IR 05000313/1993002

Insp Repts 50-313/93-02 & 50-368/93-02 on 930118-22.No Violations Noted.Major Areas Inspected:Radiochemistry Radiological Confirmatory Measurements Programs

ML20138D940
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/16/1993
From:	Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20138D938	List: IR 05000313/1993002 ML20138D932
References
50-313-93-02, 50-313-93-2, 50-368-93-02, 50-368-93-2, NUDOCS 9302230134
Download: ML20138D940 (20)

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' l APPENDIX )

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Inspection Report: 50-313/93-02 50-368/93-02 Operating Licenses: DPR-51 )

NPF-6 Licensee: Entergy Operations, In Operations, Arkansas Nuclear One )

Route 3, Box 137G .I Russellville, Arkansas 72801 l

Facility Name: Arkansas Nuclear One Inspection At: Russellville, Arkansas Inspection Conducted: January 18-22, 1993 Inspector: L. Wilborn, Radiation Specialist Facilities Inspection Programs Section Approved: D/AAC/45 B. Murray, Chief, facilit es Inspection Date h

Programs Section Insoection Summary Areas Insoected (Units 1 and 2): Routine, announced inspection of the radiochemistry radiological confirmatory measurements program Results:

• The nuclear chemistry section organization structure and staffing met the requirements and commitments of the Technical Specifications and -

Updated Safety Analysis Reports (Section 1.2).

• The nuclear chemistry program was managed and implemented in accordance with station procedures (Section 1.2).

. The nuclear chemistry staff turnover was low (Section 1.2).

• The licensee's radiochemistry radiological confirmatory measurements performance was outstanding (Section 2.2).

.9302230134.930217?

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-2-Attachments

• Attachment 1 - Persons Contacted and Exit Meeting

• - Attachment 2 - Radiological Confirmatory Measurement Results a Attachment 3 - Criteria for Comparing Radiochemistry Analytical Measurements.

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_3 DETAILS 1 ORGANIZATION AND MANAGEMENT CONTROLS (84750)

The inspector reviewed the licensee's organization, management controls, and staffing of the nuclear chemistry section to determine compilance with the requirements in Sections 6.2 of the Units I and 2 Technical Specifications and agreement with commitments in Chapter 12 and Chapter 13 of the Units 1 and 2 Updated Safety Analysis Reports, respectivel .1 Discussion ~

The inspector verified that the organizational structure of the nuclear chemistry section was as defined in the Technical Specifications and Updated Safety Analysis Reports. Management control procedures contained the assignment of responsibilities for the management and implementation of the nuclear chemistry section. There had been no staffing changes in the nuclear chemistry section that would adversely effect performance since the previous NRC inspection of the nuclear chemistry area conducted in March 1991. The nuclear chemistry section had experienced a personnel turnover of approximately 4 percent since March 199 .2 Conclusions The nuclear chemistry section organization structure and staffing met the requirements and commitments of the Technical Specifications and Updated Safety Analysis Reports. The nuclear chemistry program was managed and implemented in accordance with station procedures. The nuclear chemistry staff turnover was lo RADIOLOGICAL CONFIRMATORY MEASUREMENTS (84750)

The inspector reviewed the licensee's radiochemical analysis program for radiological confirmatory measurements to determine compliance with the requirements in Sections 3.1.4 and 6.8 of the Unit 1 Technical Specifications and Sections 3/4.4.8 and 6.8 of the Unit 2 Technical Specification .1 Discussion Radiological confirmatory measurements were performed on standards and split samples by the licensee in the radiochemistry counting room and the inspector in the Region IV mobile laboratory on site. The standards and samples were analyzed using routinn methods and equipmen ___ _____ ___ - -__- - _ ___

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-4-Radiological confirmatory measurements were performed on the following standards and samples:

• NRC Air Particulate Filter Standard (44710-109)

= NRC Scott Charcoal Cartridge Standard (44712-109)

e Waste Liquid Monitor Tank Sample - 100 ml in a 1000 ml Marinelli beaker (Liceasee - 500 mi in a 500 ml bottle and 3900 mi in a 3900 ml bottle)

e Containment Atmosphere Sample - 33 cc in a 33 cc gas bulb (Licensee -

143.7 cc in a glass winkler)

