IR 05000289/1977006
| ML19261E851 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/22/1977 |
| From: | Kottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261E846 | List: |
| References | |
| 50-289-77-06, 50-289-77-6, NUDOCS 7910170894 | |
| Download: ML19261E851 (6) | |
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Form 12 (L '75) (Rev)
U. S. NUCLEAR REGULATORY CCMMISSION
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OFFICE OF INSPECTION MID CEORCD!DIT 2EGION I
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IE Inspection Report No:
50-289/77-06 Docket No: 50-289 i'
Licensee:
Metropolitan Edison Company License No: DP R-50 P. O. Box 542 Priority:
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C Reading, Pennsylvania 19603 Category:
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Safeguards
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Group:
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Location:
Three Mile Island 1, Middl etswn, Pennsylvania i
Type of Licensee:
Ty1]pfInspection:
Independent Measurements (Supplemental)
March 4, 1977
! ' Dates of Inspection: _
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! Dates of Previous Inspection:
February 22-25, 1977 b
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Reporting Inspector: d, k[ [hb
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J. J. Kottan', Radiation Specialist
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Accocpanying Inspectors:
NONE
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DATE DATE DATE Other Accccpanying Personnel:
NONE DATE Revie'aed By;
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S tTin r, Chief, Environmental ano special DA:s
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ojects Section, FF&MS Branch g8k '337
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SUMMARY OF FINDINGS Enforcement Action A.
Violations None.
B.
Infractions
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None.
C.
Deficiencies None.
License? Action on Previously Identified Enforcement Items
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(Independent Measurements)
Not applicable.
Unusual Occurrences
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None.
Other Stanificant Findings A.
General A tabulation of the results from the verification test samples taken during the inspection of July 13-16,1976, (Region I Inspection Report No. 50-289/76-16) and sent to the NRC reference laboratory, Idaho Health Services Laboratory (IHSL), for analysis indicatc.
that neither of the measurements were in agreement with the reference la boratory.
(See Management Interview and Details, Paragraph 1)
B.
Unresolved Items None.
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C.
Infractions and Deficiencies identified by the Licensee None.
D.
Deviations _
None.
t Management Interview
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I The results of this inspection were discussed with Mr. R. Dubiel in a telephone conversation on March 4,1977.
The inspector stated that the sample analysis comparison indicated that neither of the measurements were in agreement. The inspector noted that a Cs-137 efficiency factor was used by both the licensee and by the NRC reference laboratory in performing the gross beta analysis.
The inspector stated that gross beta measurements are difficult to compare and, as it is generally accepted, these measurements by themselves are of limited value. The inspector had no further questions in this area at this time.
(Details,
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Paragraph 1)
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i DETAILS 1.
The comparison of the licensee's measurements with those of the NRC reference laboratory, Idaho Health Services Laboratory (IHSL)
for verification test samples taken during an inspection on July 13-16, 1976, and sent to the NRC reference laboratory, IHSL, for analysis indicates that neither of the licensee's measurements were in agreement under the test criteria used by the Office of Inspection and Enforcement for comparison of measurements.
(See Attachment 1)
The type of samples tested and the results of the measurements are listed in Table 1.
The results of other verification tests performed
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j on the site, using the Region I Mobile Lab, are detailed in Region I
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Inspection Report No. 50-289/76-16.
The inspector noted that the licensee's tritium measurement was j
higher than the NRC reference laboratory measurement, and this difference was in a conservative direction and, therefore, would not result in the licensee exceeding any technical specification limitations in the discharging of liquid radioactive wastes.
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TABLE 1 f
THREE MILE ISLAND 1 - VERIFICATION TEST RESULTS l
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SAMPLE IS0 TOPE NRC VALUE LICENSEE VALUE COMPARISON
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RESULTS IN MICR0 CURIES PER MILLILITER WECST "A" Gross Beta 2.45 1 0.07 E-6 4.51 10.35 E-7 Disagreement 0953 hrs 7/14/76 it-3 4.14 1 0.04 E-2 5.60 1 0.01 E-2 Disagreement l
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'I Attachment 1
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Criteria for Comparing Analytical 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",
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l increasas the acceptability of a licensee's measurement shculd be more
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selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
i LICENSEE VALUE RATIO = NRC REFERENCE VALUE
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Possible Possible Resolution Agreement Agreement A Agreement B
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<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
- i 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
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>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
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"A" criteria are applied to the following analyses:
l 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:
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Ga=ma Spectrometry where principal gamru 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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