IR 05000335/1993009
| ML17228A157 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/06/1993 |
| From: | Robert Carrion NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17228A155 | List: |
| References | |
| 50-335-93-09, 50-335-93-9, 50-389-93-09, 50-389-93-9, NUDOCS 9305180260 | |
| Download: ML17228A157 (17) | |
Text
~0 RE0Ij, (4 0p0 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 lgyop~
Report Nos:
50-335/93-09 and 50-389/93-09 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-335 and 50-389 Facility Name:
St.
Lucie 1 and
Inspection Con te
April 5-9, 1993 License Nos.:
Date Signed Da e igned SUMMARY
. Carrio,
R diation Specialist Approved by:
3'
R. Decker, Chief Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards Scope:
This routine, announced inspection was conducted in the areas of the organization of the Chemistry Department and Radwaste Group, audits, facilities renovation, plant water chemistry, the Semiannual Radioactive Effluent Release Report, unplanned releases, effluent processing and monitoring, the Meteorological Monitoring Program, radioactive waste processing and transportation, and decommissioning planning records.
Results:
The licensee's organization of its Chemistry Department and Radwaste Group satisfied Technical Specification (TS) requirements (Paragraph 2).
Audits were found to be well-planned and documented with detailed comments and recommendations to aid the implementation of corrective actions (Paragraph 3).
The licensee had completed renovations and upgrades to the Chemistry Department offices and Secondary/Environmental Laboratory (Paragraph 4).
The licensee's plant water chemistry was maintained within required TS limits (Paragraph 5).
The Semiannual Radioactive Effluent Release Report met the requirements of the TSs (Paragraph 6).
9305l80260 930507 PDR ADQCK 05000335
The licensee's program for liquid and gaseous processing and monitoring was effectively implemented.
In general, effluent processing and monitoring was adequate to assure that all TS requirements were met.
However, three unplanned releases were documented (Paragraphs 7 and 8).
The licensee's Meteorological Monitoring Program was well maintained and fulfilled its required function (Paragraph 9).
Radwaste processing and shipping was conducted in a competent, professional manner (Paragraph 10).
The licensee had adequately addressed the issue of Decommissioning Planning Records (Paragraph 11).
REPORT DETAILS Persons Contacted Licensee Employees
- G. Boissy, Plant General Manager
- J. Breen, Licensing Engineer
- H. Buchanan, Health Physics (HP) Supervisor
- C. Burton, Operations Manager
- R. Cox, Chemistry Effluents Supervisor
- R. Dawson, Maintenance Manager D. Faulkner, Primary Chemistry Supervisor
- R. Frechette, Chemistry Supervisor
- J. Geiger, Vice President, Nuclear Assurance J. Holt, Licensing Engineer
- D. Lowens, Independent Safety Evaluation Group (ISEG)
- G. Madden, Licensing Engineer M. Mullins, Nuclear Energy Analyst
- D. Sager, Plant Vice President
- J. Scarola, Engineering Manager R. Somers, Radioactive Waste Supervisor
- J. Voorhees, guality Assurance (gA) Supervisor
- T. Ware, Technical Training Supervisor
- D. Wolf, Site Engineering Supervisor Other licensee employees contacted during this inspection included technicians and administrative personnel.
Nuclear Regulatory Commission
- S. Elrod, Senior Resident Inspector
- M. Scott, Resident Inspector
- Attended exit interview Organization (84750 and 86750)
Technical Specification (TS) 6.2 describes the licensee's organization.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department and Radioactive Waste Group to verify that the licensee had not made organizational changes which would adversely affect the ability to control radiation exposures or radioactive material.
There had been no structural changes in the Chemistry Department since the previous inspection.
However, the Supervisor of Secondary Chemistry had been temporarily transferred to the Unit I Outage Management Group and his place had been filled by a senior technician of the group on an
"acting" basi There had been no changes in the Radwaste Group since the last time this area was reviewed.
(Refer to Inspection Report (IR) 50-335,
-389/92-22, Paragraph 2.)
The inspector concluded that the licensee's organization in the areas of Chemistry and Radioactive Waste satisfied the requirements of the TS.
No violations or deviations were identified.
