IR 05000285/1989025

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Insp Rept 50-285/89-25 on 890605-09.No Violations or Deviations Noted.Major Areas Inspected:Licensee Chemistry/Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements
ML20246A898
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/26/1989
From: Baer R, Nicholas J, Wilborn L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20246A895 List:
References
50-285-89-25, NUDOCS 8907070127
Download: ML20246A898 (26)


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, APPENDIX U.S. NUCLEAR REGULATORY COMMISSION ,

REGION IV

pa NRC Inspection Report: 50-285/89-25 -Operating License: DPR-4 Docket: 50-285 Licensee: Omaha Public Power District (OPPD)

'444 South 16th Street Mall

' Omaha, Nebraska 68102-2247 Facility Name: Fort Calhoun Station (FCS)

Inspection At: 'FCS Site, Blair, Nebraska Inspection Conducted: June 5-9,'1989 Inspectors: _ J U j) 4 rdLA.) (of2 DYE 9

+ J.~B. Nipholas, Senior Radiation Specialist- Date Facilitfes Radiological Protection Section nko Al6s &

L.'Wilboyh, Radiation Specialist, Facilities U24/89 Date Radiological Protection Section Approved: dl/h/ M///2A44 R. E. 8aer, Chief, Facilities Radiological Ob!O i

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. g , Protection Section y I_nypection Summary Inspection Conducted June 5-9, 1989 (Report 50-285/89-25)

Areas liapected: Routine, unannounced inspection of the licensee's chemistry /,7 biochemistry program and water chemistry and radiochemistry confirmatory measurement Results: The NRC inspectors determined that the licensee had developM and implemented a water chemistry program and radiochemistry program baseo on regulatory and industry guidelines. The water chemistry and radiochemistry j programs were being conducted in accordance with Technical Specification (TS)

requirements. The licensee's chemistry and radiochemistry staffs had e907070127 890630 ,-'

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' experienced a growth of approximately 30 percent over the past 12 month Quality Assurance (QA). surveillance and audits had been performed as required and were technically comprehensive. The results of the water' chemistry ,

confirmatory measurements indicated 92 percent agreement. This was'a improvement over the previous 88 percent'ogreement in the secondary chemistry laboratory during'the NRC inspection conducted in June 1988. The licensee's j radiological confirmatory measurements results were in 98 percent agreement '

'with the NRC results. The licensee's performance in the area of radiological confirmatory measurements was comparable to the 97 percent agreement achieved .

during the last NRC inspection of this area in July 198 I Within the areas inspected, no violations or deviations were identifie ;

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c Persons' Contactedt e -

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  • G. R. Peterson, Manager, FCS'
  • A. W. Richard, Assistant' Plant Manager, FCS~

W *J.'B. Biggs, Senior' Chemistry Technician K -

  • J.:Ps Bobba, Supervisor, Radiation Protection- >

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  • T. R. Dukarski, Laboratory Supervisor

. *F. F. Franco,. Manager, Radiological Services g *J. M. Glantz,, Senior Chemistry Technician

  • D..J. Matthews, Supervisor, Station Licensing-

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'*T. C. Matthews, Station' Licensing Engineer

  • W.LW. Orr, Manager, QA and Quality. control (QC)
  • B. A.-Schmidt, Supervisor,' Secondary Chemistry-
  • C. F. Simmons, Station Licensing Engineer
  • F. K. Smith, Plant' Chemis '

NRC

~PJ H. Harrell, Senior R'esident Inspector, FCS T. Reis, Resident Inspector, FCS

  • Denotes.those present during the exit interview on June 9, 198 ! Organization and Management Controls (84750)

l The NRC inspectors reviewed the licensee's organization and' staffing of the chemistry / radiochemistry section (C/RS) to determine agreement with L commitments in Chapter 12 of the Updated Safety Analysis Report (USAR)=and-F ' compliance with the requirements in Section 5.2 of the'T The NRC inspectors verified that the organizational structure of.the' C/RS 4 was as described in the USAR and TS. The NRC inspectors reviewed the C/RS  !

staff. assignments and management controls for the assignment of

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responsibilities for management and implementation of the FCS water p~ chemistry and radiochemistry programs. The NRC inspectors verified that

