IR 05000302/1986016

Insp Rept 50-302/86-16 on 860519-23.No Violation or Deviation Noted.Major Areas Inspected:Radwaste Processing, Effluent Releases & Environ Monitoring

ML20211K860
Person / Time
Site:	Crystal River
Issue date:	06/06/1986
From:	Harris J, Stoddard P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211K852	List: IR 05000302/1986016 ML20211K849
References
50-302-86-16, NUDOCS 8606300295
Download: ML20211K860 (8)

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>"A FErg UNITED STATES

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D NUCLEAR REGULATORY COMMISSION o

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j 101 MARIETTA STREET, N.W.

• ATL ANTA, G EoRGI A 30323 s,m.+/

JUN 161993 Report No.:

50-302/86-16

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Licensee:

Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No.:

50-302 License No.:

DPR-72 Facility Name: Crystal River 3 Inspection Conducted: May 19-23, 1986 lL [J. b L $2 hY b Inspectors:

J.' O. Harris Date Signed Accompanying Perso 1:

R. R. Marston b

Approved by:

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Date Signed P. G. StocW25, Acting Section Chief Division of Radiation Safety and Safeguards SUMMARY Scope:

This routine, unannounced inspection involved radioactise waste processing, effluent releases and environmental monitoring.

Results:

Of the three areas inspected, no violations or deviations were identified.

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8606300295 860616 PDR ADOCK 05000302 G

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REPORT DETAILS 1.

Persons Contacted Licensee Empleyees

• J. A. Frijouf, Compliance Specialist

• L. W. Moffatt, Nuclear Safety Supervisor (Acting)

• G. Westafer, Director, Quality Program

• K. Lancaster, Manager Site Quality Assurance

• M. Mann, Compliance Specialist

• R. H. Pinney, Manager, Quality Systems

• J. L. Bufe, Nuclear Compliance Specialist

• S. D. Powell, Senior Licensing Engineer

• P. J. Skramstad, Nuclear Chemistry / Radiation Protection Superintendent

• T. A. Kamann, Nuclear Operations Records Manager

• R. Fuller, Supervisor, Radiological Support Services

• D.

Kurtz, Supervisor, Quality Audits

• P. Alberdi, Manager Nuclear Site Support

• L. A. Hill, Manager, Site Nuclear Services

• J. W. Tunstill, Senior Nuclear Licensing Engineer

• E. H. Davidson, Nuclear Staff Engineer

• J. L. Roberts, Nuclear Chemistry Manager

• G. R. Clymer, Nuclear Waste Manager

• R. Pinner, Nuclear Chemistry Supervisor

• D. Wilder, Environmental and Radiochemistry Specialist B. Roberts, Chief Operator, Nuclear Waste

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L. B. Mikell, Acting Instruments.and Controls Supervisor C. Barbour, Senior Quality Auditor B. Julius, Lead Technician, Nuclear Chemistry NRC Resident Inspecter J. Tedrow

• Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on May 23, 1986, with those persons indicated in Paragraph 1 above.

One inspector followup item was identified involving an evaluation to assure that the upper instrumentation of the newer meteorological tower is within the thermal boundary layer (see Paragraph 10).

The licensee did not identify as proprietary any of the materials provided

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to or reviewed by the inspector during this inspection.

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3.

Audits and Appraisals (80721, 84723, 84724)

Technical Specification 6.5.2.9 requires audits of the radiological

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environmental monitoring program at least once per twelve months, and of the Offsite Dose Calculation Manual (0DCM) and its implementing procedures at least once per 24 months.

The inspectors reviewed the following audits:

Audit QP-280 Radiation Protection Program, performed November 21, 1985 through January 7, 1986 Audit OP-282 Environmental and Effluent Technical Specification Conformance, performed December 12, 1985 through January 13, 1986 Audit QP-286 Preventive and Corrective Maintenance, performed February 28 through March 21, 1986 The audits reviewed were thorough and appeared to be effective.

The inspector followed the disposition of audit findings to ensure that such findings were resolved in a timely manner.

The inspector noted that responses were timely and addressed short term and long term corrective dCtions.

The inspectors noted that final corrective actions for some concerns appeared to be less timely.

Weaknesses in personnel frisking at the radiation controlled area exit were noted by NRC and licensee personnel earlier in the year.

However final corrective action, installation of passive frisking monitor booths, is not scheduled to be completed until the summer of 1987. Also, the inspectors were informed that a new data recovery system for meteorological data was onsite, but had not been scheduled for

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placement into service.

The inspector noted that procurement and other factors are involved in these cases.

