IR 05000244/1991008

From kanterella
Jump to navigation Jump to search
Safety Insp Rept 50-244/91-08 on 910401-05.No Violations Noted.Major Areas Inspected:Radiological Environ Monitoring & Radioactive Liquid & Gaseous Effluent Monitoring Including,Mgt Controls & Audits
ML17262A480
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/02/1991
From: Bores R, Jang J, Peluso L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17262A479 List:
References
50-244-91-08, 50-244-91-8, NUDOCS 9105160140
Download: ML17262A480 (17)


Text

U.S.

NUCLEAR REGULATORY CONNISSION

REGION I

RN.

~24492-Docket No.

50-244 License No.

DPR-18 Licensee:

Rochester Gas and Electric Cor oration 89 East Avenue Rochester New York 14649 Facility Name:

R.E.

Ginna Nuclear Power Plant Inspection At:

Scriba New York Inspection Conducted:

A ril 1-5 1991 Inspectors:

L. Peluso, Radiation Specialist, Effluents Radiation Protection Section (ERPS)

Approved By:

49~ t

/~,

C. Jan

,

S nior Radiation Specialist, ERPS

&1<>W

. J. Borg, Chief, ERPS, Facilities Radiolo real Safety and Safeguards Branch, Division of Radiation Safety and Safeguards S=z.-'7(

date

~424ee lff date Ins ection Summar Ins ection on A ril 1-5 1991 Ins ection Re ort No.

Areas Ins ected:

Routine, unannounced inspection of the radiological environmental monitoring and radioactive liquid and gaseous effluents monitoring programs including:

management controls, audits, quality assurance, and implementation of the above programs.

Results:

Within the scope of this inspection, no violations were identified.

However, two unresolved items have been identified in the areas of the radiological environmental monitoring program (Section 4.4)

and radioactive effluent controls program (Section 6.5).

Upgrading the radiation monitoring systems was noteworthy.

9)05i60l40 9j,0~0'DA ADOCK v"000~44

F'DF.'

DETAILS 1.0 Individuals Contacted 1. 1 Licensee Personnel J. Catlin, Environmental Laboratory Technician Helper

  • D. Filion, Radiochemist
  • D. Filkins, Manager, Health Physics and Chemistry

'.

Gasper, Lead Technician, Chemistry

'.

Goodman, HP Technician foreman

  • A. Harhay, Manager, Chemistry Services G. Joss, Result and Test Supervisor
  • N. Kiedrowski, Training Coordinator, HP/Chemistry
  • J. Mallia, Mechanical Engineer F. Mis, Health Physicist J.

Pagani, Environmental Technician

  • B. guinn, Corporate Health Physicist
  • J. St. Martin, Corrective Action Coordinator
  • B. Selbig, gC Specialist, HP/Chemistry
  • J. Widay, Superintendent, Ginna Production
  • J. Wierowski, Health Physicist ls2 NRC Personnel

~T. Moslak, Sr. Resident Inspector

  • N. Perry, Resident Inspector
  • Denotes those individuals present at the exit interview on April 5, 1991, Other licensee personnel were also contacted and interviewed during the course of this inspection.

2.0

~Per ose The purpose of this routine inspection was to review the licensee's program in the following areas.

o The licensee's ability to control and quantify effluent radioactive liquids, gases, and particulates during normal and emergency operations.

o The licensee's ability to effectively implement the Radiological Environmental Monitoring Program (REMP), including the Meteorological Monitoring Progra The inspector reviewed the licensee's-quality assurance audit b'90-19:GS,

"Audit of Health Physics, Chemistry and Radwaste",

conducted May 21, 1990 through June 4,

1990.

This audit was conducted by the licensee's (Iuality Assurance Department in the areas of the REMP and the radiological effluent controls.

Even though many weaknesses were identified during the previous NRC inspection'of the REMP, there were no gA audit findings.

Because the audit was focused on administrative controls rather than technical aspects, the inspector stated that the gA audit program might be improved with the aid of an experienced technical specialist to assess these areas more thoroughly.

4.0 Radiolo ical Environmental Monitorin Pro ram 4.1 Pro ram Chan es The inspector-reviewed the licensee's organization for the management of the REMP.

There were no changes in the licensee's REMP since the last inspection conducted April, 1990.

4.2 Direct Observations The inspector examined 'various environmental sampling stations.

These stations included air particulate and iodine samplers, intake and discharge water composite sampling stations, milk sampling locations, the vegetable garden, and the thermoluminescent dosimeter (TLD)

stations.

All air sampling equipment and the composite water sampling equipment were operable and the TLDs were placed at the specified locations't the'ime 'of this inspection.

Vegetation and milk samples appeared to be readily obtainable at the locations specified in. the Offsite Dose Calculation. Manual (ODCM).

