IR 05000424/1987064: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML20237A304
| number = ML20148H725
| issue date = 12/03/1987
| issue date = 03/10/1988
| title = Insp Rept 50-424/87-64 on 871116-20.Violation Noted.Major Areas Inspected:Qa & Confirmatory Measurements for in-plant Radiochemical Analysis & Previously Identified Inspector Followup Items
| title = Ack Receipt of 880212 Submittal of Analytical Results of Spiked Liquid Samples,Per Insp Rept 50-424/87-64.Comparison of Results to Known Values & Acceptance Criteria of Comparisons Encl.All Comparative Results in Agreement
| author name = Adamovitz S, Gloersen W, Kahle J
| author name = Collins D
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =  
| addressee name = Head G
| addressee affiliation =  
| addressee affiliation = GEORGIA POWER CO.
| docket = 05000424
| docket = 05000424
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-424-87-64, NUDOCS 8712140392
| document report number = NUDOCS 8803300070
| package number = ML20237A273
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
| page count = 15
}}
}}


Line 19: Line 18:


=Text=
=Text=
{{#Wiki_filter:- _ _ _ _ _ _ _
{{#Wiki_filter:P '
pRtopg . UNITED STATES
.
  *
  ,
Do NUCLEAR REGULATORY COMMISSION
      $flL&W MAR 101988 Georgia Power Company ATTN: V.r. George F. Head Senior Vice Dresident-Nuclear Operations P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
  / "',#
SUBJECT: DOCKET NO. 50-424, CONFIRMATORY MEASUREMENT RESULTS, SUPPLEMENT TO INSPECTION REPORT N0. 50-424/87-64 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on November 5, 1987, to your Vogtle facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated February 12, 1988, and subsequent to verification of your values as per our conversation by telephone on fiarch 1, 1988, the following comparison of your results to the known values are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by your cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facilit These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection
8$-  REGION li h ()
  *
  , ! C 101 MARIETTA STREET, ATLANTA, GEORGIA 30323
  %, *****J /
DEC 0 81987 Report No.: 50-424/87-64 Licensee: Georgia Power Company   -
P. O. Box 4545     l Atlanta, GA 30302   {
i Docket No.: 50-424   License No. : NPF-68 l I
Facility Name: Vogtle    l
 
Inspection Conducted: November 16-20, 1987
        ]
Inspector: [//. s 7 "
    /14s  /#N/57 f B. Gloe'rse '    Cat:e Signed d/'l5*. "5'l.~ Ab/ M hA v i t z "'' " " ' /S, Y amo  'Date Signed Accompanying Personnel: C. A. Hughey Approved by:  L[.,k  / L/3/77
  '.
J B/ Kahle, Section Chief  Date Signed D sion of Radiation Safety and Safeguards SUMMARY-Scope: This routine, announced inspection was conducted in the areas of quality assurance and confirmatory measurements for in plant radiochemical analysis and previously identified inspector followup item Results: One violation was identified - failure to perform surveys for in plant noble gas concentration calculation PDR ADOCK 05000424 G  PDR


k
Sincerely, Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards Enclosures:
 
1. Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encis: (See page 2)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ ____
8803300070 880310 PDR ADOCK 05000424 0  PDR
  -
      .C Ec F ,, .
  .
Georgia Power Company- 2 cq w/encis:
REPORT DETAILS Persons Contacted Licensee Employees
'
  * M. Bellamy, Plant Manager
9'. D. Rice, Vice President, Project
  *A. L. Mosbaugh, Assistant Plant Support Manager
' Director p W. Hayes, Vogtle Quality-Assurance Manager (G( Bockhold, Jr. , General Mar.ager, Nuclear Operations M Gucwa, Manager, Nuclear Safety and Licensing g A. Bailey, Project Licensing Manager g W. Churchill, Esq., Shaw, fittman, Potts and Trowbridge W. Kirkland, III, Counsel, Office of the Consumer's Utility Council (p'. Feig, Georgians Against Nuclear Energy bSc w/encis:
  * F. Kitchens, Operations Manager
LE.f Reis, 0GC W. Hopkins, NRR M. Sinkule, RII D y Technical Assistant WC Resident Inspector Dv.:ument Control Desk
  *T. Greene, Plant Support Manager
"State of Georgia RII  RII RII ,y
  *J. E. Swartzwelder, Manager-NSAC
    >kV J oorsen f abl(e kule MSip/88 3/f/88  3/7/88 3/4 ll
  * R. Frederick, QA Site Manager-Operations
  * F. Hallman, Chemistry Superintendent
  *A. E. Desrosiers, Health Physics Superintendent
  *I. Kochery, Health Physics Superintendent ( Acting)
  *R. M. Odom, Engineering Supervisor
  * L. Cross, Senior Regulatory Specialist
  *J. R. Petro, Senior Quality Assurance Field Representative
  *R. Hand, Plant Chemist S. Ewald, Manager, Health Physics and Chemistry A. Stalker, Health Physicist (Corporate)
S. Sundaram, Senior Plant Chemist
,
J. B. Sills, Lab Supervisor l  J. A. Carswell, Health Physics Foreman J. L. Willcox, Senior Quality Assurance Field Representative S. McCann, Consultant R. Cislo, Consultant Other licensee employees contacted included engineers, technicians, and office personne NRC Resident Inspectors
  *H. L. Livermore
  *J. F. Rogge
  *C. W. Burger
  * Attended exit interview Exit Interview
'
          !
l The inspection scope and findings were summarized on November 20, 1987, with those persons indicated in Paragraph 1 abov One violation (Paragraph 4) concerning the failure to perform adequate surveys for airborne radioactive material in areas within the plant was discusse The inspectors also discussed areas for improvement in the Health Physics and Chemistry laboratory quality assurance p r.og ram s . No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspection.
 
