IR 05000424/1990014

Insp Repts 50-424/90-14 & 50-425/90-14 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected: Radiological Effluents,Environ Monitoring,Plant Chemistry & post-accident Sampling Sys

ML20055H611
Person / Time
Site:	Vogtle
Issue date:	07/02/1990
From:	Adamovitz S, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20055H608	List: IR 05000424/1990014 ML20055H607
References
50-424-90-14, 50-425-90-14, IEIN-90-020, IEIN-90-20, NUDOCS 9007270083
Download: ML20055H611 (13)

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UN11 ED ST ATES

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/ pn nef NUCLEAR REGULATORY COMMIS$10N :

.[ g REGION 11

. ;! ' O 101 MARIETTA STREET, N.W.

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• If' ATI.ANTA, GEORGI A 30323

.;...*! JtJt. 0 61990 Report Nos.: 50-424/90-14 and 50-425/90-14 Licensee:- Georgia Power Company-P. O. Box 1295 Birmingham, AL 35201-Docket Nos.: 50-424Tand-50-42 * License.Nos.: NPF-68 and NPF-81 Facility Name: Vogtle'1.and 2

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Inspection Conducted: -June'11-15, 1990 Inspector: ./Yd?M//K 45A b'9 9 0 5. S. Adamov tz g ______

Cate Jidgned Approved by: MN4 / MAb

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7/,2/hd T.R.DecFeE~tiile? Date Signed Radiological. Effluents and Chemistry Section Nuclear Materials Safety and Safeguards Branch  ;

Division of. Radiation Safety and Safeguards i

.i SUMMARY I Scope:

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This routine, unannounced inspection was conducted in the areas of radiological effluents, environmental monitoring, plant chemistry, and the post ~ accident

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sampling (PAS) system Results: ,

In the areas inspected, violations or. deviations were~not identifie ~

The licensee's program to control and monitor liquid and gaseous radioactive effluents had been effectively implemented (Paragraphs 2, 3, 4,'and 5). Liquid and gaseous effluents and the resulting doses were maintained _ within Technical Specifications (TSs),10 CFR 20; and 40 CFR 190 limitations. ' Liquid fission  ;

and activation products had decreased by 75 percent during 1989 (Paragraph 2).- 1 The status of the Process and Effluent Radiation Monitoring System (PERMS)

maintenance program and the out-of-service -(00S) channels was discussed (Paragraph 3). During 1989, the licensee had significantly reduced the number ,

of 00S channels and had maintained this number during 199 j The Units' I and 2 PAS' systems. were examined (Paragraph 6). Due to continued operability problems with the systems, the inspector requested that a program and schedule be established to improve overall system reliability. Two IFIs .

were identified in this are '

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.An -:inhouse emergency response- drill was observed and theiobservationsicentered'- 1

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' upon operation of the PAS system (Paragraph 7).

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Selected:. primary and secondary chemi.stry i (Paragraph 11). Low dose equivalen iodine (parameters

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wereH reviewedDEI)' values

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cladding integrit "

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REPORT DETAILS-

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1. - Persons Contacted , ;

Licensee Employeesu ,

'*J. Aufdenkcmpe, Manager, Technical: Support o

• H. Beacher,-Senior Engineer, Technical Support P.. Berwinkle. Plant Engineering Superviso L. Clark, Health. Physics Specialist,. Chen.istry

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S. Conner, Senior Nuclear' Specialist '

• D. Hallman, Superintendent Chemistry G. Jeffers, Rad' Waste Foreman ' .

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• S.. Kitchens, Assistant General Manager, Operation * Kochery, Superintendent _ Health Physics R. Lee, Chemistry Supervisor ..

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R. ~LeGrand, Manager, Health Physics and Chemistr '

• M. Odom, Health Physics / Chemistry Specialis '

• R. Odom, Plant Engineering Supervisor D. Schreiber, Radwaste Supervisor, Operations

• J. Sills, Laboratory Supervisor

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Nuclear Regulatory Commission

• L. Trocine i

• Attended exit interview Semiannual Radioactive Effluent Release Report (84750)L Technical Specification (TS)_ 6.8.1.4 requires the licensee Lto submit Semiannual Radioactive Release = Report within 60 dayshafter January 1 and

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July 1 of each year covering the operation of the facility during the <

previous six months of operatio The inspector reviewed the Semiannual Radioactive Effluent Release Report '

for July - December 1989 and' discussed; the. report with licensee:

representatives. The -effluent information presented in ' Table A' was obtained from current and previous effluent report .

