ML20149F899

Insp Repts 50-295/88-04 & 50-304/88-05 on 880112-15 & 19.No Violations Noted.Major Areas Inspected:Qa & Confirmatory Measures for in-plant Radiochemical Analyses & Action on Open Items Previously Identified

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: ML20149F892 ML20149F899
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

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-295/88004(DRSS); 50-304/88005(DRSS)

Docket Nos.. 50-295; 50-304 Licenses No. DPR-39; DPR-48

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

Inspector:

. a a h6

Date

8

Accompanied By: R. Bocanegra

Approved By:

h/b d4tWAbu

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

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PDR

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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,

H-3, Sr-89, Sr-90 and Fe-55. The licensee will report his results

to Region III (0 pen Item 50-295/88004-03; 50-304/88005-03). The

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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

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TABLE 1

U S NUCLEAR REGl.LATORY COMMISGION

i

OFFICE OF IN?PECTION AND ENFORCEMENT

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 RES T

C FILTER BR-182 7.1E-11 3.0E-12 5.3E-11 2.lE-12 7.5E-01 2.4E 01 D

(perJ) 1-131 2.0E-11 1.1E-12 2.1E-11 2.0E-12 1.0E 00 1.8E 01 A

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

CO-57 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

,

CD-109 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

CS-137 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

CS-137 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

C SP!KED CO-57 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)

P Y-66 2.IE-0? 2,IE-04 2.SE-03 0.OE-01 1.1E 00 1.1E 01 A

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

CS-137 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

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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 RES 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

CS-137 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

CO-60 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

CS-137 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

I-135

1.6E-02

7. 0E-02

8.3E-05

8.6E-04

1.5E-02

2.7E-02

1.4E-02

1.*E-03

9.2E-01

8.9E-01

2.OE 02

3.5E 01

A

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

1.cE-00 1.4E-07 6.9E-01 1.2E 01

'

I-133 I.dE-06 1.6E-07 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

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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) CS-137 2.4E-06 1.3E-07 2.2E-06 2.!E-07 9.3E-01 1.8E 01 A

OFF GAS kR-85 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 #) 1E-133 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

I-131 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

MO-99 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

CS-137 3.2E-04 1,3E-05 3.3E-04 4.4E-05 1.OE 00 2.5E 01 A

OFF GAS KR-85 9.0E-04 3.2E-04 6.2E-04 7.4E-05 6.9E-01 2.0E 00 A

1E-131M 1. 7E-04 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

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h*NO CCW ARISON

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, 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.

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