I f
!
!
_ _ _ _ _ _ _
_ - . _ _ _ - - _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ - _
,
*
.
3. Quality Assurance Program (84725) Radiochemistry Laboratory The inspectors toured the radiological sample preparation and counting laboratories to examine the equipment that was used for radiological sample counting activities. Analytical equipment in the radiochemistry count room included one Nuclear Data Series 76 stand-alone multichannel analyzer, one Nuclear Data Series 76 terminal and four intrinsic germanium detectors with two detectors having nominal efficiencies of 10?s, a third detector with a nominal efficiency of 20?; and a fourth detector with an efficiency of approximately Si Date processing and management for the gamma spectroscopy system was accomplished by a Microvax 11 central processing unit. This system also had a backup Microvax. Additional analytical equipment included a Beckman LS3801 liquid scintillation counte The inspectors reviewed the licensee's quality assurance program for the radiochemical counting laboratory. The guidance contained in Regulatory Guide 4.15 (Quality Assurance for Radiological Monitoring Program (Normal Operations) - Effluent Streams and the Environment, February 1979) was used to evaluate the licensee's program. The inspectors noted an overall improvement in the area of quality assurance since the last inspection (50-424/86-119). At the time of this inspection, the Chemistry and Health Physics groups had undergone a reorganization so that the two groups had formed one Department. The Chemistry and Health Physics Department was divided into three sections: Health Physics, Chemistry, and Support Service The inspectors were informed that approximately ten chemistry specialists were qualified to operate the counting equipmen The inspectors verified that written procedures were reviewed and approved for activities involved in in plant radiochemical analyses according to administrative control instruction The inspectors reviewed selected procedures for sample collection, sample logging, sample preparation and analysis and operation and calibration of radiological analytical eq ui pme nt . The inspectors noted that the licensee had incorporated some of the comments made during inspection 50-424/86-119 into Procedures 3300-C, Preparation of Liquid Samples for Radiochemical Analysis, Rev. 4, October 20, 1987, and 33015-C, Obtaining Ventilation and Gaseous Samples for Radioactivity Analysis, Rev. 4, October 26, 198 Laboratory quality control included the use of NBS traceable reference standards to determine counting efficiencies for specific radionuclides and to determine the counting efficiency as a function of gamma ray energy for the gamma spectroscopy systems. The inspectors observed that efficiency determinations for all four detectors were made for a variety of geometries at various shelf l
l
        . . _ _ _ _ _ _ _ _ _ _ _ _ _ _


_ _ _ _ _ _
    .~  -_
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _
        . . _ _ .
l
        ..*
   *
          ."
  .
ENCLOSURE 1 Conri rmatory Measurement Compa ri sons of' H-3, Fe-55, and Sr-90 Ana lyses for Vogtle Nuclear Plant, November 5, 1987 Licensee  NRC   tio Isotope  Lupi/mi ) (uCi/mi1 Hesolut193  LLi',ensee/NRC) Compa ri son H-3  2.1 E-5 2.0310.084 E-5 52  1.01 Ag reement Fe-55  1.3 E-5 1.27 1 0.03 E-5 f2 4  1.02 Ag reement
$r-90  2.2 E-6 2.57 i O.10 E-6 26  0.86 Ag reement NOTE: Due to the extended decay time for the isotope Sr-89, the analytical resu l ts we re no t compa re *
v
        .
          .
          -


heights. The following efficiency data records were reviewed l  (calibrations were performed during November 1986):
p- -
l Detector 1 (SN 1731) - 10cc gas vial shelf 1; 1 liter bottle; 1 liter liquid Marinelli; 4 liter gas marinelli; 4 liter liquid Marinelli; charcoal cartridge shelves 0,1, 2, 3; particulate filter shelves 0, 1, 2, 3; reactor coolant and scintillation vial shelves 0, 1, 2, 3; 125cc gas container shelf Detector 2 (SN 1759) - 1 liter bottle; 1 liter liquid Marinelli; charcoal cartridge shelf 0; particulate filter shelf 0; reactor coolant scintillation vial shelf Detectors 3 (SN ''37) and 4 (SN 1755) - 10cc gas vial shelves 1 and 2; 1 liter oottle; 1 liter liquid Marinelli; 4 liter gas Marinelli; charcoal cartridge shelves 0,1, 2, 3; particulate filter shelves 0,1, 2, 3; reactor coolant scintillation vial shelves 0, 1, 2, 3; 125cc gas container shelves 0, 1, The inspectors reviewed the 1987 daily performance checks for the gamma spectroscopy system The licensee graphically tracked the detector efficiencies and resolutions for three radionuclides (Co-57, Co-60, and Cs-137) on all four detectors. The baseline and the t 2 sigma, 3 sigma control limits were determined at the time the detectors were calibrate It was noted, however, that the daily QA/QC data was plotted on control charts with time durations of one month. The inspectors discussed with the licensee the advantages of plotting the daily QA/QC data on control charts with time spans covering at least six month The licensee monitored daily performance checks to ensure that the measured values were within specified control limits. Corrective actions and measurements outside the specified control limits were documented in equipment logbook Although, the inspectors observed that copies of the calibration source certificates should be kept in the laboratory, all other records were generally well organized and easily accessibl Last year, the licensee had participated in a cross-check program with a vendor who supplied the licensee with unknown spikes periodicall During this inspection, it was apparent that the cross-check program was not given as much attention. The inspectors discussed ways to improve the cross-check program by participating, perhaps on a quarterly basis but only using one or two different geometries per quarte The licensee indicated that plans were developed to have a cross-check program with Plant Hatch, b. Health Physics Laboratory The inspectors toured the Health Physics counting laboratory to examine the equipment that was used mainly for in plant radiological sample counting activities. The inspectors were informed that the Health Physics gamma spectroscopy system could be used as a backup to the Chemistry laboratory in the event that the Chemistry lab would be
          :
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _      l
 
