IR 05000289/1975026
| ML19256D556 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/08/1975 |
| From: | Everett R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D555 | List: |
| References | |
| 50-289-75-26, NUDOCS 7910190516 | |
| Download: ML19256D556 (5) | |
Text
.
.
..
.
.
.:I Form 12
' n 75) (Rev)
-
.,
,
,
"
uj U. S. NUCLEAR REGULSTORY COW!ISSION I
0FFICE OF INSPECTION AND ENFORCDLT
-
t
REGION I
'
-
,
_
. Inspection Report No:
50-289/75-26 Docket No:
50-289
.censce:
Metropolitan Edison Company License No: DPR-50 P. O. Box 542 Priority:
_
,
Reading, Pennsylvania Category:
C Safeguards Gro.up:
cation:
Three Mile Island Unit 1, Middletoten, Pennsylvaniz
'
pe. of. Licensee:
PWR, 871 MWe
-
Independent Measurements, Results of Previous pe
' Inspection:
Inspection (July 22, 30, 31, and Augusc 1,1975)
-
i
.
tes of Inspection: November 11, 1975
-
tes of Previous Inspection:
October 28-November 3, 1975
.
. porting Inspector:
b.
r/4t4d
//d4[77
'
'
R. J. Everett, Radiation Specialist DATE
conpanying Inspectors:
DATE
~
.
.
DATE DATE
-
her Accompanying Personnel:
DATE aved By:
/
/2-
[
, _
J./.Sto$tr, h
Section Leader
' DAT"
^
g f
J 5/6
)
-
7930190
. me..
'
'
'
... _..
.
.
-
.
I i
.
SUMMARY OF FINDINGS
.
.
...
I
'
I
.
.
Enforcement Action
'
I e
,e A'..
Items of Noncompliance rg,,
I:.:.
'
kh.
1.
Violations
- .
l
...
None
- ...
l
[:::
.
'
2.
Infractions
.
None
,
"
3.
Deficiencies
-.
.
,.
...
.
..
.._.
_.
None
.
B.
Deviations:
.
None
.
(
)
Licensee Action on Previousiv Identified Enforcement Items (Independent Measurements)
'
,
None Unusual Occurrences.
.
None
.
Other Significant Findings
..
A.
Current Findings 1.
General
.
..
A tabulation of the sample results from the inspection of July 22, 30, 31 and August 1, 1975 (Report No. 50-289/75-16),
indicate that three measurements were in agreement with the reference laboratory, and one measurecent in disagreement.
(Details, Paragraph 1)
.
1451 269
-
)
-
-
..g
'
.
,
'
-2-
,
f
._
.
h, -
v
-
-
,
2.
Unresolved Items
"
...;
..
-
.
None
" ' '
,
,
'
ib.=..
3.
Open Items
-
t.. _.
G;;::;.
.
- - ::
None
- +a
- :
g n
,
4.
Infractions and Deficiencies Identified by the Licensee
+-
-
\\
None
e :. : - -
,
- ..
B.
Status of Previously Reoorted Unresolved Items (Indeoendent:
,
Measurements)
.
.
None i
'
- , ?
'
R4;-
-
Management Interview
-
The results of these analyses were discussed with the licensee in tele-phone conversations of November 11, 1975.
The licensee stated that the method of tritium measurement would be examined regarding the dist; illa-
.. Z
]
tion of the sample prior to counting.
The inspector stated that because
,
of the low levels of Sr-89 and Sr-90 in the verification samples, the
'
- - - =
licensee will be required to analyze a standard Srvj9, Sr-90 sa=ple sup-plf.ed by NRC.
(Details, Paragraph 1)
The inspector stated that these actions would be. reviewed in the next
=M Independent Measurements inspection.
'"'
-
..
.
..ee
^ * * '
- - -
1451 270
-
-
. -.
e.-4 e
0 :
.
.
.
.
.
-
.
'
.
d
.
DETAILS
-
....
.
.
1.
Results of Verification Test Samples
.
This inspection showed three of the licensee's measurements were
[.!
-
acceptable under the test criteria used by the Office of Inspection ii::
and Enforcement for co= paring test results (see attach ent).
However,
-
one of the licensee's measurements was not acceptable under the t'est n
criteria.
The type of sample tested and the results of measurement
.
were:
I h.H
.
Type of sample:
Liquid Waste - Misc. Waste Storage Tank, 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />,
{
7-30-75.
,
Acceptable'
Results in Units of Microcuries ner Milliliter Radionuclide NRC Measurement Licensee Measurement Gross beta 3.01 2 0.07 E-6 2.87, 0.13 E-6 Co-58 1.29 0.03 E-5 1.67 2 0.05 E-5 I-131 1.33 0.07 E-6 1.59 1 0.15 E-6
.s
.
I I
Not Acceptable
,.
'
H-3 6.90 2 0.03 E-4 1.03 t 0.ll E-3
.
.
.
.
1451 271
.
e G
'
.....:
.
.
,
-.y
.-
...
-
.
.
.
...
Attachment 1
-
.*
.
Criteria for Co= caring Analytical Measurements
. _,
This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an
- -
empirical reldtionship which combines prior experience and the accuracy
,
g..
needs of this program.
-
.
,
In these criteria, the judgement limits are variable in relation to the ie,. =
comparison of the NRC Reference Laboratory's value to its associated gj(=
uncertainty.
As that ratio, referred to 11 this program as " Resolution.",
increases the acceptability of a licensee's measurement should be more
~'
selective.
Conversely, poorer agreement uust be considered acceptable as the resolution decreases.
i
.
'
~
LICENSEE VALUE RATIO = NRC REFERENCE VALUE
, :.? 7.
'
Possible Possible
-
.
~
Resolution Agreement Aereement 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:
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 gam =a energy used for identification is less than 250 Kev.
89Sr and 90Sr Determinations.
Gross Beta where sample.s are counted on the came date using the same reference nuclide.
"
7"
-
-
.
I451 272
'
'
..
.
-
.
.