IR 05000424/1986100
| ML20214P237 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/18/1986 |
| From: | Dan Collins, Gloersen W, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214P214 | List: |
| References | |
| 50-424-86-100, NUDOCS 8612040124 | |
| Download: ML20214P237 (15) | |
Text
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ATLANTA, GEORGI A 30323
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NOV 21 1986 Report No.: 50-424/86-100 Licensee: Georgia Power Company P.-0. Box 4545 Atlanta, GA 30302 Docket No.: 50-424 License No.: CPPR-108
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Facility Name: Vogtle 1 s
Inspection Conducted: October 20-24, 1986 Inspectors:
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Approved by:
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D. M. Collins, Chief
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Date_ Signed Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards
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SUMMARY
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Scope: This routine, unannounced inspection involved an onsite assessment in the areas of liquid and gaseous radioactive waste mariage. ment, effluent treatment-systems, effluent monitoring systems, post-accident sampling system, and quality assurance and confirmatory measurements for in-plant radiochemical analyses.
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Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. Green, Plant Manager
.
- P. D. Rice, Vice-President, Project Engineering, Corporate
- H. P. Walker, Operations Assistant to Senior Vice President
- C. E. Belflower, QA Site Manager
- D. F. Hallman, Chemistry Superintendent
- A. Desrosiers, Health Physics Superintendent
- S. C. Ewald, Manager, Radiological Safety, Corporate
- W. C. Gabbard, Regulatory Specialist A. Stalker, Chemistry, Corporate W. F. Jocher, Laboratory Supervisor W. Carter, Countroom Foreman M. J. Kurtznen, Supervisor, Health Physics and Chemistry Training S. J. Connor, Senior Methods and Training Specialist P. E. Jackson, Plant Engineer R. C. Hand, Plant Chemist
.,
Other applicant employees contacted included engineers and technicians.
NRC Resident Inspectors
- H. Livermore, SRI - Construction
- R. J. Schepens
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 24, 1986, with those persons indicated in Paragraph 1.
The inspector described the areas inspecta.1 and discussed in detail the inspection findings provided in this report.
No dissenting comments were received from the applicant.
The applicant did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Precedures(84523,84524,84525)
a.
The inspectors reviewed selected portions of the following procedures that were related to radiological effluent management and in-plant radiochemical analysis.
33005-C, Determination of Gross Beta-Gamma Radioactivity, Rev. 1,
March 16, 1986 i
,
'
.
t
33010-C, Determination of Gross Alpha Radioactivity, Rev. 2,
March 16, 1986 33036-C, Calibration of the Gama Spectroscopy System (draft)
33040-C, Compositing Samples Weekly, Monthly, Quarterly, Rev. O, April 9, 1986.
33045-C, Preparation of Radioactive Calibration Sources, Rev. O,
April 7,1986.
b.
The inspectors discussed various aspects of the procedures with the applicant and the following observations were noted:
(1) 33005-C, Determination of Gross Beta-Gamma Radioactivity:
The inspector noted that in Step 2.1, a calibration was defined as establishing a voltage plateau.
Technically, a calibration involves the determination of the detector's efficiency in addition to the voltage plateau.
Step 6.1.1 described the preparation of a sample by mounting a filter in the planchet. The inspector did not note a calibration standard preparation procedure in 33045-C for this particular geometry. The applicant indicated that this portion of the procedure would ba deleted.
(2) 33010-C, Determination of Gross Alpha Radioactivity:
Step 6.1.1 of this procedure also described the preparation of a sample by mounting a filter in the planchet.
Similarly, a calibration source preparation procedure in 33045-C for this type of geometry was not noted.
If this type of geometry is to be used, filter standards for alpha / beta counting should not be prepared by absorption of the liquid onto the filter since self-absorption would be significant and the standard may not be reproducible.
The applicant indicated that this portion of the procedure would be deleted since this particular geometry was not going.to be used.
Additionally, the inspector did not note a self-absorption study for gross alpha measurements.
The applicant indicated that this study was in progress.