_ _ _ _ _ _ _ _ .
  *
  .
,
l
!    4 l-inaccessible due to radiological concerns. Analytical equipment in
;  the counting room included two intrinsic germanium detectors and Nuclear Data Series 76 processing equipment, two NMC proportional counters (Model PCC 11T) which were not operational, one Eberline SAC-4 for alpha counting, and an Eberline HP-210 shielded pancake prob The inspectors reviewed the licensee's quality assurance program using the guidance contained in Regulatory Guide 4.1 The inspectors and licensee representatives discussed 'various areas for improvement of the quality assurance program and the following list summarizes the discussion:
Assignment of a lab manager or supervisor to the count room to monitor the day-to-day operation Consideration of the participation in a cross-check program for gamma spectroscopy measurement Participation of lab technicians in a gamma spectroscopy classroom training progra Trending of daily QA/QC data on graph Establishment of control limits ( 2, 3 sigma) associated with gamma spectroscopy system performance at each calibration cycle (typically annually).
 
Daily tracking of the resolution of at least two well-defined photopeaks in addition to tracking photopeak activitie Keeping copies of QA/QC trend data for the current calibration cycle in the lab, preferably in notebook Use serial numbers for identification of the two gamma detector Keep copies of source certificates in the la Establish a communication link between the Health Physics group and the Chemistry group, especially for technical assistanc The licensee agreed to consider the items listed abov The inspectors also reviewed selected Health Physics related counting room procedure It was noted that in 43813-C, Reliability Checks for Nuclear Data Gamma Spectroscopy System, Rev. 6, April 30, 1987, Step 4.3.5.2 for evaluating the energy difference between the known and measured values, the licensee should consider using a tolerance
_ _______-______-_______j
 
- _ - - --
  *
  *
.
       ,
 
5 of 0.5 kev instead of i 1 kev. Additionally, the check source that is used for the daily QA/QC checks should be changed at each calibration cycl No violations or deviations were identifie . Confirmatory Measurements (84725)
l During this inspection, samples of reactor coolant, containment l atmosphere, and liquid and gaseous waste monitor tanks were collected and i the resultant sample matrices were analyzed for radionuclides l concentrations using the gamma-ray spectroscopy systems of the licensee's l
counting laboratories and the NRC Region II mobile laboratory. The l
purpose of these comparative measurements was 'o verify the licensee's
! capability to measure quantities of radionuclides accurately in the various plant systems. Analyses were conducted using the licensee's six gamma spectroscopy systems (four detectors located in the chemistry count room and two detectors located in the health physics count room). Sample types and counting geometries included: (1) containment atmosphere -
l charcoal cartridge; (2) reactor coolant system (RCS) dissolved gas - 10 cc l vial; (3) degassed reactor coolant - 20 cc vial; (4) liquid waste monitor tank - one liter Marinelli; (5) waste gas decay tank - 125 cc gas I container and one liter gaseous Marinelli. A spiked charcoal cartridge and particulate filter were provided for analysis in addition to the licensee sample A comparison of licensee and NRC results is listed in Attachment 1, Table 1 with the NRC acceptance criteria listed in Attachment 2. For the spiked particulate filter, Americium-241 was not detected by the Health Physics Detectors 1 (PGT 1851) and 2 (PGT 1768). Discussions with count room personnel indicated that these two detectors were not calibrated for energies below 80 kev and therefore could not identify the 59.5 kev gamma for Am-24 Initial analysis of the containment atmosphere charcoal cartridge by the four Chemistry detectors did not identify the isotope Br-8 Licensee personnel indicated this isotope was not in the computer's isctopic identification, librar The library was modified to include the isotope and subsequent re-analysis of the spectrums identified Br-8 A dissolved gas sample from the reactor coolant was analyzed by three detectors in the Chemistry count roo Detectors 1 (PGT 1731) and 3 (PGT 1737) showed agreement for all isotope However, Detector 4 (PGT 1755) did not identify Ar-41 or Kr-87. It was noted that Detector 4 (PGT 1755) was the least efficient of the four Chemistry detectors (5?;
efficiency as compared to 10'. to 20?J for the other detectors) but also that this detector was the primary system for counting reactor coolant liquid and gaseous samples. The inspectors discussed with count room personnel the advantages of extending sample count times or utilizing a more efficient detector for analyzing RCS dissolved ga A degassed i
reactor coolant sample was counted on the four Chemistry detectors and
'
showed agreement for Detectors 1 (pGT 1731) and 4 (PGT 1755). The isotope I-132 was not detected on Detector 3 (PGT 1737) and I-132 activities were in disagreement for Detector 2 (PGT 1759). However, as noted above, Detector 4 (PGT 1755) was the primary system for analyzing reactor coolant
 
    . _ _ _ -_ _ __ _ - - -
.
 
