified and the shipping documents were being maintained as required.
c.
Record Retention TS 6.10.1.f requires that records of radioactive materials shipments be retained by the licensee "for at least five years."
The inspector went to the licensee's Document Control Vault and requested the shipping records for the randomly-selected year of 1989. The documents were produced for the inspector's review in a j
timely manner. The inspector randomly chose the following five i
i shipments to assess the licensee's compliance with the TSs:
89-01, 89-16, 89-20, 89-SEG-04, and 89-QUAD-03. The records were complete, containing the same elements as the shipping packages of subparagraph b, above.
The inspector concluded that the Radwaste Group was staffed by competent personnel who effectively implemented the program.
7.
Decommissioning Planning Records (84750)
10 CFR 50.75(g) requires that licensees maintain " records of information important to the safe and effective decommissioning of the facility in an identified location until the license is terminated by the Commission." Furthermore, information considered important by the Commission for decommissioning is identified as " records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site" and that the records "must include any known information on identification of involved nuclides, quantities, forms, and concentrations." Also identified are "as-built drawings and modifications of structures and equipment in restricted areas where radioactive materials are used and/or stored and of locations of possible inaccessible contamination such as buried pipes which may be subject to contamination."
i The inspector requested the licensee's decommissioning planning records to verify compliance with the regulations. Discussions with the i
Supervisor of Radiation Protection determined that the subject i
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information had been retained per administrative procedure. However, the records were not segregated into one readily identifiable area nor was a listing identifying pertinent information for decommissioning planning available.
The Corporate Procedure Group had written Nuclear Standard addressing requirements for decommissioning a nuclear station, including commitments for compliance with 10 CFR 50.75, among others. The inspector reviewed Nuclear Standard. LINS-2809, " Nuclear Unit -
Decommissioning," which specifically addressed the requirements of 10 CFR 50.75 in Section 4.5, " Records Retention." The standard was effective June 30, 1993.
In addition, Procedure HP-8.0.12 NAPS,
" Radiological Survey Records," had been revised to ensure that potential decommissioning information was forwarded to radiological engineering for determination of retention review.
The inspector concluded that the licensee is making progress in this area. However, because full implementation of the program has not been accomplished, this issue will be revisited during a future inspection.
No violations or deviations were identified.
8.
Exit Interview The inspection scope and results were summarized on September 24, 1993, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection. The licensee did not identify any such documents or processes as proprietary.
Dissenting comments were not received from the licensee.
9.
Acronyms and Initialisms CFR
- Code of Federal Regulations Ci
- curie DAW
- Dry Active Waste DEI
- Dose Equivalent Iodine D0
- Dissolved Oxygen D0T
- Department of Transportation g
- gram
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- Health Physics LLD
- Lower Limit of Detection LSA
- Low Specific Activity uCi
- micro-Curie (1.0E-6 Ci)
NRC
- Nuclear Regulatory Commission ODCM - Off-Site Dose Calculation Manual OLCMS - On-Line Chemistry Monitor System PCP
- Process Control Program ppb
- parts per billion ppm
- parts per million RCS
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REMP - Radiological Environmental Monitoring Program Rev
- Revision
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SEG
- Scientific Ecology Group, Incorporated SFP
- Spent Fuel Pool
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TS
- Technical Specification
UFSAR - Updated Final Safety Analysis Report VEPC0 - Virginia Electric and Power Company
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