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Insp Rept 50-395/87-21 on 870713-17.Violations Noted.Major Areas Inspected:Qc & Confirmatory Measurements,Including Review of Lab QC Program,Procedures & Instructions,Qc Records & Logs & Counting Room & Chemistry Lab Facilities
	ML20237J156
Person / Time
Site:	Summer
Issue date:	08/05/1987
From:	Adamovitz S, Kahle J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20237J140	List: ML20237J136; ML20237J147; ML20237J156;
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 50-395-87-21, NUDOCS 8708180007
	Download: ML20237J156 (16)
	v • d • e

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@ MGg Ue51TED STATES

Do NUCLEAR REGULATORY COMMISSION

[" -E o REGION ll

.$* ._ j 101 MARIETTA STREET, N.W.

~ 's ATLANTA, GEORGI A 30323

\...../ AUG 0 71987

Report No.: 50-395/87-21

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Licensee: South Carolina Electric and Gas Company

Columbia, SC 29218 '!

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License No.:

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Docket No.. 50-395 NPF-12

Facility Name: Summer

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Inspection Conducted: July 13-17, 1987 -I

Inspector: -

YM r/%- [ $ // 7

S. S. Adamov1ti ~ / Qdte' Signed

Accompanying Personnt /lR.R.Marston !

Approved by: ,'

J.B./Ka/le,SectionCnief

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Dste' Signed

Di vi s'i of Radiation Safety and Safeguards

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SUMMARY

Scope: This routine, unannounced inspection was conducted in the areas of

quality control and confirmatory measurements including review of the

laboratory quality control program; review of procedures and instructions;

review of quality control records and logs; review of the counting room and

chemistry laboratory facilities and results of split samples analyzed by the

licensee and the NRC Region II Mobile Laboratory.

Results: One violation was identified - failure to make adequate surveys.

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

0. S. Bradham, Director, Nuclear Plant Operations y

M. N. Browne, Group Manager, Technical & Support Services t

L. A. Blue, Manager, Support Services i'

A. R. Koon, Manager, Technical Support

J. W. Cox, Associate Manager, Health Physics j

W. F. Bacon, Associate Manager, Chemistry {

E. M. Rollins, Associate Manager, Corporate Health Physics )

W. R. Baehr, Manager, Corporate Health Physics & Environmental Programs

J. R. Proper, QA Supervisor, Operations

G. M. Gowdy, Staff Health Physicist (CHP) 1

D. C. Blanks, Licensing Engineer

M. D. Blue, Regulatory Compliance Engineer

G. A. Robertson, ISEG Engineer

D. M. Franklin, Jr. , Health Physics Specialist

Other licensee employees contacted included several technicians.

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Nuclear Regulatory Commission

R. L. Prevatte, Senior Resident Inspector

Attended exit interview

2. Exit Interview ]

The inspection scope and findings were summarized on July 17, 1987, with

those persons indicated in Paragraph I above. One violation concerning

failure to make proper surveys -(Paragraph 10.a) was discussed. Licensee

management representatives acknowledged the inspector's comments, but

disagreed that a violation existed since the measurement errors were

conservative and would not result in any limits being exceeded.

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

to or reviewed by the inspector during this inspection.

3. Licensee Action on Previous Enforcement Matters

This subject was not addressed in the inspection.

4. Audits (84725)

Technical Specification (TS) 6.5.2.8 states audits of unit activities

shall be performed under the cognizance of the Nuclear Safety Review

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I Committee (NSRC) encompassing conformance of unit oceration to provisions

contained within the TSs and applicable license conditions at least once

per 12 months; the radiological environmental monitoring program and the

results thereof, including the performance of activities required by.the

quality assurance program per Regulatory Guide 4.15, Rev. 1,

February 1979, at least once per 12 months; and the Offsite -Dose

Calculation Manual and implementing procedures at least once per 24

months. The inspectors reviewed the following audit reports:

II-18-85-F, Plant Chemistry Control, July 1985

II-26-86-L, Station Radiation Control, October 1986

II-23-86-M, Environmental _ Monitoring October - November 1986

The inspectors also reviewed the following surveillance:

9-BLT-86-L, QC Checks of the Whole Body Counting System , April 30,

1986.

2-LCN-86-F, Plant Chemistry Control, January 30, 1986.

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10-JRN-87-M, Environmental TLDs, May 27, 1987.

Other audits and surveillance reviewed were discussed in a previous

report (50-395/86-20).

