ML20149F899
| ML20149F899 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/10/1988 |
| From: | Januska A, Schumaher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20149F898 | List: |
| References | |
| 50-295-88-04, 50-295-88-4, 50-304-88-05, 50-304-88-5, NUDOCS 8802180007 | |
| Download: ML20149F899 (8) | |
See also: IR 05000295/1988004
Text
.. ;
..
U.S. NUCLEAR REGULATORY COMMISSION
<
REGION III
Reports No. 50-295/88004(DRSS); 50-304/88005(DRSS)
Docket Nos.. 50-295; 50-304
Licenseer Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
. Facility Name: Zion Nuclear Generating Station, Units 1 and 2
Inspection At: Zion Site, Zion IL 60099
Inspection Conducted: January 12-15 and 19, 1988
h6
8
Inspector:
a
a
.
Date
Accompanied By:
R. Bocanegra
h/b d4tWAbu
Approved By:
M. Schumacher, Chief
M/
Radiological Effluents
Date
and Chemistry Section
Inspection Summary
Inspection on January 12-15 and 19, 1988 (Report No. 50-295/88004(DRSS);
50-304/88005(DRSS)).
Areas Inspected: Routine, announced inspection of: (1) quality assurance
and confirmatory measurements for in plant radiochemical analyses and
(2) action on an open item identified during a previous inspection.
Results: No violations or deviations were identified during this inspection,
pgg2100007 800210
0
ADOCK 05ooop95
2
F
.
DETAILS
1.
Person Contacted
- C. 0011, Chemist
- G. Plim1, Station Manager
- C, Sprandel, Quality Assurance Engineer
- W. Stone, Regulatory Assurance Supervisor
G. Trzyna, Rad / Chem Supervisor
- P. Zwilling, Station Chemist
- 0. Damon, Resident Inspector
- P. Eng, Resident Inspector
- Denotes those present at exit interview
2.
Licensee Action on Previous Inspection Findings
a.
(Closed) Open Item (50-295/86018-03; 50-304/86017-03):
Verify
calibration calculations for I-131 and one other iodine isotope and
recalibrate if necessary.
The licensee has performed two complete
routine calibrations since this item was opened. A review of the
most recent calibration for this geometry revealed no problems.
b.
(0 pen) Open Item (50-295/87029-01; 50-304/87030-01): Complete
procedure to make systematic corrections for background radiation
in gamma spectroscopy systems. The licensee's procedure has been
completed and is in the review chain.
The finalized procedure will
be examined during a subsequent procedure.
3.
Confirmatory Measurements
a.
Sample Split
Seven samples (containment air particulate, containment charcoal,
charcoal spike, crud filter, gas, reactor ecolant and liquid) were
analyzed for gamma emitting isotopes by the licensee and in the
Region III Mobile Laboratory on site. Comparisons were made on
combinations of the licensee's four normally used count room
detectors and the Post Accident Radionuclide Analysis Portable
System (PARAPS).
Results of the sample comparisons are given in
Table 1; the comparison criteria are given in Attachment 1.
The
licensee achieved 73 agreements out of 77 comparisons.
The licensee's containment air particulate sample was analyzed
(results not shown) to verify the licensee's results of no
detectable activity.
In order to test the particulate geometry,
a reactor coolant filter was analyzed as an air particulate filter.
Charcoal spike and air particulate (primary coolant filter) samples
were analyzed resulting in all agreement.
3
.
.
A containment charcoal sample analyzed on Detector 3 resulted
in a nonconservative disagreement for Br-82.
Since a charcoal
spike analyzed on Detector 3 had all agreements, the containment
sample disagreement appeared to be attributable to the licensee's
counting technique and deposition of Br-82 into the cartridge.
The licensee tested the sample and coiscurred with the inspectors
that the Br-82 was not face deposited and therefore their
calibration would underestimate the t-tivity present.
The licensee
agreed to; (1) determine if this sample was an anomaly and if not
apply an appropriate factor when Br-82 is present and (2) implement
a counting technique that will assure accurate quantification of
activity on charcoal samples regardless of nuclide deposition (0 pen
Item 50-295/88004-01; 50-304/88005-01).