samples and all isotopic values were in agreement for Detector A liquid waste monitor tank sample was analyzed by the Chemistry and Health Physics count room Results from the Health Physics Detectors 1 (PGT 1851) and 2 (PGT 1768) were biased low and generally in disagreement with values ranging from 36?; to 61?; below the NRC results. A waste gas decay tank was also sampled and counted using two different geometries; i.e., a 125 cc gas container and a gaseous Marinell For the gaseous Marinelli geometry results from the Health Physics Detectors 1 and 2 were biased high (33?J to 55?4 above NRC values) and in disagreement for Xe-133 and Xe-135. Discussions with Health Physics count room personnel indicated an erroneous volume of 1100 cc had been deter.nined for the gaseous Marinelli when the actual volume was approximately 1250 c However, when factoring out the error due to using the wrong container volume, the licensee results would still be biased high by 17?; to 37?; and in disagreement for Xe-133. The incorrect volume had been used for approximately one year to determine noble gas concentrations in restricted areas within the plan The inspectors indicated to licensee representatives that the use of the incorrect volume for the gaseous Marinelli was an apparent violation of 10 CFR 20.201(b) and 10 CFR 20.103(a)(3) (50-424/87-64-01). 10 CFR 20.201(b) requires each licensee to make or cause to be made such surveys as (1) are necessary for the licensee to comply with the regulations in this part and (2) are reasonable under the circumstances to evaluate the extent of radiation hazards that may be presen CFR 20.103(a)(3) requires for the purposes of compliance with the requirements of this section, that the licensee use measurements of concentrations of radioactive materials in air for determining and evaluating airborne radioactivity in restricted area One violation was identified - failure to make adequate survey . Process and Effluent Radiation Monitoring and Sampling System (84723)
The inspectors and licensee representatives discussed the spurious alarm problems with the Process and Effluent Radiation Monitoring and Sampling System (PERMSS). Chemistry Department personnel indicated that high level management attention had been given to resolve the apparent computer problems with the system vendo The inspectors discussed the need to strive for an early resolution and indicated that this area will be reviewed during subsequent inspection No violations or deviations were identifie . Licensee Action on Previously Identified Inspector Followup Items (92701)
  (Closed) 50-424/86-119-05: Review gamma-ray spectroscopy  system calibrations for various geometries at different shelf heights and efficiency determinations for gas geometries greater than 500 ke The inspectors reviewed the licensee's efficiency determination records which were completed in November-December 1986. The various geometries used for the four intrinsic germanium detectors are listed in Paragraph The
_ _________
 
_ ___-___ _ _
-
.
 
i inspectors noted that the licensee had purchased gas calibration (mixed gamma) sources in which each geometry had been filled with styrofo'am spheres. These sources were going to be used during the next calibration cycle. During- the last calibration cycle, the licensee prepared the gas geometries using a material that approximated the density of ai This item is considered close (Closed) 50-424/86-119-06: Review results of the spiked simulated liquid radwaste sample containing Fe-55, H-3, Sr-89, and Sr-90. The comparison  !
between the licensee and known results can be seen in Attachment 1, Table 2. The licensee was in disagreement for Fe-5 This disagreement was discussed with licensee representative The licensee agreed to address this matte This item is considered close ;
I
______________-_Q
 
o ttt ttt ttt ttt tat tat  ttttttt ttttttt s nnn nnn nnn nnn npn npn    nnnnnnn nnnnnnn i
eee eee eee eee eme eme    eeeeeee eeeeeee r mmm mmm mmm mmm mom mom    mmmmmmm mmmmmmm a eee eee eee eee eCe eCe    eeeeeee eeeeeee p eee rrr eee rrr eee rrr eee e rrr e e e rtr rtr eeeeeee eeeesee rrrrrrr rrrrrrr m
o ggg ggg ggg ggg gog gog  ggggggg ggggggg C  AAA AAA AAA AAA ANA ANA    AAAAAAA AAAAAAA
          '
C R
N        -
o/  824 857 034 1 656 2 2  4 9 7222557 6053336 ie  999 909 099 999 9 9 9 8    9909999 9909999 te as  000 01 0 1 00 000 00 00  001 0000 0010000 Rn e
ic L
n i
o t
u 3l s 342 4 3484 344 344 344  601 704 1601704 5fif4 l      1 51 f4 1 f
o  1 51 41 541  541 541  7547243 7547243 s  1 1 1 1 1 1 13 2 2 13  2 2 e
R R O
F N
O I7 T8  332 332 332 332 332 332  2O33231 2O33231 A9  - - - - - - - - - - - - - - - - - -  - - - - - - - - - - - -
U1  EEE EEE EEE EEE EEE EEE  EEEEEEE EEEEEEE  V L          e A ,        5 5 5 5 k V0  301 301 301 301 301 301  5089100 50891 00 E2  10  0    001 0020 N6
-
C
 
  . .
 
    . 0 1 1
    .
1 1
      .
0 1
      .0 1 1 1
        . 0  001 0020 .  .
 
8 000 000 000 000 000 000    000U000 0000000 O1 R          w 1 S nN  i iii i 11 i1i 1i1  1i1iiit 1 i i1i o I R o          l T 1 RE i 584 584 588 4 58l e 584 582  4898797  4 898797  e N
E AB t  931 931 931 93l 931 930  5723201 15723201  b E PM a  ..  ..  . .
64 .  .  .  .  . t I
P L ME r  641 6'41 641  641 6141  8176281 817628I  s
 
1 B OV t          e C A CO n          i A T N e          g T E c    d d    r T LE n      e e    e A PL o      t t    n MT C      c c    e AG e 332 332 332 332 3e2 3e2  2O33231 2O33231 SO e - - - - - - - - - - - - t - t - - - - - - - - - - - - - t V s EEE EEE EEE EEE EeE EeE  EEEEEEE EEEEEEE  c E  n    d d    e ET e 317 4 01 477 470 0 5 4 2 7436582 4 6095253  t SN c 800 f861 900 611 t0 f5.ot 0  2648161 1 669151  e NA i  .  . . o    .  . . d EL L 641 6f 41 641 641 6N1 6N1  8175271 81 75271 CP      ) )
o 1 1    t IL      ( (
-          d C          e R          t N          a r
e          b p  17 17 17 17 17 17  939 7 939 7 i o 043 043 043 043 0f 43 0f 4 3 00137 3 00137  3 l t 621 621 621 621 621 621  61 1 1581 61 11 581  a o - - - - - - - - - - - - - - - - -  - - - - 8 - - - - - - 8 - c s oms oms oms oms oms oms    odneo s odneo  s i
CAC CAC CAC CAC CAC CAC    CCSCCYC CCSCCYC  t o
n e
r e    a g
d    s i    r r    o t    t r    c e      a    e
.
_
1 2
_  t9      C    t a1    r r    e
.
l 0 1 2 3 84 o o l 1  2  d u-    t t a cS 1 r 9r 7 r 5r 1 c 8c o 1 r  9r  s
_
iM 3o 5o 3o 5o 3e 6e c r
3o  5o  c t - 7t 7t 7t 7t 6t 7 t  7t  7t  i rC 1 c 1 c 1 c 1 c 1 e 1 e a3 1 c  1 c  s
_  aR e e e e D D h0 e  e  y PN Tt Tt T t I t i T C0 T t  T t  h Ce Ge Ge Gn GP GP  - Ge  Ge  P dr PD PD PD Pu PH PH dC PD  PD ee      eC    h
-
_
_
l iI
  -
pi t
  . .  .  .
l iC
        <
pR
        -
        .  .
l t
_
_  e SI a b d f SN a  b  l
_
-
lp          l
_
            )
m_
a
-
  .      . 1 S 1      2    (
-
-
-
-
 
