IR 05000220/1990020
| ML17056A951 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/16/1990 |
| From: | Bores R, Kottan J, Mcnamara N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056A950 | List: |
| References | |
| 50-220-90-20, 50-410-90-19, NUDOCS 9009050326 | |
| Download: ML17056A951 (24) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION.
REGION I
50-220/90-20 Report Nos.
50-410/90-19 50-220 Docket Nos.
50-410 OPR-63 License Nos.
NPF-69 Licensee:
Nia ara Mohawk Power Cor oration 301 Plainfield Road S racuse New York 13212 Facility Name:
Nine Mile Point Units 1 5
Inspection At:
Scriba New York Inspection Conducted:
Jul 23-27 1990 Inspectors N.
T.
Mc amara, Physical Science Technician Effluents Radiation Protection Section (ERPS),
Facilities Radiological Safety and Safeguards Branch ( FRSSB), Division of Radiation Safety and Safeguards (DRSS)
5 -/4 -9o date J. J.
Ko an, Laboratory Specialist, ERPS, FRSSB, ORSS
& -/&-lo date Approved by:
RE J.
Bores, Chief, ERP
,
F SB, D
SS 8-/4-7o date Ins ection Summar
Ins ection on Jul 23-27 1990 Combined Ins ection Re ort Nos. 50-220/90-20 and 50-410/90-19 Areas Ins ected:
Routine, unannounced inspection of the radiological and non-radiological chemistry programs.
Areas reviewed included:
confirmatory measurements-radiological, standards analysis-chemistry, and laboratory QA/QC.
Results:
Of the areas reviewed, no violations were identifie DETAILS 1.0 Individuals Contacted Princi al Licensee Em lo ees
"W. Allen, MATS
- J. Blasiac, Chemistry and Radiochemistry Supervisor
"G. Corell, Unit 1 Chemistry Supervisor
"K. Dahlberg, Unit 1 Station Superintendent
"J. Firlit, Vice President Nuclear Generation
- T. Kurtz, Unit 2 Chemistry Supervisor
'. Volza, Superintendent of Chemistry and Radiation G. Brownell, Regulatory Compliance C.
Senska, Unit 1 Assistant Chemistry Supervisor B. Holloway, General Engineer Unit 1 Chemistry J.
Woods, Unit 1 Chemistry, Chief Technician M. West, Unit 1 Chemistry Technician P.
Shene, Unit 1 Chemistry Technician S.
Sipowicz, Unit 1 Chemistry Technician C. Nessel, Unit 1 Chemistry Technician C. Merritt, Unit 2 Assistant Chemistry Supervisor D. Leuengerber, Unit 2 Chemistry, Chief Technician L. Albrecht, Unit 2 Chemistry Technician R.
Samson, Unit 2 Chemistry Technician P. Thingvoll, Unit 2 Chemistry Technician P. Tardane, Unit 2 Chemistry Technician Protection 1.2 Other Personnel W. Cook, NRC Senior Resident Inspector R.
Laura, NRC Resident Inspector R.
Temps, NRC Resident Inspector
"Denotes those personnel who attended the exit meeting on July 27, 1990.
The inspectors also interviewed other licensee personnel including other members of the chemistry staffs.
2.
~Pur ose The purpose of this routine inspection was to review the following areas.
The licensee's ability to measure radioactivity in plant systems and effluent samples, and ability to measure chemistry parameters in various plant systems.
The licensee
'
ability to demonstrate the acceptability of
'analytical results through implementation of a laboratory QA/QC progra.
Laborator Or anization and 0 eration Nine Mile Point Units 1 and 2 each had a dedicated chemistry laboratory and a dedicated counting room.
The chemistry laboratories and counting rooms were similarly equipped with the exception of an atomic absorption spectrometer (AA) which was located in the Unit 1 laboratory.
All site metals analyses were performed using this AA.
The chemistry laboratory and counting room of each unit operated under the direction of a Unit Supervisor, each Unit Supervisor reported to the site Chemistry and Radiochemistry Supervisor who in turn reported to the site Superintendent of Chemistry and Radiation Protection.
The data listed in Tables I and II identify which counting room (and detector)
or which laboratory was used for the sample analyses.