(3) 33036-C, Calibration of the Gamma Spectroscopy System for Radiochemistry (draft):
The inspector noted that the procedure should list the sources, associated geometries, and the activity levels used for calibration including the mixed gamma calibration check source. The inspector also noted that there was no apparent provision to compare new efficiency data with the previous efficiency data.
Additionally, the inspector and an applicant representative discussed plotting the experimentally-determined efficiency data points along with the fitted efficiency data
~
.
points to aid in identifying bad data.
The inspector also
!
discussed gas calibrations and noted that for initial gas
!
calibrations, the validity of the gas transfer process should be evaluated.
Also, during the procedure review, the inspector did _.
_ _ - _ _ _ _ _ _ -
'4 not note any formalized requirement for independent review, verification, and sign-off of data by an individual other than the one performing the calibration.
The applicant acknowledged the inspector's comments.
. (4) 33045-C, Preparation of Radioactive Calibration Sources:
The inspector noted that liquid standards should be prepared by weighing the sample, since standards are calibrated in terms of activity per unit mass. Additionally, it was noted that there was.
no specification in the procedure for the preparation of evaporated liquid samples on metal planchets.
The applicant acknowledged the inspector's comments.
The items mentioned above will be reviewed in greater detail during a subsequent preoperational cuality assurance and confirmatory measurements inspection.
No violations or deviations were identified.
4.
Laboratory Facilities (84525)
At the time of this inspection, the radiological counting laboratory was not operational due to construction activities within the laboratory facility.
The laboratory was scheduled to become operational again during the week of October 27, 1986. The inspector noted that a laboratory supervisor had been hired since the last inspection whose duties included the management of the radiological counting laboratory.
A newly hired counting room foreman who was directly involved with the counting laboratory reported to the Laboratory Supervisor.
Discussions with laboratory management concerning personnel qualifications indicated that lab technicians would have a minimum of a two-year associate degree in science or engineering.
Presently, six senior technicians and two foremen had oeen trained. The applicant plans to have a total of 12 technicians qualified to operate the equipment in the counting laboratory.
It was noted that many of the counting room technicians had minimal or no nuclear plant experience.
There was no apparent established mechanism to send the inexperienced personnel to other nuclear plants in order to gain experience. The inspector briefly reviewed the training program provided for the counting room technicians, which was administered by the applicant's Corporate Training Center.
The.alle ing three course subjects were offered to the technicianr:
(1) Nuclear Data's data base management system; (2) principles and practices of preoperational counting and scintillation counting; and (3) principles of gamma ray spectroscopy, which included description and setup of electronic equipment, computer description and capabilities, spectroscopy software, and spectroscopy procedures.
The inspector noted that the applicant needs to pursue aggressively its efforts in establishing an operational counting laboratory with adequately trained technicians to operate the equipment in order to support the startup schedule.
The inspector discussed the NRC's confirmatory measurements inspection program with applicant representatives including the use of the Region II
_ _ _
_
.
__
_
_
.
_ - _ _ _ _
.__
_
f
Mobile Laboratory._ In particular, specifications for parking arrangements and utility services were discussed. One location for the Mobile Laboratory should be as close as practicable to the facility countroom which would be
.
used during routine inspections.
One advantage of locating the Mobile Laboratory within the protected area is the ease of transporting radioactive samples from the plant to the Mobile Laboratory. The second location should be near the emergency operations facility and would be used during emergency situations.
The vehicle dimensions are approximately 30 feet long, eight feet wide, and 14 feet tall.
Electrical service should include three lines with separate circuit breakers each with 120 volts, 30 amps located within 25 feet of the Mobile Laboratory. The receptacles. should be compatible with Hubbell 125 volt, 20 amp three prong twist lock plugs.
One standard telephone outlet within 25 feet of the Mobile Laboratory should be provided.
Additionally, the inspector discussed some of the elements of the Quality Assurance and Confirmatory Measurements inspection program and informed laboratory personnel that spiked samples would be submitted for analysis during the next inspection.
No violations or deviations were identified.
5.
Post Accident Sampling System (PASS) (84523)
The inspectors discussed the Post Accident Sampling System (PASS) with applicant personnel and performed a walkdown of the system in the company of an applicant representative.