Audits (84750)
TS 6.5.2.8 specifies the types and frequencies of audits to be conducted under the cognizance of the Company Nuclear Review Board (CNRB).
The inspector reviewed audits conducted by CNRB within the scope of this inspection.
In order to evaluate compliance with the TSs and assess quality of the licensee's programs, the inspector reviewed the following audits:
Offsite Dose Calculation Hanual, gSL-OPS-92-875, conducted April 13 through June 17, 1992 Process Control Program, gSL-OPS-92-862, conducted February
through Harch 18, 1992 Radiological Environmental Honitoring Program, gAS-ENV-92-1, conducted Hay 8 through August 13, 1992 Secondary Water Chemistry, gSL-OPS-92-914, conducted December 3,
1992 through January 13, 1993 The audits were found to be well-planned and documented.
Findings were addressed by the responsible group via a written response which included:
actions taken/planned to correct and/or prevent recurrence of the identified finding; date when the corrective action was (or will be)
achieved; identification of the individual(s) responsible for the corrective action; and the results of their review and investigation of the findings.
The inspector noted that the comments and recommendations were detailed and would aid the implementation of adequate corrective actions.
The inspector verified that the audit program was conducted in accordance with the TSs.
The inspector concluded that the audit process was capable of identifying programmatic weaknesses and making recommendations for corrective action.
No violations or deviations were identifie Facilities Renovation (84750)
The licensee had recently completed a renovation of its offices for'hemistry personnel and the Secondary/Environmental Laboratory.
In addition to providing more personnel office space, a computer center had been established.
The new computer system was designed to minimize human input (and therefore the associated potential errors such as the transposition of numbers during the data input process or the plotting of control charts).
The results of analyses done in the Counting Room were automatically entered into the system.
Notice of periodic surveillances and calibrations were printed out on the date which they were due as part of a daily "card file report" and included such items as a description of what task was to be performed, the normal testing frequency, the date last performed, the next scheduled date, and any special instructions.
The system was structured such that the Chemistry supervisors could call up the data from terminals in their respective offices to obtain the latest status of plant conditions or retrieve previously-inputted data.
The inspector toured the Secondary/Environmental Laboratory.
The renovations had resulted in a "clean room" with its own Heating Ventilation and Air Conditioning (HVAC), which incorporated High Efficiency Particulate Air (HEPA) filters into the design to assure the cleanliness of the air supply.
The instrumentation in the "clean room" included two Dionex cation ion chromatographs (ICs), two Dionex anion ICs, and a new (yet to be installed)
Atomic Absorption (AA)
Spectrophotometer which will be dedicated to the Steam Generator and Feedwater System.
The AA spectrophotometer will be set up and used in the furnace mode only for the detection of low level concentrations of metals such as iron, copper, and magnesium.
The ICs were accessed by computer and calibration checked daily. If the calibration check did not satisfy the acceptance criteria, a software-controlled three-point check and/or an external calibration check using a technician-prepared standard was performed.
A linearity check was done on a weekly basis.
Outside the "clean room," the instrumentation was virtually the same as referenced in Paragraph 12 of IR 50-335,
-389/90-12.
The inspector noted the readout for in-line solids had been upgraded from an analog to digital readout.
The biggest change was that the computer system had become such a dominant part of the daily routine, to the point where no logs were maintained.
All data management was done on and by the computer.
Some of its capabilities were demonstrated to the inspector by producing plots of control charts and plots of various parameters against each other.
Trends were also identified by the computer.
The Environmental section of the laboratory had been also enlarged.
Typically, diesel fuel, biocide, chlorine, etc.
samples were analyzed there and the results were reported to the Environmental Protection Agency of the State of Florid The inspector concluded that the licensee's renovations had significantly upgraded capabilities of the Chemistry Department, especially in the areas of information retrieval and the elimination of potential human error in the recording/manipulation of data.
No violations or deviations were identified.
Plant Water Chemistry (84750)
During the inspection, St.
Lucie Units 1 and 2 were operating at zero percent and one hundred percent power, respectively.
Unit 1 was in its eleventh refueling outage and Unit 2 was in its seventh fuel cycle.
The Unit 1 refueling outage had begun on Harch 28 and was scheduled to be completed by mid-Hay.
