IR 05000244/1978019
| ML17244A204 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/18/1978 |
| From: | Kottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A203 | List: |
| References | |
| 50-244-78-19, NUDOCS 7812010150 | |
| Download: ML17244A204 (18) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-244/78-19 Docket No.
50-244 License No.
DPR-18 Priority Category C
Licensee:
Rochester Gas
& Electric Com any 89 East Avenue Rochester, New York 14649 Facility Name:
Ginna Nuclear Station Inspection at:
Ontario, New York Inspection conducted:
Sept ber 19-21, 1978 Inspectors: +
J. J. Kott
,
Ra iation Spectra
~st D.
M. Gloski Co-o da signed date signed Approved by:
r, e,
nvsronmen a
and Speci 1 Projects Section, FF&MS Branch date signed 0 lb7P date s gned Ins ection Summar:
Ins ection on Se tember 19-21 1978 Re ort No.
50-244 78-19
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d radiochemical measurements program using NRC: I Mobile Radiological Measurements Laboratory and laboratory assistance provided by DOE Radiological and Environ-mental Services Laboratory.
Areas reviewed included:
program for quality control of analytical measurements, audit results, performance on radiological. analyses of split actual effluent samples, and effluent control records and procedures.
The inspection involved 20 inspector-hours onsite by one NRC regional based inspector.
Results:
Of the four areas inspected, no'items of'oncompliance were identified.
8 1 2 0 1 0 1 5c Region I Form 12 (Rev. April 77)
DETAILS 1.
Persons Contacted Princi al Licensee Em lo ees
- B. A. Snow, Plant Superintendent
- E. Demeritt, Supervisor, Chemistry and Health Physics
- D. Filien, Radiochemist N. Shaw, gC Specialist The inspector also interviewed other licensee employees including members of the chemistry, health physics and gC staffs.
- denotes those present at exit interview.
2.
Licensee Action on Previous Ins ection Findin s
(Closed)
Unresolved item (50-244/77-12-01):
Air ejector monitor.
During a previous inspection (NRC Inspection Report 50-244/77-12, dated July 19, 1978) the NRC inspector noted the licensee's air ejector monitor was inoperative.
The inspector noted that if the licensee's air ejector monitor is inoperative at least five 'days per week specific sample analyses are required.
This inspector noted that the 1icensee's air ejector was not inoperative five days per week and therefore sampling was not required.
This inspector also reviewed data which indicated that the air ejector monitor had been repaired.
In addition,.this inspector examined the air ejector monitor to verify its operability.
This item is closed.
3.
Laborator C Pro ram The inspector reviewed the licensee's program for quality control of analytical measurements and noted that the licensee's program remains the same as documented in Inspection Report 50-244/77-12 with the licensee's quality control program contained in the following procedures:
HP-10.1 HP-10.4 HP-10.5 HP-10.6 guality Control of Counting Systems Calibration of Alpha and Beta Counters Efficiency Calibration of Gamma Spectometer Calibration of the Liquid Scintillation Counter
~,
These procedures provide for calibrations and operational checks of counting equipment including backgrounds, source checks and periodic chi-squared tests.
The inspector reviewed the licensee's background, source check and chi-squared data for the period January to August 1978.
The inspector discussed laboratory gC with the licensee.
The inspector also discussed various aspects of NRC Regulatory Guide 4.15, guality Assurance for Radiological Monitoring programs (Normal Operations) -'Effluent Streams and the Environment.
The inspector noted the licensee had no regulatory requirements in the area of laboratory gC and had no further questions in this area.
No items of noncompliance were identified.
Audit Results The inspector determined that the licensee's effluent monitoring program was on the corporate gA audit list.
The inspector reviewed audits 78-22:GS dated July 1978 and 78-12:GS dated April, 1978; which were the most recent audits performed in this area.
The
~ inspector noted that an audit for this area was scheduled for December, 1978.
The inspector had no further questions in this area.
No items of noncompliance were identified.
5.. Confirmator Measur'ements During the inspection, actual liquid and gaseous effluent samples were split between the licensee and NRC: I for the purpose of inter-comparison.
The effluent samples were analyzed by the licensee using his normal methods and equipment, and the NRC using the NRC: I Mobile Radiological Measurements Laboratory.
Joint analyses of actual effluent samples determined the licensee's capability to measure radioactivity in effluent samples.
In 'addition, a liquid effluent sample was sent to the NRC reference laboratory, Department of Energy, Radiological and Environmental Services Laboratory (RESL), for analysis requiring wet, chemistry.
The analyses to-be performed on the sample are:
gross alpha, gross beta and tritium.
These results 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 the sample measurements compared indicated that all of the measurements were in agreement under the criteria used for comparing results (see Attachment 1) with the exception of the measurement of
6.
radioiodine in charcoal cartridges.