The inspectors noted that chemical and radiological measurement program

areas were audited against applicable sections of the Technical

Specifications, Regulatory Guides 1.21 and 4.15, and approved plant

procedures. The audits appeared to be conducted' in accordance with

Quality and Procurement Services Procedures (Attachment 2) and were

conducted from comprehensive and in-depth checklists.

No violations or deviations were identified.

5. Changes to the Laboratory Quality Control Program (84725)

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The inspectors reviewed selected portions of the Quality Assurance program

with cognizant licensee representatives and determined that program

management had not changed since the last inspection. Equipment had been

replaced as necessary and procedures were reviewed and upgraded. The

inspecters noted that the program implementation met the general guidance

of Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring

Programs," with respect to the radioactive effluent monitoring program.

No violations or deviations were identified.

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6. Procedures (84725)

Technical Specification 6.8.1 requires written procedures to be

established, implemented, and maintained covering the applicable

procedures recommended in Appendix "A" of Regulatory Guide 1.33,

Revision 2, 1978; surveillance and test activities of safety-related

equipment; the Offsite Dose Calculation Manual; and 'the effluent and

environmental monitoring program -using the guidance in Regulatory

Guide 4.15, Revision 1, February 1979.

The inspectors ' reviewed selected parts of the procedures specified. in

Attachment 2. The procedures were from the following areas:

(1) Quality & Procurement Services Procedures;

(2) Station Administrative Procedures;

(3) Health Procedures;

(4) Surveillance Test Procedures;

(5) Chemistry Procedures; and

(6) System Operating Procedures

The inspectors noted that the procedures had been reviewed and approved in

accordance with established directives.

l No violations or deviations were identified.

7. Records (84725)

The inspectors reviewed selected parts of the following records:

a. Liquid Scintillation Counter (LS-1800) Quality Control Logs for

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December 1986 - June 1987 including:

(1) Daily Background, Efficiency, and Calibration Determinations

(2) Daily Background and Efficiency Trend Charts

b. LB-1 Alpha and LE-2 Beta Quality Control Logs for January 1986

- March 1987 (LB-1 through May 1987) including:

i (1) Daily Background and Efficiency Determinations

(2) Daily Background and Efficiency Trend Charts

(3) Weekly Chi-Squared Value Determinations

(4) Quarterly Operating Voltage Determinations

(5) Quarterly Percent Slope Determinations

(6) Alpha Plateau Curves

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c. GeLi Detector Systems 4, 5, and 6 Quality Control Logs for April -

June 1987 including: j

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(1) Daily Centroid Determinations

(2) Daily Efficiency Checks a

(3) Daily Resolucion Checks-

(4) Weekly Background Data

d. Post .ccident Sampling - System Quarterly Check, conducted April 2,

1987.

e. Efficiency Calibration Data for Gamma Spectroscopy Detectors ,

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(1) Detector 4 - 57 mm filter paper for shelves 0 and 1, face-loaaed

charcoal cartridge for shelf 0, and I liter liquid marinelli for 1

shelf 0-for 1987

(2) Detector 5 - 57 mm filter paper for shelves 0 and 1; face-loaded

charcoal for shelf 0; one and four liter liquid marinellis,

25 ml and one liter gas marinellis for shelf 0; 25 ml gas for

shelves 2 and 3; for 1985 and 1986.

(3) Detector 6 - 57 mm filter paper for shelves 0 and 2; 47 mm

filter paper for shelf 0; face-loaded CP-100 and MITE charcoal

cartridges for shelf 0; one and four liter liquid marine 111s for

shelf 0; 100 ml and one liter gas marine 111s for shelf 0; 25 mi

l gas for shelves 0, 2, and 3; 15 mi liquid vial:for shelf 0; for

1985 and 1986. ,

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l f. Standard Radionuclides Source Certificates

g. 1986 Intercomparisons Involving V. C. Summer Nuclear Station HP count

Room and Environmental Surveillance Laboratory.

h. 1986 Intracomparisons

l *Some comparisons were made by counting a sample on the three HP Count

l Room detectors and the Environmental Surveillance Laboratory detector.

