IR 05000295/1986018

Insp Repts 50-295/86-18 & 50-304/86-17 on 860721-25.No Violations or Deviations Noted.Major Areas Inspected: Confirmatory Measurement Program & Review of Counting Room QC Program

ML20205B828
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	08/05/1986
From:	Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20205B820	List: IR 05000295/1986018 ML20205B814
References
50-295-86-18, 50-304-86-17, NUDOCS 8608120173
Download: ML20205B828 (8)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-295/86018(DRSS); 50-304/86017(DRSS)

Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 ,

Facility Name: Zion Nuclear Generating Station, Units 1 and 2 Inspection At: Zion Site, Zion, IL 60099 Inspection Conducted: July 21-25, 1986 Inspector:

f/ & : maw A. G. Januska M //M Date Approved By: M. C. Schumacher f/.fIA Inspection Summary Date Inspection on July 21-25, 1986 (Reports No. 50-295/86018(DRSS);

50-304/86017(DR55))

Areas Inspected: Routine unannounced inspection of (1) Confirmatory Measurement Program including sample split and onsite analysis with Region III Mobile Laboratory; review of the licensees counting room quality control program and (2) review of an open item identified during a previous inspectio Results: No violations or deviations were identified 8608120173 860805 PDR ADOCK 05000295 G PDR

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DETAILS Persons Contacted

• E. Fuerst, Production Superintendent

• T. Rieck, Services Superintendent

• P. Zwilling, Lead Chemist

• J. Rappeport,-QA Engineer

• C. Doil, Chemist

• C. Schultz, Regulatory Assurance Supervisor

• R. Budowle, Assistant Services Superintendent G. Trzyna, Rad / Chem Supervisor D. Hemmerle, Chemist K. Miedlar, Chemist L. Lanes, Lead Health Physicist Foreman

• L. Kanter, NRC Resident Inspector

• Denotes those present at the exit meetin . Licensee Action on Previous Inspection Findings (Closed) Open Item (50-295/84016-01; 50-304/84014-1): Update calibration stickers on environmental air samplers and rework piping to eliminate potential leakage paths. The inspector visited environmental air sampling stations of four locations and found that (1) the pumps bore current calibration tags, (2) all were operating properly and (3) there was no evidence of leakage when the system was tested. In addition, the Offsite Dose Calculation Manual, Revision 11, June 1985 was selectively reviewed and appears to list proper sampling location . Confirmatory Measurements Sample Split Six samples (air particulate, charcoal, lake discharge, waste gas decay, reactor coolant and charcoal standard) were analyzed for gamma emitting isotopes by tne licensee and in the Region III mobile laboratory onsit Samples were analyzed in detectors 1 and/or 3, and the lake discharge and reactor coolant samples additionally on the Post Accident Radionuclide Analysis Portable System (PARAPS). Results of the sample comparisons are listed in Table 1; comparison criteria are given in Attachment The licensee achieved six agreements on the particulate filter and a total of 19 agreements on the three reactor coolant sample analyse Anrlyses of the lake discharge sample (L WASTE and PARAPS2) yielded conservative disagreements (33% and 47%) for C0-60. To verify the validity of the sample split, the licensee's portion was analyzed in the Region III Mobile Lat, oratory resulting in no apparent Co-60 bias in the licensee's sample. A review of data did not reveal the source of the disagreement. A review of L WASTE results obtained during the inspection conducted in August 1985 also indicated conservative Co-60 results (37% and 57%), although both resulted in agreements. The licensee agreed to verify the Co-60 efficiency calculations and also analyze a spiked liquid sample supplied by the NRC

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(0 pen Item 295/86018-01;304/86017-01). The licensee also agreed to analyze a portion of the discharge sample for gross beta, H-3, Sr-89 and Sr-90 and report the results to Region III (0 pen Item 295/86018-02; 304/86017-02).

Analyses of a charcoal absorber on both detectors 1 and 3 yielded a disagreement for I-131 on detector 1. To obtain additional information regarding this geometry, the licensee's charcoal standard was also analyzed on detector 1 and compared as though a real sample using gamma lines with energies that approximated those of the iodine isotope No reason for the disagreement was found; the licensee agreed to verify the efficiency calculations for I-131 and one other iodine isotope and recalibrate if necessary (0 pen Item 295/86018-03; 304/86017-03).

