IR 05000289/1977033
| ML19256D159 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/09/1977 |
| From: | Paperiello C, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D156 | List: |
| References | |
| 50-289-77-33, NUDOCS 7910170658 | |
| Download: ML19256D159 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EHFORCEMENT
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i Report No. 77-33
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Docket No. 50-289 License No. DPR-50 Priority Category C
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Licensee:
Metrooolitan Edison Company P. O. Box 542 Readino, Pennsylvania 19603 Facility Name: Three Mile Island Nuclear Power Plant, Unit 1 Inspection at: N/A Inspection conducted: October 13, 14, 28, 1977
Inspectors:
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. C. J. Papefiello, Radiation Spcialist date signed (n/
date signed date si ned Approved by:
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J. P. Stohr, hiAf, Environmental & Special date signed Projects ctiori, FF&MS Branch
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Inspection Summary:
Inspection on October 13,1977 (Recort No. 50-289/77-33)
Areas Insoected:
This report contains the results of the split verification test sample taken during a previous inspection on May 31 - June 2, 1977 (Report No. 50-289/77-17). The comparison of these results involved no cnsite time.
R_esul ts : Within the area inspected, no items of noncompliance were identified.
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7910170 s
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}446 270 Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
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Mr. James O'Hanlon, Unit 1 Superintendent t
Mr. Richard Dubiel, Radiochemistry and Health Physics Supervisor Mr. J. Gary Reed, Unit 1 Chemist
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2.
Results of Confirmatory Measurements-In a previous inspection conducted'on May 31 - June 2, 1977, IE Inspection Report No. 50-289/77-17, a liquid effluent sample was split with the licensee and gama analysis was performed on site
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using the NRC mobile laboratory. Those analyses requiring wet chemistry (i.e., gross beta, tritium, Sr-89, and Sr-90) were per-formed t,y the NRC reference laboratory, the Idaho Health Services Laboratory (IHSL).
The results of these analyses requiring wat chemistry are presented in this report.
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The results of the intercomparisons are presented in Table 1.
Tne criteria for comparing measurements are presented in Attachment 1.
O Sr-90 cannot be compared since it was not measured by IHSL.
The results presented in Table 1 show Sr-89 and gross beta measurements to be in agreement while the tritium (H-3) results are 50% higher than the NRC's reference laboratory results.
The j
inspector noted for the past three years that the licensee's
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results have been higher than the NRC's results for this measure-ment by about 50%.
The inspector noted that this is a conservative error and could not result in the licensee exceeding a regulatory limit.
No items of noncompliance were noted.
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Airborne Tritium Measurements
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(0 pen) Unresolved Item (77-17-01); Airborne Tritium Rele Since a conservative error in the tritium measurement coulses.
d have contributed to the higher than expected airborne tritium releases reported by the licensee, this item remains unresolved.
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Telephone Discussions with Licensee Representatives These results were discussed with the licensee's representatives in telephone conversations on October 13,14, and 28,1977.
l The licensee's representative stated ths; a new tritium standard was being ordered and the calibration of the instrument used for tritium analyses would be checked.
The inspector stated that after the calibration was checked, l
he would request IHSL to send the licensee a sample spiked with
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a known standard for tritium analysis.
The licensee stated that l
this analysis would be performed and the results reported to the NRC.
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'J TABLE 1 TMI 1 - VERIFICATION TEST RESULTS
Results in uCi/cc SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARIS0N Spent Fuel 11-3 (2. 21 10.02 ) ~ E-2 (3.50 1 0.02) E-2 Disagreement Pool - 1115 6/1/77
- (3.1210.31) E-2 Disagreement Gross Beta (4.8 1 0.2) E-3 (5.80 1 0.06) E-3 Agreement l
- (4.63 1 0.46) E-3 Agreement Sr-89 (6 1 3) E-6 (6.55 1 0.66) E-6 Agreement
- Contractor Value i
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Attachment 1
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Criteria for Comparing' Analytical Measurements
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This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria.are based on an
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.apirical relationship wh'ich combines prio.r experience and the accuracy
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needs of this program.
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In these criteria, the judgement limits are variable in relation to the j
comparison of the NRC Reference Laboratory's value to its associated
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l uncertainty.
As that ratio, referred to in this program as " Resolution",
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j increases the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable l--
as the resolution decreases.
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LICENSEE VALUE RATIO = NRC REFERENCE VALUE'
Possible Possible
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Resolution Agreement Agreement A Agreement B E3 0.4 - 2.5 0.3 - 3.0 No Comparison
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4-7 0.5 - 2.0
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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 Y
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"A" criteria are applied to the following analyses:
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Gamma Spectrometry.whera principal. gamma energy used for identification is greater than 250 Kev.
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I Tritium analyses o'f liquid samples.
"3" criteria are appli'ed to the following analyses:
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Gamma Spectrometry where pr1ncipal 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.
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