1. Latest Calibrations and Operational Checks for the following

Radiation Monitors:

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(1) RM-A3, Main Plant Exhaust Atmospheric Radiation Monitor

l (2) RM-A4, Reactor Building Purge Exhaust Atmospheric ' Radiation

Monitor

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(3) RM-A13, Main Plant Vent Atmospheric Radiation Monitor and

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(4) Reactor Building Purge Exhaust System Atmospheric Radiation

Monitor

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The inspector noted that the records appeared to be developed and

maintained in accordance with appropriate procedures. 2

No violations or deviations were identified.

8. Semiannual Radioactive Effluent Release Reports (84723, 84724)

Technical Specification 6.9.1.8 requires the licensee to submit within 60 ;

days of January 1 and July 1 of each year, routine radioactive effluent ,

release reports covering the operation of the unit during the previous six l

months of operation. Technical Specification 6.9.1.9 requires that the l

report include a summary of the quantities of radioactive liquid and i

gaseous effluents and solid waste released from the unit as outlined in '

Regulatory Guide 1.21. Additionally, the reports that are submitted 60

days after January 1 of each year shall inclJde 3n assessment of doses due

to the radioactive liquid and gaseous effluents released from the unit or

station during the previous calendar year.

The inspector reviewed the Semiannual Radiological Effluent Release Report

for the period July 1, 1986 through December 31, 1986. The review

included an examination of the liquid and gaseous effluent release data as

well as dose estimate data. Selected data from this report and previous

reports are presented in Attachment 3. The inspector noted that :

quantities of radionuclides in gaseous releases were significantly lower )

! than for any other operating Region II Pressurized Water Reactors (PWR) l

l for 1985 and 1986. The radionuclides. in the liquid effluents were lower

i than the average for Region II PWRs for the same two year period.

No violations or deviations were identified.

9. High Range Noble Gas Monitors and Particulate and Iodine Samplers

(NUREG-0737,II.F.1)

The inspector reviewed licensee documer.tation, examined the applicable

monitors, and discussed the systems with cogn1zant licensee

representatives.

A letter from the licensee to NRR (Denton), dated November 6, 1980,

i Subject: Effluent Treatment Systems Branch, TMI Questions was reviewed

l and indicated that the condenser air removal system exhausts through the

Auxiliary Building charcoal filters through the Auxiliary Building vent

stack under normal conditions. This system was not required to operate

during an emergency. In a letter from the licensee to' Denton, NRR,

! Subject: TMI Item II .F.1, dated December 22, 1980, referring to ETSB

comments on the V. C. Summer Response to TMI Concerns (April 1980), the

licensee identified the high range noble gas effluent monitor (RM-A13) as

the high range backup to the normal range main plant vent exhaust monitor

(RM-A3). The November 6,1980 letter also designated this configuration )

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and further designated RM-14 as the high range monitor backing up normal 'I

range monitor RM-A4, Reactor Building Pur;;e Ver.t Exhaust Moni tor.. !

Table 7-1 of the Radiological Emergency Plan showed that the high range i

monitors (RM-A13 and RM-A14) had a range extending 'up to IE+5 microcuries i

per cc (Xe-133 equivalent), and extending down to a factor of 20 below the 1

top of the range of the normal range monitors. Normal and high range l

particulate and iodine sampling was conducted at Monitors RM-A3 and RM-A4. j

The inspector took a tour and examined the installation and location of q

Monitors RM-A3 and RM-A4 (485 foot level of Auxiliary Building) and RM-A13 1

and RM-A14 (roof of Auxiliary Building). T_he inspector reviewed the 1

Surveillance Test Procedures (list in Attachment 2), for calibration of

the monitors and flow measurement instruments, and for operational checks f

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of the monitors. The inspector also reviewed printouts showing completion

I of the above procedures. The inspector determined that based on the above 1

information, the criteria of NUREG-0737, II.F.1, Attachment 1, Noble Gas j

Effluent Monitor, and Attachment 2, Sampling and Analysis of Plant J

Effluents, have been met and IFI 87-01-01 is closed. {

No violations or deviations were identified.