The next Unit 2 refueling outage was tentatively scheduled to begin in early 1994.
a ~
Primary Water Chemistry The inspector reviewed the plant chemistry controls and operational controls affecting primary plant water chemistry since the last inspection in this area.
TS 3.4.7 specifies that the concentrations of dissolved oxygen (DO), chloride, and fluoride in the Reactor Coolant System (RCS)
be maintained below 0. 10 parts per million (ppm), 0. 15 ppm, and 0. 10 ppm, respectively.
TS 3.4.8 specifies that the specific activity of the primary coolant be limited to less than or equal to 1.0 microcuries/gram (pCi/g) dose equivalent iodine (DEI).
These parameters are related to corrosion resistance and fuel integrity.
The oxygen parameter is established to maintain levels sufficiently low to prevent general and localized corrosion.
The chloride and fluoride parameters are based on providing protection from halide stress corrosion.
The activity parameter is based on minimizing personnel radiation exposure during operation and maintenance.
Pursuant to these requirements, the inspector'eviewed daily summaries for both units which correlated reactor power output to chloride, fluoride, and dissolved oxygen concentrations, and specific activity of the reactor coolant.
For Unit 1, the period of January 1,
1993 through Harch 16, 1993 was reviewed and the parameters were determined to have been maintained well below TS limits.
Typical values for DO, chloride, and fluoride were less than five parts per billion (ppb), less than four ppb, and six ppb, respectively.
Likewise, for Unit 2, the period of December 12, 1992 through January ll, 1993 was, reviewed and the parameters were also determined to have been maintained well below TS limits.
Typical values for DO, chloride, and fluoride were
less than five ppb, less than five ppb, and less than five ppb, respectively.
Typical DEI values at steady-state conditions ranged from 6.85E-3 pCi/g to 2.27E-2 pCi/g for Unit 1 and from 1.51E-5 pCi/g to 1.31E-2 pCi/g for Unit 2.
Neither unit had shown any evidence of leaking fuel.
Secondary Water Chemistry 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 "Nuclear Plant Chemistry Parameters Hanual," JNO-CHH-1.2, Rev.
15, dated April 6, 1992, identified not only the parameters associated with the Steam Generators, but ranges of normal values for different modes of operation, and levels at which mitigation actions were to be initiated.
Justification for the values of the parameters at different modes of operation as well as a description of the control chemicals were also included in the manual.
Procedures used to analyze the critical variables were made available to the inspector and included such things as the determination of boron, sodium, and cation conductivity.
Process sampling points were identified as being at each hotwell and the discharge of the condensate pumps per Chemistry Operating Procedure No. C-51,
"Haintaining Condensate and Feed System Chemistry,"
Rev.
19, approved February 25, 1992.
The procedure further identified the sampling schedule, defined action levels, and specified actions to be taken with respect to given action levels to remedy the adverse condition.
The procedure also stipulated the requirements for maintaining required records.
The sampling schedule for the steam generators was defined in Chemistry Procedure No. C-01,
"Schedule for Periodic Tests,"
Rev. 35, approved February 25, 1993.
guality Instruction gI I-PR/PSL-2,
"Operations Organization,"
Rev.
13, approved April 29, 1987, defined the responsibilities of the Chemistry Group in general and of the Chemistry Supervisor in particular.
2.
Records Review The inspector reviewed records of Steam Generator lA of Unit 1 for the month of January 1992, and Steam Generator 2A.
of Unit 2 for the month of August 1992, and determined that the required parameters were generally maintained within their respective limits.
(The limits were developed from the Electrical Power Research Institute (EPRI)
"PWR Secondary Water Chemistry Guidelines" and represent the first administrative action level.)
Unit 1 operated at 100
percent of capacity for the month reviewed and only one parameter was outside of the limits for a few hours before being restored to its required levels.
Unit 2 experienced a
period where it went from 100 percent power to Hot Standby and back to 100 percent power.
During this period, some of the parameters experienced excursions outside of the limits but were restored before or during power ascension.
TS 6. 10.2.m requires that the license retain records of secondary water sampling and water quality "for the duration of the unit Operating License."
