IR 05000440/1990017

Insp Rept 50-440/90-17 on 900709-13 & 25.No Violations Noted.Major Areas Inspected:Confirmatory Measurements & Radiological Environ Monitoring Programs Including,Audits & Appraisals,Changes in Organization & Equipment

ML20058M059
Person / Time
Site:	Perry
Issue date:	08/01/1990
From:	House J, Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20058M055	List: IR 05000440/1990017 ML20058M053
References
50-440-90-17, NUDOCS 9008090318
Download: ML20058M059 (11)

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U.S. NUCLEAR REGULATORY COMMISSION a

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REGION III: ,

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Docket No. 50-440 License No. NPF-58

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Licensee: The Cleveland Electric Illuminating Company ^

( , 10 Center Road i- Perry, Ohio 44081

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,_ -Facilit) Name:: Perry Nuclear Power Plant', Uni. .

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'ei l;j Insp6ction At: Perry Site, Perry, Ohio 1 <

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Inspection' Conducted: Juiy 9-13 and 25, 1990 -

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' Inspectors: J. E. House 8 +,

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iL ' ' ) Approved By

M. C. Schumacher, Chief 'N ## .,

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, f~' q . ' Radiological Controls and Date

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Chemistry Section

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Inspection Stmmary 9 :t t i' s 't

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' h [j y' ~ i Inspection en July 9-13 and'25, 1990 (Report No. 50-440/90017(DRSS)) *j 1?

Xreas InspeQted: Routine announced inspection of the licensee's confirmatory

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f l measurements and radiological environmental monitoring programs including: ,

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audits and appraisals; changes,in organization, equipment and instrumentation; implementation of the quality assurance and confirmatory measurements program;

, implement? tion of the' Radiological Environmental Monitoring Program (REMP) and q implementation of the REMP quality assurance program _(IP 84750, 84725) and , o review-of Open' Items (IP 92701)~. ~

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. TheLfo11owing strengths and. weakness <ss were note )

i Strengths: (1) chemist responsible for laboratory QA/QC, (2) good gamma spectroscopy performanc . Weakness: strontium confirmatory messurements comparison !

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DETAILS U lc ' y J

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Persons' Contacte s

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. 2 R.' Bowers, Manager, Radiation Protection Section ,

y J 4 2W. E. Coleman, Manager. QAS ' '

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1. 2. .,2J, J. Grimm... Plant Chemist e E 2H. H.,Hegrat, Compliance Engineerf s .j T '/

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f; 25. : F. Kensicki, Director, Engineering . 4'

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2R.'A. Newkirk, Manager, licensing & Compliance; & -

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2,20. A.- Shelton, General Supervisor, Chemistry '

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1-9< 4 2R. A. Strathman, Plant Manager -

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T" . 2J. J. Traverso, Acting Corporate Health Physicist

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.  ? '2Li VanDerHorst,LPlant Health Physicist- t

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4 2P. Hiland, Senior Resident Inspect'or, NRC "

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2Present at the Exit Meeting on-July 13, 199 <

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,s l2PresentduringtelephonediscussiononJuly 25, 1990. ' t

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' ' Licensee Action on Previous Inspection Findings (IP 92701) ,

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, (Closed) Open Item (50-440/89004-01)i Licensee to reW ow performance -

,4 { l ~ of vendor radiochemistry laboratory and take corrective action if g .

