IR 05000289/1975016
| ML19256D588 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/12/1975 |
| From: | Everett R, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D582 | List: |
| References | |
| 50-289-75-16, NUDOCS 7910190554 | |
| Download: ML19256D588 (10) | |
Text
.
r
,
,
___
Form 12
- -
.
.
(Jan 75) (Rev)
. D**]D * }L hf 3
'"
o o Ju of.
_J
~
a U. S. NUCTEAR REGUIATORY Com!ISSION
,
.
OFFICE OF INSPECTION AND EWORCDfENT
~
REGION I
-
,,
.
.
=
,
.
G Inspection Report No:
_50_;to /7 s_16 Docket No:
50-289
.
,1censee: Metropolitan Edison Company License No:
DPR-50 P. O. Box 542
-
Priority:
'
.
Reading, Pennsv1vania 19603 Category:
C
'
Safeguards
.
ocation: Three Mile Island Unit 1 (TMI), '!iddletown, Pa.
-
.,
.
',
of Licensce: PWR,.9 7,1 MWe
,
'ype - of Inspection:, Independent MeasuremenM. Announced
-
'
- - =
>a t, of Inspection: July 22, 30, 31, Aucust 1. 1975
'a _.s of Previous Inspection: July 15, 1975
'eporting Inspector:
/T".4
', '
h
l
.
,
R.
)
vdrett, Radiatio'n Specialist
' D AT P.
ccompanying Inspectors:
f.
"
DATE
.
,.
,
.
DATE
.
.
DATE ther Accompanying Persor.ncl:
"-
DATE
.
.
P1
'7
'c:cd By:
S' nior EnviroEc tal Scientist
' DATE J. P. Stohr,/ -
e 1452 010
-
'
7910190.
.
.
.
-
.
.s L
.
.
t i.*p.
~.
g d
.
J SUFDIARY OF FINDINGS
,
_
'
Enforcement Action A.
Items of Noncompliance j
.,i a
1.
Violations None 2.
Infractions
,
_
a.
Licuid Waste Monitor (RM-L6)
The alarm setpoint on this monitor fails to meet the sensitivity requirements as specified in Technical Specification 2. 3.1.b.
(Details, Paragraph 5)
'
3.
Deficiencies None
.
j B.
Deviations
,.
None Licensee Action on Previously Identified Enforcement Items (Independent Measurements)
..
None
-
Unusual Occurrences
.
"
..
None Other. Sis;nificant Findines
..
A.
Current Findin es
-
.
..
1.
General
..
... -
This report summarizes the licensee's performance on verifica-tion test samples taken during the inspection of Januar'f 9, 1975 and during the cur;=
inspection.
Sixt/-seven (67) per-cent of ecasurements i:cre in agreement, fourteen (1'.) percent
)
1452 011
,
.
.
.s
.
..
-2-
\\
j possible agreement and nineteen (19) percent disagreecent.
..
(Details, Paragraph 3)
.
2.
Acceptable Areas
'
~
a.
Liquid Waste Compositing Practice.
(Details, Paragraph 3)
b.
In~~,e Charcoal Sample Measuremen Practice.
(Details, Para raph 3)
o 3.
Unresolved Iteus
.
None
.
4.
Infractions and Deficiencies Identified bv the Licensee
.
None
.
B.
Status of Previousiv Renorted Unresolved Items (Indeoendent Measurements)
None
-
'
Management Inte rvieu
""'"-
The following individuals attended the management interview at the con-clusion of the inspection.
__
=
Mr. J. Herbein, Ibnager, Get.cration Operations-Nuclear, TMI
.-
Mr. J. Colitz, Unit 1 Superintendent, TMI Mr. J'. Romanski, Chemistry and Health Physics Supervisor, TMI Mr. V. Orlandi, Lead I6C Engineer, TMI
,-
Mr. M. Buring, lhtropolitan Edison, Reading Office
During the meeting the following areas were discussed:
A.