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the' administrative control responsibilities specified in the FCS procedures were being implemente The'NRC. inspectors noted that the new C/RS' organizational structure; included four.specifically defined n- = supervisory positions reporting to the plant chemist, who' reports directly S to the plant manage The;NRC inspectors reviewed the staffing of the C/RS. Since the previous NRC water chemistry / radiochemistry inspection in June 1988, the C/RS had added six new chemistry technic.ians. This' increased the C/RS staff to a total.of 19 leaving 4' authorized ~ positions to be-filled. :The licensee was

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actively' recruiting to fill the four vacancie All of the six recently hired technicians have the educational and experience backgrounds to meet the ANSI N18.1-1971 and TS qualification requirements. The six new technicians were currently undergoing shift qualification training. The hiring of 6 new technicians indicated a staff increase of approximately 30 percent in the past 12 months. This is a positive indication of C/RS staff stability as compared to the high rate of C/RS personnel turnover experienced in the previous 3 year No violations or deviations were identifie . Light Water Reactor Chemistry Control and Chemical Analysis (79701, 84750)

The NRC inspectors reviewed the licensee's water chemistry control and analysis program including implementation of a water chemistry control program, water sampling, facilities and equipment, implementation of a QC program for chemical measurements,.QA audits and surveillance, and water chemistry confirmatory measurements to determine agreement with the commitments in. Chapters 4, 9, 11, and 14 of the USAR and compliance with the requirements in Sections 2.20, 5.8, and 5.13 of the T l The NRC inspectors' review of the water chemistry program tound that the licensee had revised and approved standing orders, surveillance

. procedures, chemical control procedures, sampling procedures, instrument calibration and QC procedures, and analytical procedures. A review of '

selected procedures revised since the previous NRC water chemistry inspection in June 1988 indicated that the C/RS had implemented sufficient programinatic procedures to meet the commitments of the USAR and the TS requirements. A list of procedures reviewed is provided in Attachment 7.

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1' The NRC inspectors inspected the secondary chemistry laboratory and laboratory instrumentation. The secondary chemistry laboratory was equipped with the necessary chemicals, reagents, labware, and analytical instrumentation to perform the required analyses. The NRC inspectors noted that the construction of the new chemistry and radiochemistry laboratory and office facilities was under constructio The NRC inspectors reviewed selected C/RS procedures for operation, calibration, and QC of the laboratory analytical instrumentation used for analysis of the NRC water chemistry standards to determine adequacy and effectiveness of the licensee's water chemistry measurements program. The NRC inspectors verified that the secondary chemistry laboratory and radiochemistry laboratory analytical instruments had been calibrated in accordance with procedures and an instrument QC program had been implemente It was noted that the licensee had initiated the use of instrument QC charts to trend QC data collected from daily or periodic QC analyses of chemical parameters. The licensee had implemented a program of standard verification for chemical standards used for calibration and QC measurements of chemistry analytical instrumentatio . _ _ _ _ _ _ _ _ _ _ - _ _ _

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The NRC inspectors reviewed secondary water chemistry data for the period January 1988 through May 1989 to determine compliance with TS requirements. It was verified that TS required water chemistry sampling and analyses had been performed. The review included inspection of the recorded trends of the secondary water quality data and reactor coolant chemistry parameter The NRC inspectors reviewed the records of

- out-of-specification chemical parameters and licensee's corrective actions

. taken when chemical parameters did not meet established chemical control limits. The NRC inspectors reviewed the effectiveness of the water chemistry program to measure and prevent the introduction of chemical contaminants into secondary water systems and the reactor coolant system and found the licensee's chemical limits were established according to the Electric Power Research Institute owner's group guidelines for pressurized water reactor secondary and primary water chemistr During the inspection, standard chemical solutions were provided to the licensee for confirmatory measurements analyses. The chemical standards were analyzed by the licensee in both the secondary laboratory and the radiochemistry laboratory using routine methods and equipment. The

. results of the measurement comparisons are summarized in Attachments 1, 2, 3, and 4 to this repor No violations or deviations were identifie . QA and Confirmatory Measurements for Radiochemistry Analysis (84750)