A reactor coolant sample (RCS) was collected, filtered and
analyzed. The comparison resulted in three disagreements each on
Detectors 2 and on PARApS. One nuclide, Mo-99 was misquantified and
the cesiums were not identified by the licensee.
The licensee stated
and substantiated that a second count is normally made and the missed
nuclides, masked by short lived nuclides, are quantified. A one day
old unfiltered RCS sample was split and analyzed resulting in one
conservative disagreement for Tc-99m on the PARAPS.
The inspectors
examined the licensee's data and found an error in the system's
nuclide library. Correcting the error resulted in an agreement.
In addition, during the inspection, the inspectors noted that the
library contained an over abundance of nuclide energy lines which
may prove to be detrimental in accurate identification. The
licensee agreed to (1) review the library contents and correct any
mistakes and (2) reduce the number of energy lines so that nuclides
arts not missed (0 pen Item 50-295/8804-02; 50-304/8805-02).
Gas decay tank results yielded a conservative disagreement for
Xe-133 on Detector 4 and had all agreements on Detector 3.
A
resample yielded all agreements on both detectors.
A split sample of a lake discharge tank resulted in conservative
disagreements for Co-58 on Detectors 1 and 4 and for Co-60 on
Detector 4.
The factor of two increase between Detector 1 and
Detector 4 for Co-60 in the same sample could not be explained.
A second sample was counted on three of the licensee's detectors,
including Detectors 1 and 4 with very good agreement for all
nuclides including Co-60.
Based on this test and an examination of
the licensee's calibrations for this geometry the disagreement is
thought to be an anomaly.
The examination of the calibrations did
not reveal the reason for the Co-53 disagreements. A portion of
this sample was split with the licensee for analyses of gross B,
The licensee will report his results
to Region III (0 pen Item 50-295/88004-03; 50-304/88005-03).
The
4
, _ _ _ _ _
_____
.-
.
inspector asked the NRC Reference Laboratory to perform a gamma
scan in addition to the Beta analyses above and will inform the
licensee of the Co-58 results and discuss any needed action,
b.
, Audits
The inspectors examined QAA 22-87-02 (onsite), January and
February,1987 and QAA 22-87-II (corporate) Septe.nber 1987. No
findings or observations relevant to this inspection were nuted.
c.
Quality Assurance
The inspectors reviewed the radioactivity mer.surements laboratory
quality assurance program including the phyr.ical facilities,
laboratory operations, and procedures. All the counting equipment
was found to be in good working order.
The inspectors also reviewed
documentation reisted to scheduled preventative maintenance, daily
performance checks and yearly calibrations.
No violations or deviations were identified.
4
Open Items
Open items are matters which have been discussed with the licensee, which
will be reviewed further by the inspector, and which involve some action
on the part of the NRC or licensee or both. Open items disclosed during
the inspection are discussed in Section 3.
5.
Exit Meeting
The inspector met with licensee representatives denoted in Section 1 at
the conclusion of the inspe: tion on January 19, 1988. The scope and
findings of the inspection were ciscussed.
During the exit interview, the inspector discussed the likely
informational content of the inspection report with regard to documents
or processes reviewed by the inspectors during the inspection.
Licensea
representatives did not identify any such documents or procedures as
proprietary.
Attachments:
1.
Table 1, Confirnatory Measurement
Program Results. 1st Quarter 1988
2.
Attachment 1, Criteria for Comparing
Analytical Measurements
5
_
.
