IR 05000416/1993017

Insp Rept 50-416/93-17 on 931018-22.Noncited Violation Identified.Major Areas Inspected:Annual Radiological Environ Operating Rept for 1992 & Semiannual Radioactive Effluent Release Repts

ML20058J425
Person / Time
Site:	Grand Gulf
Issue date:	11/15/1993
From:	Decker T, Mcneill N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058J414	List: IR 05000416/1993017 ML20058J410
References
50-416-93-17, NUDOCS 9312140112
Download: ML20058J425 (8)

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- UMITED STATES jrpn me a%, NUCLEAR REGULATORY COMMISSION y+ 4 REGloN 81

S 101 MARIETTA STREET, N.W., SUITE 2930 ;C ATLANTA, GEORGIA 303234199 gy*****/ UOY 1 B 1993 Report No.

50-416/93-17 Licensee: Entergy Operations, In Jackson, MS 39205 Docket No.: 50-416 License No.: NPF-29 Facility Name: Grand Gulf Inspection Conducted: October 18-22, 1993 Inspector: UzI,lhh / O'llM N. G.'McfMill, Radiati'on Specialist

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Date Signed Approved by: V d ov M /[M T. R. Decker, Chief r N Thf Date ' Signed i

Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY

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Scope: ,

This routine, announced inspection was conducted in the areas of the Annual !

Radiological Environmental Operating Report (ARE0R) for 1992, Semiannual Radioactive Effluent Release Reports, Decommissioning Records and contaminated soil onsite,_ the Radiological Environmental Monitoring Program (REMP); the licensee's program to monitor and prevent microbiological attack on service water system piping, Area Radiation Monitor calibration and surveillances, and ;

followup on a previously identified ite ,

Results:

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The inspector accompanied licensee personnel on the environmental sampling route as outlined in the REMP and observed sampling proccdures and sample  :

collection locations (Paragraph 2). .

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The licensee's plant operations had caused minimum impact to the environment as outlined in the Annual Radiological Environmental Operating Report (Paragraph 3).  ;

i The licensee's Semiannual Radioactive Effluent Release report (SRERR) for 1992 !

was received and the totals for effluent releases were found to be within TS .

9312140132 DR 931118 ADOCK 05000416 PDR

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REPORT DETAILS ,

, Persons Contacted ,

Licensee Employees

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• J. Antoine, Chemistry Supervisor (Technical Support) i

• J. Antoine, Acting Superintendent, Chemistry

• L. Daughtery, Superintendent, Plant Licensing *

• C. Dugger, Manager of Operations

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C. Hutchinson, Plant General Manager H. Meisner, Director, Nuclear Licensing ,

• D. Pace, General Manager  !

• Poe, Environmental Specialist, Chemistry

• Ruffin, Specialist, Licensing l

• T. Tankersley, Superintendent, Radiological Control

1. Williamson, Superintendent, Chemistry Other licensee employees contacted included maintenance personnel, technicians, and administrative personne ;

i Nuclear Regulatory Commission

• R. Bernhard, Senior Resident Inspector

• F. Cantrell, Section Chief i

• C. Hughey, Resident inspector

• Sykes, Intern

• Attended exit interview Environmental Monitoring (84750)

Technical Specification (TS) 3.12 states the requirements for the licensec's radiological environmental monitoring program. The program -is implemented through Surveillance Procedure No.06-EN-S000-V-0001,

" Radiological Environmental Sampling," Revision 2 The inspector accompanied plant personnel on a typical weekly sample collection tour of the environmental sampling stations to verify compliance and evaluate quality. The sample points were located as specified in the requirements, and the air samplers were in current calibration. The inspector and specialist examined air samplers, vegetation sampling plots, TLD stations, liquid effluent outfalls, rain >

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gauges, and two cisterns. The air sample stations were changed out in !

accordance with the above-referenced procedures and the personnel were !

familiar with both the equipment and the collection of the dat !

l No violations or deviations were note j Annual Environmental Operating Report (84750) l TSs 6.9.1.6 and 6.9.1.7 state the requirements for the timeliness, format, and content of the Annual Radiological Environmental Operating !

Repor '

The monthly Grand Gulf Radiological Environmental Monitoring Program-(REMP) Report included all analyses performed on environmental samples l for the year through the current month. The results included results for '

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duplicate samples included for quality control purposes. In general, all results were in the lower limit of detection level ;

From a review of the licensee's environmental report, observation of the ,

technicians in the field, and general review of the REMP, the inspector concluded that the Radiological Environmental Technical Specification :

(RETS) requirements were being fulfilled and that plant operations had !

negligible impact on the surrounding environment. Furthermore, any

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activity vhich may have been present as a result of. plant operations did ;

not represent a significant contribution to the exposure of the members of the publi No violations or deviations were note . Semiannual Effluent Report (84750)

TS 6.9.1.8 states the requirements for the Semiannual Radiological !

