IR 05000302/1989004

Insp Rept 50-302/89-04 on 890227-0303.No Violations or Deviations Noted.Major Areas inspected:post-accident Sampling Sys,Confirmatory Measurements,Radiological Effluents & Reactor Coolant Chemistry

ML20244C514
Person / Time
Site:	Crystal River
Issue date:	04/05/1989
From:	Kahle J, Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20244C513	List: IR 05000302/1989004 ML20244C511
References
50-302-89-04, 50-302-89-4, NUDOCS 8904200245
Download: ML20244C514 (13)

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Report N'o.: 50-302/89-04

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L Licensee:" Florida Power Corporation 3201 34th Street, South '

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Docket No.f '50-302 License No.: DPR-72-

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'3 l Facility Name: Crystal River 3 ,Ll L*L iInspection. Conducted: February 27 - March 3,'1989 Inspector:

R.-R..Marston

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Accompanying Pers nel: T. R. Volk- ,

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. Approved by: o hTe, Chief N (~ d M/s 79 Dste Signed-J ./ .B Radiol gical Effluents and Chemistry Section ,

Emer ncy Preparedness and Radiological-k Protection Branch Division of Radiation Safety'and Safeguards .l l t L SUMMARY i

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Scope This routine, unannounced' inspection was conducted in the areas of confirmator measurements, radiological effluents, post accident sampling systems, and reactor coolant chemistr Results The licensee's Nuclear Chemistry and Radiation Protection organization has been

. effective under the current organization and management. Management support was shown through . provision of a Chemical Engineer staff position for

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specialized support and the interest shown by upper management i n'

radiochemistry and chemistry comparisons with the NR While the Radiochemistry and Chemistry facilities were crowded, the equipment appeared to be .up-to-date and properly maintained. The Chem / Rad organization demonstrated I its' capability through the close agreement that was achieved with NRC results ll on the comparative radiochemical analyses that were performed during the L inspection.

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REPORT DETAILS Persons Contacted Licensee Employees G. Clymer, Nuclear Waste Manager C. Davis, Nuclear Waste Supervisor

• P. Ezzell, Radiological & Environmental Specialist

• D. Harper, Nuclear Regulatory Specialist V. Hernandez, Supervisor, Nuclear QA Surveillance

• D. McCollough, Nuclear Chemistry Supervisor

• P. McKee, Director, Nuclear Plant Operations R. Pinner, II, Nuclear Chemistry Supervisor

• S. Robinson, Nuclear Chemistry & Radiation Protection Superintendent

• Rossfeld, Manager, Nuclear Compliance D. Vanoosterwyk, Health Physics Supervisor D. Worley, Nuclear Chemistry Manager NRC Resident Inspector i P. Holmes-Ray

• Attended exit interview Audits and Appraisals (84750)

The inspector discussed the audit and surveillance programs with licensee .

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representatives. The inspector reviewed Audit Report 88-08-REMP for the audit. which was conducted August 8-26, 1988. This audit evaluated the Radiological Environmental Monitoring Program, the Process Control Program, the Offsite Dose Calculation Manual, the Radiological Effluents Monitoring Program, and the Radioactive' Waste Transportation Program. The audit appeared to be comprehensive and in depth, and endorsed recommendations made for the water treatment plant in a refarenced INP0 repor j The insp(ector Reports QPSR): also reviewed the following Quality Programs Surveillance 88-12, Second Radioactive Liquid Excess Release Rate Due to Incorrect Chart Paper, July 12, 198 , Make-up Water From Crystal River Coal Plant, October 6,198 No violations or deviations were identifie !

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., . Procedures (84750)

The inspector reviewed- selected, chemistry and- radiation protection

! procedures and surveillance procedures applicable to the areas in the scope of the inspection. The procedures appeared to be adequate for the purposes stated.

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No violations or deviations'were identifie . Liquid Radioactive Waste Processing Systems (84750)

The inspector. discussed - operation of the liquid radwaste system with

' licensee representatives, reviewed operating records, ard toured the plant, examining. components of the . syste Reactor Coolant (RC) was

' processed through an RC evaporator syste The evaporator bottoms were processed and the boron recovere Liquid radwastes from the Reactor Building Sump, Auxiliary Building Sump, the Decay Heat Pits, and the Reactor Coolant Drain Tank were collected in the Miscellaneous Waste Storage Tank' (MWST); processed in the Nuclear Waste Demineralized System; and sent to either of two Evaporator Condensate Storage Tanks (ECSTs). The ECSTs could be recirculated and sampled, then released through the liquid radwaste radiation monitor or transferred to one of two Reactor Coolant Bleed Tanks or the MWST. The

. Nuclear Waste Demineralized System consisted of six processing tanks and was capable of being placed in various configurations in order to process the radwaste in the most efficient manner. At the time of the inspection, the tanks were configured as follows:

(1) Charcoal (2) Cation Demin. (Stron (3) Anion Demin. (Weak) g)