I)lii  )ji  i!
_
_
_
  .
  ,
n o ttttttt  ttttttt  ttttttt ttttttt  tt tt tt tt tt tt s nnnnnnn nnnnnnn nnnnnnn nnnnnnn    nn rn nn nn nn nn
          :
eeeeeee eeeeeee eeeeeee eeeeeee    ee ee ee ee ee ee ir mmmmmmm mmmmmmm mmmmmmm mmmmmmm    mm mm mm mm mm mm ee ee ee ee ee ee a eeeeeee eeeeeee eeeeeee eeeeeee    ee eerreerree eeeeeee eeeeeee  eeeeeee eeeeeee    rr ee rr ee p
m rrrrrrr  rrrrrrr rrrrrrr  rrrrrrr  rr rr o ggggggg ggggggg ggggggg    ggggggg  gg gg gg  gg gg gg C AAAAAAA AAAAAAA AAAAAAA AAAAAAA    AA AA AA AA AA AA
_
C
_
R N
_
_
o/ 8315237  2566981  9872625 8832713  54 52 95  43 05 00 e
_
i 9909999 0909990 9909999 9909999    98 98 98 09 00 00 t e a s 0010000  1010001  0010000 0010000  00 00 00  10 11 11 R n e
ic L
n io t
u l
1601704  1601704  1601704 1601704  22 22 22 22 22 22 o 7547243  7547243  7547243 7547243  26 26 26 26 26 26 s 13 2 2 1 3 2 2 13 2 2 13 2 2 e
R 32 32 32 32 32 32 2O33231  2O33231  2O33231 2o33231  11 11 11 11 11 11
  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
EEEEEEE EEEEEEE EEEEEEE    EEEEEEE  EE EE EE EE EE EE 5 5 5 5 5 5 5 5
_ )  50891 00 5089100 5089100    5089100  29 29 29 29 29 29
_
d  0010020  001 0020 0010020  0010020  20 20 20 20 20 20
  .  .  .
_ 't  C 0000000 0000000 0000000 0000000    00 00 00 00 00 00
_
n  R o n N_ 11iiit  1111  1i 11i11 i 11i1iii  1t 1i 1 11 i1 1t
_ c o 37 37 37 37  37 i 1 i 4898797  f
 
898797 4898797  f4898797    31 t 5723201  5723201  5723201 5723201  85 85 85 85 85 85 1 E a  .  .  .  .
L r 8176281  8176281  8176281 8176281  45 45 45 45 45 45 T B t I
T A n E T e
_
M  c H  n
_
C  o A C        32 32 32 32 32 32 T  e 2O33231  2O33231  2O33231 2O33231  11 11 11 11 11 11 T  e - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
A  s EEEEEEE  EEEEEEE EEEEEEE  EEEEEEE  EE EE EE EE EE EE
.
n
_  e 5588904  7930498  7434941 8444199  38 99 05 48 45  17
-
3630051  6671281  47881 41 3758230  66 55 87  01 88 85
_
ic  .  . . . . .  .  .
_
_
L 8176271  8176271  8175271 8175271  44 44 44 55 45 45
_
_
_
_
.
-  e          _
p 939 7 939 7 939 7 939 7    _
-
o 00137 3 00137  3 00137 3 00137 3 12 12 12 12 12 12 t 6111581  6111581  6111581 611 1581  38 38 38 38 38 38 o
.
_
-
  - 8- - 8 -  8- - 8- 1 - 1 - 1 - 1 - 1 - 1 -
_
. s odneo s odoeo s od n e o s    0dneo s  r - r r - r r r i
CCSCCYC CCSCCYC CCSCCYC 0CSCCYC    1B IB lB lB I B lB
-
-
_
-
e
_
r e
h
            -_
1  2  pe  1 2 sg r  r od  r r 3  4  o  o mi tr 1 2 3 is o o t  t    t t 7r  5r  1 c  8c  Atr 1 r 9r 7r 5r 1 c 8c 3o  5o  5e  6e  3o 5o 3o 5o 5e 6e 7t 1 c e
7t 1 c e
8t 1 e D
7t 1 e D
ta nC e
7t 1 c e
7t 1 c e
7t 1 c e
7t 1 c e
8t
 
D e
7t 1 e O
            -
Tt  Tt  T  ml
            -
T  Tt Tt 1t Tt 1 T Ge  Ge  GP  GP  na Ge Ce Ge Ge GP GP PD  PD  PH  PH  io2 PD PD PD PD PH PH ac6 tr5 na2
  .  .  .  . ohE .  . . .
l e c  d  e  f  CCR a d e r p
m a      .
_
            .
_
S      3
_
r llll!
 