4.3 Review of Annual Re ort The inspector reviewed the Annual Radiological Environmental Report for 1989.

This report provided a comprehensive summary of the results of the REMP around the Ginna site-and met the Technical Specification (TS)

reporting requirements.

The inspector also reviewed available 1990 analytical data for the REMP.

The data for 1990 appeared to be reasonable with no anomalous data.

No violations were identifie.4 Im lementation of the REMP The inspector reviewed the following procedures as part of the review of the implementation of Technical Specification requirements.

CE-I, "Schedule for Environmental Samples and Parameters Analyzed" CE-2.1, "Collection of Milk Samples"=

CE-2.3,

" Iodine-131 Analysis of Milk" CE-4.2, "Collection and Gross Activity Determination on Environmental Water Samples" CE-4.3,

"Analysis for Low Level Iodine-131 in Water" CE-5. 1, "Collection and Calculation of Beta Activity for-Environmental Air Samples" Based on the review of the above procedures, the inspector determined that the licensee's procedures were adequate.

However, there was one weakness in the tritium analysis which the inspector discussed with the licensee.

An improved method wi,ll be considered.

During the previous NRC inspection conducted on April 1'6-20, 1990 (Inspection Report No 50-244/90-08),

the inspector identified that the individual who performed the enviroi>mental sampling and analyses had limited knowledge of counting statistics and counting equipment.

The licensee indicated that this individual would receive appropriate training for the counting equipment and in counting statistics, because this individual essentially runs the Environmental Laboratory.

During this inspection, the inspector conducted an interview with this same individual in the areas of basic counting statistics, counting equipment, and procedures.

This individual was unable to answer questions in this area.

This individual still essentially runs the Environmental Laboratory without supervision.

The inspector noted that the Environmental Laboratory Technician, who has responsibility to run this laboratory under the Radiochemist's supervision, has not worked in the Environmental Laboratory since October 1990 due to other assignments in the Chemistry Department.

No other qualified individual has provided any routine supervision of'he laboratory either.

Based on the above interview and observations, the inspector stated that the individual performing the analyses did not appear to be qualified for the currently assigned position without routine supervision'he inspector noted that the licensee had a meeting to resolve this matter during this inspection.

The inspector stated that this matter relative to the permanent assignment of a qualified individual to the Environmental Laboratory and routine supervision of the laboratory will be reviewed during a subsequent inspectio.5 The inspector noted that the licensee analyzed I-131 in milk and water samples using an upgraded procedure.

The inspector reviewed this procedure and determined that the procedure was adequate to analyze iodine in the above sample media.

The inspector, however, noted that the licensee calculated I-131 activity using an old counting equipment (Baird alpha/beta/gamma counter) self-absorption correction factor for a new gas flow proportional counter (Tennelec alpha/beta counter)

since December 1990.

The licensee stated that calculations of I-131 activity will be done using a new self-absorption correction factor in the near future and all of the results since the change in counting equipment will be recalculated using the new correction factor.

The inspector stated that this was an unresolved item pending the completion of the self-absorption correction factor and the correction of the I-131 activities for all applicable sample results (50-244/91-08-01).

It should be noted that the determination of the new self-absorption correction factor was in progress during this inspection.

ualit Control Pro ram for the REMP Anal tical measurements The inspector reviewed the licensee's quality control program for analytical measurements.

The inspector noted that the gC Specialist established a quality control program within the Health Physics and Chemistry Section.

The inspector reviewed the gC program document, which appeared to be good.

The gC Specialist visited the Yankee Atomic Environmental Laboratory and the FitzPatrick Environmental Laboratory as per previous inspection discussions.

Also the gC Specialist prepared a

set of spike samples as part of a gC check for the Environmental Laboratory, The licensee participates in the EPA cross-check program.

The gamma isotopic comparison results were positively biased.

Comparisons between the set of gC spikes and analytical results were made by the gC Specialist and the results were now within the licensee acceptance criteria.

The licensee will provide another set of spike samples to evaluate the performance of instrumentation and personnel, The inspector also noted that the gC Specialist reviews daily source and background checks and control charts.

The inspector reviewed the control charts of the environmental laboratory instrumentation with the exception of the Liquid Scintillation Counter (LSC).

The licensee kept this LSC in the in-plant counting laboratory and used this LSC.for measurements of tritium for in-plant and environmental samples.

The control charts were established for the alpha/beta counter and the Ge(Li)

gamma spectroscopy system.

The source check results were within the 2-sigma control limi Based on the above review, the following item will be reviewed during a

subsequent inspection.

o Implementation of gC program in the in-plant Chemistry and the Environmental Laboratories, including analytical results of spike; blind, and duplicate samples.