4.'adiolo ical and Chemical Measurements 4. 1 Confirmator Measurements Radiolo ical I
During this part of the inspection, liquid, airborne particulate (filter) and iodine (charcoal cartridge),
and gas samples were analyzed by the l'icensee and the NRC for the purpose of intercomparison.
The same samples were analyzed by the licensee and the NRC with the exception of the reactor water samples and the Unit 1 waste collector tank sample, which were actual split samples.
Where possible, the samples are actual effluent samples or inplant samples which duplicated the counting geometries used by the licensee for effluent sample analyses.
These samples were. analyzed by the licensee using routine methods and equipment and by the NRC: I Mobile Radiological Measurements Laboratory.
Joint analyses of actual effluent samples are used to verify the licensee's capability to measure radioactivity in effluent and other samples with respect to the Technical Specifications and other regulatory requirements.
In addition, a liquid effluent sample was sent to the NRC reference laboratory, Department of Energy, Radiological and Environmental Sciences Laboratory (RESL), for analyses requiring wet chemistry.
The analyses to be performed on the sample are Sr-89, Sr-90, Fe-55, H-3, and gross alpha.
The results of these analyses will be compared with the licensee's results when received at a later date and will be documented in a subsequent inspection report.
The results of an effluent sample split between the licensee and the NRC during a previous inspection on August 3-7, 1987 (Combined inspection Report Nos.
50-220/87-15 and 50-410/87-24)
were also compared during this inspectio The results of the sample measurements comparisons indicated that all of the measurements were in agreement under the criteria for comparing results.
(See Attachment i.)
The results of the radioactivity measurements comparisons are listed in Table I.
The inspector had no further questions in this area.
No violations were identified.
4.2 Standards Anal ses Chemical During this patt of the inspection, standard chemical solutions were submitted to the licensee for analysis.
The standard solutions were prepared by Brookhaven National Laboratory (BNL) for the NRC, and were analyzed by the licensee using routine methods and equipment.
The analysis of standards is used to verify the licensee's capabi,lity to monitor chemical parameters in various plant systems with.respect to Technical Specifications and other regulatory requi rements.
In addition, the analysis of standards is used to evaluate the licensee's procedures with respect to accuracy and precision.
I The standards were submitted to the licensee for analysis in triplicate at three concentrations spread over the licensee's normal calibration range.
The boron analyses were performed in duplicate at the Unit 1 laboratory and singly at the Unit 2 laboratory due to the lack of sufficient volume of the NRC supplied standard to perform the analysis in triplicate.
The results of the standards measurements comparisons indicated that all of the measurements were in agreement or qualified agreement under the criteria used for comparing results.
(See Attachment 2.)
The data for the comparisons are presented in Table II.
The Unit 2 laboratory chloride results presented in Table II are those obtained after a reintegration of the chromatogram chloride peak with corrections made for an interference peak which was present in the chromatogram.
The Unit-=1 laboratory ion chromatography ( IC) system rou'tinely resolved the chloride and interference peak.
The inspector discussed this matter with the licensee, and the licensee stated that this area would be reviewed and the Unit 2 laboratory IC method parameters adjusted as necessary.
The inspector stated that this area would be reviewed during a subsequent inspection.
The inspector had no further questions in this area.
No violations were identified.
The inspector reviewed the licensee's chemistry and radiochemistry laboratory QA/QC program.
This program is described in Procedure S-CSP-15V,
"Quality Assurance of Chemistry/Radiochemistry Analytical Results".
This procedure provides for both an interlaboratory QC program and an intralaboratory QC program.
The intralaboratory QC program
i
consisted of instrument and procedure control charts.
The interlaboratory program consisted of the analysis of unknown samples from outside laboratories.
Two outside laboratories were used to supply unknown samples for the analysis of chemical parameters and one outside laboratory was used to supply unknowns for radioactivity analyses.
The licensee's procedure contained acceptance criteria for comparing these results.
The inspector noted that these spiked samples were used by the licensee as technician proficiency checks.
Also included in the interlaboratory program was the vendor laboratory utilized by the licensee for performing radiochemical analyses of effluent samples.
The inspector review selected data generated by the licensee's laboratory gC program for 1989 and 1990 to date and noted that, the licensee appeared to be implementing the program as required.
had no further 6.0 Exit Interview In reviewing the above data the inspector noted that the interlaboratory gC program was just being implemented at the Unit 2 laboratory.
