IR 05000416/1982049
| ML20055A223 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Clinton  |
| Issue date: | 06/21/1982 |
| From: | Evans C, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20055A220 | List: |
| References | |
| 50-416-82-49, NUDOCS 8207150587 | |
| Download: ML20055A223 (5) | |
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UNITED STATES
'o NUCLEAR REGULATORY COMMISSION q
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.p 101 MARIETTA ST., N.W.. SUITE 3100 g
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Report No. 50-416/82-49 Licensee: Mississippi Power and Light Company P. O. Box 1640 Jackson, MS 39205 Facility Name:
Grand Gulf Unit 1 Docket No. 50-416 License No. CPPR-118 Inspection at NRC Regional Office (Followup of Inspection Report No.
50-416/81-54).
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/Dare Signed j
Approved by:
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[jM D. M. Montgomery), Chiej, IM&EP Section
'Uate Signed EPOS Division SUMMARY Inspection on June 3-4, 1982 Areas Inspected This followup inspection involved 3 inspector-hours in office regarding the comparison of licensee results with values of the simulated liquid and partic-ulate samples prepared by the NRC Contract Laboratory and comments on radio-chemical procedures submitted to R:II for review.
The comparison of the results and procedure review involved no onsite time.
Results Of the two areas inspected, no violations or deviations were identified two in areas.
8207150587 820621 PDR ADOCK 05000416 G
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DETAILS 1.
Persons Contacted Licensee Employees R. D. Brown, Plant Chemist 2.
Exit Interview The inspector discussed the results of the sample comparison and procedure review in a phone conversation on June 4, 1982 with the licensee repre-sentative denoted in paragraph 1.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of Radiochemistry Procedures a.
The inspector reviewed the following procedures submitted by the licensee to NRC:RII.
(1) 08-S-04-626, " Iron-55/59, Calibration and Analysis", 3-8-82.
(2) 08-S-03-120, " Germanium System Calibration Summary", 3-13-82.
(3) 08-S-03-20, "Interlaboratory Monitoring Program", 3-13-82.
(4) 08-S-04-617, "Sr-89, Sr-90, Y-90, Analyses", 1-8-82.
The inspector discussed the procedure review with the licensee i
representative denoted in paragraph 1.
b.
The inspector noted that procedure 08-S-03-20, "Interlaboratory Monitoring Program", establishes a schedule of quarterly cross checks with a different sample geometry for each quarter. The independent laboratory preparing the spiked samples is required to demonstrate traceability to NBS. This closes a previously identified item (50-416/81-54-02).
c.
The inspector noted that procedure 08-S-03-120, " Germanium System Calibration Summary", delineates the preparation of counting geometries and specifies direction for entry of data i6to the calibration computer program. This closes a previously identified item (50-416/81-54-01).
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d.
The inspector reviewed procedures 08-S-04-617, "Sr-89, Sr-90, Y-90 Analyses" and 08-S-04-626, " Iron-55/59, Calibration and Analysis",
and noted that the procedures had been approved by the Plant Safety Review Committee. The inspector found the procedures to be adequate.
This closes a previously identified item (50-416/81-54-05).
6.
Capability Test During the previous inspection (Inspection Report No. 50-416/81-54)
licensee representatives were informed that a simulated liquid waste sample and a spiked particulate filter prepared by the NRC contract laboratory would be sent to the licensee for Sr-89/90, H-3, and Fe-55 analyses. The analyses serve to verify the licensee's capability to measure radionuclides in effluent samples. The comparison between the licensee's results and NRC values for the two samples are presented in Table 1 with acceptance criteria in Attachment 1.
The comparison shows
" agreement" or "possible agreement" for all radionuclides. This closes a previously open item (50-416/81-54-06).
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TABLE 1 f<! Sul Is of CAPABILITY 1EST BY GRAND GULF Concentration, f4i c rocu r i e s Sampjej l h011?pe G ra tid Ce s I f'
HRC Patio Re so J. tit i pn f'ompa r ihon Spiked Particulate Sr-89 6.90 t-03 8.29t.12E:-03
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Agreement litter Sr-90 1.98 T-03 S.92 t. 28 E-Ol4 1. 384 PS Possible Agreement
Simulated H-3 6.1 ')
[-03 6.801.06l-03
.95 113 Agreement
Liquid Waste Sr-89 7.67 I-03 8.291.12E-03
.92
Agreement
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S r-90 1. 9's I-03 5. 92 t. 214 E-014 1. 3 14
Possible A9reement 1.85 L-OS 1.281.08E-05 1.13 584 Ag reemen t 1e-59
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o Attachment 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS
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This attachment provides criteria for comparing results of capability
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tests and verification measurements.
The criteria arc based on an
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empirical relationship which combines prior experience and the accuracy needs of this program.
In these criteria, the judgment 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
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selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.
LICENSEE VALUE
" NRC REFERENCE VALUE Possible Possible Resolution Agreement Agreement A Agreement B
<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 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
"A" criteria are applied to the following analyses:
Camma 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:
Camma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89 Sr and Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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