The licensee s radioiodine measurements were higher than the NRC measurements and were in a conservative direction and would not result in the licensee exceeding any effluent release limits..
The licensee agreed to check his calibration in this area.
The inspector stated this would be reviewed in a subsequent inspection.
(78-19-01)
The results of the comparisons are listed in Table I.
In splitting the liquid samples the inspector noted that in certain instances the licensee's computer based multi channel analyzer system reported no. activity present whe~ in fac) activity was present in amounts of approximately
to 10 uCi/ml.
The licensee stated that when more than a certain number of counts, were accumulated in any one channel this seemed to happen.
The inspector noted that the licensee performs gamma isotopic analyses of weekly liquid composite samples to meet his technical specification re-quirements.
The inspector inquired if the licensee had noted this problem with liquid waste composite samples.
The licensee stated that he,had not noticed this problem and that an excessive number of counts would only occur in a "hot" sample and radwaste samples contained'ow levels of radioactivity.
The inspector noted that although the waste samples contained low levels of activity, they were counted for a. long period of time which could result in an excessive number of counts being accumulated in a channel.
The inspector determined that the licensee had installed this computer based multichannel analyzer in July 1978 and, therefore, he reviewed all the waste composite sample analyses from'July, 1978 to determine if this error had been made in the analysis.
The inspector noted no samples in which the error had been made.
The licensee stated that he would attempt to resolve this problem.
In a telephone conversation between J. J.
Kottan of NRC: I and. D. Filion. of RGSE on October 10, 1978, the licensee stated the computer 'problem had been repaired.
The inspector stated this area would be reviewed during
'- a subsequent inspection.
(78-19-02)
The inspector had no further questions in-this area.
No items of'oncompliance were identified.
Records and Procedures F
The inspector reviewed the following records and procedures:
a.
Gaseous effluent analysis-data (January, 1978 to August, 1978)
b.
Liquid effluent analysis data, including weekly composite gamma isotopic analysis (January, 1978 to August, 1978)
c.
Counter cal,ibration and check records (January, 1978 to August, 1978)
d.
The following procedures:
(1)
RD-Z, Containment Purge Releases (2)
RD-3, Plant Vent Iodine and Particulate Releases Sampling and Analysis (3)
RD-4, Vent Radiogas Background and Factor Determination (4)
RD-6, Gas,Decay Tank Releases (5)
RD-8, Liquid Radwaste Compositing and Analysis 7.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on September 21, 1978.
The inspector summarized the purpose and scope of the inspection and the inspection finding TABLE
GINNA VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE RESULTS IN TOTAL MICROCURIES COMPARISON RESL Standard Filter Co-57 Cs-134 Cs-137 Co-60 (1.06~O.03)E-2 (1.54+0.06)E-2 (7.840.3)E-3 (1.0240.05)E-2 (9.83+?)E-3 (1.30+?)E-2 (7.0+?)E-3 (9.78+?)E-3 Agreement Agreement Agreement Agreement Charcoal Car tridge 0902 hrs 9/20/78 I-131 I-133 (4.38%.22)E-3 (3.39+0.17)E-3 (8.43+0.04)E-3 (6.27+0.34)E-3 Disagreement Disagreement
TABLE
GINNA VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE RESULTS IN MICROCURIES PER MILLILITER COMPARISON Waste Gas Decay Tank Xe-133 1405 9/19/78 (1. 70%.17) E-4 ( 2. 57+? ) E-4 Agreement Waste Hold Up Tank 1800 9/19/78 Cs-137 Co-60-Cs-134 (4.64+0.02)E-2 (5.74+0.29)E-4
.
(5. 4240.05) E-3 (5.11+?)
E-'2 (5.84+?)
E-4 (5.59+?)
E-3 Agreement Agreement Agreement
TABLE
GINNA VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE RESULTS IN MICROCURIES PER MILLILITER COMPARISON Reactor Coolant 1345 I-131 9/20/78 I-133 I-135 (2.0540.03)E-2 (2.2640.05)E-1 0.33+0.02 (2.13+0.82)E-2 (2.0540.11)E-1 (2.6340.24)E-1 Agreement Agreement Agreement
Attachment
Criteria for Com grin 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 judgement 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 RATIO~ NRC REFERENCE VALUE Resolution
~Arcement Possible A reement A
Possible A reement B
(34-7 8-15 16 50 51 200
>200 0.4 - 2.5 0 5 2.0.66 0.75 1.33 0.80 1.25 0.85 1.18.0 0.4 - 2.5.0.66 0.75 - 1.33 0.80 1.25 No Comparison.0.5.0.66 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" criteiia are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide'.