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Table A-Effluent Release and Dose Summary for Vogtle '

t StivityReleased(curies)

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• 1988' 1989 Gaseous Effluent ..

Fission and Activation Products 1.15E+2 5.48E+2 lodines and Particulates 1.75E-5- 1.26E-3 S

Tritium 8.33E+1- .9.10E+2 1 1 ui Qqui,d_ Effluents-

Fission and Activation Products 1.66E0 4.07E-1 1

Tritium 3.90E+2 9.18E+2 1 DoseEstimates(mred Gaseous Effluents - Noble Gas Exposure d. si Whole Body 2.69E0 '8.23E-3 l Skin 4.85E0 2.01E-2' Liquid Effluents Whole Body 1.74E-2 2.93E-2

• 0nly Unit I was in operation during 1988 .

In general, 1989 gaseous effluents increased as compared to 1988 values,

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and this increase was attributed to the startup of Unit.2. Liquid fissio and activation products decreased by 75 percent during 1989 andithe-licensee attributed this decrease to improved processing, recycling:

liquids as appropriate, and daily monitoring of inleakage rates, y Liquid - :j and gaseous effluents and the resulting doses were well within TSs,1 10 CFR 20, and 40 CFR 190 effluent limitation <

The Semiannual Effluent Report covering the last six months of 1989 did-not identify any abnormal releases or effluent monitors inoperable for i;

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greater than 30 day The inspector concluded that the TS reporting requirements regarding the effluent report had been met and that the releases were within TS and regulatory requirement w -i

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No violations or deviations were identifie . Effluent Monitoring Instrumentation (84750) TSs 3/4.3.3.9 and 3/4.3.3.10 define the operating and surveillance requirements for monitors of radioactive liquid and gaseous effluent stream The inspector, accompanied by a licensee representative, toured selected effluent monitoring stations and and verified the operability of monitor read outs in the control room. The inspector reviewed monitor calibration and functional test packages for the following monitors:

2-RE-018 Waste Liquid Effluent Monitor, May 24, 1990 2-RE-12442 Plant Vent Air Monitor including particulate, iodine, and noble gas detectors, Apri' ?5,1990 1-RE-018 Weste Liquid Effluent Monitor, October 16, 1989 1-RE-12442 Plant Vent Effluent Monitor including particulate, todine and noble gas detectors, February 12, 1990 The examined records appeared complete and the calibrations were performed within the required time perio In rev, ewing the calibration packages and selected procedures, the inspector noted that the percent tolerance for the target count rate of the transfer standards varied among detectors. The licensee provided the inspector with the supporting documentation for the f

varying tolerances per a utility memo entitled " Calibration of the Process and Effluent Monitoring System," dated August 24 1988. The memo discussed earlier problems of non-uniform response w,ith the beta scintillator detector Plastic beta scintillator tubes, used for particulate and noble gas radionuclide detection, had not been manufactured with uniform layers of mylar. The mylar was used to protect the scintillator crystal f 9m damage and the non-uniform layers of mylar caused differing responses among the detectors. As a result, the licensee returned the beta scintillator tubes to the manufacturer for refurbishment and then the licensee performed onsite primary and transfer calibrations. The target count rates with the associated uncertainties for the transfer standards resulted from these measurement Sio11ar measurements were performed for the sodium iodide liquid monitors to identify the target count rates for the transfer source The inspector observed portions of the channel calibration for the component cooling water process monitor, RE-0017A. An approved procedure, 34208-C " Channel Calibration of the Liquid DRMS Monitors," '