A waste gas decay sample compared yielded a disagreement for Xe-13 Analysis of a resample also yielded a disagreement for Xe-133 and except for Xe-131 on the first sample, results on both samples appear to be conservatively biased. The licensee has a gas standard on order and agreed to calibrate his gas geometries within two weeks after receipt of the standard (0 pen Item 295/86018-04; 304/86017-04).

No violations or deviations were identifie . Counting Room Quality Control Program The inspector reviewed the counting room quality control program. The licensee performs daily QC performance tests on gamma spectrometers, alpha counters, beta gamma counters and liquid scintillation counters (LSC). The gamma spectrometers and beta gamma counters are automated and, if a parameter fails, will only perJnt performance tests to be rerun, not sample analyses. Test results are entered automatically into a data base which is used to generate a trend plot upon request or routinely on a weekly basis. Selective daily tests of these types of equipment were examined and indicated that they have been run on the proper schedule. The inspector noted during the inspection that a beta gamma counter had failed and was physically tagged out of service according to procedur The alpha counters (2) and LSCs (2) are not automated and daily test results are entered into a book on preprinted forms by Radiation Chemistry Technicians. In addition, a form specifying whether the instrument passed on the first or second performance test is completed daily and submitted to chemists for review. Test results are also entered into a data base by Radiation Chemistry Technicians through any of a number of available terminals. The inspector examined six month trend plots for all counting equipment and found them to be well don The interval, six month by the day, appears to be proper to allow a trend to be determined and yet not too cluttered. The inspector reviewed ZCP 530-13, Daily Performance Check of the Packard Liquid Santillation Counters and ZCP 531-7, Performance Test for the Eberline Model SAC-4

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Scintillation Alpha Counter and their associated Tables and noted that they are in the process of being revised. The licensee agreed to complete these versions and have them ready for review by September 1, 1986 (0 pen Item E95/86018-05; 304/86017-05).

The licensee is involved in a gamma isotopic cross-check program with the Byron Nuclear Generating Station. These results were examined during the Byron inspection conducted in March 1986. The licensee also analyzes selective samples offered in the EPA cross-check program. The licensee indicated that he is having difficulties in obtaining agreement for gamma in wate Discussions indicate that the samples, which are at environmental levels, are not being counted for a long enough perio The licensee indicated he will extend the count time. The inspector also discussed the advantage of entering into a cross-check program where levels of radioactivity in the sample are representatives of those seen in a power plant. The licensee acknowledged the comment No violations or deviations were identifie . Open Items Open items are matters which have been discussed with 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 Sections 3 and . Exit Interview The inspector reviewed the scope and findings of the inspection with licensee representatives listed in Section 1. Disagreements noted in Section 3 were discussed in detail. The licensee acknowledged the inspectors comment During the exit interview, the inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. Licensee representatives did not identify any

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such documents or processes as proprietar Attachments: -

1. Table 1, Confirmatory Measurements Program Results, 3rd Quarter 198 . Attachment 1, Criteria for Comparing Analytical Measurements.

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TAELE 1

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U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: ZION *

FOR THE 3 OUARTER OF 1986

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NRC , ----LICENSEE- ---LICENSEE: NRC----

