IR 05000528/1986003
| ML17299B037 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/05/1986 |
| From: | Hamada G, Johari Moore, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17299B036 | List: |
| References | |
| 50-528-86-03, 50-528-86-3, 50-529-86-03, 50-529-86-3, NUDOCS 8602250106 | |
| Download: ML17299B037 (10) | |
Text
8~O2250Xog 86Oao7 ADOCK 05000528 paR U. S.
NUCLEAR REGULATORY COMMISSION REGION V'eport Nos. 50-528/86-03, 50-529/86-03 Docket Nos. 50-528, 50-529 License Nos. NPF-41, NPF-46 m
J Licensee:
Arizona Nuclear Power Project P. 0. Box 52034 Phoenix, Arizona 85072-2034 Facility Name: Palo Verde No.
1 and No.'2
'nspection at:
Wintersburg, Arizona Inspection conducted:
January 13-17, 1986 Inspectors:
J.
Moo e Radiatio S ecialist D te Signed G.
Ham a
Radiati n aboratory Specialist D te Signed By:
. Yuh s, hief Facilit Radiological Protection Section Da e igned
~Summau Ins ection of Januar 13-17, 1986 (Re ort Nos. 50-528/86-03, 50-529/86-03)
Areas Ins ected:
This was an announced inspection of Unit 1 chemistry laboratory capability to accurately measure radioactivity in various routine sample media.
The inspection involved split sample measurements with the NRC Mobile Laboratory.
A review of Unit 2 chemistry status was also performed.
A total of 70 man hours were expended on module 84725 by two inspectors and
man hours on module 79701.
Modules 70701 and 84725 are now closed.
Results:
No items of noncompliance were identified in the areas inspecte tr~,
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- J. B. Cederquist, Manager, Chemical Services
- R. D. Goodwin, Unit 1, Chemistry Lead
- S. G. Penick, Quality and Monitoring Supervisor
- C. N. Russo, Manager, Quality Audits and Monitoring
- T. Warren, Unit 1, Chemistry Supervisor u
- Indicates personnel present at exit interview.
2. Discussion i, Split sample comparisons were performed where feasibl'e. 'or those cases where splitting was not practicable, e.g'. charcoal cartridge or filter", paper samples, the same sample was meas'ured by both parties. This was permitted because similar standards were used by both parties for calibrating these geometries. Another aspect of this inspection involved measurement of a liquid sample from the evaporation pond'nd a sample from the chemical waste neutralizer tank which discharges to the evaporation pond. Inputs to the evaporation pond for concentrations exceeding 5 E-7 microcuries per milliliterare prohibited. The chemical waste neutralizer tank sample showed no measurable activity for a two hour count. The lower limit of detection (LLD) for.Cs-137 for the NRC measurement was 2 E-8 microcuries per ml. The evaporation pond sample (1 liter) was counted overnight (16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />), and for this counting condition, the LLD for Cs-137 was 1 E-12 microcuries per ml. A trace (3 E-8 microcuries per ml) of 60 day Sb-124 was detected in this sample. Results of measurement verification comparisons for the sample categories tested are summarized below. Table (Unit 1 Containment) Nuclide PV Unit NRC Ratio uCi/cc uCi/cc PV/NRC
- Agreement
~Rau e I-131 4.11 E-11 4.15 E-11 0.99 0.60-1.66