No violations or deviations were identified.

4.

Procedures (84723, 84724)

Technical Specification 6.8.1 requires written procedures to be established, implemented and maintained. The inspector reviewed selected portions of the following procedures.

CH-269, Gaseous Radwaste Evaluation, Rev. 6, September 6, 1985 SP-731, Gaseous Radwaste Release Surveillance Program, Reactor Building i

Continuous Mode, Rev. 9, May 28, 1985 SP-732, Gaseous Radwaste Release Surveillance Program, Waste Gas Decay Tanks

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3A, 3B, 3C, Rev. 5, May 28, 1985 SP-733, Gaseous Radwaste Release Surveillance Program, Reactor Building Batch Mode, Rev. 4, August 2, 1985

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SP-734, Gaseous Radwaste Composites and Grab Sample Surveillance Program, Rev. 5, May 28, 1985 SP-735, Gaseous Radwaste Release Surveillance Program Auxiliary Building

- Continuous Mode, Rev. 7, December 18, 1985 SP-736, Liquid Radwaste Release (Batch Mode) Surveillance Program, Rev. 4, May 28, 1985 SP-737, Liquid Radwaste Release (Continuous Mode) Surveillance Program, Rev. 3, May 28, 1985 SP-738, Liquid Radwaste Composites Surveillance Program, Rev. 4, October 3, 1985 SP-186, Control Room Emergency Ventilation Systems, Rev.13, November 21, 1984 SP-187, Auxiliary Building Ventilation Exhaust Systems Testing, Rev. 12, July 4,1985 SP-345, Auxiliary Building Ventilation Exhaust System Monthly Test, Rev. 4, September 2, 1981 SP-353, Control Room Emergency Ventilation System Monthly Test, Rev. 5, October 31, 1984 CP-138, Secondary Water Chemistry Guidelines, Rev. O, March 26, 1986 The inspector noted several procedures had been revised recently to incorporate improvements and changes, including greater detail for certain procedures. The inspector noted that all procedures reviewed had followed the proper chain of approval as required.

No violations or deviations were identified.

5.

Semi-Annual and Annual Reports (80721, 84723, 84724)

Technical Specification 6.9.1.5 requires submittal of the Annual Radiological Environmental Operating Report and Semi-annual Effluent Release Reports.

The inspector reviewed the Semi-Annual Radioactive Effluent Reports for 1985. No technical discrepancies were noted and the reports were consistent with the guidance given in Regulatory Guide 1.21.

Doses for liquid and gaseous pathways were within applicable Technical Specification limits. The inspectors noted that the licensee included trend charts for doses to the population and amounts of radioactivity released. Since 1981 there has been a general downward trend in gaseous releases and a general upward trend in liquid releases. The inspector had no further questions.

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The inspector reviewed the 1985 Annual Radiological Environmental Report.

The radiological monitoring program is performed by the Florida State Department of Health and Rehabilitation Services and the University of Florida.

The inspector determine-that the program was performed 'as required and no adverse impact on the environment was noted.

No violations or deviations were identified.

6.

Radioactive Gaseous Waste (84724)

Technical Specification 3/4.11.2 establishes upper limits for the dose rate at or beyond the site boundary due to gaseous effluents.

The inspectors reviewed release permits for the period January - May 1986.

Dose projections for each release and monitor setpoint calculations were performed with the approved methodology of the Offsite Dose Calculation Manual. The inspector noted that all the samples for the releases reviewed were counted within ten minutes of collection to ensure all Lower Limit of Detection requirements were met.

All releases reviewed were within applicable limits.

No violations or deviations were identified.

7.

Radioactive Liquid Waste (84723)

Technical Specification 3/4.11.1 defines the limits for concentrations of radioactive material in liquid effluents.

The inspector reviewed selected release records for the period January -

May 1986. For the releases reviewed all were within applicable limits. The inspector discussed the waste processing system with cognizant licensee personnel.

Currently, the licensee was using two trains of filters consisting of six 20-cubic foot containers each.

The component vessels contained charcoal, cation and anion resins in various mixtures to match the system to the effluent streams.

Currently, a train of filters lasts up to eight months before replacement.

The ion exchange resins are not regenerated. The waste evaporators were being used successfully to process reactor coolant and most of the evaporator condensate is being reused.

The inspectors noted that while no formal leakage reduction program is in place, the licensee has been very successful in reducing the processing load on the liquid radwaste system. From 1983 to 1985, the average leakage rate in the Auxiliary Building was reduced from 4.5 gallons per minute to 3.2 gallons per minute.