The NRC inspectors reviewed the licensee's radiochemical analysis program including procedures, facilities and equipment, implementation of chemistry control of the reactor coolant system and plant borated water systems, implementation of an instrument QC program, and radioanalytical confirmatory measurements to determine agreement with commitments in Chapters 4 and 9 of the USAR and compliance with the requirements in Sections 2.1, 3.2, 5.8, and 5.15 of the T The NRC inspectors reviewed standing orders and radioanalytical procedures revised and approved since the previous NRC radiochemistry inspection in June 1988 and determined that the licensee had implemented sufficient radioanalytical procedures to meet USAR and TS requirement The NRC inspectors reviewed the licensce's records for the period January 1988 through May 1989 to determine compliance with TS requirements for samplir,g and analysis of the reactor coolant system, safety injection refueling water tank, boric acid storage tanks, safety injection tanks, and spent fuel pool. The E-Bar data for the period February 1988 through April 1989 was inspected. The NRC inspectors verified that all TS required chemistry sampling and analyses of the above listed systems or components had been performe The NRC inspectors reviewed the licensee's records for the period f January 1988 through May 1989 involving radiochemistry counting room instrumentation calibration and QC. It was verified that the

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radiochemistry counting room instrumentation had been calibrated accor' ding to' procedures and an instrument QC program was being implemente ,

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b During the inspection, radiological confirmatory measurements were performed on standards and split samples by the licensee and.the.NRC

' inspectors .in the Region IV mobile laboratory onsite. The standards and samples were analyzed by the licensee using routine methods and equipmen The results of the measurements comparisons are summarized in

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< Attachments 1, 5, and *

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No violations or deviations were identifie , 'QA Program (79701,>84750) . _ .7 The NRC inspectors reviewed the licensee's QA surveillance and audit programs regarding water chemistry and radiochemistry activities to determine agreement with commitments in Chapter 12 of the USAR and-compliance with the requirements in'Section 5.5 of the T The NRC inspectors reviewed the surveillance and audit schedules for 1988 and 1989, QA surveillance and audit plans and checklists, and the qualifications of the QA auditors. Audit and surveillance reports generated from QA activities during the period January 1988 through May.1989 in the areas of water chemistry and radiochemistry were reviewed for scope to ensure thoroughness of chemistry / radiochemistry program evaluation and timely followup of identified deficiencie The NRC inspectors determined that the surveillance, audit. plans, and checklists i were comprehensive and designed to ensure compliance with the USAR, TS, )

and FCS procedure The NRC inspectors verified that the QA surveillance and audit had been performed in accordance with FCS QA procedures and schedules.and by qualified auditors who were knowledgeable of nuclear power facility chemistry / radiochemistry activities. -The documents which were reviewed are listed in Attachment 7 to this repor No violations or deviations were identifie . Exit Interview (30703)

The NRC. inspectors met with'the licensee representatives identified in

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paragraph 1 of this report at the conclusion of the inspection on June 9, 198 The NRC inspectors summarized the scope of the inspection and discussed the inspection findings and the results of the water chemistry and radiochemistry confirmatory measurements as presented in this repor _ - ________-__ - _ _ ._

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ATTACHMENT I'

, Analytical Measurements

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Fort Calhoun Station L, NRC' Inspection Report: 50-285/89-25.

p ' . Water Chemistry Confirmatory Measurements'

During' the inspection, standard chemical solutions were provided to the licensee'for analysis. .The standard solutions were prepared by the Brookhaven National Laboratory-(BNL), Safety and Environmental Protection -

Division, for.the NRC. The standards were analyzed by the licensee using L routine methods'and equipment. .The analysis of chemical standards is used to verify the licensee's ' capability to monitor _ chemical parameter in various plant systems with respect to Technical Specification-(TS)

requirements and other-industry standards. In addition, the analyses of

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standards are used to evaluate the licensee's analytical procedures with respect to accuracy and precisio The results of the measurement comparisons are listed in Attachment 2 ,

.for the' secondary' chemistry laboratory and in Attachment 3 for the '

radiochemistry-laboratory. Attachment 4 contains the criteria used to compare results. All standards were analyzed in triplicat The licensee's analytical results from the'first'run indicated some problems with the analyses for chloride, iron, and nickel. The following are some observations noted by the NRC inspectors: The licensee's first run chloride results were all in disagreement and biased'high. The licensee prepared new calibration standards and' recalibrates the ion chromatograph in-the secondary chemistry laboratory. . The licensee prepared new BNL standard-dilutions and reanalyzed the BNL-standards. The second run results were also in disagreement and biased high. The chloride results indicated a systematic high bias which was not indicated by the quality control standard result. As the results on Attachment 2 show, all chloride and 2 out of 3 lithium values were slightly outside of the statistical acceptance range shown on Attachment 4. However, the NRC inspectors do not view the licensee's results for chloride and lithium as a significant problem because the BNL acceptance criteria,

