IR 05000295/1988004

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)

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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

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 inspectio Results: No violations or deviations were identified during this inspection, pgg2100007 800210 0 ADOCK 05ooop95 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 (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 problem (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 procedur . Confirmatory Measurements 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 The licensee achieved 73 agreements out of 77 comparison The licensee's containment air particulate sample was analyzed (results not shown) to verify the licensee's results of no detectable activit In order to test the particulate geometry, a reactor coolant filter was analyzed as an air particulate filte Charcoal spike and air particulate (primary coolant filter) samples were analyzed resulting in all agreemen . .

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 cartridg 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 PARAP The inspectors examined the licensee's data and found an error in the system's nuclide library. Correcting the error resulted in an agreemen 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 detector 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 explaine 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-5 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, , 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 nute 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 calibration No violations or deviations were identifie 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 . 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 ciscusse 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 proprietar Attachments:

1. Table 1, Confirnatory Measurement Program Results. 1st Quarter 1988 2. Attachment 1, Criteria for Comparing Analytical Measurements

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e 4 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

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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

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CD-109 3.7E-01 4.1E-03 3.8E-01 0.0E-01 1.0E 00 8.9E 01 A

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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

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TABLE 1 i

U S t*JCLEAR REGlLATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT t

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CONFIRMATORY MEASI1REMENTS PROGRAM FACILITYI ZION FOR THE 1 OUARTER OF 1988

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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

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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

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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

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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

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D*DISAGPEEMENT ,

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! ** 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

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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

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(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

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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

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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 progra .

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 acceptanc RESOLUTION RATIO = LICENSEE VALVE /NRC REFERENCE VALVE

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Agreement

<4 0.4 - 2.5

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4- 7 0.5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 -

200 - ,

0.85 - 1.18

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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 shee ,

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