SAMFLE ISOTOPE RESULT ERRCR RESULT ERROR RATIO RE9 T

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C FILTER BR-82 1.7E-07 1.6E-08 1.6E-07 0.0E-01 9.6E-01 1.0E 01 A lb 67~ l I-131 9.6E-06 4.1E-08 1.2E-05 0.0E-01 1.2E 00 2.3E 02 D I-133 9.4E-06 5.1E-08 1.1E-05 0.0E-01 1.2E 00 1.8E 02 A I-135 2.8E-06 1.2E-07 2.9E-06 0.0E-01 1.0E 00 2.3E 01 A P FILTER NA-24 1.5E-07 1.0E-08 1.5E-07 0.0E-01 9.7E-01 1.5E 01 A TC-99M 2.2E-08 2.1E-09 2.7E-08. 0.0E-01 1.2E 00 1.0E 01 A 1(T 3 I-131 1.3E-07 6.0E-09 1.3E-07 0.0E-01 9.9E-01 2.2E 01 A I-133 5.3E-07 1.5E-08 5.4E-07 0.0E-01 1.0E 00 3.7E 01 A CS-134 7.7E-07 9.8E-09 7.1E-07 0.0E-01 9.3E-01 7.8E 01 A CS-137 7.7E-07 1.0E-08 6.9E-07 0.0E-01 8.9E-01 7.7E 01 A C FILTER BR-82 1.7E-07 1.6E-08 1.7E-07 0.0E-01 1.0E 00 1.0E 01 A I-131 9.6E-06 4.1E-08 1.1E-05 0.0E-01 1.1E 00 2.3E 02 A ET 3 I-133 9.4E-06 5.1E-08 1.0E-05 0.0E-01 1.1E 00 1.8E 02 A I-135 2.8E-06 1.2E-07 2.8E-06 0.0E-01 1.0E 00 2.3E 01 A PRIMARY I-131 3.6E-03 9.8E-05 3.6E-03 0.0E-01 1.0E 00 3.7E 01 A I-132 1.5E-02 1.2E-04 1.4E-02 0.0E-01 9.3E-01 1.3E 02 A ED ET I I-133 2.1E-02 1.2E-04 2.2E-02 0.0E-01 1.0E 00 1.8E 02 A I-134 4.1E-03 1.4E-04 4.5E-03 0.0E-01 1.1E 00 3.0E 01 A I-135 2.9E-02 4.0E-04 2.7E-02 0.0E-01 9.3E-01 7.3E 01 A CS-134 4.5E-03 7.6E-05 4.8E-03 0.0E-01 1.1E 00 5.9E 01 A CS-137 4.4E-03 8.7E-05 4.2E-03 0.0E-01 9.6E-01 5.0E 01 A NA-24 4.4E-03 1.1E-04 4.2E-03 0.0E-01 9.6E-01 4.0E 01 A L WASTE FE-54 1.5E-06 3.2E-07 2.0E-06 0.OE-01 1.3E 00 4.8E 00 A CO-58 1.8E-06 1.9E-07 1.4E-06 0.0E-01 7.7E-01 9.6E 00 A DFT 3 I-131 7.8E-07 1.5E-07 8.4E-07 0.0E-01 1.1E 00 5.1E 00 A CS-134 1.5E-06 2.0E-07 1.1E-06 0.0E-01 7.5E-01 7.3E 00 A CS-137 1.4E-06 1.5E-07 1.7E-06 0.0E-01 1.2E 00 9.7E 00 A

' CO-60 7.5E-06 3.3E-07 1.0E-05 0.0E-01 1.3E 00 2.3E 01 D i

T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT-o=CRITEPIA RELAXED N=NO COMPARISON

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, TABLE 1 U S NUCLEAR-REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIPMATORY MEASUREMENTS PROGRAM FACILITY: ZION

FOR THE 3 QUARTER OF 1986-NRC - -

LICENSEE---- LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

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PRIMARY I-131 3.6E-03 9.8E-05 3.4E-03 .0.0E-01 .9.4E-01 3.7E 01 A I-132 1.5E-02 1.2E-04 1.5E-02 0.0E-01 1.0E 00 1.3E 02 A