~ based on parts per billion (ppb) levels, were as TS requirements appear as parts per million (ppm) level The licensee's first run for iron midrange and high concentration results were in disagreement and biased low. The licensee recalibrates the atomic absorption system for iron, prepared new BNL standard dilutions, and retested the BNL standards. The second run results were all in agreemen _ _ _ - _ _ _ _ - - _ _ ____ - _ _ _ _ _ _ - _

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u 1-LAttachment'1- -2- .The licensee's first run for nickel midrange and.high concentratio results were in disagreement and biased low. The licensee.

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rere'.ibrated the atomic absorption system for nickel, Irepared new RNL standard dilutions, and retested the BNL standards. The second run results were all in agreemen The licensee's water chemistry confirmatory measurement results showed-o about 89 percent. agreerncat. Analytical results indicated some minor problems with the chloride midrange. concentration and the. lithium low and midrange concentrations. The. identified disagreements are not considered to indicate- any significant' programmatic problems. The licensee's results were with.in expected-industry performance level Radiological Confirmatory Measur'ements

~ Confirmatory measurements.were performed on the following standards and samples in the NRC. Region IV mobile laboratory at Fort Calhoun Station during the inspection; (1) FCS' Air Particulate Filter Standard (26735-22)

1(2) FCS Charcoal Cartridge Standard (26737-22)

(3) . Stack . Charcoal Cartridge (RM-060)

(4) Waste Liquid Sample - 1.0 liter Marinelli beaker-(5) Waste Liquid' Sample -4.0 ' liter Marinelli beaker (6) . Containment Atmosphere (RM-050/051) - 1.0 liter Gas Marinelli beaker (7) Reactor Coolant Gas Sample - 15cc Gas Vial

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.(8) Reactor Coolant Liquid Sample - 8mi Liquid Vial (9) Reactor Coolant Tritium Sample

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ATTACHMENT i 3 ,

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The' radiological confirmatory measurement testa consisted of comparing the analysis results of the licensee and the NRC Region IV mobile laborator ~

The NRC's mobile laboratory measurements are referenced i to the National Institute of Standards and Technology by laboratory i l intercomparison Confirmatory measurements are made only for those l

nuclides identified by the NRC as being present in concentrations greater than 10 percent of the respective isotopic values for liquid and gas concentrations as stated in 10 CFR Part 20, Appendix B, Table I The licensee maintains two germanium-lithium detector systems in the radiochemistry counting room. Both gamma spectrometer systems are used for routine isotopic analysis of radioactive samples to demonstrate comoliance with TS and regulatory requirements. The analytical results from these two detector systems were compared with the NRC results. The licensee performed the tritium analysis on their liquid scintillation counting system. The individual sample analyses and comparison of analytical results of the radiological confirmatory measurements are tabulated in Attachment 5, as Series 80 system first and Series 90 system second. Attachment 6 describes the criteria used to' compare the analytical result The licensee's gamma isotopic results from the listed standards and samples in Attachment 5 showed 98 percent agreement with the NRC analysis results based on 118 agreement results out of 121 total results compare The licensee's tritium result of the reactor coolant sample was in agreement with the NRC analysis result. The licensee's performance in the area of radiological confirmatory measurements was comparable to the 97 percent agreement achieved during the last NRC inspection of this area in July 198 l

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ATTACHMENT 2 l Water Chemistry Confirmatory Measurements Results (Secondary Chem. Lab.)

Fort Calhoun Station NRC Inspection Report: 50-285/89-25 Ghloride Analysii (0.5-1000 ppb) Ion Chromatograph FCS Results NRC Results FCS/NRC Comparison Sample foob) (oob) Ratio Decision 87A 10.31 .31 .1110.02 Disagreement 87B 42.71 .31 .1410.03 Disagreement 87C C2.0 .51 .07iO.02 Disagreement Retest - after recalibration of the ion chromatograph and prepa ation of new BNL standard dilutions 87 .61 .31 .1410.05 Disagreement 87B 44. Oi .3 .1810.03 Disagreement-87C 87.0 .51 .1410.03 Disagreement Fluoride Analysis (0.5-1000 ppb) Ion Chromatograph FCS Results NRC Results FCS/NRC Comparison Sample ipob) (pob) Ratio Decision 87A 10.11 .31 .89io.08 Agreement 87B 43.3 .31 .0210.02 Agreement 87C 83.01 .8i .0110.02 Agreement Sulfate Analysis (0.5-1000 ppb) Ion Chromatograph FCS Results NRC Results FCS/NRC Comparison Sample (pob) ipob) Ratio Decision 87A 10.41 .8 .0710.08 Agreement 87B 40.71 .31 .0610.08 Agreement 87C 79.71 .01 .0210.04 Agreement l