,-f neede The licensee has performed sample splits with and audited -; -i

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the vendor. Based on=this audit and the' investigation of changes n' 4

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made by.the vendor,4the licensee will. continue using this vendor,

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'however oth'er contractor laboratories are being reviewe , (Closed) Open Item (50-440/89004-02): Licensee to investigate a negative-bias that occurred in analyses of Mn-54, Mn-56,1Cr-51~and-take corrective actio The licensee's investigation indicated that-the counting geometry was not correct. The licensee stated tha analyses of.NBS traceable sources on two multi-channel analyzers y ,

indicated that no biases we q present. 'The above nuclides were

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agreements during the prestat confirmatory measurements inspectio . (Closed) Open Item (50-440/89027-01): Licensee to, spike reactor

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water with anions, split sample with Brookhaven National: Laboratory

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(BNL), analyze and send results to Region III. Thetcontract between the NRC and BNL was terminated before the split could'be made. This 1 item is considered close d., (Closed) Open Item (50-440/89004-03): Licensee to analyze a portion of a liquid waste sample for gross beta, H-3, Sr-89,LSr-90'ano re-55 and report the results to Region III. Results of the' sample comparisons are given in Table 1 and the comparison criteria ar given in Attachment 1. Nonconservative disagreements resulted,for gross beta and Fe-55. The beta disagreement appeared to* result from ,

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sample,self-absorption. A spiked sample was then sent to the licensee.~

The results are given in Table 2. The licensee achieved' agreements s,

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.I y'- forgrossbetaandFe-55buthada}nonconservativedisagreementfor M}g.3', y '

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c Sr-89;and St-90.': Licensee representatives agreed to' send additionali .,x r spiked samples to their. vendor for strontium and Fe-55 analyses,c and" t ' '

to review'past liquid ieleases and make appropriate corrections and- y,

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., . issue errata as:needed to their semiannual effluentireportsa _This' ip

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matter'will be followed under open item 50-440/90017_-010 '

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. (Closed)'Oden Item (50-440/ 89004-04)i * Licensee to implement o ;< - - *

routine technician Post Accident Samp1ing. System (PASS) training f,'

by July 1989 and subsequently conduct: PASS training on a regular _ '

c-F frequency.' 'The training,was implemented in June _1989, tThe '~

' inspectors reviewed documentation which defined the objective of3 W *,

E" 1 the PASS continuing trair>ing program, ' training discussion' topics (

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and"clas's completion records which included evaluator' sign offs of- /

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the training, items-completed by the trainee. The PASS schedule

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o (assure's training to PASS qualified (technicians. biannually, i

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' 13. - Management Control', Organization and Training (IP 84750) ,y 4 ,

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The inspectors reviewed.the management and organization of the' Radiation s g" ', '

Protection Section (RPS) which includes both nonradiological'and .. + .

radiological chemistryE The structure is the same as*was found'in"th 't-

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previous inspection (Region III Inspection Report 89027).. The position of quality assurance chemist appears to be working well as it provides'

N O the laboratory with an individual whose main responsibil,ity isito oversee laboratory QA/Q .

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" Radiological Confirmatory Measurementst (IP 84750, IP 84725) 1

, m o e Sample Split

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Six samp'at (air. particulate, charcoal,offgas-1iquidwaste,l filtere '

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reactor coolant and:the reactor coolant crud filter) were analyzed. -

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f for gamma *1emitJna nuclides'by the, licensee and2in the Region III .

w;,1 _ Mobile Laboratory on sitei Comparisons were made with the licensee's ,

,y a two count room detectors , The licenseeiachieved 86 agreements out of

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88 comparisons as listed in Table 3; the comparison criteria are C

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given in Attachment,1. Kr-85M (offgas)ias a conservative b ' '

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OL e . y$ 1 ' ' disagreement when counted on each of the licensee's. two: detector <

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A second ofNas s' ample showed Kr-85M to be in agreement 'on both 6  ;> '

licensee detectors.~ The licensee's most recent air particulate-

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filter, analyzed by the inspectors, resulted in little activity.-

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, The RCS crud f.ilter was used for additional comparison The '

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I, < w ., licensee perfo'rmed well in' the Confirmatory Measurements Program. . -

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< ,1 F*',,j, A portion 'of a:11gu'id waste'sa'mple collected during this ' inspection j, ;

I( i , .will be analyzed for gross alpha, gross beta,,H-3,.Sr-89, Sr-90 and ,

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.4 Fe-55 by the licensee's vendor laboratory .and'the results reported to

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,  ; Region III for comparison with an analysis by the NRC Reference

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P cLaboratory on a split of the sample.(0 pen Item 50-440/90017-02).