The PASS was a Sentry Model B system.
Separate systems have been provided for llaits 1 and 2.
Preoperational inspections of the PASS were not completed as of the end of the inspection and had been scheduled for approximately October 31, 1986.
Results of the precperational tests will be reviewed during the next inspection.
No violations or deviations were identified.
6.
Process and Effluent Radiological Monitoring and Sampling System (PERMSS)
(84523,84524)
The Process and Effluent Radiological Monitoring and Sampling System (PERMSS) was discussed in meetings between the inspector, applicant personnel, and contract personnel.
All plant gaseous effluents will be i
released through a common stack which discharges to the environment from a point near the top of the dome of the containment building. The stack has a nominal rectangular cross-section of five feet by ten feet and has a design volumetric flow of 200,000 scfm.
Three sample collection systems are provided for monitoring gaseous effluents.
The sampling heads are located approximately 38 feet downstream
-
of the last vent system feeding into the train vent.
Each samplirg system has four collecting nczzles in one line across the approximate center of the duct.
One sample line is for collection of normal operation samples; the other two are for tne accident range monitor.
Flow tests and vent stack profiles will be run at a later date when all ventilation systems are
..
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6 operable.
As of the date of the inspection, only about one-half of the systems had been balanced and made operable.
The containment atmosphere particulate air monitor used for detection of primary coolant in containment takes its sample through a 3/4" diameter stainless steel tube.
Isolation valves on this system, at the time of the inspection, were being replaced with gate valves to minimize flow distortion in the sample line and therefore, -the sample line had not been declared operable.
Liquid effluent monitors were provided for four effluent lines:
processed radwaste liquids, turbine building drains, steam generator blowdown, and service water.
These monitors had removable liners to facilitate decontamination.
Preoperational tests of the PERMSS had not been completed as of the end date of this inspection. A detailed review of all aspects of the PERMSS will be conducted during the next inspection.
No violations or deviations were identified.
7.
'!entilation Exhaust Filter / Charcoal Treatment Systems (84524)
The impector discussed the ventilation exhaust HEPA filter and charcoal adsorber treatment systems with applicant personnel and walked down several of the systems in the company of an applicant representative.
Engineered safety feature systems were supplied by American Air Filter (AAF)
Corporation. None of these systems had been loaded with filters or charcoal at the time of the inspection.
The inspector noted that all filter system drains had been capped to prevent bypass leakage and that inadvertent flooding had been prevented by the use of removable spool pieces or reversible " spectacle" flanges whit.h required deliberate manual action to complete the path for water to enter the deluge system. All units are designed for four inches of charcoal adsorber and are of the bulk load type.
The applicant expressed some concern over the use of flat door gaskets physically mounted on the body frame rather than being fitted to the door, as is the more common practice.
System leak tests, however, indicated adequate sealing characteristics.
All systems have been balanced using blank-offs in place of filters to simulate filter loading; this practice is acceptable under ANSI /ASME N510-1980.
Workmanship of the filter systems appeared good.
Substantial bulges were observed in the charcoal retaining screens of all of the MSA systems; this is attributable to the wide spacing between support elements and has not been a serious problem at other installations.
The filter systems are scheduled to be loaded with HEPA filters and charcoal starting November 1, 1986.
As systems are loaded, they will be checked for leakage and possible bypass by contractor (NUCON) personnel using the tests specified in ANSI /ASME N510-198 t
The inspector noted that the Technical Specifications had been recently changed to read " efficiency" instead of " penetration and bypass leakage" as originally (and correctly) stated (Example: TS 4.7. on page 3/4.7-15). The
_
tests specified in ANSI /ASME N510-1980 are very clearly and specifically identified as " leak tests" and the standard clearly states that these are not efficiency tests.
The applicant would be technically in violation of the Technical Specifications if a test recognized only as a leak test were to be used to quantify " efficiency."
.
The ventilation exhaust filter treatment systems will be further reviewed at the next inspection.
No violations or deviations were identified.
8.