10. Confirmatory Measurements (84725)

a. During the inspection, reactor coolant and selected liquid and j

gaseous effluent process streams were sampled and _ the resultant i

sample matrices analyzed for radionuclides concentrations using i

licensee and NRC Region II Mobile Laboratory gamma ray spectroscopy

systems. The purpose of these comparative measurements was to verify

the licensee's capability to measure radionuclides accurately in

various plant systems. Analyses were conducted utilizing as many of

the licensee's gamma spectroscopy systems as practicable. Samples

included the following: reactor coolant sample -(RCS), liquid waste,

and gaseous waste. Spiked particulate filter and charcoal cartridge

samples were provided for analyses in lieu of licensee samples which

did not have sufficient levels of activity for analysis. Comparison

of licensee and NRC results are listed in Attachment 4 with the

acceptance criteria listed in Attachment 1. Results were in

agreement for the liquid waste, reactor coolant, and particulate

filter samples. The inspector noted that the licensee's results for

the liquid waste samples were biased 7-10?; high for Detector 4 and

l 5-8?s low for Detector 6. The licensee's results for the charcoal

cartridges were consisten+1y biased low (8-24?s) with disagreement

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noted for Cd-109 on Detectors 4 and 5. Results for the waste' gas

analysis were biased low with one disagreement for Xe-135 on Detector

5. Further inspection did not resolve the reason for these

differences; however, a licensee representative stated that the

detectors would be recalibrates during September 1987.

l An inspector accompanied licensee personnel and observed sampling

being done. When the waste gas sample was being taken using the "one

liter" marinelli, the inspector asked the licensee representative

what volume was used to calculate the activity per cubic centimeter

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when the counting was done. The licensee representative responded )

l that 1000 cc was used as the flask volume when calculating the !

l activity per cc. The inspector stated that verification of the j

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volume of a "one liter" gas marinelli flask had shown that the true ):

volume of the container was approximately 1250 cc. Calculating the

specific activity of a gas using 1000 cc rather than the true volume

would result in an activity per cc 25% higher than the correct

activity per cc. The activity of the sample taken was' high, i

resulting in excessive dead time on the counting systems, so a )

smaller known volume of gas was injected into the "one liter" l

marinelli, then counted. The inspector stated that using the i

incorrect volume when calculating the concentration of radioactive j

material in a gas was a violation of 10 CFR 20.203(b), failure to 1

make adequate surveys (50-395/87-21-01). j

b. The inspectors noted that the licensee was provided with a simulated i

liquid waste sample by the NRC contract laboratory and was requested

to complete radiochemical analysis for H-3, Fe-55, Sr-89, and SR-90

concentrations. Licensee representatives provided the inspector

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with a copy of the results from the vendor laboratory. The results j

l and comparisons are shown in Attachment 5. All comparisons were in

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agreement per the criteria shown in Attachment 1.

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ATTACHMENT 1

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 these criteria, the judgement limits denoting agreement or disagreement

between licensee and NRC results are variable. This variability if a function

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of the NRC's value relative 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 decreases.

For comparison purposes, a ratio 2 of the li;ensee value to the NRC value for

each individual nuclide is computed. This ratio is then evaluated for

agreement based on the calculated resolution. The corresponding resointion and

calculated ratios which denote agreement are listed in Table 1 below. Values

outside of the agreement rations for a selected nuclide are considered in

disagreement.

Resolution = NRC Reference '!alue for a Particular Nuclide

Associated Uncertainty for the Value

! 2 Comparison Ratio = Licensee Value

l NRC Reference Value

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Table 1

Confirmatory Measurements Acceptance Criteria

Resolutions vs. Comparison Ratio

Comparison Ratio

for

! Resolution Agreement

i <4 0.4 - 2.5

4-7 0.5 - 0.2 1

8 - 15 0.6 - 1,66

16 - 50 0.75 - 1.33

51 - 200 0.80 - 1.25

l >200 0.85 - 1.18

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-ATTACHMENT 2

Procedures Reviewed by Inspector

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Health Physics Procedures

HPP-707, Health Physics Actions and Surveillance for Unplanned Releases, i

Revision 4, April 2,1987. l

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HPP-709, Release of Radioactive Gaseous Effluents, Revision 4, Change A, i

May 27, 1987. f

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HPP-710, Release of Radioactive Liquid Efficents, Revision 5, January 29,

1987.

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HPP-801, Quality Control Test of LS-1800 System, GM Counters, and Gas Flow J

Proportional Counters, Revision 4, June 25, 1987.

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HPP-803, Operation of the Tennelec LB 5100 Automatic Counting Systems, J

Revision 3, February 26, 1986. 1

HPP-807, Operation of the Nuclear Model 1024D Multichannel Analyzer,

Revision 1, June 19, 1986,

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HPP-808, Sample Analysis, Revision 8, May 29, 1987,

t HPP-810, Sampling of Radioactive Gases and Liquids, Revision 7, March 31,

j 1987.