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/* ,b.H- Quality Assurance - 'f ,

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1ji 4 > quality assurance program including physical facilities, laboratory-

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y s'- i g 7, operations and selected procedures. Housekeeping was generally good;,

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laboratory and counting roor work space was adequate,: Chemistry

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3 Technicians were. observed during sample acquisition, preparation, <

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appeared to be knowledgeable, followed proper laboratory procedures. '

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/*/ 7 b,4 - The licensee participates in an intercomparison cross-chech p'rogram'" . ; with an outside vendor. The inspectors examined selected results '

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from 1989 and 199 The licensee. achieved 40' agreements in d ' N;

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41' comparisons, the one disagreement being gross beta. In the last-  ! ! ?,

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f two intercomparisons,~the gross betas were agreement ..

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t j }. 3 E ; The inspectors examined selected data for the instrument quality control program. : Check standards were run as required and the I(

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(SD) warning limits and +'3 SD control limits Results that exceeded

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the warning or control limits were flagged and brought.to the' *

attention of laboratory management as required,'and properly

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No violations of-deviations were identifie . Radiological Environmental Monitoring Program (REMP)-

The inspectors examined the adherence of the REMP to the Technical -

- - Specifications-(T/S), itsiimplementation, the Annual Operating Report

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and also toured some selected air sampling stations. The program

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- listed in the 1989 Annual Environmental Operating Report complies with  :

requirements of Table 3.12.1-1 of the T/S. More samples are collected than the program required. The program is being implemented properly and samples are collected on the proper frequency. Missed samples are documented along with the reann. 'A review of the 1989 Annual Report

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to the operation of the plant, The inspector toured'several near site air sampling stations with the licensee's sample collector during the

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_ normal weekly collection. The collector appeared very. knowledgeable of the program. Equipment was well maintained and!was within the required calibration frequency. The report of an audit of the program was examine .The audit was comprehensive, in good depth and program oriented when appropriat e No violations or deviations were note *

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Open items are matters which have been discussed with'the licensee, which  ;

will be reviewed further by the inspector, and which involve some action

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on the part of the NRC or licensee or both.~ Open items disclosed during j the inspection are discussed.inl Sections 2.d and ,

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Exit Interview I

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,' The. scope and findings of the/ inspection were' discussed with licensee ci representatives (Section 1) at the conclusion of the inspection on

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July 13 1990. The inspectors stated'that the licensee nad performed

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J well on the gamma spectroscopy comparisons but noted there were sti?1-P'

u difficulties with beta analyses,'particularly for strontiu The inspectors discussed the likely informational content of the inspection

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report. . Licensee representatives did not identify any' documents or

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processes reviewed by the , inspectors as' proprietar Attachments: .

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1. Table.1, Confirmatory Measurements '

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Program Results,- First Quarter,y1989 Table 2, Confirmatory Measurements

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Program Results,-Fourth Quarter, 1989 -

' Table 3. Confirmatory Measurements Program Results,-Third Quarter,~1990

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, < Attachment 1, Criteria for Comparing ' -

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i U.S. NUCLEAR REGULATORY COMMISSION

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OFFICE OF INSPECTION AND ENFORCEMEN .

CONFIRMATORY MEASUREMENTS PROGRAM  !

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FACILITY. PERRY l FOR THE 1ST QUARTER 1989 4

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SIMPLE .NUCLIDE NRC V4L. NRC ERR. LIC. VA LIC. ERR. IIATIO -RESOL.' RESULT f

LJOU1 .G BETA. 5.10E-06 2.OOE-07 1.OOE-06 1.OOE-07 0.20 -

2 'd WAST H- .10E-04 6.OOE-06' 4.60E-04 2.20E-05 0.90 8 A !