.
e
4
TABLE 1
U S NUCLEAR REGl.LATORY COMMISGION
OFFICE OF IN?PECTION AND ENFORCEMENT
i
CONFIRMATORY MEASUREMENTS PRt.% RAM
FACILITY: ZION
FOR THE 1 OUARTER OF 1989
NRC-------
LICENSEE----
---L I C ENSEE : NRC----
SAMPLE
ISOTOPE RESULT
ERROR
RESLLT
ERROR
RATIO
T
C FILTER BR-182
7.1E-11
3.0E-12
5.3E-11
2.lE-12
7.5E-01
2.4E 01
D
1-131
2.0E-11
1.1E-12
2.1E-11
2.0E-12
1.0E 00
1.8E 01
A
(perJ)
1-133
6.3E-11
2.8E-12
6.1E-11, 6.2E-12
9.7E-01
2.3E 01
A
,
C SPIKED CO-60
1.5E-02
3.8E-04
1.?E-02
1.2E-03
1.7E 00
3.oE 01
A
5.7E-03
1.2E-04
6.3E-03
0.0E-01
1.lE 00
4.9E 01
A
{per3)
Y-88
2.3E-03
2.!E-04
2.3E-03
0.0E-01
1.0E 00
1.!E 01
A
3.7E-01
4.1E-03
3.8E-01
0.0E-01
1.0E 00
8.9E 01
A
,
SN-113
2.1E-03
1.6E-04
2.3E-03
0.0E-01
1.lE 00
1.3E 01
A
<
2.4E-02
4.!E-04
2.8E-02
2.7E-03
1.2E 00
5.BE 01
A
CE-139
1.oE-03
8.4E-05
1.9E-03
0.0E-01
1.0E 00
2.2E of
A
P FILTER NA-24
1.3E-03
1.6E-04
1. 3E-03
1.5E-04
1.0E 00
7.9E 00
A
CR-51
2.0E-03
5.2E-04
1.5E-03
3.9E-04
7.4E-01
3.9E 00
A
CO-58
2.0E-03
9.0E-05
1.9E-03
0.0E-01
9.5E-01
2.2E 01
A
(ECT'()
1-131
2.9E-04
6.3E-05
2.9E-04
5.8E-05
1.0E 00
4.6E 00
A
l-132
7.0E-03
4.8E-04
6.7E-03
3.8E-04
9.6E-01
1.4E 01
A
l-133
4.lE-03
1.2E-04
4.2E-03
3.8E-04
1.0E 00
3.4E 01
A
I-135
7.1E-03
6.3E-04
7.9E-03
4.7E-04
1.1E 00
1.1E 01
A
3.3E-04
5.4E-05
4.8E-04
6.5E-05
1.5E 00
6.!E 00
A
BA-139
4.1E-01
5.5E-03
4.2E-01
3.7E-02
1.0E 00
7.4E 01
A
BA-140
!.2E-02
3.9E-04
1.3E-02
7.0E-04
1.1E 00
3'.!E 01
A
5.7E-03
1.2E-04
5.7E-03
1.0E-04
9.oE-01
4.9E 01
A
CO-L?
- SE 32
7. I'C
4
i . 4 E -02
3. d- v 4
't * -o !
(PMtW)
Y-66
2.IE-0?
2,IE-04
2.SE-03
0.OE-01
1.1E 00
1.1E 01
A
P
CD-100
3.7E-01
4.lE-03
3.4E-01
3.PE-0?
o. 0E -01
0.oE 01
SN-113
2.lE-03
1.6E-04
2.0E-03
1.7E-04
9.8E-01
1.3E 01
A
2.4E-02
4.lE-04
2.4E-02
3.5E-04
c.8E-01
5.9E ol
A
CE-139
1.9E-03
8.4E-05
1.6E-03
0.0E-01
8.8E-01
2.2E 01
A
P FILTER NA-24
1.3E-03
1.oE-04
1 ?E-03
1.4E-04
o.5E-01
7.9E 00
A
T TEST RESLLTSI
A= AGREEMENT
!
OsDISAGREEMENT
- = CRITERIA RELATED
l
NsNO COMPARISON
e
.
.
.
.