Liquid Radwaste Process Systems (84523)
The inspector discussed the liquid radwaste system with applicant personnel, reviewed drafts of proposed procedures, reviewed system operator training, and walked down the system accompanied by an applicant representative.
The liquid radwaste system originally proposed in the FSAR was a conventional mix of evaporators, ion exchange demineralizers, and filters.
By FSAR amendment, the applicant revised the proposed system to incorporate a new facility featuring a fluidized bed system to produce a dry product from liquid radwaste and a reverse osmosis (RO) system for purification of low level liquid radwaste.
Completion of construction of the facility and systems was later postponed pending evaluation of ongoing tests of these systems by other utility groups.
By further amendment of the FSAR, construction of an interim waste processing facility was indicated.
The interim facility will use conventional ion exchange demineralizers for treatment of non-reactor grade liquid radwaste.
This facility will incorporate waste storage space, packaging of dry active waste (DAW) and the collection and packaging for shipment of expended radioactive resins.
The inspector estimated that the interim facility was approximately three to four weeks away from completion at the time of the inspection.
The liquid radwaste operating group, at the time of the inspection, consisted of the Radwaste Supervisor, a radwaste engineer, a laboratory supervisor, two foremen and 13 operators.
A review of training records of operators showed the specified training to be from 50% to 80% complete, with
" hands-on" training on the demineralizer system of the Interim Waste Process Facility to be provided at an early date by the system vendor.
The applicant's objective is to have eight operators fully qualified by the projected December fuel load date.
The liquid radwaste system will be reviewed in greater detail at a later
'
date.
No violations or deviations were identified.
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-
_ I
9.
WasteGasSystems(84524)
The inspector discussed the waste gas systems with applicant personnel. Two
,
acceptance tests being run on the system at the time of the inspection will be reviewed at a later date.
Operating procedures had not been formally approved and will be reviewed at a later date.
No violations or deviations were identified.
.
10. Applicant Action on Previously Identified Inspector Followup Items (92701B)
(Closed) IFI 50-424/86-32-01:
Revise Procedure 3000-C, Step 6.5, to delete reference to concentrating liquids as a way to improve LLD.
The applicant made appropriate changes to the procedure mentioned above.
This item is considered closed.
(Closed) IFI 50-424/86-32-02:
Evaluate an acceptable alternative to reporting zero in the Semi-Annual Effluent Release Reports.
The inspector reviewed procedure 36025-C, Sen.1-Annual Effluent Release Report Preparation, and noted that zero would be defined in the Semi-Annual Effluent Reports as being less than the analytical lower lirait of detection.
This item is considered closed.
.
-
i
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. Green, Plant Manager
- P. D. Rice, Vice-President, Project Engineering, Corporate
- H. P. Walker, Operations Assistant to Senior Vice President
- C. E. Belflower, QA Site Manager
- D. F. Hallman, Chemistry Superintendent
- A. Desrosiers, Health Physics Superintendent
- S. C. Ewald, Manager, Radiological Safety, Corporate
- W. C. Gabbard, Regulatory Specialist A. Stalker, Chemistry, Corporate W. F. Jocher, Laboratory Supervisor W. Carter, Countroom Foreman M. J. Kurtzman, Supervisor, Health Physics and Chemistry Training S. J. Connor, Senior Methods and Training Specialist P. E. Jackson, Plant Engineer R. C. Hand, Plant Chemist Other applicant employees contacted included engineers and technicians.
NRC Resident Inspectors
- H. Livermore, SRI - Construction
- R. J. Schepens
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 24, 1986, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection findings provided in this report.
No dissenting comments were received from the applicant.
The applicant did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Procedures (84523, 84524, 84525)
a.
- The inspectors reviewed selected portions of the following procedures that were related to radiological effluent management and in-plant radiochemical analysis.
33005-C, Determination of Gross Beta-Gamma Radioactivity, Rev. 1, March 16, 1986
.
,
3-L 33010-C, ' Determination of Gross Alpha. ' Radioactivity, Rev. 2,
March 16, 1986
33036-C, Calibration of the Ganna Spectroscopy System (draft)
33040-C, Compositing Samples Weekly, Monthly, Quarterly, Rev. O, April 9,1986.