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ATTACHMENT 2 2

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- Iron Analysis (5-50 ppb; Graphite Furnace Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Samole (pobl (pob) Ratio Decision -

87G 9.31 .31 .OCiO.03 Agreement 87H 18.41 .91 .9210.02 Disagreement 87I 36.11 . Oi O.93io.03 Disagreement Retest - after recalibration of the atomic absorption instrument and preparation of new BNL standard dilutions 87G 9.81 .3i .05 0.04 Agreement 87H 19.71 .91 .99iO.02 Agreement 87I 40.11 .01 .~O310.03 Agreement Cooper Analysis (5-50 ppb) Graphite Furnace Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Sample (oob) (pob) Ratio Decision 87G 10.31 .0 .0310.02 Agreement 87H 20.61 .21 .0210.04 Agreement 87I 38.51 .01 O.96iO.03 Agreement Chromium Analysis (5-50 ppb) Graphite Furnace Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Sample (pob) (pob) Ratio Decision 87G 10.01 .91 .01iO.03 Agreement 87H 19.71 .3 .0210.02 Agreement 871 38.41 .71 .99iO.02 Agreement Nickel Analysis (5-50 ppb) Graphite Furnace Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Samnte (pob) (pob) Ratio Decision 87G 9.41 .21 .9210.04 Agreement 87H 19.11 .9 .9110.02 Disagreement 87I 41.11 .41 .9110.04 Disagreement Retest - after recalibration of the atomic absorption instrument i and preparation of new BNL standard dilutions I

87G 9.51 .21 .9310.05 Agreement l 87H 18.91 .9 .9110.05 Agreement 87I 38.21 .3i .9510.04 Agreement l

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I ATTACHMENT 2 3 Sodium Analysis (1-1000 ppb) Flame Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Sample (nob) (oob) Ratio Decision 87J 6.01 .1 .99io.14 Agreement 87K 24.0 .21 .13iO.08 Agreement 87L 83.31 .0 .05 0.06 Agreement Lithium Analvsis (20-3000 ppb) Flame Atomic Absorption FCS Results NRC Results FCS/NRC Comparison Sample (oob) (opb) Ratio Decision 87J 20.31 .7i .03iO.04 Agreement 87K 63.01 .0 .0510.03 Agreement 87L 214.31 .51 .0410.03 Agreement 1 Ammonia Analysis (20-3660 ppb) Spectroscopy FCS Results NRC Results FCS/NRC Comparison Sample (opbl (oob) Ratio Decision 87M 106.01 .01 .0210.08 Agreement 87N 305.Oi1 .01 .0110.04 Agreement 870 1026.0 1 .014 .0410.05 Agreement 1 Hydrazine Analvsis (2-600 ppb) Spectroscopy FCS Results NRC Results FCS/NRC Comparison Sample (nob) (pob) Ratio Decision 87P 19.01 .9i .?S10.03 Agreement 870 96.7 .81 .9710.02 Agreement 87R 485.01 .01 .9710.02 Agreement I i

i 1 Silica Analysis (4-2000 ppb) Spectroscopy FCS Results NRC Results FCS/NRC Comparison Sample (opb) (pob) Ratio Decision 87S 29.31 .41 .1110.07 Agreement 87T 53.31 .01 .0310.04 Agreement 87U 147.31 .01 .9410.03 Agreement

Retest - using the 86 Series BNL standards; no changes in instrument calibration  !

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ATTACHMENT 3 '.

Water Chemistry Confirmatory Measurements Results (REdiochem. Lab.)