The inspector went to the licensee's Document Control Vault and requested the records for the lA Steam Generator of Unit 1 for the arbitrarily-chosen months of January and February 1979.
The documents were produced (via microfiche) for the inspector's review in a timely manner.
The records were complete, satisfying regulatory requirements.
The inspector concluded that the Plant Water Chemistry was maintained well within the TS requirements.
No violations or deviations were identified.
Semiannual Radioactive Effluent Release Report (84750)
TS 6.9. 1.7 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.
This review included an examination of the liquid and gaseous effluents for that period as compared to those of years 1990, 1991, and 1992.
The data for those years are summarized in Attachment l.
A comparison of the listed data for 1990, 1991, and 1992 showed no significant changes.
for 1992, St.
Lucie liquid, gaseous, and particulate effluents were well within TS,
CFR 20, and
CFR 50 effluent limitations.
Two Unplanned Releases were identified in the Report.
(Refer to Paragraph 7 for details.)
No revisions were made to the Offsite Dose Calculation Nanual (ODCH) nor to the Process Control Program (PCP) during the second half of 1992.
The following table summarizes solid radwaste shipments for burial or disposal for the previous three years.
These shipments typically include spent resins, filter sludges, dry compressible waste, and contaminated equipmen St. Lucie Solid Radwaste Shipments 1990 1991 1992 Number of Waste Disposal Shipments Volume (cubic meters)
222.8
182,1
213.8 Activity (curies)
5886.4 825.7 388.2 In 1992, the licensee made twenty-eight radwaste shipments, including seven to Scientific Ecology Group, Incorporated (SEG), fourteen to guadrex, and seven to the disposal facility.
To date, April 7, 1993, the licensee had made four radwaste shipments, including one to guadrex, and three to the disposal facility.
For solid radwaste, the most significant change noted for the period reviewed was that the activity of the shipments declined while the volume leveled off.
The inspector concluded that the Semiannual Radioactive Effluent Release Report was complete and satisfied TS requirements.
No violations or deviations were identified.
Unplanned Releases (84750)
On September 16, 1992, the contents of Gas Decay Tank (GDT) 2A were'eing released in accordance with Gas Release Permit No. 2-92-130 when the Senior Nuclear Plant Operator (SNPO) noted that the pressure of GDT 2B had decreased.
The release was terminated.
The licensee determined that the most probable cause of the event was a failure of an outlet valve from GDT 2B to the release header to fully seat during the release of GDT 2A.
An estimated 9.84E+1 millicuries (mCi) were released from GDT 2B during this event, which represented only 0.007 percent of the Administrative Limit allowed for this pathway.
Plant Work Order (PWO)
92048806-01 was written to adjust the remote handwheel assembly for Valve V-6594 to ensure full valve closure.
The PWO was completed shortly thereafter.
The other unplanned release occurred on November 4, 1992 when the nitrogen system was isolated at the bulk gas house to repair a
prematurely lifting safety valve.
During that time, the system pressure in the downstream piping decreased.
Later the Steam Jet Air Ejector (SJAE) radiation monitor alarmed.
The steam generators were sampled for radioactivity with negative results.
However, a grab sample of SJAE exhaust gases indicated the presence of radioactivity.
It was confirmed that prior to the event that the SJAE exhaust was aligned to its normal exhaust path, the Plant Vent Exhaust, which is a TS continuous release monitored pathway.
The licensee conducted an investigation of the event
which indicated that Gas Decay Tank (GDT)
1B had backflowed into the nitrogen system through the normally-closed nitrogen supply valve (V-6596) to the GDT.
The nitrogen system was isolated by closing the root nitrogen supply valve (V-6788)
and PWO 92047980 was initiated to repair the nitrogen supply valve (V-6596).
'(The PWO was completed on January 4,
1993.)
In addition, the licensee performed a root cause analysis to determine an appropriate corrective action to prevent recurrence.
The resulting recommendation was to install a double check valve on the nitrogen supply line to the Unit 1 Reactor Auxiliary Building (RAB) to prevent back flow from the potentially radioactive RAB to the Secondary Plant side of the nitrogen system.
(The recommended installation would bring the Unit 1 design to a par with the Unit 2 design, which incorporated the double check valve into its original design.)