Effluent Report including timeliness, content, and forma '

The Grand Gulf Nuclear Station ODCM , Sections 1.2 and 2.2, specifies the method to calculate the annual and quarterly dose calculations for calculations for liquid and gaseous effluents, respectivel ;

The inspector reviewed the reports issued for the-first and second !

halves of calendar year 1992 to determine compliance and reviewed data from previous reports to evaluate trends in liquid and gaseous release i At the time of the last inspection (50-416,93-06; April 19-23,1993), ,

only preliminary data was available for effluent totals. Therefore final, complete records for the year were compared to previous year ,

The final values for the effluent information presented in the following table was obtained from current and previous effluent reports:

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EFFLUENT RELEASE SUMMARY FOR GRAND GULF NUCLEAR STATION t

Activity Released (Curies) 1990 1991 1992

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Gaseous Effluents:  ;

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Fission and Activation 1.36E+2 3.17E+1 7.46E+1 Products

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Iodines and Particuiates 2 52E-3 1.09E-3 2.07E-1 Tritium 3.32E+0 5.57E+0 8.87E+0 Liquid Effluents:

Fission and Activation 6.45E-1 8.77E-1 1.20E-1 Products  !

Tritium 1.88E+1 2.16E+1 2.29E+1 .,

Inoperable Effluent  ;

Monitoring Instruments ,

for Greater Than 30 days 0 0 0  ;

Unplanned Releases Liquid 1 0 0 Gaseous 0 0 0 i

The licensee's program to control and quantify radioactive effluent was !

effective. The quantities of radioactive material released due to plant-operations in 1992 resulted in negligible calcu?ated offsite dose .

There were no unplanned radioactive releases t';at required reporting to :

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the NRC in 1992 or in 1993 to dat The inspector reviewed the yearly dose commitments ~ Lo a member of the i'

public from the radioactive materials in gaseous and. liquid effluents

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released during 1992. The inspector also reviewed the licensee's  ;

methodologies for calculating the various individual- doses and found no apparent problems. The quarterly doses as recorded in the report, were based on actual meteorological conditions, real pathways, and receptor- !

locations which were identified in the last land use survey. The ,

following table summarizes the cumulative doses from effluents for #

calendar year 199 ,

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Cumulative Doses from Effluents - Calendar Year 1992 Grand Gulf Nuclear Station Dose Pathways Dose Annual Percent Limits Annual Airborne-Gamma Air Dose 2.9E-2 20 mrad <1%

Airborne-Beta Air Dose 4.2E-2 40 mrad <1%

Airborne-Skin Dose 1.2E+0 30 mrad 4.1 %

Liquid-Total Body Dose 5.8E-2 6 mrem <1%

Liquid-Max Organ Dose 2.0E-1 20 mrem <1%

Total Dose-Thyroid 3.6E+0 75 mrem 4.8 %

Total Dose-Total Body Grgan other than Thyroid 8.7E-2 25 mrem <1%

Direct Radiation (TLD) 2.4E+0 As can be seen from the data presented above, the annual dose contributions to the maximum exposed individual from the radionuclides in liquid and gaseous effluents released to unrestricted areas were well '

within limits specified by TSs and the ODC No violations or deviations were identifie '

5. Decommissioning Planning Records (84750)

10 CFR 50.75(g) requires, in part, that licensee's maintain " records of information important to the safe and effective decommissioning of the .

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facility in an identified location until the licensee is terminated by the Commission." furthermore, information considered important by the Commission for decommissioning is identified as " records of spills or i other unusual occurrences involving the spread of contamination in and i around the facility, equipment, or site" and that the records "must include any known information on identification of involved nuclides, ;

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quantities, forms, and concentrations." ,

The Grand Gulf site has experienced no unusual spills onsite and has detected measurable levels of activity in samples offsite only in the _

two sedimentation basins. The sedimentation samples were discussed in a previous inspection (50-416/92-14, September 21-24, 1992,'. The basin areas have been evaluated and are not considered to be problem, although ,

continued characterization and monitoring is consideved appropriate. The ,

potential problem of identification of spills on site in the future ha been addressed by the license ,

Discussion with cognizant site personnel determined that while no i records on the subject of unusual occurrences were required considering [

that no spills had occurred, the licensee was aware of reporting !

requirements should they become necessary in the futur No violations or deviations were note l l

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6. Microbiologically Induced Corrosion (84750) ,

TS 3/4.4.4 specifies the chemistry control requirements for the reactor coolant syste The inspector discussed with cognizant licensee personnel the continuing actions that the plant was taking in order to prevent microbiological attack of cooling water piping and heat exchangers by the plant service ,

wate l Protection against ingress of corrodants from plant cooling system is discussed belo '