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SR-09 9.60E-OB 1460E-OB 9.90E-OB- 4.OOE-09 1.03 A

"E SR-90 1.50E-00 4.OOE-09 (5.OOE-09 0.33 3;7 N i

FE-55' 7.40E-06~ 1.OOE-07 1.50E-06 5.OOE-OB O.20 .7 D !

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A= AGREEMENT

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~P-CRITERIA RELAXED

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U.S.. NUCLEAR REGULATORY COMMISSION: .!

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1,0 ' CONFIRMATORY MEASUREMENTS PROGRAM l

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F FOR THE.4TH QUARTER'OF 1989 ,f) r

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i j SIMPLE NUCLIDE NRC VAL.:NRC ERR L2C.VALi 'LIC. ER RAT 10 RESOL; RESULT-IJ LIQUID G BETA 2.37E-05 7.OOE-07' 2.31E-05 4.60E-02 0.97 3 A SPIKE, ' H-3 1.47E-05 .4.OOE-07 1.15E-05: 0.78 .36.B- A

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h- SR-09 6.56E-05 2.OOE-06 2.60E-OS O.40 3 D !

I SR-90: 3.48E-06 1.40E-07 1.27E-06 0.'36 2 D !

[.,> FE-55- 1.36E*05 4.OOE-07 1.69E-05 1.24 3 A- .;

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i TABLE 3 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAN FACILITY PERRY FOR THE 3RD QUARTER 1990 I

SAMPLE NUCLIDE NRC VAL. NRC ER LIC. VAL. LIC.KRR. RATIO RESOL. RESULT -

PRIMARY NA-24 6.49E-03 1.51E-04 5.66E-03 1.43E-04 0.87 4 A OOOLANT CH-51 2.06E-02 5.74E-04 1.7eE-02 5.71E-04 0.86 3 A HCA #2 CO-60 2.21E-04 7.02E-05 1.37E-04 5.75E-05 0.62 A ZN-65 1.61E-03 1.56E-04 1.45E-03 1.33E-04 0.90 1 A- '

ZN-69M 4.01E-04 5.61E-05 3.13E-04 4.72E-05 0.78 A AS-76 1.86E-04 9.74E-05 2.78E-04 4.06E-05 1.49 A NP-239 1.33E-03 1.75E-04 1.15E-03 0.00E+00 0.86 A I-131 3.96E-04 6.46E-05 3.38E-04 4.78E-05 0.85 A I-133 2.83E-03 7.64E-05 2.52E-03 1.08E-04 0.89 3 A I-135 5.87E-03 4.02E-04 5.29E-03 3.27E-04 0.90 1 A -

SR-91 3.33E-03 3.12E-04 2.22E-03 2.45E-04 0.67 1 A MO-99 1.61E-03 3.99E-04 9.60E-04 0.00E+00 0.60 A TE-132 1.76E-04 4.17E-05 1.22E-04 3.52E-05 0.69 A

, 1-132 5.95E-03 1.60E-04 5.19E-03 1.87E-04 0.87 3 A ,

I-134 1.82E-02 1.06E-03 1.52E-02 1.37E-03 0.84 1 A SR-92 5.75E-03 2.23E-04 5.03E-03 2.06E-04 0.87 2 A i BA-139 6.68E-03 1.02E-03 6.60E-03 8.18E-04 0.99 A ,