Fort Calhoun Station NRC Inspection Report 50-285/09-25 - Chloride Analysis (0.5-1000 ppb) Ion Chromatograph-FCS Results NRC Results FCS/NRC Comparison Sample ( oob ) - (oob) Ratio Decision '

87A 10.1 .3i .0910.05 Agreement 87B 41.0 .3 .1010.03 Disagreement 87C 79.01 .5 .03iO.02 Agreement- Fluoride Analysis (0.5-1000 ppb) Ion Chromatograph FCS Results NRC Results FCS/NRC Comparison Sample- (pob) (oob) Ratio . Decision 87A 9.3i .3 .83 0.09 Agreement 87B 43.7i ,3 .03 0.02 Agreement 87C- 81.7i .8i .9910.02 Agreement Sulfate Analysis (0.5-1000 ppb) Ion Chromatograph

'FCS Results NRC Results FCS/NRC Comparison Sample (pob) (pob) Ratio Decision 87A 10.3i .8 .0610.08- Agreement 87B 40.01 .3i .04iO.09 Agreement 87C 78.7 .0 .0110.04 Agreement Baron Analysis (100-2000 ppm) Manitol Titration FCS Results NRC Results FCS/NRC Comparison Sample (ppm) (com) Ratio Decision 87D 99.4 .01 .96 0.02 Agreement 87E 598.41 .81 .9710.02 Agreement 87F 1597.51 .613 .9610.02 Agreement

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' . Lithium Analysis ~(20-3000 ppb) . Flame Atomic. Absorption

,FCS Results NRC Results FCS/NRC Comparison Sample foob) (pob) Ratio Decision

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87J 24.011.0- 19.71 .21io.06 Disagreement-87 .71 .01 .1010.03 Disagreement 87L 217.7 .5i .05iO.03 Agreement

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This attachment provides criteria for_ comparing results of capability

. tests. -In these criteria the .)udgement' limits are based on the uncertainty of the ratio of the licensee's value to the NRC valu The following steps are performed:

(1) The ratio of the licensee's value to the NRC value is computed

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(ratio = Licensee's Value );- and

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NRC VALUE (2) the uncertainty.of the ratio is propagate If the absolute value of one minus the ratio is less than or equal to.twice the ratio uncertainty, the results are in agreement.-

(l1-ratio l A 2 x uncertainty).

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l 1(From: Bevington, P. R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill., New York, 1969)

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ATTACHMENT 5 ,

Radiological' Confirmatory Measurement Results

Fort Calhoun Station NRC Inspection Report: 50-285/89-25 l~ 1.- FCS Air Particulate Filter Standard (26735-22)

-(Standardized: 08:00, CDT, June 6, 1989)

l l FCS.Results- NRC Results FCS/NRC Comparison Nuclide (uCi/ sample) (uCi/ sample) Ratio Decision

'Cd-109 1.0310.503E+O 8.57510.029E-1 1.20 Disagreement 1.OOiO.485E+O 1.17 Agreement Co-57 1.4 bio.050E-2 1.3OOiO.OO8E-2 1.14 Agreement

'1.5310.049E-2 1.18 Agreement Ce-139 5.2710.218E-3 5.23610.064E-3 1.01 Agreement 5.10iO.227E-3 0.97 Agreement Sn-113 7.9310.306E-3 7.69610.134E-3 1.03 Agreement 7.5310.368E-3 0.98 Agreement Cs-137 5.79iO.170E-2 S.604tO.034E-2 1.03 Agreement 5.71tO.235E-2 1.02 Agreement Y-88 1.0910.035E- .130tO.026E-2 0.96 Agreement 1.09 0.039E-2 0.96 Agreement Co-60 6.0710.158E-2 5.982iO.042E-2 1.01 Agreement 6.02iO.175E-2 1.01 Agreement FCS Charcoal Cartridae Standard (26737-22)

(Standardized: 08:00, CDT, June 6, 1989) '

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ sample) (uCi/ sample) Ratio Decision

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Cd-109 1.1410.056E+0 1.08410.OO4E+0 1.05 Agreement 1.1110.056E+O 1.02 Agreement Co-57 1.5910.053E-2 1.46710.OO9E-2 1.08 Agreement 1.5110.052E-2 1.03 Agreement Ce-139 5.65tO.227E-3 6.33610.063E-3 0.89 Agreement 5.47 0.226E-3 O.86 Agreement I

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FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ sample) luCi/ sample) Patiq > Decision Sn-113 8.12iO.297E-3 8.430iO.169E-3 0.96 Agreement 7.72io.308E-3 0.92 Agreement