, Plant Service Water The licensee was continuing to utilize it's scale model of the plant's service water system. The model had been used to test new chemicals and alternative treatments in order to determine the potential effect upon the actual system. The licensee was i utilizing dispersants, an nonoxidizing biocide, and sodium hypochlorite. No corrosion inhibitors were being used as the l system is a once through design. Since the water source,-through i the Ranney Wells system is high in iron and manganese, the primary objectives of chemical treatment is to disperse the metals and to inhibit microbial growt Circulating Water System i

Proper treatment of this water is designed to prevent fouling of the condensers and subsequent loss of efficiency. The licensee was utilizing dispersants, sulfuric acid, antifoaming agents, and non-oxidizing biocides. The sulfuric acid is used to modify the tendency of source water to be basic in pH and therefore either corrosive or deposit forming. The antifoaming agent counters unwanted side effects of the dispersan Cooling Tower While the plant was in shutdown, operations were continuing to wash the cooling tower fill material with a hydrogen peroxide

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solution. Previous problems with fouling of the fill material had been encountered and this action was taken to preclude a recurrence. Concentrations of 800 to 1000 parts per million (ppm)

were being used in spraying hose lines and was being manually applied. The fill had been replaced during RF05 ( April 1992). Main Condenser The licensee was continuing to control slime and bacteria through the addition of biocide and utilization of the batch addition lines for pH control. The system had been installed at the inlet to the condenser to aid in mixing and an orifice was installed to

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control the flow rate. The licensee had previously used " button" balls, sponge balls encrusted with a grainy outer surface to scour the tubing. These were found to be more efficient 'n cleaning the tubes without scarring the tube surfaces than other method Standby Service Water Previously encountered problems with microbiological 1y induced :

corrosion (MIC) in the Standby Service Water (SSW) system were being addressed with mechanical, chemical, and operational changes '

to the SSW system. Weekly recirculations were continuing, the basins were air sparged every six to eight weeks, and sodium hypochlorite at higher concentration was added. The biocide effectiveness was monitored with coupons installed in a sidestream off the basi Conclusions The licensee was continuing to take positive actions to prevent microbiological attack and system corrosion and fouling of the raw water systems. Side stream monitoring, system scale models, evaluations of chemical additives and biocides was being implemente No violations or deviations were identified, i 7. Effluent Monitoring Instrumentation (84750)

TSs 3.3.7.11 and 3.3.7.12 identify the surveillance and calibration requirements for liquid and gaseous effluent monitor TS 4.3.7.1 requires that radiation monitoring be demonstrated as being :

operable by channel checks. An Area Radiation Monitor (ARM) is required to be operable in the Dryer Storage Area when fuel is stored in the are :

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New fuel was placed in the Dryer Storage Area on October 6,1993, at

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approximately 08:07 hours. The channel check was not performed within the required 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time frame. The monitor was in fact found after the fact to have been operable during the time frame in question. With i radiation monitors inoperable, area surveys should be performed with a portable monitor instrument at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This was accomplished by the portable ARM installed on the refueling bridge after the required time frame had passed. While continuous air monitors for beta activity were operable during this time frame, these offer no gamma ;

activity protection. These events were outlined in Quality Deficiency Report (QDR) No. 0224-93, dated October 9, 199 '

The fact that only the surveillance was missed and not ARM operability, the safety function provided by the monitor was present during all activities performed in the Dryer Storage Area. Since the required surveillance was missed in the required time frame, and in accordance !

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with the licensee's efforts to identify the violation and amend .

procedures to prevent recurrence as per Section VII.B of the Enforcement :

Policy, a Non-Cited Violation (NCV) was identified. The licensee was informed that required survellances on area and effluent monitors will be reviewed in future inspections (NCV 50-416/93-17-01).

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One NCV was identified.

1 Previous Inspection Items {

(Closed) IFI 50-416/93-06-01: Effluent Monitoring Instrumentation '

Geiger-Mueller (GM) tube replacemen This item was identified in relation to the sensitivity of gaseous beta monitor GM tubes discovered during routine calibrations. Tubes which ,

were operating within calibration standards were returned to the ,

manufacturer to obtain replacement tubes for the next series of calibrations. These were obtained and used to satisfactorily perform the calibrations during the summer of 1993. Future supplies of optimal e performance tubes were on order. This action appears to address the ;

concerns for potential problems identified in the IFI and therefore the -

item is close ,

t 1 Exit Interview The inspection scope and results were summarized on October 22, 1993, '

with those persons indicated in Paragraph 1. The inspector described the :

areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection. The licensee did not identify any such documents or processes as proprietar .

Item Number Description and Reference 50-416/93-17-01 NCV - Failure to perform required surveillances on ARMS (Paragraph 9),

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