Results of Ve 'fication Test Samples The licensee stated that action would be taken to obtain a stand-i
ard gas sample container and to recalibrate using gas standa.rds or make appropriate attenuation corrections.
The inspector stated that action may be necessary on the strontium analysis, pending the results of a recent split satple.
(Details, Paranraph 3)
1452 012
.
e
. &G
'
-
,,
.
.
3-
-
-
_ %)
.
B.
Gas Sampling of Decay Tanks The licensee stated that relocation of the exhaust duct over the gas sampling port would be completed within 60 days.
(Details, Paragraph 4)
.
,
.
_.
C.
Compositing of Radwaste Liquids The inspector stated that the current practice had been reviewed
. and had no further questions.
(Details, Paragraph 3)
D.
Liquid Waste Discharge Monitor (RM-L6)
The inspector stated that the monitor clarm setpoint did not meet the sensitivity requirements as required in the licensee's Techni-cal Specification and constituted an Item of Noncompliance.
(De-tails, Paragraph 5)
.
.
E.
Laboratory QA/0C Impleme:nting Procedure
.11e licensee stated that this procedure would be completed and available for inspection within 60 days.
(Details, Paragraph 6)
...
.
)
-
.
~
1452 013
-
.
W
.
.
.
'
g *
-
.
9
.
.
.s
-
-
.
.
.
,,
-
,
DETAILS 1.
Persons Contacted
'
Mr. J. Herbein, }bnager, Generation Opucations-Nuclear, TMI Mr. J. Colitz, Unit 1 Superintendent, TMI Mr. J. Romanski, Supervi ar of Chemistry a.d Health Physics, TMI Mr. K. Beale, Health Physics Supervisor, TMI Mr. K. Frederick, Staff Chemist, TMI Mr. B. Potts, Supervisor of Quality Control, TMI 2.
General The inspection consisted of a review of the licensee's performance on verification test samples collected by Region I personnel and analyzed by the NRC's reference laboratory, Idaho Health and Safety Laboratory (IHSL) and the Region I mobile lab.
These samples test the licensee's capability to measure radioactive ma.erial in actual effluent samples.
Some test standards were also submit'ted to TMI-f or analysis.
The activity of the test standards and IHSL's measure-ments'of their effluent samples are referenced to the National Bureau of Standards by laboratory intercomparisons.
The, inspector also re-
,
~
viewed corrective action on items from the last Independent Measure-
.
ments inspection.
(IE Inspection Report No. 50-289/75-02)
3.
Results of Verification Test Samples Results of split and standard samples reviewed during the inspection
-
reveal ~67% agreement, 14% possible agreement and 19% disagreement. *
The liquid waste sample remains to be analyzed and will be reported by the licensee within 60 days.
The required measurements on this sample are:
gross beta, tritium, strontium-89, 90 and gamma isotopic.
The types of samples collected and analyzed and the results of measurements were:
.
type of Sample:
Liquid radwaste, 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />. 1-9-75
'
Acceptable Results in units of microcuries per milliliter Radionucliue NRC MeasurcMent Licensee Measurement Gross beta
! 03
.05 E-3 8.54 1 2 E-4~
H-3 1. 32 1 01 E-1 1.26 i.002 E-1 n
- See Attach: ant 1 of this report for a description of. the criteria j
used to evaluate differences betueen analytical results.
.
1452 014
..
.
.
.s
.
-5-
'
r (
.
Radionuclide NRC Measurement Licensee Measurement
.
Sr-89 6.0
+.2 E-6 3.62 +.03 E-6 (1)
1-131 1.6 i.2 E-4 1.79 i.08 E-4 Cs-137 2.36 +.08 E-4 3.16 +.I E-4 Co-58 4.2 +.1 E-3-5.11 +. 04 E-3
.
Mn-54 1.17 i.04 E-4 1,.29 i.07 E-4 Co-60 5.3 12 E-5 4.90 i.5 E-5
~~
not Acceptable Sr-90'
2.8 +.4 E-8 7.27 + 2.5 E-8
'
11 E-6 not reported Cs-134 3.7 14 E-5 not reported type of Sample:
Gas, decay tank, 11:45, 1-9-75
.....