Revision 6, December 11, 1989, was used, and Cs-137 and Co-60 were l

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used as the transfer sources. The calibration process had to be terminated prematurely due to inadequate monitor response in the upper voltage range. The inspector noted that the technician-was knowledgeable of the procedure, past detector performance anti expected detector response, During 1987 and 1988, the licensee had experienced recurrent problems with out-of-service (OSS) monitors due to failed components. In a previous inspection report (50-424/89-28 and 50-425/89-32), the licensee's corrective actions to effectively reduce the number of 005 channels were discussed. Durinq 1988, the number of 005 channels for Unit I and common channels averaged 23 out of a total of 76. During 1989, this number was reduced to an average of eight 005 channel Unit 2 OOS channnis averaged six for 1989 out of a total of-54 channel During the current inspection, the inspector reviewed weekly PERMS status reports for April - June,1990. The total number of 005 channels for both units ranged from four to_ ten during this time period. The inspector concluded that the licensee's program to minimize the number of 005 channels had remained effectiv No violations or deviations were identifie . LiquidandGaseousReleases(84750)

TSs 3/4.11.1.1 through 3/4.11.1.4 define the operating requirements, radioactive effluent limits and surveillance requirements for the liquid radwaste treatment system TSs 3/4.11.2.1 through 3/4.11.2.6 define the operating requirements, radioactive effluent limits, and surveillance requirements for the gaseous radwaste treatment systems, The inspector, accompanied by a cognizant licensee representative, toured the Auxiliary Radwaste Building (ARB) and the associated control room. The two 20,000 gallon capacity Waste Monitor Tanks (WMTs) were not used during the latter part of 1989 due to inoperable i pumps. New pumps had since been installed during 1990 and the tanks were currently in service. The two 20,000 gallon WMTs, in addition q i

to the four 5,000 gallon WMTs, previded extra storage capacity for I the treated liquids and allowed reprcressing in order to minimize radionuclide concentrations in the liquid discharge A temporary microfiltration unit had been installed for Unit 1 to. aid !

in particulate removal. Permanent installation of a microfilter was currently being discussed with the vendor, The inspector reviewed seven 1990 liquid waste release permits and seven 1990 gaseous waste release permits. The examined packages appeared complete per procedural requirement No violations or deviations were identifie ,

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Leak Testing of High Efficiency Particulate Air (HEPA) Filters and

' Charcoal Absorbers in Ventilation Treatnent Systems (84750)

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TSs 3/4.7.6 and 3/4.7.7 define the operating and surveillance requirements for HEPA filter and charcoal adsorber systems. The inspector reviewed the .

test packages and results of in-place leak tests, nethyl iodide laboratory e tests, heater tests and visual inspections for the following systems:

Normal Containment Purge - Unit 1:

February 28, 1990 (in-place HEPA leak test and methyl iodide ,

laboratory test)

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Piping Penetration Filter IA:

February 1, 1990 visual inspection)

February 6,1990 heater test)  ;

February 7, 1990 in-placeHEPAandcarbonleaktests)

February 9, 1990 methyl iodide laboratory test)

Piping Penetration Filter IB:

January 30, 1990 heatertest) '

January 31, 1990 methyl iodide laboratory test)

February 1, 1990 in-placeHEPAandcarbonleaktests)

Fuel Handling Building Filter B:

Junuary 17, 1990 methyl iodide laboratory test)  :'

January 18, 1990 visualinspection)

January 22, 1990 in-placeHEPAandcarbonleaktests;heatertest) :

Control Room filter 2A:  !'

February 7, 1990 (methyl iodide laboratory test)

February 13,1990(visualinspection)

i february 22, 1990 (in-place HEPA and carbon leak tests)

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The inspector noted that laboratory testing of the charcoal was conducted

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at 30*C and 70 percent humidity per TS requirements. From discussions with licensee reatesentatives and review of the referenced tests, the .

inspector concluced that the filter testing program was being implemented according to TS requirements.

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No violations or deviations were identified.