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CRARCOAL I-131 5.61E-12 3.67E-13 4.68E-12 6.19E-13 0.83 1 A MCA #1 1-133 6.44E-12 8.35E-13 4.89E-12 8.85E-13 0.76 A CHARCOAL I-131 5.61E-12 3.67E-13 5.08E-12 6.05E-13 0.91 1 A HCA #2 I-133 6.44E-12 8.SSE-13 4.31E-12 7.17E-13 0.67 A Cfyd FIL NA-24 5.84E-05 2.50E-06 5.45E-05 5.65E-06 0.93 2 A '

hdA #2 CR-51 4.26E-04 1.04E-05 3.85E-04 2.97E-05 0.90 4 A HN-54 1.81E-05 1.78E-03 2.41E-05 3.80E-06 1.33 1 A CO-58 3.66E-05 2.05E-06 4.22E-05 4.00E-06 1.15 1 A CO-60 4.32E-05 2.06E-06 4.49E-05 4.95E-06 1.04 2 A CU-64 1.45E-03 2.99E-04 8.53E-04 3.35E-04 0.59 A ZN-65 2.18E-04 5.97E-06 2.48E-04 1.27E-05 1.14 3 A ZN-69H 4.36E-05 1.74E-06 4.53E-05 3.50E-06 1.04 2 A NP-239 1.66E-05 1.72E-06 1.67E-05 4.77E-06 1.01 A I-133 1.66E-05 1.37E-06 1.78E-05 3.63E-06 1.07 1 A SR-91 2.71E-04 1.04E-05 3.30E-04 2.06E-05 1.22 2 A RU-105 6.51E-05 7.37E-06 7.01E-05 1.38E-05 1.08 A SB-122 6.94E-06 1.32E-08 6.75E-06 1.52E-06 0.97 A n_._____________a_ - _ _ _ _ __

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SAMPLE NUCLIDE NRC VAL. NRC ER LIC. VA LIC. ER RATIO RESOL. RESULT

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BA-140 9.63E-05 5.38E-06 8.71E-05 1.15E-05 0.90 1 A LA-140 1.44E-05 1.67E-06 1.53E-05 3.30E-06 1.06 A MN-56 1.37E-04 7.01E-06 1.39E-04 3.58E-05 1.01 1 A I-132 3.92E-05 6.17E-06 3.82E-05 1.17E-05 0.97 A SR-92 6.37E-04 1.26E-05 0.67E-04 2.57E-05 1.05 5 A Y-92 1.97E-03 5.18E-05 1.88E-03 8.98E-Ob 0.95 3 A BA-139 2.45E-03 4.69E-05 2.38K-03 1.30E-04 0.97 5 A CRUD FIL NA-24 5.84E-05 2.50E-06 5.84E-05 6.22E-06 1.00 2 A MCA #1 CR-51 4.26E-04 1.04E-Ob 4.41E-04 3.08E-05 1.04 4 A MN-54 1.81E-05 1.78E-06 2.40E-05 4.33K-06 1.33 1 A CO-58 3.66E-05 2.05E-06 3.76E-05 4.54E-06 1.03 1 A CO-60 4.32E-05 2.00E-06 4.90E-05 5.74E-06 1.13 2 A CU-64 1.45E-03 2.99E-04 1.60E-03 6.88E-04 1.10 A ZN-65 2.18E-04 5.97E-06 2.41E-04 1.42E-05 1.11 3 A ZN-69M 4.36E-05 1.74E-06 4.26E-05 4.29E-06 0.98 2 A NP-239 1.66E-05 1.72E-06 1.03E-05 5.31E-06 0.62 A 1-133 1.66E-05 1.37E-06 1.86E-05 4.19E-06 1.12 1 A SR-91 2.71E-04 1.04E-05 3.25E-04 2.40E-05 1.20 2 A RU-105 6.51E-05 7.37E-06 6.24E-05 1.68E-05 0.96 A SB-122 6.94E-06 1.32E-06 7.02E-06 3.22E-06 1.01 A BA-140 9.63E-05 5.38E-06 9.70E-05 1.25E-05 1.01 1 A LA-140 1.44E-05 1.67E-06 1.35E-05 3.68E-06 0.04 A MN-56 1.20E-04 1.89E-05 1.04E-04 4.57E-05 0.87 A I-132 3.92E-05 6.17E-06 4.24E-05 1.40E-05 1.08 A GR-92 6.37E-04 1.26E-05 6.77E-04 2.99E-05 1.06 5 A Y-92 1.97E-03 5.18E-05 1.84E-03 1.04E-04 0.93 3 A BA-139 2.45E-03 4.69E-05 2.35K-03 1.50E-04 0.96 5 A LIQUID CR-51 4.75E-05 1.52E-06 5.44E-05 2.65E-06 1.15 3 A WASTE MN-54 7.32E-07 1.80E-07 9.83E-07 2.54E-07 1.34 A MCA #1 CO-60 2.19E-06 2.32E-07 2.98E-06 3.95E-07 1.36 A ZN-65 3.51E-06 4.15E-07 4.16E-06 6.61E-07 1.19 A AG-110M 6.75E-06 2.72E-07 8.13E-06 4.60E-07 1.20 2 A LA-140 1.89E-06 1.75E-07 1.93E-06 3.10E-07 1.02 1 A SR-92 3.50E-06 3.33E-07 3.61E-06 5.17E-07 1.03 1 A OFFGAS KR-85M 1.22E-02 5.97E-05 1.58E-02 3.73E-04 1.30 20 D ONE KR-87 4.76E-02 3.86E-04 4.88E-02 1.38E-03 1.03 12 A MCA #1 XE-133 1.67E-02 1.35E-04 1.59E-02 3.83E-04 0.95 12 A XE-135 6.0bE-02 1.27E-04 6.01E-02 1.05E-03 0.99 47 A XE-135M 1.80E-01 1.13E-02 1.74E-01 1.07E-02 0.97 1 A KR-88 3.65E-02 2.20E-04 3.85E-02 1.15E-03 1.05 16 A XE-138 4.82E-01 3.23E-02 4.49E-01 6.48E-02 0,93 1 A OFFGAS KR-85M 1.22E-02 5.97E-05 1.57E-02 2.91E-04 1.29 20 D ONE KR-87 4.76E-02 3.86E-04 5.00E-02 1.67E-03 1.05 12 A MCA #2 XE-133 1.67E-02 1.35E-04 1.56E-02 2.95E-04 0.93 12 A XE-135 6.05E-02 1.27E-04 6.04E-02 8.61E-04 1.00 47 A KR-88 3.65E-02 2.20E-04 3.82E-02 7.80E-04 1.05 16 A t