Acceptable Results in units of microcuries per milliliter Radionuclide NRC' Measurement Licensee Measurement
.
Xe-133 2.10 i.08 E-3 3.47 i.03 E-3(1)
g- =
l
)
type of dample:
Gas, decay tank, 0910, 7-31-75.
---
not Accep~ table Results in units of microcuries per milliliter
.
Radionuclide NRC Measurement Licensee Measurement
.
.
Xe-133 9.68 i.06 E-4 1. 8 6 i. 004 E-3 type of Sample:
Reactor k'ater, 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, 7-31-75
,
.
Acceptable Results in units of microcuries cer. milliliter Radionuclide NRC Measurement Licensee Measurement
_.
.
, 2.00 i.04 E-2 2.2 i.02 E-2 I-133 1.08 +.03 E-2 1.03 +.02 E-2
.
....
Possible agreement.
.
.
.
.s
.
.
- 6' -
,
._/
type of Sample:
Standard Filter, reference date 10-28-74, measured on 7-31-75 Acceptable Results in units of microcuries Radionuclide NRC Measurement,
ticensee Maasurement
.
Sb-125 2.2 +.1 E-2 2.79 +.04 E-2 Cs-134 3.1 I.7 E-2 3.23 +.02 E-2 Ag-110M 1.34][.08E-2 1.34][.1 E-2 Na-22
.57 1 04 E-2
.52 i ?
E-2 type of Sample:
Standard Charcoal, ref erence date 10-?.8-74, measured on 7-31-75 Acceptab' e-Results in units of microcuries
.
l Radionuclide NRC Measurement Licensee M'easurement
x+=
'
Ba-133
' 7. 61 1 01 E-2 8.4 i.04 E-2
'
type of Sample:
Standard Charcoal, ref erence date 8-6-75, counted on 7-31-75
)
'
.-
'
Acceptable Results in units of microcuries Radionuclide
,NRC Measurement Licensee Measurement Ba-133 1.~3 1 04 E-2
-
1.89 i.02. E-2(1)
The inspector noted the discrepancy on the strontium analysis and stated that the strontium concentration in the sample was low and
.
any proposed action would await the outcome of the sample t'aken during the current inspection.
The licensee stated that the ga=ma emitters not reported on the liquid waste sample was due to insufficient sample size since higher levels were. expected.
The inspector verified that the li-censee's present procedure calls for 3.5 liter sample for analysis which will allow the measurement of levels as specified in Regula-
,
tory Guide 1.21.
The inspector reviewed the licensee's radwaste Compositing Procedure and had ng..further questions.
( ~t )
' Possib1c agreement.
1452 016
.
=r-
.
.
..
.
,,
.....
.
.
.
._
-7-D "" "S D D'"D}{f
.t
,i
_oo a
s
.s
..
.
./
The inspector stated that the lack of agreement on gas samples was
.,
apparently due to the use of liquid standards for calibration which
"^
would yield high results on actual gas samples.
The licensee
- ...
stated that a standard geometry container would be selected and 7.{.
t cecalibration performed using available gas standards or perform attenuation corrections on the liquid standards.
~
=
a+:
,
The inspector reviewed the licensee's procedure for counting char-coal cartridges for iodine and noted that the technique would be appropriate for iodine activity of any distribution on the cartridge.
No further questions.
mur
-
4.
Gas Sampline The inspector observed the collection of gas sampl'es from a decay tank and noted the licensee's uce of a needle and gas syringe to penetrate a rubber hose to withdraw a sample from the moving gas
=
stream.
The ' inspector stated that this procedure had the potential for inadvertent release of gas and the use of a standard container filled by slow purge wa's a more acceptable procadure.
The liceneee stated that this procedure would be adopted af ter selection of a new gas container.