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6. PostAccidentSampling(PAS) Systems TS 6.7.4.9 provides for the establishment, implementation, and 1 maintenance of a PAS syste The inspector discussed PAS system !

operation and maintenance experience with licensee personne Operation and maintenance of- the Units' I and 2 PAS systems for liquid and gaseous sampling was the responsibility of the Chemistry department. The systems had the capability to collect liquid samples of reactor conlant or containnent sump, and in-line monitoring was '

provided for pH, chloride, boron, dissolved hydrogen and isotopic

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analyses by gamma spectroscop The PAS systems for Units 1 and 2 previously contained inline monitors for dissolved oxygen but these i had been subsequently removed due to operational problems. The :

licensee had experienced continuous operational problems with var'ous components of both PAS systems ene had assigned a Chemistry -

Specialist fulltime to the systems. The inspector observed oper6 tion

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of the Unit 2 system twice, (one operation wes part of an emergency ;

response drill); reviewed test packages, and maintenance work order for both systems; and discussed the overall system operabilit !

testing with licensee representative ;

Earlier in 1990, the licensee had determined the cause and corrected I a problem with inconsistent automatic dilution of liquid samples by ;

increasing the system nitrogen injection pressure from one pound to

- two and half pounds. This increase in the injection pressure ensured that all of the dilution volume was delivered to the mixing chambe ,

A second problem involved hydrogen analyses of degassed reactor coolant. Inconsistent hydrogen results between PAS system samples as compared to normal coolant samples were recorded. Also continuously decreasing hydrogen results for one sample as determined by the PAS !

system inline gas chromatograph were noted. The licensee identified I and repaired leaks throughout the PAS system which corrected the problem of decreasing hydrogen results. Further steps to resolve the differences between the PAS system and normal coolant hydrogen analyses included the determination of a minimum mixing time within '

the PAS system; the identification and isolation of a specific area within the panel in which to degas the liquid; and the elimination of ,

reactor coolant flow throughout the remaining portion of _ the panel, when the liquid sampled was being degassed. The licensee had ,

determined that allowing liquid flow through the remaining portion of the panel, when degassing the coolant sample, seemingly created a venturi effect for the gaseous portion and decreased the hydrogen ,

concentration. The inspector noted that the majority of the work had been performed on Unit 2 and an inspector followup item (IFI) had '

been previously identified for Unit 1 (50-424/87-68-02) concerning the PAS system hydrogen results. The insSector determined that since the Units 1 and 2 PAS systems were identtcal, the 1987 IFI would be closed based open the work that had been done to determine and ,

correct the cause of the low hydrogen results. However an IFI for both units was identified to review the results of the hydrogen anclyses for the Units 1 and 2 PAS systems (50-424, 425/90-14-01).

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The PAS systems' inline boron analysers and gas chromatographs for hydrogen analyses exhibited consistent problems with failed electronic boards. The licensee had not conclusively identifjed the '

source of the problem and estimated that failed boards occurred every couple months in the Unit 2 boron analyzer. During the course of the ,

current inspection, the licensee was able to perform inline boron analysis using the Unit 2 system. Additionally both units had-experienced failed containment isolation valves (valve No. 8220) to the PAS panels which contributed to the systems' inoperability. In-order for the valves to seat properly, periodic inking and !

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resurfacing were required. New valves for both units had been ordered but installation required outage condition The inspector observed operation of the Unit 2 PAS system twic l During both instances, the licensee was able to obtain a dilute grab t sample and comparable gama spectroscopy results between the PAS '

system sample and normal reactor coolant. The PAS system inline gamma spectroscopy system was not used for the game isotopic analysis. The dilute PAS sample was counted in the Chemistry count ;

room using a calibrated liquid geometry. For one of the two tests which the inspector observed, the Unit 2 inline boron analyzer was operational and the results compared well with normal reactor coolant number An IFI had been identified for the Unit 2 PAS system (50-425/88-70-01) to evaluate the panel's performance and the IFI was closed based upon the observed tests. However, the inssector and licensee discussed the need to maintain increased attentdon to these ,

system Progress had been made in specific problem areas ( inconsistent results, inoperable inline monitors, system leaks) but overall system operability was not cofr;istently maintained. The licensee agreed to implement a program and time schedule to improve overall system reliability and the iaspector informed the licensee that review of this program would be considered an IFI (50-424, 425/90-14-02).

b. The inspector reviewed the following procedures for PAS system operation:

35611-C Remote Operation of the Post Accident Sampling Syste Revision 11. April 9, 1990 35614-C Local Operation of the Post Accident Sampling System, Revision 6, August 2, 1989 35615-C Remote Operation of the Post Accident Sampling System Under Accident Conditions, Revision 11. May 23, 1990 j 35620-0 Local Operation of the Post Accident Sampling System (PASS)

After an Accident, Revision 7, January 30, 1989 35623-0 Gamma Spectroscopy Data Acquisition and Analysis for the Post Accident Sampling System, Revision 1, April 14,1987

35626-C Calibration. Troubleshooting, and Verification of the PASS '

i Panel pH Monitor, Revision 2. January 6, 1988 35627-C Calibration, Troubleshooting, and Verification of the PASS Boron Analyzer, Revision 5, October 6, 1988 35630-C Calibration of Gamma Spectroscopy System for the Post Accident Sampling System, Revision 5, August 2,1989

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31010-C Process Analyzer Calibration Scheduling Program, l Revision 9. May 10, 1990  ;

The inspector noted that the procedure 35630.C " Calibration of Gama ,

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Spectroscopy System for the Post Accident Sampling System" referenced a procedure, 35636-C " Gamma Spectroscopy Quality Control for the Post Accident Sampling System " which had previously been deleted from the station's procedures. The licensee agreed that the procedure 35630-C i needed revising in order to remove references to the deleted procedur Two IFIs were' identified:

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50-424, 425/90-14-01: Review the results of tb hydrogen analyses for both units' liquid PAS system I 50-424, 425/90-14-02: Review the Chemistry department's implementation of a program and time schedule to improve overall PAS system reliabilit No violations or deviations were identifie , Emergency Response Drill (84750)

The inspector observed portions of an inhouse emergency response drill that was conducted by the licensee in preparation for a planned full scale :

dril The inspector's observations were centered upon operation of the PAS system and subsequent sample analy:,1s. The licensee was able to obtain a diluted grab sample from the Unit 2 PAS system and perform inline boron analysis. The grab sample was successfully analyzed in the backup HealthPhysics(HP)countroomforgammaisotopicanalyses. The backup HP count room was utilized since the Chemistry count room was declared off limits due to high dose rates per the exercise scenario. The licensee had also initiated steps for transportation of the liquid sample offsite to a vendor laboratory and verified the laboratory's contact numbe No violations or deviations were identifie . InformationNotice(92717)

The inspector reviewed the Notice 90-20; " Personnel Injuries Resulting from Improper Operation of Radweste Incinerators" with licensee personne The notice had been received and distributed to the appropriate groups for information and evaluatio No violations or deviations were identifie . CountingInstrumentation(84750) )

The inspector discussed a recent incident at a waste facility where an incorrect detector efficiency had been used due to source strength assurrption errors for the strontium-90 (Sr-90) radioactive standard. The o

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i certificate of activity supplied by the source manufacturer did not l include the activity contribution from the strontium daughter product, yttrium-90 (Y-90), which was equal to that of the Sr-90. This resulted in an instrument beta efficiency that was twice the correct value and i subsequently underestimated the beta activity by a factor of two. The inspector vetermined that inplant count rooms did not use Sr-90 as a calibrati(n source but as a check source in certain instances. The licensee noted this information for possible future us .

No violations or deviations were identifie i

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10. Environmental Monitoring (84750)

TS 3/4.12.1 defines the sampling and analytical requirements for the I plant's radiological environmental monitoring program. The inspector !

reviewed the licensee's Environmental Report for 1989. The licensee's t evaluation of the environmental data identified an upward trend for :

tritium levels in river water as compared to previous calendar years- '

(CYr). The average control and indicator values for CY 1989 were reported as 538 pC1/1 and 1,293 pCi/1 respectivel maximally exposed individual (a child) y, and was an annual calculated organ to be dose 0.087 to the mrem (0.78 percent of the TS limit). Tritium was also identified in drinking '

water quarterly composites and the licensee indicated similar results had been obtained in previous years. Average 1989 tritium levels at the intake and discharge for the indicator water treatment plant were reported as 2,249 pC1/1 and 1,977 pC1/1 respectively, after correcting for <

background levels. The water treatment plant was located more than a hundred miles downstream of the plan Activation products were identified in downstream sediment samples at levels slightly lower than CY 1988 values. A whole body dose by direct radiation was calculated to be 0.0026 mrem per year (0.087 percent of the TS limit). Although not required by the- plants' TSs. the licensee also gathered aquatic vegetation samples at upstream and downstream river ,

locations. Similar to the sediment samples, activation products (Mn-54, '

