IR 05000338/1981028
| ML20039A049 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/17/1981 |
| From: | Evans C, Montgomery D, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039A044 | List: |
| References | |
| 50-338-81-28, 50-339-81-25, NUDOCS 8112160175 | |
| Download: ML20039A049 (8) | |
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UNITED STATES
NUCLEAR RE"ULATORY COMMISSION
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I REGION 11 101 MARIETTA ST., N.W., SUITE 3100 o
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ATLANTA, GEORGIA 30303 e
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Report Nos. 50-338/81-28 and 50-339/81-25 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, VA 23262 Facility Name: North Anna Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and NPF-7 Inspection at North Anna site near Mineral, VA Inspectors:
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_] / -/ 6 -91 D. Montgomer (/
Date Signed i /Aa/
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Gr'DV Ev4ns D/tWSigned Accompanying Personn 1:
We,11 baum Approved by:
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d. Phflip Stohr.gPPS Branch Chief Date Signed SultMARY Inspection on October 19-22, 1981 Areas Inspected This routine, unannounced inspection involved 40 inspector-hours on site in the areas of quality control and confirmatory measurements including:
review of the laboratory quality control program; review of chemical and radiochemical proce-dures; quality control audits; comparison of the results of split samples analyzed by the 'icensee and the NRC Region II Mobile Laboratory.
Results Of the five areas inspected, no violations or deviations were identified in any areas.
8112160175 811119 PDR ADOCF 05000338 G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees.
- W. R. Cartwright, Plant t1anager
- J. A. Hanson, Superintendent, Technical Services
- E. W. Howell, Assistant Plant Manager
- M. Follows, Staff Assistant
- L. B. Jones, Chemistry Supervisor
- M. A. Harrison, Quality Control Engineer
- A. Hc Stafford, Health Physics Supervisor
- F. L. Thomasson, Senior Health Physicist, Corporate
- J. A. O'Connell, Acting Assistant Health Physics Supervisor Other licensee employees contacted included two technicians.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 22, 1981 with those persons indicated in paragraph 1 above.
In addition, the inspector requested that the licensee provide an area with power receptacles for the NRC Mobile Laboratory. A licensee representative agreed to provide the requested services by January 1,1982.
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Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Laboratory Quality Control Program The inspector reviewed the licensee's quality control program for chemical and radiochemical measurements in the following areas:
a.
Assignment of responsibility and authority to manage and conduct the QC programs:
The Health Physics Supervisor is responsible for radiological measure-ments including the QC program for radiation detection instrument & tion.
Authority to manage day to day operations of the QC program has been
' delegated to an Assistant Health Physics Supervisor who is responsible for the counting room. The Chemistry Supervisor is responsible for the QC program for stable chemistry and associated instrumentation.
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Provisions for Audits / Inspections:
Chapter 18 of the VEPC0 Nucle'ar Power Station Quality Assurance fianual provides for annual audits in the areas of chemistry and health physics to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program. T b Station Resident Quality Control Engineer is responsible for toe implementation of the station audit program.
c.
Methods for Assuring Deficiencies and Deviations in the Program are P.ecognized, Identified, and Corrected:
The individuals conducting audits are required to become familiar with the requirements of the areas to be audited and prepare an audit checklist that is approved prior to use. A written audit report is prepared and distributed within five days from the past audit con-ference. All audit reports are reviewed by the cognizant supervisor and when, applicable, members of the Station Nuclear Safety Operating Committee. The Quality Control Staff is responsible for follow-up action to:
(1) Obtain the written reply to the audit report.
(2)
Evaluate the adequacy of the response.
(3) Assure that corrective action is identified and scheduled for each recommendation.
(4) Assure that any required cuditee follow-up reply is received when due.
(5) Confim that corrective action is accomplished as scheduled.
d.
Quality Control Cross Checks Specific quality control cross checks for laboratory and counting equipment are detailed in the Corporate Health Physics Procedure CHP-3, Rev.1, " Confirmatory tieasurements Using Spiked Samples." Acceptance criteria for the quality control checks are provided with corrective action.
e.
Quality Control of Purchased and Contracted Services Analyses of composite liquid effluent samples for Sr-89, Sr-90, and P-32 are contracted to Teledyne Isotopes, Inc. The Teledyne quality assurance program was audited by Corporate Quality Engineering (Audit Subject - Analytical Measurements of Environmental Samples dated October 21,1981) and found to be acceptable.
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6.
. Review of-Procedures and Records The inspectors reviewed the following procedures and records:
a.