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'b ET 3 I-133 2.1E-02 1.2E-04 2.3E-02 0.0E-01 1.1E 00 1.8E 02 A I-134 4.1E-03 1.4E-04 4.3E-03 0.0E-01 1.0E 00 3.0E 01 A I-135 2.9E-02 4.0E-04 3.0E-02 0.0E-01 1.0E 00 7.3E 01 A CS-134 4.5E-03 7.6E-05 4.7E-03 0.0E-01 1.0E 00 5.9E 01 A CS-137 4.4E-03 8.7E-05 4.2E-03 0.0E-01 9.6E-01 5.0E 01 A C SPIKED CO-60 5.0E-02 6.6E-04 5.2E-02 0.0E-01 1.0E 00 7.6E 01 A Y-88 3.2E-03 3.8E-04 3.8E-03 0.0E-01 1.2E 00 8.6E 00 A DETI SN-113 3.2E-03 3.2E-04 3.3E-03 0.0E-01 1.0E 00 1.0E 01 A CS-137 5.9E-02 6.2E-04 6.2E-02 0.0E-01 1.0E 00 9.6E 01 A PARAPS1 NA-24 4.4E-03 1.1E-0+ 3.8E-03 0.0E-01 8.7E-01 4.0E 01 A I-131 3.6E-03 9.8E-05 3.7E-03 0.0E-01 1.OE 00 3.7E 01 A Pe man.j .I-133 2.1E-02 1.2E-04 2.2E-02 0.0E-01 1.0E 00 1.EE 02 A I-135 2.9E-02 4.0E-04 2.7E-02 0.0E-01 9.3E-01 7.3E 01 A CS-134 4.5E-03 7.6E-05 4.9E-03 0.0E-01 1.1E 00 5.9E 01 A CS-137 4.4E-03 8.7E-05 4.4E-03 0.0E-01 1.0E 00 5.0E 01 A OFF GAS KR-85 3.6E-03 3.5E-04 4.2E-03 0.0E-01 1.2E 00 1.0E 01 A XE-131M 1.8E-04 2.2E-05 1.7E-04 0.0E-01 9.7E-01 8.OE 00 A 1>ert XE-133 6.5E-03 2.0E-05 7.8E-03 0.0E-01 1.2E 00 3.2E 02 D YE-133M 3.4E-05 5.6E-06 5.1E-05 0.0E-01 1.5E 00 6.0E*00 A i

PARAPS2 FE-59 1.5E-06 3.2E-07 1.4E-06 0.0E-01 9.2E-01 4.8E 00 A CO-58 1.8E-06 1.9E-07 2.0E-06 0.0E-01 1.1E 00 C.6E 00 A-

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L k, A rny CO-60 7.5E-06 3.3E-07 1.1E -05 0.0E-01 1.5E 00 2.3E 01 D I-131 7.8E-07 1.5E-07 6.1E-07 0.0E-01 7.8E-01 5.1E 00 A CS-134 1.5E-06 2.0E-07 1.5E-06 0.0E-01 1.0E 00 7.3E 00 A CS-137 1.4E-06 1.5E-07 1.5E-06 0.0E-01 1.1E 00 9.7E 00 A OFF GAS KR-85 3.8E-03 3.7E-04 4.1E-03 0.0E-01 1.1E 00 1.0E 01 A EES An P LG T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT

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o= CRITERIA RELAXED N=NO COMPARISON

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TABLE 1 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: ZION FOR THE 3 QUARTER OF 1986 NRC- -

LICENSEE-- LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T OFF GAS XE-131M 1.4E-04 2.6E-05 2.5E-04 0.0E-01 1.8E 00 5.3E 00 A XE-133 1.1E-02 2.6E-05 1.3E-02 0.0E-01 1.2E 00 4.2E 02 D XE-133M 9.4E-05 8.2E-06 1.2E-04 0.0E-01 1.3E 00 1.2E 01 A XE-135 7.6E-05 1.7E-06 9.2E-05 0.0E-01 1.2E 00 4.4E 01 A T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED N=NO COMPARISON

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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS

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_This attachment provides criterir for comparing results of capability tests and verification measurements. The criteria are based on an empirical

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relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgment limits are variable in relation to the com-parison 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 to maintain statistical consistency with the number of significant figures reported i by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptanc RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement I

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<3 No Comparison

.33 and <4 .5 J4 and <8 .0

.1p and <16 .67 jt,16 and <51 0.75 - 1.33

.351 and <200 0.80 - 1.25

.1200 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 shee .. ._ __ . _ _ _ _ . __ _ _ _ _ _ . _ ___ _ _ __ _ . _ . _ _ _ _ _ _ -- _ . _ _ _ -_ _ _ _ .