TABLE 1
i
U S t*JCLEAR REGlLATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
t
'
CONFIRMATORY MEASI1REMENTS PROGRAM
FACILITYI ZION
FOR THE 1 OUARTER OF 1988
NRC-------
L I C ENSEE----
---LICENSEEtNRC----
SAMPt. E
ISOTOFE RESI.LT
ERROR
RESULT
ERROR
RATIO
T
P FILTER CR-51
2.OE-03 5.2E-04
2. 3E-03 4.7E-04
1.1E 00
3.9E 00
A
CO-58
2.OE-03
9.OE-05
2.OE-03
1.9E-04
1.OE 00
2.2E 01
A
(DET2)
1-131
2.9E-04
6.3E-05
3.6E-04
6.2E-05
1.2E 00
4.6E 00
A
I-132
7.OE-03
4.8E-04
6. t E- 03
4.OE-04
9.2E-01
1.4E 01
A
I-133
4.1E-03
1.2E-04
4.!E-03 3.8E-04
1.0E 00
3.4E 01
A
1-135
7.1E-03
6.3E 04
7.7E-03
4.6E 04
1.OE 00
1.IE 01
A
3. 3E-04
5.4E-05
3.IE-04
7.2E-05
9. 3E-01
6.1E 00
A
BA-139
4.1E-0!
5.5E 03
4.1E-01
3.6E-01
1.OE 00
7.4E 01
A
BA-140
1.2E-02
3.9E-04
1.4E-02
8.OE-04
1.2E 00
3.1E 01
A
'
L VASTE CO-58
2.2E-06
1.3E-07
3.3E-06
0.OE-01
1.5E 00
1.7E 01
D
5. !E-06
1.7E-07
5.7E-06 3.6E-07
1.OE 00
3.3E 01
A
{pg t)
!-131
5.3E-06
1.2E-07
5.6E-06
4.1E-07
1.OE 00
4.4E 01
A
I-133
1.7E-06
1.2E-07
1.7E-06
1.7E-07
9.BE-01
1.4E 01
A
SB-125
2.5E-06
2.4E 07
2.4E-06
2.6E-07
9.7E-01
1.OE 01
A
!
CS-134
1.4E-06 8.3E-08
1.lE-06
1.OE-07
8.OE-01
1.6E 01
A
2.6E-06
1.2E-07
2.3E-06
1.2E-07
9.OE-01
2.OE 01
A
PR! MARY
NA-21
2.4E-03
6.2E-05
2.3E-03
2.6E-04
9.6E-01
3.9E 01
A
1-131
1.4E-03
2.5E-05
1.3E-03
1.7E-04
9.0E-01
5.8E 01
A
g g)
!-133
1.6E-02
8.3E-05
1.5E-02
1.4E-02
9.2E-01
2.OE 02
A
I-135
7. 0E-02
8.6E-04
2.7E-02
1.*E-03
8.9E-01
3.5E 01
A
MO-90
1.4E-03
1.1E-04
1.3E-03
2.lE-04
9.1E-01
1.3E 01
A
TC-MM
1.4E-03
1.7E-05
1.SE-03
1.TE-04
1.1E 00
8.OE 01
A
c,;
1 = c .;
,,7: . %
4 id-04
2. h -v5
1.UE 90
1. 3
n:
CS-177
3.SE-04
!.7E 05
3.3E-04
4.SE-05
4.4E-01
2.1E O!
A
L VASTE
CO-58
2. TE-Oe
1.2E-07
3.OE-Oo
0.OE-01
1.3E 00
1.9E 01
D
F
CO-e0
5.5E-Oo
1. 7E- 07
1.OE-05
7. OE- O'
2.OE 00
3.OE 01
D
(Dcr4)
1-131
5.!E-Co
1.3E-07
S.6E-06
3.8E-06
1.0E 00
4.2E 01
A
'
I-133
1.cE-00
1.4E-07
I.dE-06
1.6E-07
6.9E-01
1.2E 01
A
SB-125
2.4E-06
2.CE-07
2.2E-Oo
2.eE-07
9.3E-01
8.1E 00
A
T TEST RESI.LTS:
A= AGREEMENT
D*DISAGPEEMENT
'
,
!
- CRITERIA RELA *ED
'
NANO CC$1PARISON
'
'
2
__ --
7
-
- - - - - - - . - - - - - - - _
.
s
,
.
