IR 05000266/1985023

Insp Repts 50-266/85-23 & 50-301/85-22 on 851209-12.No Violations or Deviations Noted.Major Areas Inspected: Effluent Release Records & Repts,Effluent Control Instrumentation & Procedures for Controlling Releases

ML20141G224
Person / Time
Site:	Point Beach
Issue date:	01/03/1986
From:	Hueter L, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20141G220	List: IR 05000266/1985023 ML20141G214
References
50-266-85-23, 50-301-85-22, NUDOCS 8601100042
Download: ML20141G224 (8)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-266/85023(DRSS); 50-301/85022(DRSS)

Docket Nos. 50-266; 50-301 Licenses No. OPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Plant (PBNP)

Inspection At: PBNP; Units 1 and 2, Two Rivers, WI

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Inspection Conducted: December 9-12, 19 5 Inspector: L. J. H V M"# ** / 8 F4'

Approved By:

W//.tYN/M M. C. Schumacher, Chief i

1. #6 Radiolobical Effluents Date and Chemistry Section Inspection Summary Inspection on December 9-12, 1985 (Reports No. 50-266/85023(ORSS);

50-301/85022(DR55))

Areas Inspected: Routine, unannounced inspection of gaseous and liquid radioactive program including: effluent release records and reports of effluents; effluent control instrumentation; procedures for controlling releases; primary and secondary coolant chemistry end activity, gaseous effluent filtration, audits and review of status of previously identified violations, unresolved item and open items. The inspection involved 35 inspector-hours onsite by one NRC inspecto Results: No violations or deviations were identifie h G

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DETAILS 1. Persons Contacted

• T. Fredricks, Radiochemist C. Gates, Radwaste Supervisor J. Knorr, Regulatory Engineer

• J. Reisenbuechler, Superintendent EQRS

• J. Zack, Manager, Point Beach

• R. Hague, NRC Senior Resident Inspector

• R. Leeman, NRC Resident Inspector The inspector also contacted other plant staff during this inspectio * Denotes those present at the exit meetin . Licensee Action on Previous Inspection Findings (Closed) Violation (266/85011-03; 301/85011-03): Failure to make adequate surveys of airborne concentrations for iodines in both restricted and unrestricted areas when charcoal adsorbers were analyzed on Detector 1, which was improperly calibrated due to an error involving a calibration constant. The computer software was modified to prohibit access to the charcoal geometries in question until recalibration of these geometries was completed with procedures modified to preclude use of erroneous calibration constants. Affected data was identified and recalculated on the basis of the correct calibration constan Appropriate' corrections were made to MPC-hr data assigned to workers as appropriate and corrections to monthly effluent release reports and semiannual offluent reports were submitted to the NR (Closed) Unresolved Item (266/85011-04; 301/85011-04): Question of possible violation of regulatory limits or licensee administrative limits from use of erroneous concentrations based on use of the detector improperly calibrited for iodine. Affected data was identified and recalculated. This evaluation indicated that no administrative or technical specification violations resulted involving either personal exposures or effluent release The maximum personal exposure involved, based on the corrected data, was about 12MPC-hrs, wall balow the 40MPC-br control measur (Closed) Open Item (266/85011-05; 301/85011-05): Licensee procedures did not require comparison of like geometrias between detectors following calibration. Chemistry and Analytical Methods and Proceduro (CAMP-300),

"MCA Efficiency Calibrations " has been modified to require initial detectorcalibrationsbeverlfledbycomparinglikegeometriesofthenew detector to those of a previously calibrated detector and to log the results on Form CHP-99. Also, this procedure has been modified to require that following detector geometry recalibrations, the new energy versusefficIencycurvebeverifiedtobeconsistentwithpast calibrations for each geometr CAMP-400, " Preparation of MCA

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Calibration Standards," has been modified tc require use of separate calibration data sheets for each standard geometry made up as well as for the working standard dilution. These procedure modifications should preclude recurrence of the problem of use of an erroneous calibration constan (Closed) Open Item (266/85011-02; 301/85011-02): Amend computer file to preclude use of affected geometries and to recalibrate detector before future use. The computer file was promptly amended to preclude use of affected geometries until recalibrated. Recalibration occurred on December 5, 1985, using the mocified procedure, after receipt of a certified standard sourc (Closed) Violation (266/84-22-02; 301/84-10-01): Inadequate monitor calibrations-only one point calibrations of the liquid and gaseous process monitors were performed. The licensee disputed the violation on the basis that the monitors are inherently linear because scintillation detectors, which are utilized as the primary detection unit, have inherently negligible dead times over several orders of magnitude and, fail-high points are set lower than the level at which appreciable dead time would be expected to occu The issue was forwarded to the NRC Office of Inspection and Enforcement, who agreed that single point routine calibrations for scintillation monitors were adequate, given the monitors inherent stability and a thorough initial primary calibration. The violation was withdraw . Gaseous Effluents The inspector reviewed selected records of radioactive gaseous effluent sampling and analysis for 1985 to date and the semiannual effluent reports for the last half of 1984 and the first half of 198 The pathways sampled and analyses performed, appear to comply with the requirements of Technical Specification Table 15.7.6-2. The licensee's Offsite Dose Calculation Manual (0DCM) and Radiolog' cal Effluent Technical Specifications (RETS) became effective October 10, 198 Basically, all radioactive gaseous effluents are exhausted by one of four vents. These are the auxiliary building vents (including waste gas decay tank (WGDT) effluent and air ejector effluent), the drumming area vent (including spent fuel pool surface exhaust system), Unit 1 containment purge vent, and Unit 2 containment purge vent (including gas stripper building ventilation). Effluents from all four vents are in effect double monitored / sample Noble gas release quantification and reporting may normally be somewhat conservative, in that both air ejector effluents and WGDT effluents are quantified as individual releases and both may effectively be quantified again in terms of response of the auxiliary building vent noble gas monito Theairejectoreffluentsaretypicallyinsignificant;however, the WGDT effluents typically c:ount for 10-25 percent of total noble gas releases annually. Iodine and particulate releases in gaseous effluents may also be quantified and reported conservatively in that activity on weekly filters / absorbers is decay corrected back to start of sample