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Cs-137 6.30iO.184E-2 5.992 0.038E-2 1.05 Agreement 5.9610.192E-2 0.99 Agreement Y-88 1.1410.034E-2 1.15910.026E-2 0.98 Agreement 1.1510.037E-2 0.99 Agreement Co-60 6.5610.166E-2 6.23710.047E-2 1.05 Agreement 6.3310.170E-2 1.01 Agreement FCS Stack Charcoal Cartridae (RM-060)

(Sampled: 08:00, CDT, June 6, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ sample) (uCi/ sample) Ratio Decision I-131 3.59 0.206E-4 3.66610.258E-4 0.98 Agreement 3.72iO.245E-4 1.01 Agreement I-133 3.8810.263E-4 3.862iO.382E-4 1.00 Agreement 3.7410.282E-4 0.97 Agreement 4 Waste Liouid Sample - 1.0 liter Marinelli beaker (Sampled: 12:00, CDT, June 7, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision Na-24 2.2610.079E-5 2.152io.048E-5 1.05 Agreement 2. Olio.OB4E-5 0.93 Agreement Co-58 6.9810.412E-6 6.815 0.366E-6 1.02 Agreement 5.9310.397E-6 0.87 Agreement Co-60 1.9910.291E-6 3.452iO.307E-6 0.60 Agreement 2.0710.265E-6 0.61 Agreement Zr-95 5.2510.15BE-5 4.60610.079E-5 1.14 Agreement 5.0710.192E-5 1.10 Agreement Nb-95 6.2410.180E-5 5.36410.055E-5 1.16 Agreement 5.8710.216E-5 1.09 Agreement

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P ATTACHMENT 5 3 FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision Tc-99m 3.19 0.133E-5 4.04610.070E-5 0.80 Agreement 3.3510.138E-5 0.83 Agreement I-131 2.70 0.OB6E-4 2.86110.OO7E-4 0.94 Agreement 2.50iO.103E-4 0.87 Agreement I-132 3.72io.161E-5 3.90310.211E-5 0.95 Agreement 3.87 0.380E-5 0.99 Agreement I-133 7.5210.262E-4 7.762io.014E-4 0.97 Agreement 7.4110.330E-4 0.95 Agreement I-135 3.88iO.104E-4 4.03610.040E-4 0.96 Agreement 3.6910.114E-4 0.91 Agreement Cs-134 8.1810.223E-5 8.52710.066E-5 0.96 Agreement 8.01 0.279E-5 0.94 Agreement Cs-136 7.2110.495E-6 8.227iO.433E-6 0.88 Agreement 6.8710.556E-6 0.84 Agreement Cs-137 1.02 0.031E-4 1.072 0.OO7E-4 0.95 Agreement 1.0110.043E-4 0.94 Ag reemen t Waste Liauid Sample - 4.0 liter Marinelli beaker (Sampled: 08:00, CDT. June 8, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision Co-58 3.85to.125E-6 3.56110.081E-6 1.08 Agreement 3.7510.152E-6 1.05 Agreement Co-60 1.4710.070E-6 1.264 0.061E-6 1.16 Agreement 1.3410.080E-6 1.06 Agreement Ag-110m 1.4610.059E-6 1.38410.077E-6 1.05 Agreement 1.50iO.085E-6 1.08 Agreement Sb-125 7.40iO.321E-6 7.09710.190E-6 1.04 Agreement 7.94iO.387E-6 1.12 Agreement Cs-134 5.9310.492E-7 6.36610.481E-7 0.93 Agreement 6.3310.569E-7 0.99 Agreement Cs-137 2.2110.087E-6 2.OS610.064E-6 1.07 Agreement 2.1610.117E-6

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1.05 Agreement

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ATTACHMENT 5 4 _

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I Containment Atmosobere Sample (RM-050/051) - 1.O~ liter Gas Marinelli l