33045-C, Preparation of Radioactive Calibration Sources, Rev. O,
' April 7 L 1986
,
.
b.
.The inspectors discussed various aspects of the procedures with the applicant and the following observations were noted:
(1)_ 33005-C, Determination of Gross Beta-Gamma Radioactivity:
The inspector noted that -in ' Step 2.1, a calibration was defined as establishing a voltage. plateau.
Technically, a calibration involves the determination of the detector's efficiency in addition to the voltage: plateau.
- Step 6.1.1 described the preparation of-a sample by mounting a filter in the planchet. The inspector did not note a calibration standard preparation procedure in 33045-C for this particular geometry. The applicant indicated that this portion of the procedure would be deleted.
- (2) 33010-C', Determination of Gross Alpha Radioactivity:
Step 6.1.1 of this procedure also described the preparation of a sample by
'
mounting a filter in the planchet.
Similarly, a calibration -
source preparation procedure ir. 33045-C for this type of geometry was not noted.
If. this type of geometry is to be used, filter standards for alpha / beta counting should not be prepared by absorption 'of the liquid onto the filter since self-absorption would be significant and the standard may not be reproducible.
The applicant irdcated that this portion of the procedure would te deleted since this particular geometry was not going to be used.
Additionally, the inspector did not note a self-absorption study for gross alpha measurements.
The applicant indicated that this study was in progress.
(3) 33036-C, Calibration of the Gamma Spectroscopy System for Radiochemistry (draft):
The inspector noted that the procedure should list the sources, associated geometries, and the activity levels used for calibration including the mixed gamma calibration check source. The inspector also noted that there was no apparent provision to compare new efficiency data with the previous ef ficiency. data.
Additionally, the inspector and an applicant representative discussed ' plotting the experimentally-determined efficiency data points along with the fitted efficiency data points to aid in identifying bad data.
The inspector also discussed gas calibrations and noted that for initial gas calibrations, the validity of the gas transfer process should be evaluated.
Also, during the procedure review, the inspector did
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not note any formalized requirement for independent review, verification, and sign-off of data by an individual other than the one performing the calibration.
The applicant acknowledged the inspector's comments.
(4) 33045-C, Preparation of Radioactive Calibration Sources:
The inspector noted that liquid standards should be prepared by weighing the sample, since standards are calibrated in terms of activity per unit mass. Additionally, it was noted that there was no specification in the procedure for the preparation of evaporated liquid samples on metal planchets.
The applicant acknowledged the inspector's comments.
The items mantioned above will be reviewed in greater detail during a subsequent preoperational quality assurance and confirmatory measurements inspection.
No violations or deviations were identified.
4.
Laboratory Facilities (84525)
At the time of this inspection, the radiological counting laboratory was not operational due to construction activities within the laboratory facility.
The laboratory was scheduled to become operational again during the week of October 27, 1986. The inspector noted that a laboratory supervisor had been hired since the last inspection whose duties included the management of the radiological counting laboratory.
A newly hired counting room foreman who was directly involved with the counting laboratory reported to the Laboratory Supervisor.
Discussions with laboratory management concerning personnel qualifications indicated that lab technicians would have a minimum of a two-year associate degree in science or engineering.
Presently, six senior technicians and two foremen had been trained. The applicant plans to have a total of 12 technicians qualified to operate the equipment in the counting laboratory.
It was noted that many of the counting room technicians had minimal or no nuclear plant experience.
There was no apparent established mechanism to send the inexperienced personnel to other nuclear plants in order to gain experience. The inspector briefly reviewed the training program provided for the counting room technicians, which was administered by the applicant's Corporate Training Center.
The following three course subjects were offered to the technicians:
(1) Nuclear Data's data base management system; (2) principles and practices of preoperational counting and scintillation counting; and (3) principles of gamma ray spectroscopy, which included description and setup of electronic equipment, computer description and capabilities, spectroscopy software, and spectroscopy procedures.