5.0 Meteorolo ical Monitorin Pro ram The inspector reviewed the licensee's meteorological monitoring program

. to determine whether the instrumentation and equipment were operable, calibrated, and maintained.

Comparisons of wind speed, wind direction, and delta temperature at the 33-ft, 150-ft, and 250-ft elevation levels were conducted between the control room, meteorological trailer, and the Technical Support Center (TSC).

The results of the comparison were in good agreement.

Surveillance checks were performed on the instruments three times weekly.

The MIDAS computer program located in the TSC is the main source of real time meteorological data for dose assessment.

The inspector noted that three analog chart recorders were inoperable't the time of this i'nspection.

'The temperature/delta temperature chart recorder for'he 33-ft level and 250-ft level for both A and B sensors at the meteorological trailer were inoperable since March '15, 1991.

Also, the wind speed and wind direction at the 150-ft level for sensors A and B were inoperable since March 20, 1991.

The licensee was aware of the situation'nd indicated that all the instrumentation for the Meteorological Monitoring Program will be replaced.

The licensee expected to have most of the project completed by Summer 1991, however, the entire project should be complete by April 1992.

The inspector stated that this item will be reviewed during a subsequent inspection.

No violations were identified in this area during this inspection.

6.0 Radioactive Li uid and Gaseous Effluent Controls 6.1 Pro ram Chan es The inspector reviewed the licensee's organization for the management of the radioactive liquid and gaseous efFluent controls.

There were no changes in the licensee's effluent control programs since the last inspection conducted on April 16-20, 199.2 Review of Semiannual Re orts The inspector reviewed the semiannual radioactive effluent release reports for 1990.

No obvious mistakes, anomalous measurements, omissions or trends were noted.

These reports provided total released radioactivity for liquid and gaseous effluents, including projected radiation exposure to the public.

The licensee met Technical Specification requirements, No violations were identified.

6.3 Radioactive Li uid and Gaseous Effluent Controls The'inspector reviewed selected radioactive liquid and gaseous effluent release control procedures and release permits as part of the examination to determine the adequacy of implementation of Section 4, 12,

"Effluent Surveillance", of the Technical Specifications and of the ODCH.

The inspector noted that radioactive effluent control procedures were well written and release permits met the requirements for sampling and analysis at the frequencies established in the Technical Specifications.

Based on the review of procedures and release permits, the inspector determined that the licensee was implementing Technical Specification requirements effectively.

During the review of analytical procedures, the inspector noted that the licensee had a

new contractor (Thermo Analytical, Inc.) to analyze Sr-89, Sr-90, and Fe-55.

The inspector. stated that the contractor's analytical procedures for Sr-89, Sr-90, and Fe-55 should be obtained, reviewed, and approved.

The inspector noted that the licensee did not send spike samples for these radi.onuclides to the contractor yet, but planned to send them in the near future.

The inspector also stated that these matters (procedures and analytical results of spike samples) will be reviewed during a subsequent inspection.

6.4 Calibration of Effluent Process Radiation Monitors The inspector reviewed the most recent calibration resu'Its for the following effluent/process monitors as part of the examination to determine the implementation of the Technical Specification requirements.

o Containment Vent Monitor o Air Ejector and Gland Steam Exhaust Noble Gas Monitor o Liquid Waste Disposal o Hain Steam Line Monitors o SPING-4 for Hain Stack Vent

The inspector noted that the licensee performed the primary calibration for the liquid waste disposal (liquid effluent)

and containment noble gas monitors.

The inspector reviewed the primary cal.ibration results for these monitors.

During the review of calibration procedures and results of the above effluent/process monitors, the inspector noted that the calibration results were within the licensee's acceptance criteria.-

However, the inspector identified following weaknesses and stated that these items should be considered for incorporation in the'calibration procedures.

o At least three (3) radionuclide sources should be used to determine the linearity and conversion factors (efficiencies).

Currently, the licensee uses two sources.

o Statistical analyses, such as linear regression, should be performed to verify the linearity.

The licensee stated that these items will be evaluated and incorporated in the calibration procedures.

The inspector stated that the procedure update will be reviewed during a subsequent inspection.

The inspector'oted that the licensee was upgrading the radiation monitoring system (RHS)

as an on-going project (RHS Upgrade Phase 3).

During Phase 3, the licensee will upgrade Radiation Monitors R-15

- through R-20A with new ratemeters and detectors.

Phase 3 was scheduled to be completed during the current outage with the exception of the Spent Fuel Pit Heat Exchanger Service Water Monitor (R-20A).

S Monitor R-20A will be upgraded after the current outage when th

"A" e

st pent Fuel Pit Exchanger can be removed from service The inspect ated that upgrading the RHS was an excellent example of management commitment and support in this area.