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'I 4 'id 7 r l s lr f74'rr 'm b ) <<d' IH ~ ~ <<' r.(. 4 'I f'1 "f,"'H'I' 7, "' lE;HW rr" d>d, 'I ,Ijdr dw rr'rd'~ I 4 m W dr ~ l 'wr Ii, Vl 4 I I I 7 Hsfi '" 4 'r 7 m> ~. . Il WI I 5t>I 7 ,',). I '"Sr '5r"",'(r r r << y, l1HI Hfi Jd" g ~<<g-rv) r 47 I'5 Imy m "4 fi > firpry I I Wd'. 4sf'rp', ~ 4 H t \\ to the liquid fraction from which the gases had been stripped), and measure only the nongaseous activity to'hich the gas activity is subsequently added, a 'high gas,efficiency is assumed: A stripping efficiency of at least 95K is'required with such a procedure. An alternate procedure would be to measure the total activity in the 'tripped liquid, gaseous as well as nongaseous activity, to which the separately measured gas activity is added. Even with this procedure, however, biases can occur from buildup of Xenon activity from their Iodine precursors if there is significant delay (many hours) between sampling and measurement. To test stripping efficiency, subsamples of stripped gas and stripped liquid were measured soon after separation of the two phases from fresh reactor coolant. Based on NRC data, the gas stripping efficiency was 97.6 percent for this particular exercise. It can be concluded that the gas stripping procedure as it is currently being implemented is adequate to provide the required accuracy for quantifying reactor coolant activity. Activities associated with trace chemical analyses in primary and secondary side systems were also reviewed. Procedures and practices were found to be adequate. Because the activities of Unit 2 chemistry have not changed significantly since the inspection of October 21-25, 1985, only a cursory review of current status was conducted during this period. The primary multi channel analyzer system has not been brought on line as yet. Unit 2 chemistry continues to rely on the Nuclear Data (ND) multichannel analyzer system which is considered to be a complementary system. The ND system is more than adequate to handle gamma spectroscopy needs. 3. Exit Interview Inspection findings were discussed with licensee personnel indicated in paragraph 1. Management personnel were informed of the agreement achieved for the split sample tests conducte ~ r 4j 4) J ' r' ~ ~ <<b J ~ 'r'" sk 1 (J * )rr~" " g'1, ' 41 b f'l<<, ~ ) 4;r;1 f Jb.rgrr jt )~ r. 4t" Q I )Jrb" b JJ ~ rrl,<<@r <<JJ.V, b 4, <<j(4 1 f-I ~ + J('p ".b f)rb (<<' 4, 4, I << r. 1 ( lilt] ( << <<JJ" ') ftfr r, ~" 4. ' I 4<< IJ ~ 4) t 1J bpJ9',r 4(r I1<< ftl "1 t) <<J )f j 4. Jr fib' J >> I t(J I '- t ig ) b, rtl 4( y 41, ( I ,r ( (rf J<<1 V<<," 4<<V g(( I)' I'4 I f )jrr~> V"> N 1 '1 J~b. I I <<J)bJ(b b.'; (. (,lS.)Il t-rb.<<( I',() b ~ fJ<<I, -Ijf 4 >>, , r ),, ~" <<414,(= I ~ ~, >> bbr<< II lt J(I Vr "'J(J ,.') f 'J,l <<Jv') <<r ~ IV)" ' ( f'<<J b 1( 1I JJb',fr)I I II J t I 1 fv lf ,$ 4 I r"'I(I rb<<I' ( 'l ffIj 4 <<I', 'a rJ+J I I J rtrr I Jjl 1 <<J I,, 1 '4 ~ b<<' I,lf fv) I b I 'l' t ~ r(b<<b 1)4 .' )f.. J(J ~, 4 r<<tv 'it 1( g( ~ Vb') . I' Enclosuie Criteria for Acce tin the Licensee's Measurements Resolution Ratio <4 - 8 - 16 - 51 - 200 200 0.4 0.5 0.6 0.75 0.80 0.85 2.5 '.0 1.66 1.33 1.25 1.18 Com arison 1 ~ Divide each NRC result by its associated uncertainty to obtain the resolution. (Note: For purposes of this procedure, the uncertainty is defined as the relative standard deviation, one sigma, of the NRC result as calculated from counting statistics.) 2. Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result/NRC). 3. The licensee's measurement is in agreement if the value of the ratio falls within the limits shown 'in the preceding table for the corresponding resolutio b k P