ML20107G469
See also: IR 05000219/1975003
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{{#Wiki_filter:- , ' , , IE I Fora 12 . (Jan 75) (Rev) , 4 U.S. NUCLEAR REGULATORY COMMISSION {{p 0FFICE OF INSPECTION AND ENFORCEMENT C t . D . . , REGION I l[ o ., < 4l IE Inspection Report No: 50-219/75-03 Docket No: 50-219 Licensee Jersey Central Power and Light Co. License No: DPR-16 Madison Avenue at Punch Bowl Road Priority: Morristown, New Jersey 07960 Category: C - Oyster Creek Station (OC) Safeguards Location: vnete,a n a s,,, no,,, tor. y nn7ti Group: Type of Licensee: BWR, 640 Mwe Routine, Announced (Independent $easurements) Type of Inspection: Dates of Inspection: January 20-23, 1975 Dates of Previous Inspection: T.,,,,ory on_?? , 1o 15 - '2[7[7C MG - Reporting Inspectors uti ' Date R. J. Everett, Radiation Specialist Accompanying Inspectors: Date . Date Date Date Other Accompanying Personnel: Dat . . ! '3- 7 D Reviewed By: J. P.- S oht , Stntfor Environmental Scientist ' Date , , 9604230244 960213 PDR FOIA DEKOK95-258 PDR .
. .. - .. _- . _ _ . . -. . . . ' . ., . SUMMARY OF FINDINGS . Enforcement Action Tll: None Licensee Action on Previously Identified Enforcement Action (Independent Measurements) None Other Significant Findings This report summarizcs the licensee's performance on verification test samples. 54% of the verification samples were'in agreement, 6% in possible agreement and 40% in disagreement. (Details, Paragraph 3) Unresolved Items None Status of Previously Reported Unresolved Items (Independent Measurements) A. Licensee action not completely effective in eliminating iodine measurement discrepancy. Item continued. (Details, Paragraph 3) 4 Management Interview A meeting was held on January 23, 1975 in the office of Mr. J. T. Carroll, Site Superintendent, following the inspection at the site. The following individuals were in attendance: Mr. R. J. Everett, Radiation Specialist, IE:I Mr. J. T. Carroll, Site Superintendent, OC Mr. J. R. Pelrine, Chemical Supervisor, OC During the meeting the following items were discussed: A. Iodine Measurements in Gaseous Effluent The licensee stated that the method of calibration of iodine ab- sorbers would be investigated in order to improve agreement with the reference laboratory. (Details, Paragraph 3) - , , - 4 - - - ..
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, , -2- B. Location of Counting Facilities $' The licensee stated that other locations would be investigated that would be more suitable in terms of lower radiation back-
ground. (Details, Paragraph 3) C. Compositing of Liquid Radwaste Samples The licensee stated that split liquid samples would be counted soon after collection in order to prevent loss of activity during storage and steps would be taken to improve the uncertainties in the composite analysis due to storage of solutions. (Details , Paragraph 3) D. Laboratory QA/QC Program The licensee stated that an implementing procedure would be written that would detail the essential elements of their QA/QC Program. The procedure would also detail the licensee's QA efforts in regard to purchased analytical services from outside contractors. (Details, Paragraph 4) r& . 4
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. , 6 . t DETAILS 1.- Persons Contacted 3,) fs5 "9I Mr. J'. T. Carroll, Station Superintendent, OC Mr. E. J. Growney, Technical Engineer, OC Hr. J. R. Pelrine, Chemical Supervisor, 0C. Mr. C. Konta, Chemical Foreman, OC - 2. General < The inspection consisted of a review of the licensee's performance on verification test samples collected by IE:I personnel and analyzed ' by the NRC's reference laboratory, Idaho Health Services Laboratory, (IHSL). These samples' test the licensee's ability to measure radio- , active materials in actual effluent samples. Some test standards ' were also submitted to OC for analysis. Samples taken during the inspection were counted in the IE:I mobile laboratory. The activity of the test standards and IHSL's and IE:I's measurements of effluent samples are referenced to the National Bureau of Standards by laboratory intercomparisons. 3. Results of Verification Test Samples Since:the last Independent Measurements inspection of November 29, 1End 30, 1973, the licensee or his contractor has analyzed 16 sampics y resulting in 54% agreement, 6% possible agreement and 40% disagree- ment.* Samples taken during the inspection will be reported in a supplemental inspection report. The samples tal en during the , inspection and the analyses required are as follows: , Stack filter - gamma isotopic and strontium analysis. a. b. Iodine absorber - isotopic analyses for iodines.
