IR 05000266/1982005
| ML20054D190 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/07/1982 |
| From: | Oestmann M, Paperiello C, Rozak S, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054D184 | List: |
| References | |
| 50-266-82-05, 50-266-82-5, 50-301-82-05, 50-301-82-5, NUDOCS 8204220425 | |
| Download: ML20054D190 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
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' Reports No. 50-266/82-05(DEPOS); 50-301/82-05(DEPOS)
Docket Nos. 50-266; 50-301 Licenses No. DPR-24; DPR-27
Licensee: Wisconsin Electric Power Company 231 West Michigan Avenue Milwaukee, WI 53203 Facility Name:
Point Beach Nuclear Power Plant, Units 1 and 2 Inspection At:
Point Beach Site, Two Creeks, WI-Inspection Conducted: March 22-24, 1982
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q l7,lg y Inspectors:
S. Rozak
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7H.}044.a ab w
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m M.'J. Oestmann
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M'N sf4hy Approved By:
. C. Schumacher, Chief
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Independent Measurements and Envir nmental Protection Section lf $&
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C. l). P llo, Chief Emergency Preparedness and Program Support Branch Inspection Summary Inspection on March 22-24, 1982 (Reports No. 50-266/82-05(DEPOS);
50-301/82-05(DEPOS))
' Areas Inspected: Routine, announced inspection of confirmatory measure-ments including collection of samples, analyses onsite with the Region III Measurements Van and discussion of results. The inspection involved'30 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance or deviations were identified during the inspection.
8204220425 820407 PDR ADOCK 05000266 G
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DETAILS 1.
Persons Contacted
- J.
Zack, Superintendent, Technical Services
- R. Link, Supervisor, Engineering, Regulatory Affairs, and Quality Assurance
- P. Skramstad, Radiochemical Engineer T. Slack, Nuclear Plant Specialist in Chemistry
- F. Zeman, Officer Supervisor The inspectors also interviewed several other licensee employees during the course of this inspection, including radiochemical technicians and health physicists, members of the security force and general office personnel.
- Denotes those present at the plant exit interview.
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Licensee Action on Previous Inspection Findings (0 pen) Open item (50-266/81-24-02; 50-301/81-25-02):
Licensee's Environmental Manual needs updating. The licensee reported that the licensee's Corporate Office is in the process of updating the Environ-mental Manual. This item remains open, pending completion of revisions to this Manual.
3.
Results of Comparative Analyses A liquid waste, charcoal adsorber, particulate filter, and a gas sample were collected at the plant and the liquid waste and gas sample split with the licensee. The samples were analyzed by the licensee in his laboratory and by the NRC using the Region III Measurements Van during this inspection. The results of comparative analyses, as shown in Table I, were reviewed with the licensee. The criteria for comparing measurement results are given in Attachment 1.
For 18 sample comparisons, the licensee's results yielded 18 agreements or possible agreements. During the analyses of the liquid waste and the
particulate filter, the licensee identified several additional radio-
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-nuclides not identified by the Region III Measurements Van. The
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inspectors observed during a tour of the licensee's counting room that i
several plastic bottles containing mixed radionuclide standard solutions were stored unshielded on a shelf in the counting room near the detector.
These sources may have been the cause of the detector identifying addi-
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tional nuclides. The inspectors discussed with licensee representatives the need to remove excess radionuclide samples from the counting room to assure they do not have an effect on the background in the counting room.
The licensee agreed to shield or remove these sources.
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The split liquid sample will also be analyzed for tritium, strontium-89
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and -90, and for gross beta (to be counted on April 26, 1982 at 12:00 noon CST) by the licensee and the NRC Reference Laboratory and the
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results compared and reported in an addendum to this inspection report.
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(Open Item 50-266/82-05-01; 50-301-82-05-01).
No items of noncompliance or deviations were identifeld.
4.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
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at the conclusion of this inspection on March 24, 1982. The inspectors
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summarized the scope and findings of the inspection. The licensee agreed:
(1) to shield or remove all excess radioactive sources from the counting
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room; and (2) to analyze the liquid waste for tritium, strontium-89 and-90 and gross beta (to be counted on April 26, 1982 at 12:00 noon CST) and
report the results to Region III for subsequent comparison.
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Attachments-1.
Attachment 1, Criteria for Comparing r
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Analytical Measurements 2.