. Reactor Coolant Gas Sample - I cc in a 15 cc gas serum vial (Licensee -

I cc in a 5 cc gas vial)

e Reactor Coolant Liquid Sample - 5 ml in a 20 ml scintillation vial (Licensee - 10 mi in a 60 ml bottle)

The radiological confirmatory measurement tests consisted of comparing the analysis results from the licensee's radiochemistry counting room with the NRC Region IV mobile laboratory analytical results. The NRC Region IV mobile laboratory's measurements were referenced to the National Institute of Standards and Technology by laboratory intercomparisons. The radiological confirmatory measurement comparisons were made only for thase nuclides identified by.NRC as being present in concentrations greater than 10 percent of the respective isotopic values for liquid and gas concentrations as stated in 10 CFR Part 20, Appendix B, Table I The licensee attempted to obtain a particulate filter sample and a charcoal cartridge sample, but the collected activity concentrations were too low in value for radiological confirmatory measurement compariso At the time of the inspection, the licensee utilized three germanium-lithium detectors in the radiochemistry counting room. These detectors were used routinely for isotopic analysis of radioactive samples to demonstrate compliance with Technical Specifications and regulatory requirements. The analytical results from the three detectors were compared with the NRC analytical results. Individual sample analysis results and their compariso.,

with the NRC radiological confirmatory measurements analytical results are tabulated in Attachment 2. Attachment 3 describes the criteria used to compare the radiological analytical results. The tabulated results from the three detectors are listed in the following order:

• Radiochemistry Counting Room - Cave 2 e Radiochemistry Counting Room - Cave 3

• Radiochemistry Counting Room - Cave 4 l

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The licensee's radiochemistry counting room gamma isotopic analysis results from-the standards _and samples listed in Attachment 2 showed 100_ percent agreement with NRC gamma isotopic analysis results based on 152 analytical result .2 Conclusion

'he licensee's radiochemistry radiological confirmatory measurements '

performance was outstandin .

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ATTACHMENT 1 i

l 1 PERSONS CONTACTED 1.1 Licensee Personnel

• C, Anderson, Man;ger, Unit 2 Operations

• Boncheff, Licensing. Specialist

• Boyd, licensing Specialist

• Cotton, Manager, Radiation Protection and Radioactive Waste  ;

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• Espolt, Technical Assistant to Plant Manager .thlit 2

• J. J. Fisicaro, Director, Licensing

• M. E. Frala, Supervisor, Nuclear Chemistry

• R. King, Supervisor, Licensing

• C. McKelvy, Chemistry Superintendent :l l

W. R. Pool, Supervisor, Nuclear Chemistry

• J. L. Taylor-Brown, Acting Director, Quality

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• J. D. Vandergrift, Plant Manager, Unit 1 .;

I 1.2 NRC Personnel ,

• S. Campbell, Resloent inspector l l *L. Smith, Senior Resident Inspector l

• Denotes personnel that attended the exit meetin In addition to the

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personnel listed, the inspector contacted other personnel during this l inspection period. EXIT MEETING An exi* .?aating was conducted on January 22, 1993. During this meeting, the insr.ector reviewed the scope- and findings of the report. The licensee did not identify as proprietary, any information provided to, or reviewed by th inspector.

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ATTACHMENT 2 RADIOLOGICAL CONFIRMATORY MEASUREMENT RESULTS ARKANSAS NUCLEAR ONE I

NRC INSPECTION REPORT: 50-313/93-02; 50-368/93-02 j

1 NRC AIR PARTICULI.TE FILTER STANDARD (44710-109)

(Standardized: 08:50, CST, January 19,1993)

Detectors Cave 2, Cave 3, and Cave 4 ANO Results NRC Results AN0/NRC Comparison Nuclide IpCi/Samplel (uCi/ Sample) Ratio Decision Cd-109 1.13810.004E0 1.01510.005E0 1.12 Agreement 1.16610.003E0 1.15 Agreement 1.16410.005E0 1.14 Agreement Co-57 2.113i0.010E-2 1.868 0.013E-2 1.13 Agreement 2.179i0.002E-2 1.17 Agreement 2.13010.014E-2 1.14 Agreement