Liquid Radwaste - gross beta, tritium, strontium 89, 90 and c. gamma isotopic analysis. d. Offgas (3 each) - gamma isotopic analysis. ' Reactor water - isotopic analysis for iodines. e. The types of samples collected and analyzed prior to this inspection and the results of measurements were: t
- See Attachment 1 to this report for a description of the griteria'used
to evaluate differences.between analytical results. 6 w
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. ., .F -4- Type of Sample: Radwaste, 1200 hours, 10-30-74 . Acceptable Results in units of microcuries per milliliter , . . d? '
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Radionuclide NRC Measurement . Licensee Measurement '/ Gross beta 7.2i.2E-6 7.7il.0E-6 H-3 7.27 .01E-3 8.0t.03E-3 6.1 .05E-7 (2) SR-89 4.71.3E-7 '.51.05E-8 SR-90 1.01.4E-8 Cr-51 6.5i.9E-6 6.6 .2E-6 Co-60 3.1 .2E-6 1.91.06E-6 (2) Not Acceptable w Ce-141 2.81.3E-6 6.51.04E-7 Mn-54 3.21.2E-6 1.31.03E-6 Fe-59 1.11.2E-6 5.2 .04E-7 Type of Sample: Stack Filter, 0945 hours, 10-27-74 Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement
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I-131 3.2 .3E-4 4.4 .8E-4 Ba-140 1.15 .08E-3 1.4 .3E-3 Not Acceptable Cs-137 8.2 .8E-5 1.5 1.3E-3 Mn-54 5.6 .7E-5 1.2 1.1E-4 Co-60 1.11.1E-4 Not found . Type of Sample: Stack Charcoal, 0945, 10-27-74 ' l Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement 1-131 2.16 .01E-1 2.2 .02E-1 l (2) Possible Agreement ,
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- - . .- -- . - . -. . - . . ! * 1( . . . -5- Type of Sample: Stack Filter, 1105 hours, 12-3-74 . . L Acceptable Results in units of microcuries 'r , - Radionuclide NRC Measurement Licensee Measurement I-131 7.31.3E-3 6.Sil.6E-3 Ba-140 4.91.6E-3 4.0tl.0E-3 Cs-137 1.91.7E-4 4.0 1.5E-4 Co-60 3.81.8E-4 6.312.8E-4 ~ La-140 2.51.2E-3 5.2 1.2E-3 (2) Type of Sample: Offgas, 1014 hours, 10-30-74 Acceptable Results in units of microcuries per milliliter Radionuclide NRC Measurement Licensee Measurement Xe-133 2.5!.5E-2 1.85 .02E-2 Type of Sample: Standard Filter #1, 10-28-74 Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement gggg Sb-125 2.2i.1E-2 2.11.1E-2 Cs-134 3.11.7E-2 2.7 .1E-2 Ag-110M 1.34 .08E-2 1.1!.1E-2 Na-22 .57!.04E-2 .53 .05E-2 Type of Sample: Standard Charcoal, (Ba-133), 1-21-75 ) 3 Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement Ba-133 (H) 2.361.06E-2 1.52.2E-2 (2) l Not Acceptable Ba-133 (Et) 1.18 .04E-2 6.4 .9E-3 l 1 (2) Possible Agreement. - i 1 I
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. , ,- 4 -6- Type of Sample: Liquid Radwaste, 1030 hours, 8-21-74 . , k , fj Acceptable Results in units of microcuries per milliliter , . . ,;.. Radionuclide NRC Measurement Licensee Measurement Gross beta 2.32 .06E-6 1.781.1E-6 H-3 4.491.02E-3 5.2 .1E-3 Not Acceptable 4 Ce-141 1.01.42-6 1.51.1E-7 ' 1- Co-60- 8.31.9E-7 3.11.04E-7 ' Mn-54 5.71.6E-7 7.1!.3E-8 - Type of Sample: Offgas, 1137 hours, 8-21-74 ' ' Acceptabla Results in units of microcuries per milliliter d Radionuclide NRC Measurement Licensee Measurement Xe-133 1.111.08E-2 1.3 .1E-2 . Not Acceptabic Xe-133M 1.021.07E-3 Not reported Xe-135 5.51.7E-2 Not reported Type of Sample: Charcoal Cartridge, 2100 hours, 8-14-74 j i Not Acceptable Results in units of microcuries per milliliter Radionuclide NRC Measurement Licensee Measurement