The inspector noted that the applicant needs to pursue aggressively its efforts in establishing an operational counting laboratory with adequately trained technicians to operate the equipment in order to support the startup schedule.
The inspector discussed the NRC's confirmatory measurements inspection program with applicant representatives including the use of the Region II
,
_ _.
_
_
,-
-
.
- - -
...
-
-
.:
,
~ -
f
-
Mobile Laboratory.
In particular, specifications for parking arrangements and utility services were discussed. One location for the Mobile Laboratory should be as close as practicable to the facility countroom which would be used during routine inspections.
One advantage of locating the Mobile Laboratory within the protected area is the ease of transporting radioactive samplesofrom the plant to the Mobile Laboratory. The second location should be near the emergency operations facility and would be used during emergency
~ ituations.
The vehicle dimensions are approximately 30 feet long, eight s
feet wide,-and 14 feet tall.
Electrical service should include three lines with separate circuit breakers each with 120 volts, 30 amps located within 25 feet of the Mobile Laboratory. The receptacles should be compatible with Hubbell 125 volt, 20 amp three prong twist lock plugs.
One standard telephone outlet within 25 feet of the Mobile Laboratory should be provided.
Additionally, the inspector discussed some of the elements of the Quality Assurance and Confirmatory Measurements inspection program and informed laboratory personnel that spiked samples would be submitted for analysis during the next inspection.
No violations or deviations were identified.
5.
Post Accident Sampling System (PASS) (84523)
The inspectors discussed the Post Accident Sampling System (PASS) with applicant personnel and performed a walkdown of the system in the company of an applicant representative.
The PASS was a Sentry Model 8 system.
Separate systems have been provided for Units 1 and 2.
Preoperational inspections of the PASS were not completed as of the end of the inspection and had been scheduled for approximately October 31, 1986.
Results of the preoperational tests will be reviewed during the next inspection.
No violations or deviations were identified.
6.
' Process and Effluent Radiological Monitoring and Sampling System (PERMSS)
(84523,84524)
,
d The Process and Effluent Radiological Monitoring and Sampling System
,
(PERMSS) was discussed in meetings between the inspector, applicant personnel, and contract personnel.
All plant gaseous effluents will be released through a common stack which discharges to the environment from a
'
point near the top of the dome of the containment building. The stack has a nominal rectangular cross-section of five feet by ten feet and has a design volumetric flow of 200,000 scfm.
Three sample collection systems are provided for monitoring gaseous j
effluents.
The sampling heads are located approximately 38 feet downstream
-
of the last vent system feeding.into the main vent.
Each sampling system has four collecting nozzles in one line across'the approximate center of the duct.
One sample line is for collection of normal operation samples; the-other two are for the accident range monitor.
Flow tests and vent stack profiles will be run at a later date when all ventilation systems are
'
.
As of the date of the inspection, only about one-half of the systems had been balanced and made operable.
The containment atmosphere particulate air monitor used for detection of primary coolant in containment takes its sample through a 3/4" diameter stainless steel tube.
Isolation valves on this system, at the time of the inspection, were being replaced with gate valves to minimize flow distortion in the sample-line and therefore, the sample line had not been declared operable.
Liquid effluent monitors were provided for four effluent lines:
processed radwaste liquids, turbine building drains, steam generator blowdown, and service water.
These monitors had removable liners to facilitate decontamination.
Preoperational tests of the PERMSS had not bean completed as of the end date of this inspection. A detailed review of all aspects of
'
the PERMSS will be conducted during the next inspection.
No violations or deviations were identified.
7.
Ventilation Exhaust Filter / Charcoal Treatment Systems (84524)
The inspector discussed the ventilation exhaust HEPA filter and charcoal adsorber treatment systems with applicant personnel and walked down several of the systems in the company of an applicant representative.
Engineered safety -feature systems were supplied by American Air Filter (AAF)
Corporation. None of these systems had been loaded with filters or charcoal at the time of the inspection.
The inspector noted that all filter system drains had been capped to prevent bypass leakage and that inadvertent flooding had been prevented by the use of removable spool pieces or reversible " spectacle" flanges which required deliberate manual action to complete the path for water to enter the deluge system. All units are designed for four inches of charcoal adsorber and are of the bulk load type.