Additionally, the inspector noted that the interlaboratory data discussed in the above paragraph was not plotted on any type of control chart.
The inspector discussed these matters with the licensee and the licensee stated that future interlaboratory gC data would be plotted, and the interlaboratory gC program at Unit 2 would be implemented to the same extent as the program at Unit 1.
The inspector stated that the above areas would be reviewed during a subsequent inspection.
The inspector questions in this area.
No violations were identified.
The inspector met with the licensee representatives denoted in Section
at the conclusion of the inspection on July 27, 1990.
The inspector summarized the purpose, scope and findings of the inspectio SAMPLE Table I Nine Mile Point Units
8 2 Verification Test Results ISOTOPE NRC VALUE LICENSEE VALUE Results in Microcuries Per Milliliter COMPARISON Liquid Radio-active Waste 1445 hrs 7-25-90 (Unit.1, Det.
1)
Cr-51 Mn-54 Co-58 Co-60 Zn-65 Na-24 (2.051+0.008)E-3 (1. 222+0. 011) E-4 (2.84+0.09)E-5 (1. 621+0. 012) E-4 (3.68+0.03)E-4 (2. 02+0. 14) E-4 (2.02+0.07)E-3 (1. 10+0. 03) E-4 (2.80+0.11)E-5 (1. 60+0. 05) E-4 (3.62+0.10)E-4 (2.00+0.06)E-4 Agreement Agreement Agreement Agreement Agreement Agreement Results in Total Microcuries Offgas Parti-culate Filter 1000 hrs 7-20-90 (Unit 1, Det. 2)
Offgas Charcoal Cartridge 1000 hrs 7-20-90 (Unit 1, Det.
1)
Ba-140 Cs-137 La-140 I-131 (3.64+0.07)E-2 (1. 90+0. 12) E-3 (2. 51+0. 03) E-1 (4.2+0.3)E-3 (3.6+0.2)E-2 (1. 8+0. 2) E-3 (2.50+0.09)E-1 (3.7+0.3)E-3 Agreement Agreement Agreement Agreement Reactor Water 1100 hrs 7-25-90 (Unit 1, Det.
2)
Reactor Water 1100 hrs 7-25-90 (Unit 1, Det.
1)
Results in Microcuries Per Milliliter Cr -51 (3. 60+0. 02) E-2 (3. 40+0. 13) E-2 Zn-65 (1. 80+0. 05) E-3 (1. 80+0. 10) E-3 Na-24 (1. 056+0. 006) E-2 (1. 05+0. 04) E-2 Cr-51 (3. 60+0. 02) E-2 (3. 7+0. 2) E-2 Zn-65 (1. 80+0. 05) E-3 (1. 8+0. 2) E-3 Na-24 (1. 056+0. 006) E-2 (1. 07+0. 04) E-2 Agreement Agreement Agreement Agreement Agreement Agreement Offgas 1330 hrs 7-24-90 (Unit 1, Det.
1)
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> count Kr-85m Kr-87 Kr-88 Xe-135 (1. 8+0. 2) E-4 (1. 36+0. 08) E-3 (7.6+0.6)E-4 (5.2+0.2)E-4 (2.0+0.2)E-4 (1. 15+0. 08) E-3 (8.0+0.6)E-4 (5.3+0.2)E-4 Agreement Agreement Agreement Agreement
SAMPLE Table I (continued)
Nine Mile Point Units 1 & 2 Verification Test Results ISOTOPE NRC VALUE LICENSEE VALUE Results in Microcuries Per Milliliter COMPARISON Offgas 1330 hrs 7-24-90 (Unit 1, Det.