, 1-131 4.341.03E-1 2.91?E-1 ' Type of Sample: Liquid Radwaste, 1125 hours, 6-7-74 Acceptable Results in units of microcuries per milliliter 4 J Radionuclide NFC Measurement Licensee Mearuremerit Cross Beta '4.61.1E-6 6.0 .5E-6 J SR-89 4.91.9E-8 7.21.9E-8 7 'SR-90 <8XE-9 7.01.7E-9 , . & 0 , .. . . . . - , - __ . _ . . . .
. . . , -7- Not Acceptable r; H-3 1.54 .01E-3 9.2 .2E-4 Cs-137 7.71.9E-7 7.4 .4E-8 Mn-54 2.61.1E-6 8.9 .4E-7 Co-60 4.4 .2E-6 3.4 .2E-7 Type of Sample: Standard Charcoal Cartridge, 1-28-74 Not Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement I-131 1.571.01E-2 1.01.05E-2 Type of Sample: Standard Particulate Filter, 1-28-74 Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement Co-60 1.271.2E-2 1.21.06E-2 Cs-137 6.981.2E-3 6.6 .4E-3 , Ce-144 7.881.1E-2 6.61.4E-2 .
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Not Acceptable SR-89 4.591.2E-4 <7.2X10-5 SR-90 5.951.2E-4 7.11.4E-3 Type of Sampic: Radwaste, 1430 hours, 11-29-73 Acceptable Results in units of microcuries per milliliter Radionuclide IEC Measurement Licensee Measurement Gross Beta 4.01.1E-5 5.2 .3E-5 SR-89 5 1E-8 4.6 .2E-8 SR-90 <2X10-8 5.5!.3E-9 Cr-51 2.2 .4E-5 2.7 ?E-5 Cs-137 2.0 .3E-6 1.41?E-6 Co-60 1.81.01E-5 1.61?E-5 , l
. , -8- i Not Acceptable . H-3 1.941.02E-3 9.8 .5E-4 lE' Ce-141 8.8 .5E-6 Not found 1 Nb-95 2.61.5E-6 " Mn-54 1.3 .1E-5 3.41?E-6 Fe-59 1.9 .6E-6 Not found Type of Sample: Offgas, 1525 hours, 11-29-73 Acceptable Results in units of microcuries per milliliter Radionuclide NRC Measurement Licensee Measurement Xe-133 2.641.02E-2 3.15 ?E-2 Type of Sample: Charcoal Cartrid2e, 1802 hours, 11-21-73 Not Acceptable Results in units of microcuries Radionuclide NRC Measurement Licensee Measurement I-131 1.591.01E-1 9.8 ?E-2 , The inspector noted that the licensee's effluent releases were PMN generally a few percent of their TS limits, and observed that these t analytical discrepancies, in themselves, would not have caused the licensee to exceed any regulatory limit. The inspector noted that recalibration and change over to a new Ge(Li) detector did not bring the licensee into agreement with the reference laboratory on the iodine absorber measurement. The licensee is typically low in his measurement. The licensee stated that the discrepancy was probably due to the calibration method and he would check further with their consultant as to the method used. The licensee stated that a temporary calibration from the inspector's two standard charcoal geometries would be used until the matter could be pursued with their consultant. The inspector noted that the location of the licensee's counting facilities was in a higher than desirable radiation background area, presumably from radwaste storage tanks. The inspector stated that this situation was undesirable in that it could lead to erro- neous reporting. The licensee stated that other locations would be investigated that would eliminate this problem. , f