Procedures (1)- HP-3.3.9
~ Health Phydes Survey -Minimum Detectable Activity (MDA) DetermNation, 4/23/79 (2)
HP-3.4.1.1-He'alth Physics Count Room - Instrumentation Opera-tions Beckman Liquid Scintillation Counter LS-1000, 4/23/79 (3)
HP-3.4.1.2 Health Physics Count Room - Instrument Operation Nuclear Measurements Corporation Proportional
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Csunter PC-4, 4/23/79 i
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HP-3.4.1.3 Health Physics Count Room - Instrument Operation
.l Nuclear Data ND 6600 Multichannel Analyzer, 3/12/80
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HP-3.4.1.5 Health Physics Count Room - Instrument Operation
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Nuclear Measurements Corporation Proportional Counter PC-5, 4/23/79 (6)
HP-3.4.1.6 Health Physics Count Room - Instrument Operation Nuclear Measurement Corporation Decade Scaler DS-3, l'
4/23/79 (7)
HP-3.4.1.7 Health Physics Count Room - Instrument Operation Eberline Instrument Corporation Mini Scaler MS-2, 4/23/79 (8)
HP-3.4.1.8 Health Physics Count Room - Instrument Operation Nuclear Data ND-100 Multichannel Analyzer, 4/23/79 (9)
HP-3.4.2.1 Health Physics Count Room - Instrument Calibration Beckman Liquid Scintillation Counter LS-1000, 9/16/80 (10)
HP-3.4.2.2 Health Physics Count Room - Instrument Calibration l
Nuclear Measurements Corporation Proportional l
Counter PC-4 or PC-5, 9/16/80 l
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HP-3.4.2.3 Health Physics Count Roon. - Instrument Instrument Calibration Nuclear Data ND 6600 Multichannel Analyzer, 12/10/80 (12)
HP-3.4.3.1 Health Physics Count Room - Standard Source-Preparation, 4/16/79
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(13) CP-11 Boron High Range Titration, 11/18/77 (14)- CP-12 Boron, Colorimetric, 12/2/77 (15) CP-32 E Calculation, 12/21/78 (16) CP-33 Fluoride, 3/24/77 (16) CP-34 Fluoride, Specific lon Electrode, 2/11/77 (18)~ CP-38 Gross Activity, Beta-Gamma, 4/14/78 b.
Records-(1)
HP-3.4.1.9.2 Multichannel Analyzer (ND-6600) - Energy Calibra-tion, Daily Response, Resolution, and Background Checks: January 1, 1981 to October 20, 1981 (2)
HP-3.4.1.9.1 Quality Control Charts for Count Room Instrumenta-tion - Proportional Counter PC-4: dated 3/1/81 to 9/30/81 Proportional Counter PC-5: dated 7/1/81 to 9/30/81 Geiger Miller Counter MS:2 dated 3/1/81 to 9/30/81 Liquid Scintillation Counter LS100C: dated 3/1/81 to 9/30/81 (3)
HP-3.2.1 Waste Gas Decay Tank Release Recor'ds (Nos. 81-GW-1 through 81-GW-20): January 19, 1981 to August 24,
1981 (4)
HP-3.4.2.3.1 Geli letector Calibration Records:
(15ml. vial, 100 m'
cup,1000 ml. Marinelli, Charcoal cartridge, 100 gas chamber, 47 mm. particulate filter geometries): January 20, 1981 to September 9,
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1981 The inspector discussed the results of the procedure and record review with licensee representatives as noted in paragraphs 8.b, 8.c, and 8.e.
7.
Review of Audits and Interlaboratory Cross Check Program a.
The inspector reviewed the following Quality Assurance audits in the areas of Chemistry and Health Physics and had no further questions:
(1) Audit N-81-05A, June 1, 1981, Health Physics and Radiological Controls.
(2) Audit N-81-04, liarch 20, 1981, Chemistry Audit.
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b.
The inspector discussed the interlaboratoy crosscheck program in the radiochemistry area administrated by the VEPC0 Corporate Health Physics s ta f f.
The inspector reviewed the following Reactor Coolant Split Sample Confirmatory Measurement Results dated February 12, 1981 and July 27, 1981, and Confinnatory Measurements using Spiked Samples dated May 13, 1981.
Disagreemtint was identified for the analyzes of the spiked charcoal cartridge and particulate filter. The licensee is continuing to investigate possible causes for this disagreement.
8.
Inspector Followup Items a.
The inspector reviewed the use of a Sr-90 source plated on stainless steel as a method of efficiency calibration for proportional counters.
The inspector questioned if the beta energy for Sr-90 would I;e representative of the average nuclide beta energies associated with plant contamination, as the use of Sr-90 could underestimate plant contamination levels. A licensee representative indicated that the use of the proportional counters was restricted to air survey filters.
Contamination smears are counted using friskers calibrated with a Tc-99 source plated on stainless steel which would approximate the average nuclide beta energy better than Sr-90. This closes a previously identified item.
(338/80-25-02,339/80-26-02).
f b.
The inspector noted the addition of performance check requirements i
along with acceptance criteria for the Ge(Li) Gamma Spectroscopy System (ND6600), the liquid scintillation counter (LS-100C), and the PC-4 and PC-5 proportional counters into procedures HP-3.4.1.3, HP-3.4.1.1 and HP-3.4.2.2 respectively. The inspector verified that the performance check requirements had been instituted in the daily counting room routine by review of the instrument's Quality Control Charts. This closes a previously identified item.
(338/80-25-01,339/80-26-01).
c.
The inspector noted that procedure HP-3.2.4 for liquid waste sampling had been revised to address improving uncertainty in measurements for the gamma spectrum analysis of a one - liter marinelli liquid composite waste sample by increasing tee counting time to 20 minutes. This closes a previously identified item.
