IR 05000275/1988020
| ML16341E741 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/12/1988 |
| From: | Tenbrook W, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341E740 | List: |
| References | |
| 50-275-88-20, NUDOCS 8808030071 | |
| Download: ML16341E741 (6) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-275/88-20 Docket No. 50-275 License No.
DPR-80 Licensee:
Pacific Gas and Electric Company 70 Beale Street, Suite 1451 San Francisco, California 94106 Facility Name:
Diablo Canyon Unit j.
Inspection at:
USNRC Region V, Walnut Creek, California Inspection Conducted:
July 5-7, 1988 Inspected by: +A W.
K. TenBrook, Radiation Specialist
'7 ii ar Date Signed Approved by:
G.
.
has, Chief Facili
'
Radiological Protection Section T />
Date igned
~Summer:
Areas Ins ected:
Routine inspection of radiochemical analysis data supplied by the licensee for measurement intercomparison.
Inspection procedure 92701 was used.
Results:
The licensee's analysis of an NRC radiochemical test sample indicates an acceptable measurement capability for most nuclides in the sample.
The followup item will remain open pending an acceptable intercomparison for tritium and Fe-55.
No items of noncompliance were identi fied.
8808030071 8850002 PDR ADOCK 0 PNU
DETAILS 1.
Persons Contacted Licensee J.
Gardner, Senior Chemistry 8 Radiation Protection (CHIRP) Engineer D. Unger, CHIRP Engineer 0 en Item 50-275/87"17-01 OPEN This item concerned a liquid capability test sample prepared by the U.
S.
Department of Energy Radiological and Environmental Sciences Laboratory (RESL) which was sent to the licensee for radiochemical analysis.
The sample contained nuclides which the NRC cannot readily intercompare during onsite inspection.
The certified amounts of radioactivity in the test sample and the licensee's analytical results are given below.
Nuclide NRC uCi/ml NRC Uncert.
DCPP uCi/ml DCPP/NRC
~Ren e
H-3 Sr-89 Sr-90 Fe-55 4. 38E" 5 5. 99E-5 5. 42E" 6 2. 67E-5 9E"7 1. 8E-6 2. 2E-7 5E-7 3. 2E-5 4. 9E-5 5. 6E-6 4. 1E-5 0. 73 0. 82 l. 03 1. 54 0. 75-1. 33 0. 75"1. 33 0. 60-1. 66 0. 80-1. 25 Results for strontium were satisfactory.
The ratio for tritium was marginally outside the agreement range established by the NRC uncertainty (See Enclosure).
The Fe-55 result was significantly outside the agreement range.
No outstanding reasons for the disagreements were identified.
This item will remain open pending a satisfactory intercomparison of tritium and Fe-55 activity in an additional capability test sample.
No violations or deviations were identified in this part of the inspection.
3.
Exit Interview On July-6, 1988, the inspector discussed the results of the test sample intercomparison with members of the licensee's Chemistry and Radiation Protection staff noted above.
The licensee representatives were informed of the marginal disagreement for tritium and the significant disagreement for Fe-55.
The licensee was also informed that the followup item would remain open pending satisfactory intercomparisons for these nuclide J
Enclosure Criteria for Acce tin the Licensee's Measurements Resolution Ratio
<4
-
8 -
16
-
51
- 200 200 0.4 0.5 0.6 0.75 0.80 0.85 2.5 2.0 1.66 1.33 1.25 1.18 Co arison Divide each NRC result by. its associated uncertainty to obtain the resolution.
(Note:
For purposes of this procedure, the uncertainty is defined as the relative standard deviation, one sigma, of the NRC result as calculated from counting statistics.)
2-Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result/NRC).
3 ~
The licensee's measurement is in agreement if the value of the ratio
,
falls within the limits shown in the preceding table for the corresponding resolution.