1)
4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. count Kr-85m (2.0+0.2)E-4
Ãe-135 (5. 3+0. 2) E-4 (2. 1+0. 2) E-4 (5.8+0.3)E-4 Agreement Agreement Liquid Radio-active Waste 0000 hrs 7-25-90 (Unit 1, Det. 2)
Liquid Radio-active Waste 1445 hrs 7-25-90 (Unit 2, Det. 4)
Co-60 Cr-51 Mn-54 Co-58 Co-60 Zn-65 Na-24 (4.7+0.2)E-7 (2.051+0.008)E-3 (1.222+0.011)E-4 (2.84+0.09)E-5 (1.621+0.012)E-4 (3.68+0.03)E-4 (2.02+0
~ 14)E-4 (4.7+0.3)E-7 (2.00+0'.07)E-3 (1. 07+0. 03) E-4 (2. 64+0. 11) E-5 (1. 50+0
~ 04) E-4 (3.70+0. 11)E-4 (2.00+0.06)E-4 Agreement Agreement Agreement Agreement, Agreement Agreement Agreement Results in Total Microcuries Offgas Parti-culate Filter 1000 hrs 7-25-90 (Unit 2, Det.
5)
Ba-140 (3.64+0.07)E-2 Cs-137 (1. 90+0. 12) E-3 La-140 (2. 51+0
~ 03) E-1 (4.0+0.2)E-2 (2.0+0.2)E-3 (2.34+0.09)E-1 Agreement Agreement Agreement Reactor Water 1100 hrs 7-25-90 (Unit 2, Det.
5)
Cr-51 Zn"65 Na-24 Results in Microcuries Per Milliliter (3.60+0.02)E-2 (3.01+0. 13)E-2 Agreement (1.80+0.05)E-3 ( 1.70+0.07)E-3 Agreement (1.'056+0.006)E-2 (9.3+0.3)E-3 Agreement Reactor Water 1100 hrs 7-25-90 (Unit 2, Det.
4)
Cr-51 (3.60+0.02)E-2 (4.0+0.2)E-2 Zn-65 (1. 80+0. 05) E-3 (1. 9+0. 2) E-3 Na-24 (1. 056+0. 006) E-2
" (1. 07+0. 04) E-2 Agreement Agreement Agreement
SAMPLE Table I (continued)
Nine Mile Point Units 1 & 2 Verification Test Results ISOTOPE NRC VALUE LICENSEE VALUE Results in Microcuri es Per Milliliter COMPARISON Liquid Radi.o-active Waste" 1015 hrs 8-5-87 Fe-55 H-3 Sr-89 Sr-90 gross alpha (2+5)E-8 (2.01+0.03)E-3 (3. 1+0. 2) E-7 (1. 1+3. 8) E-9 (5+7) E-10
<1. 2E-6 (2. 0+0. 1) E-3 (3. 1+0. 3) E-7
<1. 5E-8
<6. 1E"8 No Comparison Agreement Agreement Agreement No Comparison Results in Total Microcuries Offgas Charcoal Cartridge 1000 hrs 7-20-90 (Unit 2, Det.
4)
Offgas Charcoal Cartridge 1000 hrs 7-20-90 (Unit 2, Oet.
5)
I-131 I-131 (4.2+0.3)E-3 (4.2+0.3)E-3 (3.5+0.3)E-3 (3.9+0.3)E-3 Agreement Agreement Results in Microcuries Per Milliliter Offgas 1330 hrs 7-24-90 (Unit 2, Det.
4)
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> count Kr-85m Kr-87 Xe-135 (2. 12+0. 15) E-4 (1.14+0.07)E-3 (5. 1+0. 2) E-4 (1.6+0.2)E-4 ( 1.30+0.08)E-3 (5
~ 1+0. 3) E"4 Agreement Agreement Agreement Offgas 1330 hrs 7-24-90 (Unit 2, Oet.