(4) Anion Demin. (Strong)

(5) Cation Demin. (Strong)

(6) Anion Demin. (Strong)

Laundry and Hot Shower Tanks were normally released untreated through the radiation monito All releases of liquid effluent to the environment were under administrative control. Liquid effluent releases were in the batch mode, and a numbered discharge permit was issued for each batch releas Dilution of the activity released was accomplished in the discharge canal where the liquid wastes were mixed with the circulating water discharge from Units 1, 2, and No violations or deviations were identifie _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _

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.. Gaseous Radioactive Waste Processing Systems (84750)-

l The inspector discussed operation of the gaseous waste processing system with cognizant licensee - representatives and reviewed system operating records. The system included three waste. gas decay. tanks. One of the tanks was used for storage and decay of primary coolant offgas removed

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during plant shutdowns, and the other tanks were alternatively used for I

the primary coolant. system cover gas syste Releases were made using a permit system for administrative control similar to that used for the liquid radwaste_ syste After sampling an analysis' of the selected tank and approval of the release, the release was initiated through HEPA and charcoal filters. The gas was monitored as it left the tank, then again after filtration and mixing with other gases in the Auxiliary Building Ventilation Syste Either monitor would terminate the discharge automatically if the setpoint was exceede No violations or deviations were identifie . PostAccidentSamplingSystem(PASS)(84750)

The inspector examined components of the PASS and discussed the system with cognizant licensee representative The system was designed by Applied Physical Technology with support from Nuclear Data for the gamma spectrometry system and NUS for the chemical analysis syste < Installation of the system was coordinated with the FPC Engineering Departmen The system was designed so that liquid samples could be taken from the following locations:

Reactor Coolant Letdowns

Pressurizer Water Pressurizer Steam Space

"C" Reactor Coolant Pump Cold Leg

"D" Reactor Coolant Pump Hot Leg The sample was cooled by passing through a heat exchanger prior to being counted by a gamma spectroscopic system. Counting geometry was varied by a computer-controlled system which would select a sample path through either of two lines (at different distances from the detector head); and behind one of several collimator slits of differing width The sample passed through a pressure reducing valve, then a 10cc undiluted grab sample took place,Thethen sample chemical wasanalyses passed throug(h a phase pH, boron, chloride, separator, where degassing and other anions). The gas phase was measured for dissolved hydrogen. The liquid sampling system could be flushed with demineralized water to remove contamination and lower external dose rates. The remaining sample could be disposed of to the MWST or the Reactor Buildiag Sump, depending on activity in the liqui __-_ -__- _-_- _ _ _ _ -

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l The containment gas sample was' taken by the PASS from either of two P

elevations _inside containment. The sample passed through the same gamma l spectrographic analysis system as the coolant sample. An undiluted 10cc!

L grab sample could be taken, and the gas flow was run through a particulate g filter and iodine cartridge. After the sample was taken, the sample lines

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were purged with service ai The-licensee had in place various. testing and QC. programs. A monthly

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liquid sample was taken and compared with a routine coolant sample. The computer had a jobstream to cycle all valves required for system operation; . The germanium detectors were energy-calibrated daily and. a monthly walkdown of the system was done which verified valve positions,

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- power supplies, and circuit breaker A licensee representative stated that the system worked well until about two years ago, when a pressurizer steam space sample was apparently not properly cooled. . Since then there had been problems with leaks in valves

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.and tubin Within the past year, permanent engineering support to the system had been received. This- led to leak testing, troubleshooting, ~and repair of-the affected component. Some valves have been replaced with different type valves. The most recent test revealed that five components were still leaking. Licensee representatives stated that engineering evaluation was continuing to determine the best fix for the proble No violations or deviations were identifie . Gaseous Effluents (84750)

The inspector reviewed the gaseous effluent release program with licensee representatives and reviewed 10 gaseous effluent release permits for the period from December 1988 through January 1989. The permits showed that releases were well within technical specification limit '

No violations or deviations were identifie . LiquidEffluents(84750)

The inspector reviewed the liquid effluent release program with licensee representatives and reviewed 22 liquid effluent release permits for the period December 1988 through February 1989. The permits were complete and showed that releases were well within technical specification limit No violations or deviations were identifie . Semiannual Radioactive Effluent Release Report (84750)

Technical Specification 6.9.1.5.d requires that a Semiannual Radioactive Effluent Release Report shall be submitted within 60 days after January 1 and July 1 of each year. The Technical Specification further specifies

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data and formatting be provided in accordance with Regulatory Guide 1.21 Revision 1, June 197 The inspector reviewed the effluent report for the period from July 1 l through December 31, 198 The report was submitted in accordance with l Technical Specifications and Regulatory Guide 1.21. The following Table l shows the comparison of the releases for the Calendar Year 1988 to the previous two years:

1986 1987 1988 Gaseous Releases Fission Gases (Ci) 2.76E+03 1.10E+03 3.42E+03 ParticulatesandIodine(Ci) 1.01E-03 3.49E-03 1.25E-03 Liquid Releases Fission and Activation Products (Ci) 8.12E-01 9.55E-01 2.31E-01 Tritium (C1) 1.73E+02 3.56E+02 5.12E+02 There were four abnormal releases during the year totaling 7.34 curie Nearly all the activity was from one release from PASS components in Novembe Three releases of relatively insignificant amounts were from steam relief valves. The annual whole body dose to an individual from all releases during the year was 1.71E-01 mrem. The annual organ dose to an individual from all releases during the year was 8.46E-01 mre No violations or deviations were identifie . Confirmatory Measurements (84750)

The inspector examined the licensee's count room equipment and process and effluent monitor The count room was equipped with two Tennelec i proportional counters for alpha and beta counting, one liquid scintillation unit for beta counting and three Ortec high purity germanium detectors with two ND 6685 systems for gamma spectroscopy. The Health Physics organization operated a Canberra gamma spectroscopic syste The inspector verified that the Reactor Building Purge Exhaust Monitor, and Condenser Vacuum Pump Exhaust (Gas) were calibrated in accordance with regulatory requirement The inspector reviewed the calibration records for the three gamma spectroscopic systems in the count room. The calibrations appeared to have been conducted at the required frequencie The inspector reviewed the QC records, including control charts for the three gamma spectroscopic systems in the count room and for the PASS gamma spectroscopic system. The control charts showed that prompt corrective action was taken when points fell outside specified limit !

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As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on January 9, 1989, to the Plant for selected radiochemical analysis. The NRC received the analytical results from FPC in a letter dated February 17, 1989. The comparison of the results to the known values are presented in Attachment i for your information. The acceptance criteria for the comparison are listed in Attachment A review of these data shuwed that all comparative results were in agreemen These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data for successive years in which samples have beer analyzed by the Crystal River - 3 facility. Members of the_ plant staff were notified of these results during this inspectio During the inspection, a spiked particulate aerosol filter and a spiked charcoal cartridge were provided to the licensee for counting on the

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plant's gamma spectrometry system The licensee took samples of gaseous radwaste, liquid radwaste, and reactor coolant for analysis on the plant gamma spectrometry system The licensee's results were compared against those obtained by the inspector from the same samples analyzed on the NRC

- Region II Mobile Laboratory gamma spectrometry system. The purpose of these comparative measurements was to verify the licensee's capability to accurately identify and quantify gamma - emitting radionuclides in various plant systems and effluent stream The inspector observed the liquid radwaste and gaseous radwaste samples being taken and prepared for analysis. The inspector observed that the appropriate procedures were followed as were good health physics practice A descript'ca of the sample types and counting geometries along with a comparison of the NRC and licensee results is listed in Attachment 2. The methodology for determining agreement with licensee results is discussed in Attachment 3. Agreement was obtained in all comparisons for all i sample Licensec Detector No. 3 was out of service during the inspection, so was not evaluated. The Health Physics detector was calibrated only for the charcoal cartridge and particulate filter geometries, so it was evaluated for only those sample All comparisons were in agreemen Certain biases were noted in the comparison The licensee's gamma spectroscopic results for the

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particulate filter, charcoal cartridge, and reactor coolant were biased l lo No violations or deviations were identified.

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l7 11. Exit. Interview The inspection scope and results were.' summarized on March 3,.1989, with those persons indicated in Paragraph 1. The inspector described the areas ,

-inspected and; discussed in detail the. inspection results. Proprietary information is not contained in this repor The licensee's analyses were all in agreement with NRC results. It was noted 'that the beta respits (Paragraph'10 and ' Attachment 1) were' biased low and the gamma spectroscopic results for the particulate filter, charcoal cartridge, and reactor coolant (Paragraph 10 and Attachment 2)

were also biased low.- These results 'should' be ' evaluated to determine if there is indeed a low bia ..

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CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests;and verification measurements. The criteria _ are based on an empirical relationship which combines prior experience and the accuracy'needs of. this program

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In -this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its - associated uncertainty referred to in this program as

" Resolution"2 increases, the range of acceptable differences between. the NRC and -licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio 2 of the licensee value to the NRC value is computed. This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote

' agreement are listed in Table 1 below. Values outside of the agreement ratios-are considered in disagreemen NRC Reference Value 2 Resolution =

Associated Uncertainty for the Value

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Licensee Value 2 Comparison Ratio =

NRC Reference Value TABLE 1 CONFIRMATORY MEASUREMENTS ACCEPTANCE CRITERIA RESOLUTION VS. COMPARISON RATIO Comparison Ratio Resolution for Agreement

<4 .4 - .5 - .6 - 1.66 16 - 50 .75 - 1.3 .80 - 1.25

>200 .85 - 1.18

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i i e i i laill

= .= .' i,,1 8 M EE b M

-

,

m

'

ii m,, i 1 Ri m M IEE

<-

% * r .o