The proposed design change was submitted to Engineering via Request for Engineering Assistance (REA)92-360 for review per the Plant Change Modification (PCM) process.
The initial screening of the REA determined that the change had low priority and a tentative date of September 1995 was given for installation.
The licensee determined that the exhaust contained an activity level of 1. 1E-07 curies per second, which was 0.00003 per cent of the site limit of 0.35 curies per second, as per the ODCH.
Due to the extremely low activity concentration levels in the Plant Vent during this event, no noticeable increase was detected by the Plant Vent Monitor.
In calendar 1993 through the date of this inspection, there had been one unplanned effluent release.
It was a gaseous release which occurred on January 29 and involved another leakby of the nitrogen supply valve (V-6596), similar to (but not the same as) the previously-referenced event which occurred on November 4, 1992.
The licensee calculated the release rate for the event to be 5. 1E-04 curies per second, far lower than the site limit of 0.35 curies per second.
No TS release rate limits were exceeded.
The most significant result of the event was the upgrading of the priority to install double check valves referenced in REA 92-360.
Discussions with cognizant licensee personnel determined that there was a possibility that the work could be done during the current Unit 1 outage, although it would most likely be done during the next Unit 1 outage due to planning/scheduling constraints.
The licensee recognized the potential for more serious problems than those experienced to date in upgrading the priority.
The inspector concluded that the licensee was taking appropriate action to upgrade the nitrogen system before a serious problem developed.
No violations or deviations were identified.
Effluent Processing and Monitoring (84750)
'a ~
Release Permit Review TSs 3. 11. 1 and 3. 11.2 define the requirements for liquid and gaseous effluent concentrations, doses and dose rates, and waste treatments released to Unrestricted Areas.
These requirements are
intended to ensure that the limits of 10 CFR 20 and
CFR 50 are satisfied.
TSs 4. 11. 1 and 4. 11.2 define the surveillance requirements for the sampling and analysis program.
The inspector reviewed three randomly-selected Liquid Release Permits (1-93-15, 1-93-19, and 1-93-29)
and three randomly-selected Gaseous Release Permits (1-93-5A, 2-93-18, and 2-93-36) to verify compliance.
Permits from both units were included, from the period since the last inspection in December 1992.
The permits included both release information and projected dose calculations and were found to be complete, including the identification of the source of the release, the activity released (identified by isotope),
and the volume of the effluent discharged.
b.
Availability of Process Monitors The inspector reviewed licensee records about availability of process monitoring equipment.
The records showed that since the last inspection, no TS-required monitors had been out of service for more than a thirty-day period.
However, three other non-TS required monitors had been out-of-service for an extended (several months) period.
They were the Unit 2 Post Accident Sampling System (PASS) Dissolved Oxygen Flow Rate Heter, which reads less than its check tolerance, and the Unit 2 PASS Hydrogen and Oxygen Per Cent Meters, which failed their calibrations.
The Instrumentation and Controls (ISC) Department was reviewing the PASS to resolve these problems.
In general, the licensee had maintained an availability exceeding ninety-seven percent for all (TS-and non-TS-required)
processing monitoring equipment.
The inspector concluded that the licensee's program for liquid and gaseous processing and monitoring was being effectively implemented.
No violations or deviations were identified.
Meteorological Monitoring Program (84750)
The information obtained from the Meteorological Monitoring Program is integral to the determination of offsite dose projection.
TS 6. 10.2.o requires an annual summary of hourly meteorological data collected over the previous calendar year, including wind speed, wind direction, atmospheric stability, and precipitation (if measured).
The inspector reviewed the Meteorological Monitoring Program of St. Lucie.
The review included direct observation and discussions with a cognizant licensee representative.
The inspector determined that St. Lucie still had one meteorological tower and that it was unchanged from the previous review.
(Refer to IR 50-335,
-389/92-02.)
a ~
b.
Neteorological Tower TS 3.3.3.4 requires operability of the meteorological monitoring instrumentation at all times.
The inspector walked down the meteorological tower and associated instrumentation to verify by direct observation that the meteorological monitoring instrumentation and related channels were operable and maintained.
Instruments utilizing continuous-recording tape were used to save information concerning the various meteorological parameters.