(338/80-25-03,339/80-26-03).
d.
The inspector determined from discussons with licensee representatives that the charcoal cartridges used for radioiodine sampling are not i
impregnated with TEDA. The inspector noted that the cartridges without
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TEDA may not be as efficient for collection of organic radiciodine species.
Licensee representatives' indicated that they are presently evaluating the collection efficiency of their charcoal cartridges for different radiciodine species and different sampling flow rates. The results of this study will be reviewed during a subsequent inspection.
(338/81-28-01,339/81-25-01).
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e.
The inspector noted that the procedure HP-3.4.1.3 for Operation of the Ge(Li) Gamma Spectroscopy System does not specify a limit for analyzer dead time. The inspector identified examples of gaseous waste charcoal cartridge and 100 cc. chamber sample analyses which exhibited dead times in excess of 20%.
Excessive dead time can effect gaseous waste
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accountability by underestimating principal nuclide gamma emitters.
The inspector noted that the calibration prccedure should incorporate provisions for calibration of the Ge(Li) detector at various distances from the detector surface to accomodate higher activity levels that are
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encountered in gaseous waste samples and in nonroutine samples.
Licensee representatives agreed to review this area of concern.
(338/81-28-02,339/81-25-02).
9.
Confimatory Measurements Liquid and gaseous samples were collected during this inspection and counted by the licensee and the NRC RII Mobile Laboratory to verify the licensee's capability to measure radionuclides in effluent samples. The samples were analyzed by gamma ray spectroscopy and included samples from the liquid clarifier effluent, reactor coolant, and waste gas decay tank (gas vial) and a charcoal cartridge and particulate filter from the plant vent. An aliquot of the liquid clarifier effluent sample was sent to the NRC contract laboratory for H-3, Sr-89, and Sr-90 analyses. The licensee was requested to perfom the same analyses and report the results to NRC:RII for comparison; this will be reviewed in a subsequent inspection. (338/81-28-03; 339/81-25-03) The results of the licensee and NRC analyses are presented in Table 1 with the acceptance criteria in Attachment 1.
The results show agreement for all analyses except the gaseous waste sample where the licensee's reported concentration for Xe-133m was 0.52 times less than the NRC concentration.
Rased on the acceptance criteria this constitutes -
"possible agreement". The inspector noted upon examination of the
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licensee's nuclide library that the Xe-133m branching decay ratio was higher than that used by the NRC library. This difference in branching decay ratios could have contributed to the lack of agreement. The inspector indicated the necessity to update the nuclide library with branching decay data from recent publications. Licensee representatives agreed to review this area of concern. (338/81-28-04, 339/81-25-04).
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ATTACHMENT 1 RESULTS OF CONFIRMATORY MEASUREMENTS AT NORTH ANNA NUCLEAR PLANT Concentration, microcuries/cc Sample Isotope NRC North Anna Ratio Resolution Comparison Particulate'
Co-58 (1.121.08)E-10 1.25 E-10 1.33
Agreement Filter Cn-60 (5.731.68)E-11 6.76E-11 1.18 8.5 Agreement I-131 (1.44*.01)E-10 Not Detected No Comparison Cs-134 (1.63.01)E-11 1.51E-10
.93 163 Agreement Cs-137 (3.241.01)E-11 3.11E-10
.96 250 Agreement Charcoal I-131 (5.24.07)E-09 5.312E-09 1.01
Agreement Cartridge Waste Gas Xe-133 (6.77.01)E-01 5.83 E-01
.86 620 Agreement Holdup Tank Xe-133m (1.091.12)E-03 0.562E-03
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Possible-Agreement Xe-131m (1.241.08)E-02 0.97E-02
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Agreement Kr-85 (9.19 3.1)E-03 Not Detected
No Comparison Reactor I-131 (2.17.05)E-02 2.08E-02
.96
Agreement Coolant I-133 (3.59 0.5)E-02 3.29E-02
.91
Agreement I-135.
(4.39.19)E-02 4.03E-02
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Agreement Cs-137 (4.21i.35) E-03 3.79 E-Da
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Agreement Cs-138 (9.991.30)E-02 1.32E-02 1.32
Agreement C0-58 (2.951.36) E-03 4.56E-03 1.54
Agreement Ru-106 (2.721.31)E-02 Not Detected No Comparison Clarifier Xe-133 (2.76.02)E-04 3.00E-04 1.08 137 Agreement Effluent Co-58 (7.05.09)E-05 7.03E-05 1.01
Agreement
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Co-60 (4.561.29) E-06 3.71E-06 0.81
Agreement I-131 ( 2. 56*. 24) E-06 2.82E-06 1.17
Agreement
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Attachment 1 CRITERIA FOR COMPARING ANAL"TICAL 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.
In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty. As that ratio, referred to in this program as " Resolution",
increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.
LICENSEE VALUE
" NRC REFERENCE VALUE Possible Possible Resolution Agreement Agreement A Agreement B
<3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Camma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and Sr Determinations.
Cross Beta where samples are counted on the same date using the same reference nuclide.