4)
4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> count Xe-135 (5.0+0.2)E-4 Kr-85m ( 1.7+0.2)E-4 (6.0+0.3)E-4 (1. 90+0. 14) E-4 Agreement Agreement Sample split during previous inspection
TABLE II Nine Mile Point Units 1 & 2 Chemistry Test Results Chemical Parameter Method of
~Anal sis*
NRC Known Value Licensee Ratio Measured Yalue
~LIC/NRC
~Com ari son Results in arts er billion b
Chloride (Unit 1)
Chloride (Unit 2)
Sulfate (Unit 1)
Sul fate (Unit 2)
Fluoride (Unit 1)
'luoride (Unit 2)
Silica (Unit 1)
Silica (Unit 2)
IC IC IC IC I.SE ISE SP SP 3.0+0.2 6.2+0.4 9.5+0.5 3.0+0.2 6.2+0.4 9.5+0.5 1.9+0.3 3.8+0.4 6.0+0.4 1.9+0.3 3.8+0.4 6.0+0.4 24.0+1.0 48+2 74+3 24.0+1.0 48+2 74+3 24+2 55.0+1.0 80.5+1.5 24+2 55.0+1.0 80.5+1.5 2.90+0.06 5.54+0.10 8.5+0.2 3.03+0.15 5.92+0.09 9.6+0.3 1.92+0.03 3.77+0.06 5.98+0.04 1.95+0.09 3.760+0.010 5.75+0.04 21+0 42.2+0.3 65.4+0 24.0+0.5 49.8+0.8 75.5+0.5 26.3+0.4 49.4+1.3 69.3+0.6 25.5+0.5 49.5+0 69.4+0.9 0.97+0.07 0.89+0.06 0.89+0.05 1.01+0.08 P.95+P.P6 1.01+0.06 1.01+0.16 0.99+0.10 1.00+0.07 1.0+0.2 0.99+0.10 0.96+0.06 0.88+0.04 0.88+0.04 0.88+0.04 1.00+0.05 1.04+0.05 1.02+0.04 1.10+0.09 0.90+0.03 0.86+0.02 1.06+0.09 0.90+0.02 0.86+0.02 Agreement Qualified Agreement Qualified Agreement Agreement
-'Agreement Agreement Agreement Agreement Agreement Agreement Agreement
'greement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Qualified Agreement Qualified Agreement Agreement Qualified Agreement Qualified Agreement
TABLE II (continued)
Nine Mile Point Units 1 5
Chemistr Test Results Chemical Parameter Method of A~nal sin*
NRC Known Value Licensee Ratio Measured Value
~LIC/MRC
~Com ari son Results in arts er billion b
Boron (Unit 1)
Boron (Unit 2)
1030+20 2990+40 5100+100 1030+20 2990+40 5100+100 1023+10'010+20'974+10'009'027'045'.99+0.02 1.007+0.015 0.98+0.02 0.98 1.01 0.99 Agreement Agreement Agreement Agreement Agreement Agreement
" NOTES IC SPTit. =
ISE Ion Chromatography UV-Vis Spectrophotometry Titration (after mannitol addition) with PHT end point Ion Specific Electrode
'Duplicate Analysis
'Single Analysis
ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICALMEASUREMENTS 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 judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty.
As the 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.
Resolution'atio for A reement'3 4-7 8-15 16 - 50 51 ; 200
>200 No Comparison 0.5 - 2.0 0.6 - '1.66 0.75 - 1.33 0.80 - 1.25 0.85 1.18
'Resolution
= (NRC Reference Value/Reference Value Uncertainty)
'Ratio
= ( License Value/NRC Reference Value)
ATTACHMENT 2 Criteria for Com grin Anal tical Measurements This attachment provides criteria for comparing result of capability tests.
In these criteria the judgement limits are based on data from Table 2. 1 of NUREG/CR-5244,
"Evaluation of Non-Radiological Water Chemistry at Power Reactors".
Licensee values within the plus or minus two standard deviation range (+2Sd) of the BNL known value are considered to be in agreement.
Licensee values outside the plus or minus two standard deviation range but within plus or minus three standard deviation range (+3Sd) of the BNL known values are considered to be in qualified agreement.
Repeated results which are in qualified agreement will receive additional attention.
Licensee values greater than the plus or minus three standard deviations range of the BNL known value.are.in disagreement.
The standard deviations were computed using the average percent standard deviation values of each analyte in Table 2. 1.
The 'ranges for the data in Table II are as follows:
A~nal te Agreement Ran<ac Qualified Agreement Ran e
Chloride 2.8-3.2 5.7-6.7 8.8-10.2 2.7-3.3 5.5-6.9 8.5-10.5 Sulfate 1.7"2.1 3.4-4.2 5.4-6.6 1.6-2.2 3 '-4.3 5.2-6.8 Fluoride 21-27 42-54 65-83 20-28 40-56 61-87 Silica 22.2-26.8 50.0-60.0 73.0-88.0 21.0-28.0 47.3-62.5 69.0-92.0 Boron 1008-1052 2926-3054 4991-5209 997-1063 2894-3086 4937-5263