TABLE I
U S tJXLEAR REGULATORY COMMIS$!rW
OFFICE CF INSFECTION AND ENFORCEMENT
CONFIRMATORY MEASttREMENTS PROGRAM
FACILITYt ZION
FOR THE 1 OUARTFR O.c 1988
NRC-------
LICENSEE----
---LICENSEE NPC----
SAMPLE
ISOTOPE RESULT
ERROR
RESULT
ERROR
RATIO
PES
T
L IJASTE
CS-134
1.SE-06
8.2E-08
1.2E-06
1.OE-07
8.IE-01
1.BE 01
A
'
(nc re)
2.4E-06
1.3E-07
2.2E-06
2.!E-07
9.3E-01
1.8E 01
A
OFF GAS
9.OE-04
3.2E-04
6,2E-04' 8.1E-05
6.9E-01
2.8E 00
A
XE-131M 1.7E-04
1.9E-05
1. 4 E- 04
1.8E-05
0.0E-01
9.3E 00
A
M #)
5.7E-03
1.8E-05
6.OE-03
0.OE-01
1.OE 00
3.1E 02 A
t
XE 133M 3.5E-05
3.SE-06
3.8E-05
4.lE-06
1.1E 00
9.lE 00
A
XE-135
3.7E-05
1.2E-06
3.6E-05
2.9E-06
9.BE-01
3.IE 01
A
PRIMARY NA-24
2.4E-03
6.4E-05
2.2E-03
2. OE- 04
9.OE-01
3.8E 01
A
l
1.4E-03
2.4E-05
1.4E-03 6.7E-05
9.9E-01
5.9E 01
A
-
( N ' N !-133
1.6E-02
8.5E-05
1.SE-02
2.8E-04
9.3E-01
1.9E 02
A
I-135
3.1E-02
8.7E-04
3.1E-02
2.8E-03
1.OE 00
3.SE 01
A
1.4E-03
1.4E-04
1.BE-03
3.5E-04
1.3E 00
9.9E 00
A
TC -99M
1.4E-03
1.9E-05
1.4E-03
0.OE-01
9.9E-01
7.6E 01
A
CS-- 134
1.5E-04
9.OE-06
1.7E-04
3.oE-05
I.lE 00
1.7E of
A
3.2E-04
1,3E-05
3.3E-04
4.4E-05
1.OE 00
2.5E 01
A
OFF GAS
9.0E-04
3.2E-04
6.2E-04
7.4E-05
6.9E-01
2.0E 00
A
1.9E-05
1.3E-04
7.4E-05
7.4E-01
9.3E 00
A
h
VE-133
S.7E-03
1.SE-05
es.OE-03
0.OE-01
1.OE 00
3.1E 02
A
'
XE-133M 3.5E-05
3.BE-06
3.6E-05
3.8E-06
1.OE 00
9.1E 00
A
'
VE-135
3.7E-05
1.2E-06
3. 5E -05
2.8E-06
9.5E-01
3.!E 01
A
.
--
1 TEST Rest 1TS:
,
/.= W PEEMENT
.Di D h' AGPEEMENT
+=CPlVERIA PELA1ED
h*NO CCW ARISON
.
.
?
?
,
- 3-
_
_
_.
.
.
..
.s
ATTACHMENT 1
,
CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS
This attachment provides criteria for comparing results of capability ttsts
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 judgment limits are variabla in relation to the comparison
of the NRC's value to its associated one sigma uncertainty,
As that ratio,
referred to in this program as "Resolution", increases, the acceptability of a
licensee's measurement should be more selective.
Conversely, poorer agreement
should be considered acceptable as the resolution decreases.
The values in the
ratio criteria may be rounded to fewer significant figures reported by the NRC
Reference Laboratory, unless such rounding will result in a narrowed category of
acceptance.
RESOLUTION
RATIO = LICENSEE VALVE /NRC REFERENCE VALVE
,
Agreement
<4
0.4 - 2.5
1
4-
7
0.5 - 2.0
>
8-
15
0.6 - 1.66
16 - 50
0.75 - 1.33
51 - 200
0.80 - 1.25
-
200 -
0.85 - 1.18
,
- -
Some discrepancies may result from the use of different equipment, techniques,
and for some specific nuclides.
These may be factored into the acceptance
criteria and identified on the data sheet.
,
J