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Ce-139 2.417i0.013E-2 2.19310.013E-2 1.10 Agreement 2.511 0.0llE-2 1.15 Agreement 2.46310.016E-2 1.12 Agreement Hg-203 4.19510.107E-3 3.70710.100E-3 1.13 Agreement 4.373 0.088E-3 1.18 Agreement 4.20010.013E-3 1.13 Agreement Sn-ll3 3.00410.023E-2 2.677 0.023E-2 1.12 Agreement 3.05210.022E-2 1.14 Agreement 3.0lli0.030E-2 1.12 Agreement

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Attachment 2 (cont')

NRC Results AN0/NRC Comparison AND Results Nuclide IpCi/ Sample) (uci/ Sample) Ratio Decision 5.628i0.033E-2 1.10 Agreement'

Cs-137 6. 20210.031E -2 1.12 Agreement 6.280i0.029E-2 1.10 Agreement 6.17410.043E-2 4.881i0.038E-2 1.07 Agreement Y-88 5.214io.035E-2 1.11 Agreement 5.42210.033E-2 1.08 Agreement 5.279 0.051E-2 Co-60 8.898 0.041E-2 8.225i0.043E-2 1.08- Agree:aent 9.12810.040E-2 1.11 Agreement 9.072 0.058E-2 1.10 Agreement

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-3-Attachment ? (cont')

2 NRC SCOTT CHARC0AL CARTRlDGE STANDARD ( 44712-109)

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(Standardized: 09:00, CST, January 19,1993)-

Detectors CLve 2, Cave 3, and Cave 4 ANO Results NRC Results AN0/NRC Compari son Nuclide heCl/ Sample) .haci/ Sample) Ratio Decision Cd-109 1.14710.004E0 1.07910.005E0 1.07 Agreement 1.19110.004E0 1.10 Agreement 1.19710.005E0 1.11 Agreement

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Co-57 2.137t0.014E-2 2.105t0.017E-2 1.02 Agreement j

' 2.21810.012E-2 1.05 Agreement 2.20510.017E-2 _

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! 2.39210.017E-2 1.04 Agreement Ce-139 Z .48010.014E 2

') .56610.015E-2 1.07 Agreement 1.05 Agreement

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tig' 20: 4. 355c 0.126E -3 3.923.0.l?5E-3 1.11 Agreement -

4.52110.102E-3 _

l.15 Agreement 4.4 8 0.109E-3 1.15 Agreement

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Sn-133 3.06910.027E-2 2.969 0.028E-2 1.03 Agreement 3.14710.024E-2 1.05 Agreement 3.055to.034E-2 i.03 Agreement i

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Cs ,27 6.301 0.035E-2 6.ll4io.038E-2 j.03 Agreement 6.43610.034E-2 1.05 Agreement

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6.22210.047E-2 1.02 Agreement

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AN0 Results NRC Results AN0/NRC Comparison- .

Nuclide (uCi/ Sample) (uC1/ Sample) Ratio Decision- l

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Y-88 5.39310.039E-2 5.22610.041E-2 1.03 Agreement j

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5.60410.036E-2 1.07- Agreement 5.477 0.052E-2 1.05 Agreement

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Co-60 9.1/410.046E-2 8.937i0.050E-2 1.03 Agreement 9.471i0.044E-2 1.06 Agreement-9.35710.062E-2 1.05 Agreement

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-5-Attachment 2 (con't)

3- WASTE LIQUID _ MONITOR TANK SAMPLE - 500 MILLILITERS AND s.9 LITERS (Sampled: 13:45, CST, January 19, 19s])

Detectors Cave 2, Cave 3, and Cave 4 ANO Results NRC Results AN0/NRC Comparison Nuclide (uti/ml (uci/ml Ratio Occision .805 0.020E-5 0.99 Agreement Mn-54 1.790i0.050E-5 0. 9'/ Agreement 1.759!0.045E-b 1.02 Agreement 1.833!0.063E-5 1.696i0.025E-5 0.94 Agreement 1.69310.024E-5 0.91 Aareement 1.62610.035E-5 0.90 Agreement

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Co-58 8.660t0.099E-5, 8.64410.039E-5 1.00 Agreement 9.05410.092E-5 1.05 Agreement 8.613i0.125'E-5 1.00 Agreement 8.582!0.053E-5 0.99 Agreement 8.320!0.048E-5 0.96 Agreement 8.47610.069E-; i 0.98- Agreement Co-60 7.07010.336E-6