The applicant expressed some concern over the use of flat door gaskets physically mounted on the body frame rather than being fitted to the door, as is the more common practice.
System leak tests, however, indicated adequate sealing characteristics.
All systems have been balanced using blank-offs in place of filters to simulate filter loading; this practice is acceptable under ANSI /ASME N510-1980.
Workmanship of the filter systems appeared good.
Substantial bulges were observed in the charcoal retaining screens of all of the MSA systems; this is attributable to the wide spacing between support elements and has not been a serious problem at other installations.
The filter systems are scheduled to be loaded with HEPA filters and charcoal starting November 1,1986.
As systems are loaded, they will be checked for leakage and possible bypass by contractor (NUCON) personnel using the tests specified in ANSI /ASME N510-1980.
,
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_ _ _ _..,
.
,
.
The inspector noted that the Technical Specifications had been recently changed to read " efficiency" instead of " penetration and bypass leakage" as originally (and correctly) stated (Example: TS 4.7. on page 3/4.7-15). The tests specified in ANSI /ASME N510-1980 are very clearly and specifically identified as " leak tests" and the standard clearly states that these are not efficiency tests.
The applicant would be technically in violation of the Technical Specifications if a test recognized only as a leak test were to be used to quantify " efficiency."
The ventilation exhaust filter treatment systems will be further reviewed at the next inspection.
No violations or deviations were identified.
8.
Liquid Radwaste Process Systems (84523)
The inspector discussed the liquid radwaste system with applicant personnel, reviewed drafts of proposed procedures, reviewed system operator training, and walked down the system accompanied by an applicant representative.
The liquid radwaste system originally proposed in the FSAR was a conventional mix of evaporators, ion exchange demineralizers, and filters.
By FSAR amendment, the applicant revised the proposed system to incorporate a new facility featuring a fluidized bed system to produce a dry product from liquid radwaste and a reverse osmosis (RO) system for purification of low level liquid radwaste.
Completion of construction of the facility and systems was later postponed pending evaluation of ongoing tests of these systems by other utility groups.
By further amendment of the FSAR, construction of an interim waste processing facility was indicated.
The interim facility will use conventional ion exchange demincralizers for treatment of non-reactor grade liquid radwaste.
This facility will incorporate waste storage space, packaging of dry active waste (DAW) and the collection and packaging for shipment of expended radioactive resins.
The inspector estimated that the interim facility was approximately thrca to four weeks away from completion at the time of the inspection.
The liquid radwaste operating group, at the time of the inspection, consisted of the Radwaste Supervisor, a radwaste engineer, a laboratory supervisor, two foremen and 13 operators.
A review of training records of operators showed the specified training to be from 50% to 80% complete, with
" hands-on" training on the demineralizer system of the Interim Waste Process Facility to be provided at an early date by the system vendor.
The applicant's objective is to have eight operators fully qualified by the projected December fuel load date.
The liquid radwaste system will be reviewed in greater detail at a later date.
No violations or deviations were identifie,
.
-9.
Waste Gas Systems (84524)
The inspector dise.ussed the waste gas systems with applicant personnel. Two acceptance tests being run on the system at the time of the inspection will be reviewed at a later date.
Operating procedures had not been formally approved _and will be reviewed at a later date.
No violations or deviations were identified.
10. Applicant Action on Previously Identified Inspector Followup Items'(92701B)
(Closed) IFI 50-424/86-32-01:
Revise Procedure 3000-C, Step 6.5, to delete reference to concentrating liquids as a way to improve LLD.
The applicant made appropriate changes to the procedure mentioned above.
This item is considered closed.
(Closed) IFI 50-424/86-32-02:
Evaluate an acceptable alternative to reporting zero in the Semi-Annual Effluent Release Reports.. The inspector reviewed procedure 36025-C, Semi-Annual Effluent Release Report Preparation, and noted that zero would be defined in the Semi-Annual Effluent Reports as being less than the analytical lower limit of detection.
This item is considered closed.