HPP-812, Operation and Calibration of the ND-66/HP-9845 Ge(Li)

Spectroscopy System, Revision 2, June 26, 1986.

l HPP-813, Quality _ Control of the NO-66/HP-9845 Ge(L1) Spectroscopy System,

Revision 4, October 29, 1986.

HPP-814, Non-Routine Gas and Liquid Sampling, Revision 4, July 26,1985.

! HPP-817, Quality Control of Sampling and Sample Analysis Methods,

Revision 4, March 31, 1987.

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HPP-818, Operation and Calibration of the LS-1800, Liquid Scintillation

Counter, Revision 1, January 22, 1987.

HPP-904, Use of the Radiation Monitoring System (RMS), Revision 5,

October 31, 1986.

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HPP-905, Methods for Correlation of RMS Readings to Lab Analysis Results,

i Revision 2, January 2, 1987.

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Attachment 2 2 l

HPP-906, Preplanned Alternate Method for Monitoring Post Accident

Parameters as Required by Technical Specifications, Revision 2,

November 10, 1986.

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HPP-920, Post Accident Reactor Building Atmospheric Sampling, Revision 4, !

January.2, 1987. l

Quality & Procurement Services Procedures

QPS-010, SCE&G Quality Assurance Audit / Surveillance Report Preparation,

Revision 0, July 1,1986.

QPS-101, Internal SCE&G QA Audits, Revision 0, July 1, 1986.

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QPS-102, Surveillance of Site Activities, Revision 0, July 1,-1986.

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QPS-103, Quality Assurance Trend Analysis, Revision' 0, July 1,1986.

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Station Administrative Procedures !

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SAP-500, Health Phyz,1cs Manual, Revision 3, June 10, 1985.

System Operation Procedures

50P-119, Waste Gas Processing, Revision 11, Change A, May 7, 1987.

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Surveillance Test Procedures 4

STP-360.035, Main Plant Exhaust Atmospheric Radiation Monitor (RMA0003), j

Calibration, Revision 2, February 12, 1987. l

STP-360-036, Main Plant Vent Exhaust Atmospheric Radiation Monitor (RM-A3

Gaseous Channel) Operational Test, Revision 4, June 18,1987. i

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STP-360.037, Reactor Building Purge Exhaust Atmospheric Radiation Monitor

(RM-A4) Calibration, Revision 2, Change D, March 5, 1987.

STP-360.038, Reactor Building Purge Exhaust Atmospheric Radiation Monitor ;

(RM-A4 Gas Channel) Operational Test, Revision 5, June 19, 1987. l

STP-360.045, Main Plant Vent Atmospheric Radiation Monitor (RM-A13) '

Calibration, Revision 3, Change A, April 21, 1987.

STP-360.046, Main Plant Vent Atmospheric Radiation Monitor (RM-A13) l

Operational Test, Revision 4, Janua,y 29, 1987.

STP-360.047, Reactor Building Purge Exhaust System Atmospheric Radiation ]

Monitor (RM-A14) Calibration, Revision 3, Change A,' February 19, 1987. l

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STP-360.048, Reactor Building Purge Exhaust System Atmospheric Radiation

Monitor (RM-A14) Operational Test.

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Attachment 2 3

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Chemistry Procedures I

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CHP-308, Interlaboratory Intercomparison Program, Revision 2, January 15 j

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1987. i,

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V. C. Summer Nuclear Station

, Semiannual Ef fluent Release Summary 1984-1986

Year 1984 1985 1986

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No. Abnormal Releases

a. Liquid 1 0 0

b. Gaseous 0 0 0

Liquid Waste Released (gallons) 4.91E+7 8.48E+7 2.31E+8

Activity Released (Curies)

a. Liquid

1. Fission and Activation 4.58 7,15E-1 3.29E-1

Products

2. Tritium 2 . 2 5i' .? 3.11E+2 3.74E+2

3. Gross Alpha 0 0 0

b. Gasecus

1. Noble Gas 1.64E+1 1.41E+2 1.39E+1

2. Halogens 3.28E-6 3.62E-5 4.39E-5

3. Tritium 2.24E-1 2.76E-1 1.51E-3

4. Gross Alpha 0 0 0

Dose Estimate (mrem)

l a. Liquid

Whole-body 1.73E-2 4.21E-2= 4.21E-2

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b. Gaseous

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Whole-body 8.95E-3 1.03E-1 3.41E-3

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