Table 1, Confirmatory Measurements l
Program Results, 1st quarter, 1982
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ATTACINEiii 1
CP1TERI A FOR rmPAnl);G ANALYTICAL lj_fASUhDiENTS This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an
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empirical relationship whicii combines prior experience anu the accuracy needs of this program.
In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory'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 con-sidered 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 by the NRC Reference Laboratory, unless such rounding will result in a
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narrowed category of acceptance.
The-acceptance category reported-will be the narrowest into which the-ratio fits-for the resolution being used.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Possible Possible Agreement Agreement "A" Agreement "B"
<3 No Comparison No Comparison No Comparison
>3 and <4 d.4 2.5 0.3 3.0 No Comparison
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2.0 0.4
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>4 and <8 0.5
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T8 and <16 0.6 -
1.67 0.5 2.0 0.4
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T16 and <51 0.75 -- 1.33 0.6
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1.67 0.5-
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2.0-I51 and <200 0.80 - 1.25 0.75 -
1.33 0.6 1.67
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T200 0.85 - 1.18 0.80 -
1.25 0.75 1.33
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"A" criteria are applied to the following analyses:
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Camma spectrometry, where principal gamma energy used for f or :!fi-cation is greater-than :250 kev.
Tritium analyses of liquid samples.
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"B" criteria are applied to the.following analyses:
Camma spectrometry, where principal Eamma. energy used for identifi-
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cation is less than 250 kev.
Sr,-89 and Sr-90 determinations.
Cross beta, where ~ samples are counted. on-the-same-date.using the -
i same' reference nuclide.
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TABLE I U S HUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AliD EriFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: POIflT BEACH
FOR THE 1 OUARTER OF 1982
fiRC-------
---LICEf(SEE-----
---LICENSEE:fiRC----
SAMPLE ISDTOPE RESULT ERROR RESULT ERROR RATIO RES T
OFF GAS XE-133 1.5E-04 1.2E-06 1.9E-04 0.0E-01 1.3E 00 1.2E 02 P
XE-135 2.5E-04 1.4E-06 2.6E-04 0. 0E-01 1. 0E 00 1.9E 02 A
KR-85M 3.5E-05 5.2E-07 3.8E-05 0.0E-01 1.1E 00 6.7E 01 A
KR-87 2.0E-05 1.2E-06 1.6E-05 0.0E-01 8.2E-01 1.6E 01 A
KR-88 6.1E-05 1.6E-06 6.7E-05 0.0E-01 1.1E 00 3.SE 01 A
L blRSTE I-131 2.6E-05 6.5E-07 2.9E-05 0.0E-01 1.1E 00 4.0E 01 A
I-132 3.6E-05 9.0E-07 4.2E-05 0.0E-01 1.1E 00 4.1E 01 A
I-133 6.6E-05 9.6E-07 7.0E-05 0.0E-01 1.1E 00 6.9E 01 A
I-134 2.5E-05 2.4E-06 2.8E-05 0.0E-01 1.1E 00 1.1E 01 A
I-135 6.8E-05 2.9E-06 9.2E-05 0.0E-01 1.4E 00 2.3E 01 P
CS-134 7.2E-06 4.6E-07 8.2E-06 0.0E-01 1.1E 00 1.6E 01 A
CS-137 1.2E-05 5.0E-07 9.7E-06 0.0E-01 8.4E-01 2.3E 01 A
CS-138 1.8E-05 2.9E-06 2.0E-05 0.0E-01 1.1E 00 6.1E 00 A
C FILTER I-131 6.1E-03 4.6E-05 6.7E-03 0.0E-01 1.1E 00 1. 3E -02 A
I-132 1.2E-03 5.9E-05 8.8E-04 0.0E-01 7.4E-01 2.0E-01-P --
I-133 1.2E-02 7.2E-05 1.2E-02 0.0E-01 1.1E 00 1.6E 02-A.
I-135 7.0E-03 1.8E-04 7.5E-03 0.0E-01 1.1E 00 3.9E'01 A-P FILTER CS-138 1.1E-01 5.8E-03 1.1E-01 0.0E-01 1.0E.00 1.9E 02n A-
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T TEST RESULTS:
A= AGREEMENT.
D= DISAGREEMENT P=POSSIBLE AGREEMENT N=Tiu COMPARISDN
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