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period rather than the customary mid point of the sample period. Weekly particulate filters from all four vents are submitted monthly to a vendor for analysis for Sr-89 and 90. Tritium in gaseous effluents is accounted for weekly by collecting a sample of water from each vent using either silica gel or condensate from a dehumidifie The inspector discovered a discrepancy between plant effluent records and the semiannual effluent report data for the first half of 1985, wherein gaseous effluents (noble gases, particulates and iodines) for the month of June and, therefore, the six month totals were reported low. The discrepancy arose when an incomplete compilation made during the training af a new individual was sent by mistake to the corporate office and was printed in the semiannual report. This error was not discovered by the licensee until the discrepancy was noted during this inspection. This matter was discussed at the exit meeting. (0 pen Item 266/85023; 301/85022).

Total curies of noble gas released in the last half of 1984 and the first half of 1985, were about 62 Ci and 46 Ci respectively, or an annual average of about 54 Ci per unit well below the national average for PWR's. During this period gaseous effluents have remained below one percent of the technical specification release limi No violations or deviations were identifie . Liquid Effluents The inspector reviewed selected records and procedures associated with controlled radioactive liquid releases for 1985, to date and the semiannual effluent reports for the last half of 1984, and the first half of 198 The pathways sampled and analyses performed appear to comply with the requirements of Technical Specification Table 15.7.6- All liquid releases, both batch and continuous, are discharged by one of three monitored pathways to the circulating water discharge which in turn discharges to the lake. The three monitored pathways are the retention pond effluent (including sewage treatment plant effluent and turbine building floor drains), the Unit 1 service water return, and the Unit 2 service water return (including their respective steam generator blowdown, the four CVCS monitor tanks, the two waste distillate tanks and occasionally other batch releases handled by special permit / procedures).

Releases via the service water are also typically monitored upstream before dilution with the service wate Liquid release activity is quantified on the basis of analyses of samples collected from each batch release and samples collected twice weekly from the continuous release paths. Analyses include in-house gamma scan and

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tritium analyses, as well as monthly vendor analyses of composite samples for gross alpha and Sr-89 and 9 Liquid radioactive effluent (excluding tritium) was about 1.25 Ci per unit in 1985, about the national average for PWR's. Tritium released in liquid was about 400 Ci per unit in ,1985, which is also about the national averag This is a significant reducti'en from 1984 when 11 curies (excluding tritium) were released from the Reactor Water Storage Tank (RWST) during Unit 2 refueling, because of high silica concentration in the tan However, releases remained below one percent of the Technical Specification release limits. Also, the non tritium activity release was probably less than reported the release from the RWST was routed through the spent fuel pit polishing dimmeralizer for which no credit was take The licensee continues quarterly tritium analysis of samples collected from four different locations in the subsoil system drains. The most recent data reported (first quarter of 1985), had concentrations below MDA at two of the locations and concentrations of about SE-7 pCi/cc at the other two locatinns. The total release during the quarter by this pathway when flow ruto was taken into consideration, was about 7.3E-3 Ci of tritiu Tritium releases by this pathway have been on a decline for several year ~

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No violations or deviations were identifie . Effluent Control Instrumentation The inspector reviewed calibration records, selected set points, monthly functional tests and/or source checks for the following monitors with no problems being noted:

Waste Distillate Tanks Outlet Monitor (RE-223)

CVCS Monitor Tanks Outlet Monitor (RE-218)

Unit 1 Service Water Monitor (IRE-229)

Unit 2 Service Water Monitor (2RE-229)

Auxiliary Bdilding Vent Stack (RE-214)

Drumming,ArvayentStack (RE-221)

Calibration constants are established to relate detector readout to concentration of activity. The calibration constants are based on a one point calibration with a fluid source. The fluid sources insist of plant generated liquid or gas sources, as appropriate, fro. the primary system. The various isotopes, as well as the calibration constants, are normalized to Co-60 for liquid effluent monitors and normalized to Xe-133 for noble gas effluent monitors, in accordance with dose conversion factors and formulas specified in the recently implemented ODCH. Also, the licensee has on 16 occasions during the past year, collected and analyzed samples Vf, liquid or gaseous effluents and compared the results

, with detector response. Reasonably good agreements were obtained with the monitors responding somekhat conservatively (indicating a concentration

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somewhat higher than Indicated by sample analysis) in all case ,

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Effluent-monitors (both noble gas and liquid monitors) are set to alarm i

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nonrestricted area reaches 10 CFR 20 Appendix B Table II limits.