During the period from 1979 to 1985 the amount of liquid radioactive waste produced dropped from 50,000 to 18,000 gallons per year.

No violations or deviations were identified.

8.

Radioactive Effluent Monitoring Instrumentation (84723, 84724)

i Technical Specifications 3/4.3.3.8 and 3/4.3.3.9 require radioactive liquid and gaseous effluent monitoring instrumentation channels, respectively, to

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i be operable with their alarm / trip setpoints set in accordance with specified limits and give minimum time intervals for channel checks, channel functional tests, and channel calibration operations.

The inspectors reviewed the most recent calibrations for the effluent

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selectively reviewed surveillance records from January to monitors and May 1986, to confirm that all requirements were being met by the licensee.

No violations or deviations were identified.

9.

Implementation of the Meteorological Monitoring Program (80721)

The inspectors noted the environment around the primary and backup meteorological towers and examined the installed instrumentation.

The towers appeared to be clear of any obstructions which would affect the observed parameters, with the exception of an extensive coal pile just to the East of the backup tower. A licensee representative stated that a study showed that the 33 foot wind speed and direction indications were affected

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to some extent by the coal pile when the wind was out of the East.

The inspectors noted that the following recorders at the primary tower had been calibrated on May 2, 1986:

175 foot wind speed and wind direction 33 foot wind speed and wind direction

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33 foot temperature and 175 foot temperature Delta-T (differential termperature)

The inspectors noted that the following recorders at the backup tower had been calibrated on January 25, 1986:

175 foot wind speed and wind direction 33 foot wind speed and wind direction Multipoint recorder (6 channel)

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175 foot temperature 2.

33 foot temperature 3.

Delta-T 4.

Dewpoint 5.

Rainfall 6.

Pressure The inspector reviewed selected portions of the following procedures pertaining to the meteorological instrumentation and display system:

SP-153, Primary System Meteorological Monitoring Instrumentation Calibration SP-158, Meteorological Monitoring Instrumentation Calibration SP-157-A, Meteorological Systea Surveillance (Daily)

SP-157-B, Meteorological System Surveillance (Weekly)

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4 SP-159, Meteorological System Quarterly Availability Procedures SP-153 and SP-158 specified calibration frequencies and system accuracies in accordance with those promulgated in Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants," with the exception of the accuracy of the temperature channel on

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the primary tower. SP-153, Step 2.3 specified an accuracy of 0.99 F, while Regulatory Guidance (RG) 1.23 specified an accuracy of 0.9 F.

A licensee representative stated that this was due to the channel width of the primary tower temperature sensor and recording system.

The meteorological system quarterly availability records generated by Surveillance Procedure SP-159 were reviewed for the period from the fourth quarter of 1984 through the first quarter of 1986.

The available records showed that the required meteorological systems were operable for more than 99 percent of the time during this period, as required.

No violations or deviations were identified.

10.

Inspector Followup Items (92701)

a.

(Closed) IFI 83-08-01, Calibration of RM-Al and RM-A2 Air Sampler Flowmeters.

The inspector reviewed calibration records to ensure both flowmeters are now included in a routine calibration schedule.

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(Closed)

IFI 83-25-04, Review Gas Calibration Data for Gamma Spectroscopy System.

The inspector noted changes in the gas calibration procedure and that the gaseous geometries have been recalibrated.

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(Closed) IFI 83-05-01, Required Effective Corrective Actions to Preclude Recurrent NCOR's Addressing Meteorological Instrumentation and Data Recording Systems Failures.

The inspectors reviewed the meteorological program in detail and found j

several improvements had been made to increase the reliability of the system (See Paragraph 9).

d.

(Closed) IFI 84-18-06 (1) Determine that upper measurements on the new tower are within the boundary layer.

(2) Complete documentation of new meteorological measurements system.

(3) Determine that accuracy of measurements complies with accuracy specifications of RG 1.23.

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The inspectors verified that the new meteorological measurements system was documented in the Final Safety Analysis Report (Section 2.3.3.4)

and the Radiological Emergency Response Plan (Section 12.2.1).

A change to the Technical Specification did not appear to be applicable.

A review of the applicable calibration procedures showed that, with the exception of the primary tower temperature reading, the measurements met the accuracy criteria of Regulatory Guide 1.23.

Licensee representatives stated that it had not yet been determined that the upper measurements on the new tower were within the thermal boundary layer. This item will be closed out, but part (1) " determine that upper measurements on the new tower are within the thermal boundary layer" will remain open under a new tracking number (50-302/86-16-01).

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