6.5 Review of the Potential Unmonitored Effluent Release Pathwa During the tour of the facility, the inspector noted that the license the capability to collect samples for particulates and iodines from e

icensee the offgas vent sampling station (SPING R-15A) located in the turbine building.

The licensee was monitoring only noble gas as required by the Technical Specifications using the R-.15 noble gas monitor and a monthly grab sample taken from the air ejector.

The flow rate and size of the offgas vent are approximately 600 cubic feet per minute (cfm) and

inches diameter, respectively.

The inspector requested to the licensee take smear samples outside of the offgas vent located on the turbine

building roof and on the surface of the roof.

The licensee took the samples and counted them for 30 minutes using a

gamma spectrometry system on April 3, 1991.

The following are the analytical results for the smear samples (report unit = uCi +/- standard error per smear).

Outside of Offgas Vent:

Cs-134 Cs-137 (5.8 0/- 0.5)E-4 (9.1 +/- 0.6)E-4 Turbine Building Roof Gravel:

Cs-134 Cs-137 (1.4 +/- 0.2)E-4 (2.2 +/- 0.3)E-4 The inspector stated that the offgas vent might be a possible unmonitored effluent pathway for particulates based on the above analytical results, and also for iodines depending on the primary to secondary leak rate and the fuel integrity.

The licensee initiated actions to install a new sampling system for particulates and iodines during this inspection, (The current sampling system (SPING R-15A)

might not collect representative samples due to moisture present in the sample stream.)

The inspector stated that this was an unresolved item (50-244/91-08-02)

due to insufficient information at the time of this inspection to assess the adequacy 'of the current monitoring for this pathway, The inspector also stated'he following items will be reviewed during a subsequent inspection.

o Installation of the=proper sampling system due to high moisture in the offgas vent sy'tem.

o Establishment of dose assessment parameters, such as X/g for the offgas vent. release, sampling procedures, and update of the ODCM as necessary.

7.0 Air Cleanin S stem The inspector reviewed the licensee's most recent surveillance test results to determined the implementation of Section 4.5.2.3,

"Air Filtration System", of the Technical Specifications.

The test results for the (1) control room emergency air treatment system, (2) post accident charcoal system, and (3) containment recirculation system were reviewed for the following inspections and tests.

o Visual Inspections o In-Place HEPA Leak Tests o In-Place Charcoal Leak Tests o System Air Flow Rate Tests o Pressure Drop Tests o Laboratory Tests for the Iodine Collection Efficiencies All reviewed test results were found to be within the licensee's acceptance criteria.

However, the inspector noted that the system air

flow test results for the containment recirculation system deviated from ANSI N510-1975,

"Testing of Nuclear Air-Cleaning Systems".

The system

.air flow (unit

cfm = cubic feet per minute)

was determined using the air velocity (feet/minute)

in the duct and the area of the duct (square feet).

The licensee used a pitot tube with a manometer to measure air velocity in the duct.

During the rev'iew of air velocity measurement results for the containment recirculation system, the inspector noted that the measurement results varied widely, indicating the measurements were made near a bend and therefore the results were not representative of the duct.

The inspector discussed air flow measurement locations with the licensee.

The inspector stated that the air velocity measurement results will be reviewed during a subsequent inspection.

No violations were identified'.0 Exit Interview The inspector met with licensee representatives, denoted in Section 1.1 of the report, on April 5, 1991.

The inspector summarized the purpose, scope, and findings of the inspectio REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9203040314 DOC.DATE: 92/02/28 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244

~

~

~

~

AUTH.NAME AUTHOR AFFILIATION ECREDY,R.C.

Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3 SUBJECT: Informs that util have deferred mod of instrumentation for Meteorological Monitoring Program,per Insp Rept 50-244/91-08 on 910401-05.

DISTRIBUTION CODE:

IEOID COPIES RECEIVED:LTR

)

ENCL G SIZE:

TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:License Exp date in accordance with 10CFR2,2.109{9/19/72).

05000244 RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: AEOD AEOD/DSP/TPAB NRR HARBUCK,C.

NRR/DLPQ/LHFBPT NRR/DOEA/OEAB NRR/DST/DIR 8E2 NUDOCS-ABSTRACT OGC/HDS1 RGN1 FILE

EXTERNAL EG&G/BRYCEPJ ~ HE NSIC COPIES LTTR ENCL

1

1

1

1

1

1

1

1

1

1

1

1 EG FIL

NRC PDR RECIPIENT ID CODE/NAME JOHNSON,A AEOD/DEIIB DEDRO NRR MORISSEAUPD NRR/DLPQ/LPEB10 NRR/DREP/PEPB9H NRR/PMAS/ILRB12 COPIES LTTR ENCL

1

1

1

1

1

1

1

1

1

1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELMINATEYOUR NAMEFROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR

ENCL

tl