_ _. _ . _ _ _ _ .-_ -- _ _ . _ _ . _ _ .- . . - } j ~, < . . ' . , . . , -9- - . , The inspector stated that licensee measurements on liquid radwaste were highly variable and not in agreement with the reference . laboratory.- The inspector stated further that the current practice l[gl of two weeks storage and a simple transfer to a counting geometry .i , was inadequate in quantitatively transferring the activity.- The w licensee stated that the liquid test samples would be counted soon after collection without. transfer and the problem in storing com-
posite sampics for long periodswould be investigated. , The licensee stated that they planned to make measurement through- . out the plant to evaluate the amount of-HT or T2 tritium in their effluents relative to tritiated water vapor. The inspector stated that the'results of these evaluations would be reviewed in the next inspection. s-:- ", l The inspector noted the licensee's corrective-action in the following areas.and had no further question. < Evaluate discrepancies in strontium analysis with the contracting l a.
laboratory. i b. Report counting errors on all radiochemical measurements. I Development of a self-absorption correction for certain gross c. beta measurements. M 4. Laborntory QA Program The. licensee described his efforts to control the quality of radio- chemical analyses on site as well as analyses contracted for. The, inspector observed that while these activities were acceptable they were informal in nature and were not documented as a complete and sufficiently detailed program. The licensee stated that a laboratory QA implementing procedure would be prepared which would set down all elements of the QA Program and document a commitment to a ] certain program. I , h - - - - -
.. . . . . . (No. /) J.., 4,, , _ , INSPECTION PIAN ' !, ,. .. , ' (R:gion I Work Fonn) Date l ~ l G ~'15
GT' b ' ' To : (Senior) j N Ytt 6ttfb ~ A on / du 3043 N7i Re : INSPECTION PLAN, i " -(I%cility or License #) (Dates) [h[.h The following areas / items are to be examined during the subject inspection: 1. Outstanding Items: (Reference #s from outstanding items list, or briefly Q - l . 9(% Q L. )
I , ' l .. ..J 2 The areas / items checked on the attached enclosure. ' 3. Additional areas / items: hGdi lMu W1Ltuu *w.4/' haaLJ Le v Dd $(Lb &$ YLG hMh
9 V N - .. ! 4. The following inspectors will assist: Inspector Area / Items /{})d 5 &L'$ a. $, k.4 1 ' b, c. . /^ IPc I Sa# ^ (Senior) V (Principal Inspector) e , '
Enclosure: Standard Insp. Areas .,
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ra WASTE MANAGEMENT SYSTEMS - TI 3300 (OPERATIONAL) - Once per year . 4 Insp. Rpt. No. So -Zif [7f-0 3 Date (s) "1 ~ 2043,(% Insp. Rpt. No. _Date (s)" Insp..Rpt. No. Date (s) Insp. Rpt. No.
- Date (s)
s ' ,' INSPECTION ITEMS Follow-up Completed Required Insp. Rpt. No. ' Analytical Capabilities - Items 4.g(1) - (2) [/3 _(1). Review of the results of the internal QA/QC Program for analytical measure- . ments MKd (2) Conduct Verification test of Lab gs capability &Lu R\\-QG cm 01L
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, lifdMtui8LC yg$ ens tuin Si;:$ 9 )A u<>h)L wy jeue!,s k At .a 1 Approved /c2d LS6nfor) (Reporting Inspector) $ l .,,j' , -(i. , . , , _ _ - - - - . . - - - }}