Co-58, and Co-60) were identified in downstream samples. Since these isotopes were not found in the control samples, the licensee concluded 1 that these isotopes were due to Plant Vogtle release No violations or deviations were identifie . Plant Chemistry (84750) Reactor Coolant System TSs 3/4.4.7 and 3/4.4.8 specify the requirements for reactor cuolant system chemistry. The inspector reviewed trend plots of Units 1 and 2 various coolant chemistry parameters. During 1990, reactor coolant chloride was typically maintained below 10 parts per billion (ppb)

and fluoride was maintained below 20 ppb for both units. These values were well below the TS steady state limits of 150 ppb. Over l

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the past twelve months, Units' I and 2 dose equivalent iodine (DEI)

values typically ranged from 2E-4 uCi/ gram to 9E-4 uC1/ gram' during steady state conditions. These numbers were well below the TS limit of I uCi/gm and indicated good fuel integrit Steam Cycle Chemistry i

Dissolved oxygen (DO) concentrations in the condensate pump discharge were tracked as an indication of circulating water inleakag A review of data for the past twelve months showed that the D0 values typically remained at or below 10 ppb during power operation A review of other selected secondary chemistry paraneters for the past twelve months indicated that the secondary chemistry values, except for minor transients, were maintained within the guidelines recommended by the Steam Generators Owners' Group. Unit I steam i generator (SG) blowdown cation conductivity typically ranged from 0.1 umho/cm to 0.3 umho/c After initial elevated cation s conductivity values due to unit start-u), Unit 2 levels decreased to approximately 0.3 umho/cm. Chloride anc sodium concentrations in the SG blowdown were nornially maintained below 20 ppb. Sulfate levels in the SG blowdown were typically I to 2 ppb for Unit I and less than 5 ppb for Unit No violations or deviations were identifie . LicenseeActiononPreviouslyIdentifiedInspectorFollowupItems(92701) (Closed) IFI 50-424/87-68-02: Review resolution of low hydrogen / dissolved gas analysis results in primary coolant PAS system sample Details for this item are discussed in Paragraph 6 of this repor Based upon the licensee's actions to identify and correct the cause of the low hydrogen results, this- item is considered closed, (Closed)IFI 50-425/88-70-01: Evaluate performance of the PAS system after 30 days operation of reactor at full power. Details for this item are discussed in Paragraph 6 of this report. Based upon the two PAS system tests that the inspector observed, this item is considered t close '

1 Exit Interview ,

The inspection scope and results were summarized on June 15, 1990, with those persons indicated in Paragraph 1. The inspector described the areas inspected and discussed in detail the inspection results listed belo Proprietary information is not contained in this report. Dissenting I consnents were not received from the license The licensee's program to control and monitor liquid and gaseous radioactive effluents had been effectively implemented (Paragraphs 2, 3 L i l

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11 4, and 5). Liquid and gaseous effluents and the resulting doses were reintained within ' TSs,10 CFR 20 and 40 CFR 90 limitations. Liquid fission and activation products had decreased by 75 percent during 1989 (Paragraph 2).

The status of the PERMS maintenance program and 005 channels was discussed (Paragraph 3). During 1989 the licensee had significantly reduced the ,

number of 00S channels and had maintained this number during 199 The Units 1 and 2 FAS systems were examined (Paragraph 6). Due to continued operability problems with the systems, the inspector requested .

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that a program and schedule be established to improve overall system reliability. Two IFIs were identified in this are .

An inhouse emergency response drill was observed with emphasis upon operation of the PAS system (Paragraph 7).

Selected primary and secondary chemistry parameters were reviewed ,

(Paragraph 11). Low DEI values indicated good fuel cladding integrit TwoIFIsconcerningthePASsystemswereclosed(Paragraph 12).

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