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- Alert setpoints are.normally set to alarm at two times established

. steady-state readings and are-intended to identify changing plant

. conditions which may need corrective actio No violations or deviations were identifie .. Primary and Secondary Coolant Radiochemistry The inspector selectively reviewed theilicensee's reactor coolant and

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secondary coolant radiochemistry results for 1985, to date to determine

compliance with technical specification requirements for coolant

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activities'and surveillance , The'most recent E bar analysis yielded 1.3 Hev/ dis for both Unit 1 and Unit 2. Primary coolant concentrations, including gross beta gamma and

, iodine-131_ dose equivalent data were reviewed for both units for 1985, to j date. All parameters remained less than applicable technical specification i limits throughout the review period. Gross beta gamma concentration of the' secondary system of both units averaged between 1E-5 and IE-8 pCi/c No discrepancies from surveillance requirements were identified.

L No violations or deviations were identified.

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7.- Air Cleaning Systems

Although technical specifications require only testing of control room filter systems, all systems are tested annually. In place filter tests

!  : and methyl iodide tests were performed on plant ventilation systems during April and May 198 The in place testing included DOP testing of HEPA

, filters,' freon testing of charcoal adsorbers and laboratory testing of charcoal adsorbers for methyl iodide removal. The ventilation systems tested include containment purge-(1F11A, 2F11A, 1F118, 2F11B), control

. room emergency ventilation (F16), auxiliary building ventilation (F20,

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F21, F23, F25, F29), drumming area ventilation (F26), combined air ejector  :

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vent (F30), and containment cleaning (1F32 and 2F32). Except for the DOP

!- tests of Unit 2 containment cleaning filter (98.8%) and combined air

. ejector vent absorber (98.7%), and freon tests of Unit 1 containment purge ,

A adsorber (96.4%), and containment purge B adsorber (98.6%), all in place '

tests indicated greater thar. 99% removal. Laboratory testing (methyl y iodide) of charcoal samples indicated greater than 90% removal except e Unit 2 containment purge (69%). The latter was replaced with a new absorber, pretested and certified by the vendor to meet ANSI-N509 criteria.

! Tests were conducted in accordance with Procedure HPIP 11.50, " Filter

' Testing" and HPIP 11.50, Appendix A, " Control Room Filter Testing."

l No violations or deviations were identifie ;

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' Audits

'An internal audit of Health and Safety. Department activities injSeptember 1985, by qualified.QA personnel was reviewed. Portions of the audit included. areas related to the gaseous and liquid radwaste program including review for compliance-with seiected technical specification requirements. Some specific areas reviewed included conversion factors used in I-131 dose equivalent calculation,Jreactor coolant system i

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isotopic analysis, secondary coolant system gross' beta gamma activity, compliance with minimizing sampling and analysis frequencies, summaries of radioactive releases, and alarm and trip set points. -No problems relating to these areas,were identified by the audi No violations or deviations were identifie . Changes to Equipment and Procedures '

o In discussion / review of changes made to procedures and equipment during ,

the past year involving the-liquid and gaseous radweste program, several o-reviewed procedures were identified and one modification requiring a'

10 CFR 50.59 revie Several revised procedures (some revised to accommodate the recently instituted C M and~RETS technical specifications) were

reviewed during the inspection. .No problems were identified. Further, in discussion with both radchem and operations personnel who are involved with the liguid.and gaseous'radwaste program, it appeared that personnel-were adequately trained and'knowledgable in radwaste procedures and related-equipment, including monitors. TP modification involved relocating an annunciator for >the Radiation M wring System (RMS) from and replacing tone genera 1Talarm with seven inoividual alarms to improve operator awareness of the RMS system status. The inspector identified no problems in review of the-licensee's 10 CFR 50.59 review pertaining,to these modification ,t % >

No violations or deviations were identifie *

1 Open-Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action

'on.the part of the NRC or licensee or both. Antopen item disclosed-during the inspection is discussed in Section 3.'

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11. , Exit Interview ,

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The inspector summarized the scope and findings of th'e inspection with licensee respresentatives (Section 1) at the conclusion of the inspection

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on December 12, 1985. The inspector discussed the likely informational content of the inspection-report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify such documents or processes as proprietary. In response to one item discussed by the inspector, the licensee agreed to submit an errata to the semiannual effluent report for the first half of 1985, to correct the~ erroneous. gaseous effluent data for the month of June and the semiannual totals. (Section 3)- $

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