n    r r  e r o tttttt tttttt atattt  tttt tmtt nnnn nenn npnn nnnn tatt tttt s nnnnnn nnnnnn pnpnnn i
eeeeee eeeeee memeee  eeee eeee emee eeee mmmm mrmm momm mmmm
_
r mmmmmm mmmmmm omommm  eeee egee ecee eeee a eeeeee eeeeee CeCeee
_
_
p eeeeee rrrrrr eeeeee rrrrrr e eee trtrrr eeee rrrr eaee rsrr e ee rtrr eeee rrrr
_
. m o gggggg gggggg ogoggg  gggg gi g g gogg gggg C AAAAAA AAAAAA NANAAA  AAAA ADAA ANAA AAAA
_
_
_
_
C
_
R      .
N
.
    -
o/ 2650f 4 0 424665  2 61 8 121 0 0297 9 26 1 995 ie  1 92200 6091 99  8 898 0002 0791 9 01 0892 te      . . .
as 1 01 1 11 1101 00  0 000 111 1 1 001 01 1 1 001 Rn e
i c
L n
i o
t u
( 243851 4 2438514  4 851 4 3026 3026 3026 3026 o
s 1 21168 1 21 168 t2168 223
 
223
 
223
 
223
 
e R
_
.
.
_
.
.
_
444333 ti a4333 444333  2333 2333 2333 2333
_
  - - - - - - - t- - - - - - - - - - - - - - - - - - -
EEEEEE EEEEEE EEEEEE  EEEE EEEE EEEE EEEE
)  803653 803653 803653  3256 3256 3256 3256 d  4 26000 426000 426000  01 03 01 03 01 03 01 03 .
        .
00O0.
 
.
_
.
't C 00O000 0000O0 000000    0000  0000 n R o nN 11ii1 11 1it 11 i1i i1ii 1iii ii11  1 i c o ( 1 i 525772 525772 525772  0085 0085 0085 0085 1 E t
a 879025 879025 879025  7453
      .
71453
        .
7 4 5,3 .
7453
          .
_
.
L r  547132 51 4 7132 5471 32  3212 3212 3212 321 2 T B t N A n
.
.
.
E T e c
_
M '
H n C o    d d    d A C    e e    e T e 4ta4333 444333 t4t433  2333 2333 2t33 2333
.
T e - - - - - - - - - - - - c c- - - - - - - - - - - c- - - - - -
.
_ 3 s EEEEEE EEEEEE eEeEEE  EEEE EEEE EeEE EEEE
_
_ n  t t    t
.
.
e 557823 1144410 e6e872  5603 1375 8e13 3473 c        1 59
_
i L
559245 6 9147132 8. t.i21 4 D8.D1 92  7. .D67 71 6491 32  t3t922  3212 31 1 2 3t12 321 2 o o    o N N    N e
p m 35 m 35 m 35 o 1 57833 1 57833 l 57833  4235 4235  t*235 4235 t 46881 1 48881 1 ta8881 1 2333 2333 2333 2333 o - - - - - - - - - - - - e - - - - 1 11 1 1 1 11 1 1 1 1 s rrrree rrrree  rr rree  a- - - a- - - a- - - a- - -
i AKKKXX AKKKXX AKKKXX  M11 I N11 1 N1 11 N11 I t
n a
l o
o C
s a    r G 1  3  14 o 1  2 3 4 t
d 1 r 7r 5r  c 1 r 9r  7r 5r e) 3o 3 o 5o  a) 3o 5o  3o 5o vl 7 t 7t 7 t  el 7t 7t  7 t 7t l
a 1 c 1 c 1 c Ra 1 c 1 c 1 c 1 c oi e  e  e  i e  e e e sV T t Tt T t dV T t T t T t T t s Ce Ge Gc  e Ge Ge  Ge Ge ic PD PD PO  sc PD PD  PD PD Dc    sc a
S0    g0 C1 .  .  .
e2 .  . . .
l e R( a b  c D( a b  c d p
m a .    .
S 4    5
 
r      eee e  eree o ttttt  ttttt  ttttt ttttt mmmtm tmamm  tttt tttt s nnnnn nnnnn nnnnn nnnnn eeene nepee      nnnn nnnn i
eeeee eeeee eeeee eeeee eeeee eemee      eeee eeee r mmmmm mmmmm mmmmm mmmmm rrrmr    mrorr  mmmm mmmm a eeeee eeeee eeeee eeeee    gggeg  e gC g g  eeee eeee p
m eeeee rrrrr  eeeee rrrrr eeeee rrrrr eeeee r rrrr aaaea sssrs ea rstss aa eeee rrrr eeee rrrr o ggggg  ggggg ggggg ggggg i i i gi  gi o i i  gggg gggg C AAAAA AAAAA AAAAA AAAAA DDDAD ADNDD      AAAA AAAA C
R N
o/  8f4420  914152 13137 2ft306 07947  1 1 53 4 039 5025 ie te 89900  99809 99989  09787 55364  65 45  f8898 9909 1000 .  .
as  0001 1 00010  00000  00000 00 00  0000 0010 Rn e
c i
L n
i o
t u
l 11 408 1 1 fs08 11 408 11408 11408  1114 08 1 926 1 926 o 1 811  18l1  1811 1811 181 1  1811  2 98 2 98 s  1  1  1  1  1  1  2 2 e
R 65777  65777  65777 65777 65777  65777  14323 f4323
    - - - - - - - - - - -  - - - - - - - - - - -  - - - - - -
EEEEE  EEEEE  EEEEE EEEEE EEEEE  EEEEE  EEEE EEEE
)  73935  73935  73935 73935 73935  73935  ti225 42?5 d  70680 70680  T0680 70680 73680  70680,  21 00 21 00
'    . . . . .  .  .
t n
C R
000U1  0O001  000O1 00001 JOO01  000O1  0000 0000 o nN  i 1iii  iii1i  ii iii i111i zti1i  1 iii 111i i i 1 +.
c o ( 1 i 814902  8i902 s 8ft902 84902 8f4 902 84902  7548 7548 t  34301  3 s301 34 301 34301 34301  34301  9082 9082 E a  . . . .
1  . . . . . . . . . . . . . .
L r  85988  85988  85988 85988 85988    14154 4154 T B t N A n E T e M c H n C o        d A C        e T e 65777 65777  65777 65777 65777  65t77  r4 8423 f4 423 T e - - - - -  - - - - -  -  -  - - c- - - - - - - - - -
A s EEEEE  EEEEE  EEEEE EEEEE EEEEE  EEeEE  EEEE EEEE n        t e 63800  21 473 28436 99400 490t *4 8 28e74  7921 4195 kL 31 821
    . 3163 . . .
 