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6.962 0.140E-6 1.02 Agreement 6.553i0.301E-6 0.94 Agreement 6.957!0.439E-6 1.00 Agreement 6.558i0.177E-6 0.94 Agreement 6.60110.161E-6 0.95 Agreement _

6.18610.253E-6 0.89 Agreement

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-6-Attachment 2 (cont')

NRC Results AN0/NRC Comparison AND Results

.(pci /ml Ratio Occision Nuclide .(nCi/m_1 1.357 0.174E-6 0.98 Agreement Ag-110H 1.331E-6 1.12 Agreement 1.514E-6 0.66 Agreement 0.892E-6 1.33010.158E-6 0.98 Agreement {

0.90 Agreement l.21810.162E-6 0.87 Agreement 1.18310.232E-6 ,

5.270i0.189E-6 1.03 Agreement Sb-124 5.440i0.480E-6 1.02 Agreement 5.363t0.415E-6 0.87 Agreement 4.56220.618E-6 0.95 Agreement 4.99410.225E-6 0.92 Agreement 4.472t0.199E-6 0.81 Agreement 4.26910.325E-6 _ .94410.063C-5 0.91 Agreement Sb-125 1.769i0.189E-5 0.86 Agreement 1.668t0.176E-5 1.00 Agreement 1.94910.202E-5 i

1.01 Agreement 1.96510.ll5E-5 1.88010.097E-5 0.97 Agreement 1.95110.135E-5 1.00 Agreement 9.072 0.105E- 3.50210.040E-5 ! 1.07 Agreement-Cs-134 9.24110.098E-5 1.09 Agreement 8.91010.135E-5 1.05 Agreement _ _ _ _ - - - _ _ - - - _ _ _

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l-7-Attachment 2 (cont')

ANO Results NRC Results AN0/NRC Comparison Nuclide Ipci/ml fpCi/ml Ratia Decision _

8.76310.059E-5 1.03 Agreement 8.54410.055E-5 1.00 Agreement 8.69610.080E-5 1.02 Agreement Cs-137 1.51210.014E-4 1.48910.005E-4 1.02 Agreement 1.532 0.013E-4 1.03 Agrcement 1.489t0.017E 4 1.00 Agreement 1.51610.007E-4 1.02 Agreement 1.47120.007E-4 0.99 Agreement 1.46710.010E-4 0.99 A9_reement _

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-8-Attachment 2 (cont')

4 CONTAINMENT ATMOSPHERE SAMPLE (Sampled: 14:34, CST, Januar.y 21, 1993)

Detectors Cave 2, Cave 3, and Cave 4 ANO Results NRC Results AN0/NRC Compari30n Nuclide (uti/cc (uCi/cc) R_a t i_o Decision Xe-133 6.35110.128E-5 5.18610.180E-5 1.22 Agreement _

6.40010.ll2E-5 1.23 Agreement _

6.381!0.160E-5 1.23 Agreement Xe-135 5.699 0.240E-6 5.655t0.498E-5 1.01 Agreement 6.22510.248E-6 1.10 Agreement l6.588i0.316E-6 1.16 Agreement

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i -9-Attachment 2 (cont')

5 REACTOR COOLANT GAS SAMPLE (Sampled: 09:57, CS1, January 20, 1993 Detectors Cave 2, Cave 3, and Cave 4 ANO Results NRC Resul AN0/NRC Comparison Nuclide (uCi/ Sample (uCi/ Sample Ratio Decision

, Ar-41 6.86310.015E-1 6.728f0.017E-1 1.02 Agreement 6.96910.016E-1 1.04 Agreement 6.767!0.025E-1 1.01 Agreement Kr-85M 2.35610.019E-2 2.28210.024E-2 _ l.03 Agreement 2.383 0.020E-2 1.04 Agreement 2.29610.025E-2 1.01 Agreement l

Kr-87 !4.3030.054E-2 4.061i0.067E-2 1.06 _

Agreement 4.26310.058E-2 1.05 Agreement 4)2300.101E-2 1.04 Agreement Kr-88 5.40810.069E-2 5.286ic.*7 E-2 1.02 Agreeme .464 0.051E-2 1.03 Agreement 5.38510.088E- 2 1.02 Agreement Xe-133M 6.322il.167E-3 S.49611.033E-3 1.15 Agreement 4.673-0.811E-3 C.e5 Agreement 6.615tl.284E-3 1.20 Agreement Xe-133 1.426 0.006E-1 1.34610.008E-1 1.06 Agreement 1.416 0.005E-1 1.05 Agreement 1.35910.006E-1 1.01 Agreement !