.
s
\\
The inspector noted the licensee's corrective ac' tion in the gas
==-
sampling. area:
use of metal quick-disconnect fittings, use of a portable rad gas monitor in the area, pressure regulation to 3-4 psi, and ~a written approved procedure to cover these requirements.
The licensee stated that the relocation of the exhaust duct to a position over the gas sampling port would be comple.ted within 60 days.
5.
Liould Waste Discharge Monitor.(RM-L6)
,.
The inspector noted the alarm setpoint on the liquid' waste discharge monitor to be 2.4 x 105 cpm raich corresponds to a concentration at the monitor and before dilvation to be 3.4 x 10-3 microcuries per milliliter.
This concentration would require a dilution of 3.4 x 10-3 + 1 x 10-7 = 34,000 in order to meet the 10 CFR Part 20 limit.
The inspector noted also that the dilution available to the licensee ranges from 5000 gpm to 38,000'gpm via the mechanical draft cooling touer.
This translates into dilution factors of 5000 + 30'= 167 for low dilution and maximum discharge rate and 38,000 + 5 = 7,600 for conditions of high dilution and minimum discharge rate.
The inspector calc.ulated that the appropriate alarm point for both con-di:icas would be 1,196 and 54,416, respectively.
The inspector stated that release records indicate conitor contamination IcVels
-)
1452 017
,
-
.
.
,s
.
.
.
8-j
-
j
-)
.
J of 6,000 to 10,000 cps, prior to a release which corplicates the '
T..
detection of levels to be monitoring as well as appropriate alarm levels.
The inspector stated that the present alarm point would
,
not alarm and close the waste discharge value prior to exceeding
"
the limits specifi2d in 10 CFR Part 20, Appendix B for unrestricted areas and therefore constituted a violation o'f the licensee's
-
""
Technical Specifications, Section 2.3.1.b.
6.
Laboratorv 0/./QC Program
.
The~ licensee described his efforts to control the quality of chemi-
==
cal analysep performed in the station laboratory.
The inspector reviewed thcae controls as well as the results of an internal QA audit by ec..,ers of the site QA staff.
The inspector observed that while these activities were acceptable they were informal in nature and'v.re not documented as a complete and sufficiently de-tailed preg /ca.
The licensee stated that a laboratory,QA imple-ps menting prc e ; dure would be prepared that would set down all elements
"]~ ~
of the QA prodram. and document a co=mitment to a certain program.
,
The inspectc discussed'uith the licensee the QA controls normally found in a 1:boratory performing low level analyses and agreed to supply refecences as to other laboratory QA programs that could
--
be used as esference material.
The licensee stated that the imple-T menting procedure would be completed within 60 ddys.
'""-
)
u m me
e
.
.
l
.
.
e g
e
.
%
a
_l
.
.s
.
.
'
.
~
Attachment 1 i
.;7 Criteria for Connaring Analytichl Measurements
'&
This attachcent provides criteria for comparing results of capability
,
testu and verification measurements.
The criteria are based on an
,
empi:ical relatio tship which combines prior experience and the accuracy
__"
necdu of this pro;; ram.
In~these criterit., the judgement limits ar% variable in relation to the comparison of the NRC Reference Laborate y's value to its associated uncertainty.
As that ratio, referred to in this program as " Resolution",
increases the acceptability of a licensee's measure =ent should be more
. selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
.
LICENSEE VALUE RATIO = NRC REFERENCE VALUE
-
Possible Possible Resolution Agreement Agreement A Agreement B
<3 0.4'- 2.5 0.3 - 3.0 No Comparisen 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 l.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 gacma energy used for Adentification
.
is greater than 250 Kev.
Tritium analysts of liquid samples.
,-
"B" criteria are applied to the following analyses:
..
Gamma Spectrometry where principal gamma energy used for identifim atien
+
is less than 250 Kev.
89sr cnd 90Sr Determinations.
I
.
Gross Beta where samples are counted on the same date using the same reference nuclide.
,,..
.
1452 019
.s
\\
J
.
.