The upper wind speed and direction were recorded on one plot and the lower wind speed and direction on another.
On yet another, upper temperature (both channels),
lower temperature (both channels),
differential temperature (both channels),
and rainfall were all recorded.
Also, a digital readout which averaged the data of the last fifteen minutes was available.
The inspector also noted that backup power was supplied by batteries.
Meteorological information was supplied to the Emergency Response Data Acquisition and Display System (ERDADS) in the control room by a
VHF radio transmitter or a redundant hard-wired landline.
In the event that the tower was out of service, there was no back-up system on the site.
However, the essential parameters could be obtained from the commercial airport of West Palm Beach, Florida, about forty-five miles south of the plant.
Calibration of Instrumentation C.
The licensee had begun its semiannual calibration of the meteorological instrumentation (as required by TS 4.3.3.4)
but had not completed it by the conclusion of the inspection.
The inspector reviewed records of the previous two calibrations.
IEC Procedure No. 1400055,
"Environmental Data Acquisition Semi-Annual Calibration," was used for the calibrations.
The earlier calibration was done between March 9 and 23, 1992, per PWO 9200346801.
The PWO indicated that new wind speed and direction sensors were installed at the 10- and 57.9-meter stations.
All calibrations were satisfactorily performed.
The later calibration was done between September 22 and 29, 1992, per PWO 9204407501 and all calibrations were satisfactorily performed.
Control Room The inspector went to the Unit 1 control room to verify the capability of the ERDADS to call up the required meteorological data.
The system functioned well, supplying wind speed, wind direction, and air temperature at both the 10-and 57.9-meter stations.
Based on the scope of this review, the inspector determined that the Meteorological Measurement System was capable of fulfillingits required functions.
No violations or deviations were identifie.
Radwaste Processing and Transportation (86750)
CFR 71.5 (a) requires 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 packages, stores, and ships radioactive solid materials.
The licensee's program for the packaging and transportation of radioactive materials, including solid radwaste, was conducted by the Radioactive Waste Group within the HP Department.
Radwaste was processed and packaged (including the preparation of shipping documentation)
by the Radwaste Group, with the assistance of Radiation Protection Hen on loan from the HP Operations Department to complete specific tasks, such as loading a shipment or compacting contaminated material.
b.
Radioactive Material Shipping Documentation Packages Seventy-four shipments of radioactive materials were made in 1992.
The inspector reviewed documentation packages for three radioactive material shipments made since Inspection 92-22.
They were Radioactive Material Shipment Nos. 92-71, 93-01, and 93-05, and included one Type B shipment of irradiated hardware to the disposal facility, one Low Specific Activity (LSA), Type A
shipment, destined for processing (incineration and/or compaction)
before final disposal, and one Limited guantity shipment to a laboratory for analysis.
The packages contained thorough documentation about 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, special comments, etc.
The radiation and contamination survey results were within the 49 CFR requirements and the shipping documents were being maintained as required.
Record Retention TS 6. 10. l.f requires that records of radioactive materials shipments be retained by the licensee "for at least five years."
The inspector reviewed the shipping logs of the Radioactive Waste Supervisor and randomly chose the following five shipments to assess the licensee's compliance with the TSs:
88-43, 89-23, 89-35, 90-24, and 91-12.
The inspector went to the licensee's Document Control Vault and requested the shipping records for the referenced shipments.
The documents were produced (via
microfiche) for the inspector's review in a timely manner.
The records were complete, containing the same elements as the shipping packages of subparagraph a,
above.
c.
Volume Reduction Program Discussions with the Radioactive Waste Supervisor determined that the licensee was in the top quartile of nuclear power plants in 1992 in smallest volume of radioactive waste disposed of.
This was explained by the licensee's sustained effort undertaken over the past several years to dispose of any accumulated wastes and to actively reduce waste generation.
Other plants had only recently started aggressively to reduce their waste, resulting in large volumes shipped last year while the licensee shipped approximately the same over the last three years.
Further reductions should be realized this year due to the approval of Revision 11 to Health Physics Procedure No. HP-41,
"Movement of Material and Equipment,"
on March 26, 1993, which allows bulk materials, containing only naturally-occurring radioactive material (such as uncontaminated sand blasting grit) to be free released rather than treating it as radioactive waste material, as had been done previously.