60568 50843
        .
20718
        . .
 
7.D53 .
1348
          .
7490 75888  85787 75867 85666  43353  52t34  14 853 4954 o
N e          m m p  4  t s
4  4  4  4 m335 m335 o 1 8029 1 8029 1 8029 1 8029 1 8029 1 8029 5333 5333 t 5561 5  5561 5 55615 5561 5 5561 5  5561 5  8111 81 11 o - - - - -  - - - - -  - - -  -  - - - - - -  - - - - - - - -
s roobe r o ob e roobe roobe roobe roobe      reee reee i
CCCSF  CCCSF CCCSF CCCSF CCCSF  CCCSF  KXXX KXXX
          ) }
2 2 ( (
2)
          #r 9        e
  #        k n
 
2 ni k)        I a ni       r  r t al 1  2  3  f4  o  o yn 1 2 T l r
t  t ao e 1  9r  7r 5r  1 c  8c  cC 1 r 7r en 3o  5o  3o 5o  5e  6e  e 3o 3o ti 7t  7t  7 t 7 t  8t  7t  Ds 7t 7t sr 1 c 1 c  1 c 1 c  1 e  1 e a 1 c 1 c aa  e  e  e  e  D  D sG e e WM T t  T t  T t T t  T  T  a Tt Tt Ge  Ge  Ge Ge  FP  GP  Gc Ge  Ge dr PD  PD  PD PD  PH  PH  c PD PD ie        e ut        t5 qi        s2 il .  .  .  .  .  . a1 . .
e L( n  b  c d  e  f  W( a b l_p m
a .        .
S 6        7 fl  il ,l
 
  .
    - ee o tttt  tmm tmm s nnnn  nee nee i eeee  eee eee r mmmm  mrr mrr a eeee  egg egg p eeee rrrr eaa rss rss eaa m
o gggg  gii gii C AAAA  ADD ADD .
C R
N o/ 6886  454 359 ie 8899  454 353 te    . .
as 0000  111 111 Hn e
i c
L n
o i
t u
l 1 926  728 728 o 2 98  1 3 13 s 2  2 2 e
R 4323  656 656
  - - - -  - - - - - -
EEEE  EEE EEE
)  4225  047 047 d  2100  201 201
    .
't n
C R
0000  O00 G0 o nN 111i  i11 i 1i c
i 1 io 7548  503 503 t 9082  454 454 1 E a L r 4154  186 1 . 86 T B t  -
N A n E T e M c H n C o A C T e 4423  646 646 T e -  - - - -  -
A s EEEE  EEE EEE n .
e 7052  925 324 i
c 2371  032 939
  . .
L 4954  219 1 1 8 e m  m m p m335  335 335 o 5333  333 333 t 81 11  1 1 1 1 1 1 o - - - -  - - -  -
s reee  eee eee i
KXXX  XXX XXX
     .
     .
_
_
  #
_
-  k
-
n)
-  ai 1
Tl
-  l r r 4 ye o o an t t 5r  ci 1 c 8c 5o  er 5e  6e 7t Da 8t 7t 1 c  M 1 e 1 e e s D D T t as T Ge Gu GP iGP PD  o PH Pl i ee
_
ts
_
sa
  .
aG . .
W(
_
e c  a b
_
l p
m a  .
_  S  8
  -
-
.
_
. t
_
-  n
.
n e
-  o t m t t
.
.
. s n e n n
_
-  i e e e e
.
.
r m r m m
-
a e g e e p e a e e
_  m r s r r o  g g
.
-  g i
_
.
.
C A D A A
.
.
-
-
.
_
.
.
_
-
S I
_
.
S
-
_
Y
.
.
-
L
.
A )
.
- N C
_
A R
-  N
.
-
0 o/
-
-
-
9 ie 0 6 7 6
- te 9 3 7
_
.
.
r as  . 9 S Rn
.
_
0 1 0 0
-  e
_
_
D  c
_ N i
_ A L
_
,68 (
.
. 99
.
-
.
-
-
-
rR
- SE B
.
.
_
_
,M
.
_ 5E
_ 5V
.
O n
_
_
.
oN o
_
T i N
.
.
t
_ 1 ,O u 8 4 3 5
- 3 l 4 5 3 2
-
- T 2 T o N HN s
_
E E A e
_
M L FL R B OP
_
I C A
_
_
A T SR
_
T NA
.
-
-
T OE
_ A SL
_ I C
_
.
-
RU
.
-
-
AN
-
-
P
.
_ ME  5 5 5 6
_ OL  - - - -
- CT  E E E E
-
G )
TO t 6 4 1 4
_
.
.
NV E
i n
0 0 1
     .
     .
ENCLOSURE 2 Criteria for Comparing Analytical Measurements This enclosure provides criteria 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 of this progra In this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty, referred to in this program as
"Resolution"2 increases, the range of acceptable differences between the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio 2 of the licensee value to the NRC value for each individual nuclide is compute This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below. Values outside of the agreement ratios for a selected nuclide are considered in disagreemen NRC Reference Value for a Particular Nuclide