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SAMPLE NUCLIDE NRC VAL. NRC ER LIC. VA LIC. ER RATIO RESOL. RESULT

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OFFGAS KR-85H 1.21E-02 7.48E-05 1.47E-02 3.59E-04 1.21 16 A TWO KR-87 4.65E-02 4.31E-04 4.71E-02 1.40E-03 1.01 10 A HCA #1 XE-133 1.66E-02 1.25E-04 1.51E-02 3.81E-04 0.91 13 A XE-135 5.84E-02 1.27E-04 5.72E-02 9.40E-04 0.98 45 A I OFFGAS KR-85M 1.21E-02 7.48E-05 1.47E-02 4.38E-04 1.21 16 A TWO KR-87 4.65E-02 4.31E-04 4.90E-02 1.44E-03 1.05 10 A HCA #2. XE-133 1.66E-02 1.25E-04 1.54E-02 3.42E-04 0.93 13 A XE-135 5.84E-02 1.27E-04 5.79E-02 8.28E-04 0.99 45 A

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TEST RESULTS A: AGREEMENT '

D: DISAGREEMENT

• CRITERIA RELAXED

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ATTACHMENT 1

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_ CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criterb for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs o;' this program, 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

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by the NRC Reference Laboratory, unless such rounding will result in a narrowed -

category of acceptanc RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement

<3 No Comparison 23 and <4 .5 2,4 and <8 .0

,23 and <16 .67 2,6 1 and <51 0.75 - 1.3 and <200 0.80 - 1.25 2200 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 identii;*d on the data shee :

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