IR 05000244/1979007
| ML17244A716 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/21/1979 |
| From: | Kottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A715 | List: |
| References | |
| 50-244-79-07, 50-244-79-7, NUDOCS 7907300050 | |
| Download: ML17244A716 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
p tp. ~pp-2 Docket No.
50-244 License No.
DPR-18 'riority Category Licensee:
Rochester Gas and Electric Cor oration 89 East Avenue Rochester, New York 14649 Facility Name:
Ginna,Nucl.ear Station Inspection at:
Ontario, New York
'
Inspection conducted:
Narc 13, 1979 Inspectors:
J: J. Kottan, Radiation Specialist da si ned date signed Approved b
J.
P. Stohr, ief, Environmental and Special Projects Section, FFEMS Branch date signed da e si ned Ins ection Summar
Ins ection on March 13, 1979 Re ort No. 50-244/79-07
~AP:
'1
'
2
ff1
pl split between the licensee and NRC:I during a previous inspection,.on September 19-21, 1978.
The comparison of these results involved.no onsite time.
Results:
Within the areas inspected, no items of noncompliance were oetserved.
Region I Form 12 (Rev. April 77)
79073000 K~
"g'('
DETAILS Persons Contacted D-. Filian, Radiochemist 2.
Confirmator Measurements 3.
In a previous inspection conducted on September 19-21, 1978, Inspection Report" 50-244/78-19, a liquid effluent sample was split with the licensee and NRC: I.
Analyses were performed by the licensee using his normal methods and procedures, and the NRC: I analyses were performed by the Department of Energy's radiological and Environmental Services Laboratory (RESL).
The comparison of the analyses results indicated that all of the measurements were in agreement or possible agreement under the criteria used for comparing results (see Attachment 1), with the exception of the gross alpha measurement.
The licensee's gross alpha measurement value was higher than the NRC value and hence in a conservative direction.
Thi's would not re'suit in the licensee exceeding any effluent release limits.
Discussions with the licensee indicated that the higher value may be due to the larger self absorption correction made by the licensee.
The NRC inspector noted that NRC reference laboratory measurement also included a systematic error of + 25K due to self absorption.
The results of the comparisons are presented in Table l.,
No items of noncomp 1 iance wer e identi fied.
Exit Interview The inspector discussed the results, of this inspection in a telephone conversation on March 13, 1979 with the licensee representative denoted in Paragraph TABLE
GINNA VERIFICATION TEST RESULTS RESULTS IN MICROCURIES PER MILLILITER SAMPLE Waste Holdup Tank 1800 hrs 9/1 9/78 ISOTOPE H-3 Gross Beta Gross Alpha NRC VALUE (1.56 + 0.02)
E-1 (4.9 + 0.2) E-2 (1.9 + 0.2) E-6 LICENSEE VALUE (1.96 + 0.02)
E-1 (6.3 + 0.2) E-2 (1.1
+ 0.4)
E-5 COMPARISON Possible Agreement Aqreement Disagreement
l7
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
~Agreement Possible A
cement A
Possible A reement B
(34-7 8 15 16-50 51 - 200
>200 0.4 - 2.5.0.66 0.75 1.33 0.80 1.25 0.85 1.18 0.3 - 3.0 0.4 - 2.5
"0.5 - 2.0.66 0.75 - 1.33 0.80 1.25 No Comparison.0.5 0.5 - 2.0.66 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" criteria 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 nuclid If