    .
Resolution = Associated Uncertainty for the Value Licensee Value
MR Cu 0 0 0 0
.
_
_
EO RF R/
Ni i 1 f 1
_
_ U C
_
S  u 9 4 3 4
_
- A ( 8 1 6 4
_
_
E  .
-
-
-
M  2 2 3 3
-
Y R
-
-
O
- T A
_ M
.
.
.
R I
F
- N O
C ei en
  )
t
_
_
su n/
5 5 5 6 E
  -
E
  -
E
    -
E
    -
-  ei cC 6 9 8 3
-  iu L( 2 2 .
_
-  e g
o 5 9 0
_  t o
s


  -
Comparison Ratio n NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio i    Comparison Ratio for Resolution  Agreement
5 8
  < 4  0'.4 - .5 - .6 - 1.66
  -
!  16 - 0   0.75 - 1.33
e r
'
    -
51 - 200  0.80 - 1.25
 
  >200  0.85 - 1.18
r
    -
I H F S S
-
 
__ _____ _-___ - _ ____ ___ _ _ _ __  - _ . _ - _ . _ ._ _ _ _ - - _
    *
    .
ATTACHMENT 2 Criteria for Comparing Analytical Measurements l
l This attachment provides criteria 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 of this program, i
In this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty referred to in this program as " Resolution"2 increases, the range of acceptable differences between the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio 2 of the licensee value to the NRC value is compute This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agr.eement are listed in Table 1 below. Values outside of the agreement ratios are considered in disagreemen Resolution = NRC Reference Value Associated Uncerainty for the Value
    ' Comparison Ratio = Licensee Value  I NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for Resolution  Agreement
    < 4  .4 - .5 - .6 - 1.66 16 - 50   .75 - 1.33 51 - 200  .80 - 1.25
    >200  .85 - 1.18 l
l
          )
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ___      J
}}
}}

Revision as of 20:15, 11 December 2021

Ack Receipt of 880212 Submittal of Analytical Results of Spiked Liquid Samples,Per Insp Rept 50-424/87-64.Comparison of Results to Known Values & Acceptance Criteria of Comparisons Encl.All Comparative Results in Agreement
ML20148H725
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/10/1988
From: Dan Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Head G
GEORGIA POWER CO.
References
NUDOCS 8803300070
Download: ML20148H725 (4)
v • d • e


Text

P '

.

,

$flL&W MAR 101988 Georgia Power Company ATTN: V.r. George F. Head Senior Vice Dresident-Nuclear Operations P. O. Box 4545 Atlanta, GA 30302 Gentlemen:

SUBJECT: DOCKET NO. 50-424, CONFIRMATORY MEASUREMENT RESULTS, SUPPLEMENT TO INSPECTION REPORT N0. 50-424/87-64 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on November 5, 1987, to your Vogtle facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated February 12, 1988, and subsequent to verification of your values as per our conversation by telephone on fiarch 1, 1988, the following comparison of your results to the known values are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by your cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facilit These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection

Sincerely, Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards Enclosures:

1. Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encis: (See page 2)

8803300070 880310 PDR ADOCK 05000424 0 PDR

.C Ec F ,, .

Georgia Power Company- 2 cq w/encis:

'

9'. D. Rice, Vice President, Project

' Director p W. Hayes, Vogtle Quality-Assurance Manager (G( Bockhold, Jr. , General Mar.ager, Nuclear Operations M Gucwa, Manager, Nuclear Safety and Licensing g A. Bailey, Project Licensing Manager g W. Churchill, Esq., Shaw, fittman, Potts and Trowbridge W. Kirkland, III, Counsel, Office of the Consumer's Utility Council (p'. Feig, Georgians Against Nuclear Energy bSc w/encis:

LE.f Reis, 0GC W. Hopkins, NRR M. Sinkule, RII D y Technical Assistant WC Resident Inspector Dv.:ument Control Desk

"State of Georgia RII RII RII ,y

>kV J oorsen f abl(e kule MSip/88 3/f/88 3/7/88 3/4 ll

!

.~ -_

. . _ _ .

..*

."

ENCLOSURE 1 Conri rmatory Measurement Compa ri sons of' H-3, Fe-55, and Sr-90 Ana lyses for Vogtle Nuclear Plant, November 5, 1987 Licensee NRC tio Isotope Lupi/mi ) (uCi/mi1 Hesolut193 LLi',ensee/NRC) Compa ri son H-3 2.1 E-5 2.0310.084 E-5 52 1.01 Ag reement Fe-55 1.3 E-5 1.27 1 0.03 E-5 f2 4 1.02 Ag reement

$r-90 2.2 E-6 2.57 i O.10 E-6 26 0.86 Ag reement NOTE: Due to the extended decay time for the isotope Sr-89, the analytical resu l ts we re no t compa re *

v

.

.

-

p- -

,

.

.

ENCLOSURE 2 Criteria for Comparing Analytical Measurements This enclosure provides criteria 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 of this progra In this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty, referred to in this program as

"Resolution"2 increases, the range of acceptable differences between the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio 2 of the licensee value to the NRC value for each individual nuclide is compute This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below. Values outside of the agreement ratios for a selected nuclide are considered in disagreemen NRC Reference Value for a Particular Nuclide

Resolution = Associated Uncertainty for the Value Licensee Value

Comparison Ratio n NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio i Comparison Ratio for Resolution Agreement

< 4 0'.4 - .5 - .6 - 1.66

! 16 - 0 0.75 - 1.33

'

51 - 200 0.80 - 1.25

>200 0.85 - 1.18

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000424/1987064&oldid=3361813"