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ANO Results NRC Results AN0/NRC-. Comparison Nuclide (uCi/ Sampl .(pCi/ Sample Ratio Decision

Xe-135M- 1.40610.049E-2 1.804 0.244E-2 0.78 Agreement

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1.23410.174E-2 0.68 Agreement.

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Xe-135 1.562 0.004E-1 1.59410.004E-1 1.04 Agreement 1.64610.004E-1 1.03 Agreement 1.65010.005E-1 1.04 Agreement (1) The isotope had decayed to below the lower 'imit of detectability prior to startir3 the analysis. Therefore, no comparision was made, i

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6 REACTOR COOLANT LIQUID SAMPLE (Sampled: 09:18, CST, January 20,1993)

Datectors Cave 2, Cave 3, and Cave 4 ANO Results NRC Results AN0/NRC Comparison Nuclide (uCi/cc igCi/cc Ratio Decision Na-24 1.137 0.009E-2 1.197 0.010E-2 0.95 Agreement 1.144 0.007E-2 0.96 Agreement

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1.104t0.012E-2 0.92 Agreement f

Co-58 3.140i0.063E-3 2.55710.070E-3 1.22 Agreement l

2.812 0.057E-3 1.10 Agreement

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2.648t0.074E-3 , 1.03 Agreement I-131 1.40610.060E-3 1.374t0.065E-3 1.02 Agreement 1.335t0.046E-3 0.97 Agreement 1$3610.075E-3 0.99 Agreement 1-132 2.724 0.011E-2 2.78110.019E-2 0.98 Agreement 2.632 0.011E-2 0.95 Agreement 2.611 0.017E-2 0.94 Agreement 1-133 1.651i0.008E-2 1.716t0.009E-2 0.96 Agreement 1.636i0.007E-2 0.95 Agreement 1.571 0.009E-2 0.91 Agreement 1-134 4.024io.027E-2 4.000 0.065E-2 1.01 Agreement 3.907 0.032E-2 0.98 Agreement 4.00210.068E-2 1.00 Agreement l

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-12-Attachment 2 (cont')

Nuclide ANO Results NRC Results AN0/NRC Comparison Ip_Ci/samplel (pCi/ sample) Ratio Decision 1-135 3.073 0.028E-2 3.173i0.036E-2 0.97 Agreement 3.05610.028E-2 0.96 Agreement 2.90810.039E-2 0.92 _ Agreement

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Cs-137 2.l?8i0.383E-4 2.84610.473E-4 0.75 Agreement 2.306t0.310E-4 0.81 Agreement 2.067 0.404E-4 0.73 Agreement Cs-138 3.26210.046E-2 3.432 0.104E- .95 Agreement 3.09510.076E-2 0.90 Agreement 2.784!0.226E-2 0.81 Agreetnent

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ATTACHMENT 3 CRITERIA FOR COMPARING RAD 10 CHEMISTRY ANALYTICAL MEASilREMENTS The- following are the criteria used in ~ comparing the results of capability tests and verification measurements. The criteria are based on an empirical relationship established through prior experience and this program's analytical requirements, in these criteria, the judgement limits vary in relation to the comparison of the resolutio Resolstion = NRC VALUE NRC UNCERTAINTY Ratio = LICENSEE VALUE NRC VALUE Comparizons are rade by first determining the resolution and then reading across the same line to the corresponding ratio. The following table shows the acceptance value '

RESOLUTION AGREEMENT RATIO

<4 0.40 - 2.50 4-7 0.50 - 2.00

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8 - 15 C.60 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

[ > 200 0.85 - 1.18

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The above criteria are applied to the following analyses:

(1) Gamma Spectrometry .

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(2) Tritium in liquid samples (3) Iodine on adsorbers

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(4) "Sr and "SR determinations (5) Gross Beta where samples are counted on the same'date using the same reference nuclid .

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