The inspector concluded that the licensee's shipping records were complete and well-maintained.
The record retention requirements of the TSs were also satisfied.
No violations or deviations were identified.
ll.
Decommissioning Planning Records (84750)
CFR 50.75(g) requires, in part, 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."
During the previous inspection (refer to IRs 50-335,
-389/92-22, Paragraph 8), the inspector discussed the status of the revision to HP Procedure HP-101,
"Identification and Reporting of Radiological Events,"
to address the issues of proper classification and timely retrieval of existing documentation.
The Facility Review Group (FRG) reviewed and approved the revisions on December 3,
1992.
Since then, the Plant Manager had signed the revision for implementatio The inspector reviewed the implementation of the new revision to verify that it satisfied the requirements of 10 CFR 50.75(g)(1)
and (2).
The licensee had reviewed all previous Radiation Event Reports (RERs)
and Radiation Incident Reports (RIRs) to reference those applicable to this subject.
The inspector concluded that the licensee had an adequate system in place to satisfy the requirements of 10 CFR 50.75(g)(l)
and (2) and that its implementation had been good.
No violations or deviations were identified.
Exit Interview The inspection scope and results were summarized on April 9, 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.
Acronyms and Initialisms AA - Atomic Absorption CFR - Code of Federal Regulations Ci - curie CNRB - Company Nuclear Review Board DEI - Dose Equivalent Iodine DO - Dissolved Oxygen DOT - Department of Transportation EPRI - Electrical Power Research Institute ERDADS - Emergency Response Data Acquisition and Display System FPL - Florida Power and Light FRG - Facility Review Group g - gram GDT - Gas Decay Tank HEPA - High Efficiency Particulate Air HP - Health Physics HVAC - Heating Ventilation and Air Conditioning 18C - Instrumentation and Controls IC - Ion Chromatograph IR - Inspection Report ISEG - Independent Safety Evaluation Group LSA - Low Specific Activity pCi - micro-Curie (1.0E-6 Ci)
mCi - milli-Curie (1.0E-3 Ci)
mRad
- milli-Rad mrem - milli-rem No. - Number NRC - Nuclear Regulatory Commission ODCM - Off-site Dose Calculation Nanual
PASS - Post Accident Sampling System PCM - Plant Change/Modification PCP - Process Control Program ppb - parts per billion ppm - parts per million PSL - Plant Saint Lucie PWO - Plant Work Order PWR - Pressurized Water Reactor gA - guality Assurance RAB - Reactor Auxiliary Building RCS - Reactor Coolant System REA - Request for Engineering Assistance RER - Radiation Event Report Rev - Revision RIR - Radiation Incident Report SEG - Scientific Ecology Group, Incorporated SJAE - Steam Jet Air Ejector SNPO - Senior Nuclear Plant Operator TS - Technical Specification
Attachment St.
Lucie Radioactive Effluent Release Summary Unplanned Releases a.
Liquid b.
Gaseous Activity Released (curies)
1990
0 1991 1992 a ~
b.
Liquid 1.
Fission and Acti-vation Products 2.
Tritium 3.
Gross Alpha Gaseous 1.
Fission and Acti-vation Products 2.
Iodines 3.
Particulates 4.
Tritium l. 59E+0 5.67E+2 5.22E-5 1. 15E+3 1.41E-2 8.05E-5 1.06E+2 1. 28E+0 1. 25E+3 3.10E-5 4.24E+3 1.43E-2 2.96E-4 1.74E+2 1.02E+0 8.00E+2 3.27E-5 9.90E+2 5.69E-3 2.31E-4 6.04E+1 Dose Estimates a ~
Gaseous Effluents 2.
3.
Noble Gas Gamma Dose (mRad)
Noble Gas Beta Dose (mRad)
Thyroid (mrem)
4.11E-2 7.49E-2 1.84E-2 1.07E-2 2.02E-2 1.65E-3 6.72E-3 1.42E-3 2.50E-3 b.
Liquid Effluents 1.
Lung (mrem)
2.
Whole body (mrem)
7.21E-1 1.74E-l 3.22E-1 7.99E-2 8.60E-1 2.08E-1