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beaker (Sampled: 12:00, CDT, June 8, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/cc) (uCi/cc) Ratio Decision Ar-41 5.19115.1E-6 3.98410.137E-6 1.30 Agreement 4.38119.5E-6 1.10 Agreement Kr-85m 2.6Bi5.15E-7 2.557io.192E-7 1.05 Agreement 2.40 18.5E-7 0.94- Agreement Kr-88 2.43i4.31E-7 2.365iO.718E-7 1.03 Agreement 2.96iO.47E-7 1.25 Agreement Xe-131m 4.0917.47E-6 4.13110.729E-6 0.99 Agreement 2.38iO.41E-6 0.58 Agreement Xe-133m 2.17 4.38E-6 2.36410.206E-6 0.92 Agreement 2.1510.15E-6 0.91 Agreement Xe-133 2.1417.13E-4 1.85710.OO6E-4 1.15 Agreement 2.60iO.08E-4 1.40 Disagreement Xe-135 5.65112.3E-6 6.081 0.070E-6 0.93 Agreement 5.8510.23E-6 0.96 Agreement Reactor Coolant Gas Sample - 15cc Gas Vial  ;

(Sampled: 17:05, CDT, June 8, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/cc) (uCi/ce) Ratio Decision Ar-41 1.53 3.44E-2 1.437 0.031E-2 1.07 Agreement 1.3710.10E-2 0.95 Agreement Kr-85m 3.8415.77E-2 3.698 0.015E-2 1.04 Agreement 3.7310.26E-2 1.01 Agreement Kr-87 6.05 12.7E-2 6.90910.049E-2 0.88 Agreement 6.33tO.53E-2 0.91 Agreement Kr-88 7.97 11.OE-2 8.657iO.051E-2 0.92 Agreement 7.80iO.48E-2 0.90 Agreement  ;

Xe-133m 9.67115.3E-3 1.135 0.074E-2 0.85 Agreement 1.12 0.13E-2 O.99 Agreement Xe-133 4.45111.1E-1 4.100iO.OO6E-1 1.08 Agreement 4.4710.43E-1 1.09 Agreement

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ATTACHMENT 5 5

'FCS Results NRC Results FCS/NRC Comp.rison

- Nuclide (uC1/cc) fuCi/cc) Ratio Decision Xe-135m 9.62 17.8E-2 9.043iO.216E-2 1.06 Agreement 9.3610.76E-2 1.04 Agreement Xe-135 2.5314.30E-1 2.89510.OO4E-1 0.87 Agreement 2.43iO.22E-1 0.84 Agreement Xe-138 2.5415.10E-1 2.587to_106E-1 0.98 Agreement

<2.731E-1 (1)

(1) Isotope had decayed to below the lower detectable limit prior to time of analysi . Reactor Coolant'Liouid Sample - aml Liould Vial (Sampled: 17:05, CDT, June 8, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision Na-24 2.22iO.49E-3 3.532iO.155E-3 0.63' Disagreement 3.84 0.51E-3 1.09 Agreement Nb-95m Not in Library 3.897 0.289E-3 -

(1)

Nb-95 <1.95E-3 2.649tO.142E-3 -

(2)

<1.94E-3 (2)

I-131 9.33iO.62E-3 9.OO710.208E-3 1.04 Agreement 8.20 0.70E-3 0.91 Agreement l . I-132 1.59to.07E-1 1.433tO.OO6E-1 1.11 Agreement l 1.3010.07E-1 0.91 Agreement I-133 9.28iO.36E-2 8.823 0.029E-2 1.05 Agreement l 8.63tO.44E-2 0.98 Agreement I-134 2.65iO.07E-1 2.451tO.021E-1 1.08 Agreement 2.3610.08E-1 0.96 Agreement I-135 1.63 0.05E-1 1.54710.012E-1 1.05 Agreement 1.48iO.06E-1 0.96 Agreement l

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ATTACHMENT 5 6 -

J l FCS Results NRC Results FCS/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision I

Cs-134 2.01 0.23E-3 1.908iO.190E-3 1.01 Agreement 1.52iO.14E-3 0.76 Agreement j l

Cs-137 2.8910.75E-3 2.119iO.191E-T 1.36 Agreement i 2.24tO.37E-3 1.06 Agreement i

Cs-138 3.4610.10E-1 3.14610.036E-1 1.10 Agreement !

3.1310.11E-1 0.99 Agreement ,

I Da-139 2.1710.31E-2 2.902iO.097E-2 0.75 Agreement 2.2310.35E-2 0.77 Agreement (1) This isotope was not included in the licensee's isotopic library; therefore, no identification was made 'yo the licensee and no comparison was made by the NR (2) No isotopic peak was identified by the licensee in the analysis spectrum results; therefore, no comparison was mad . Reactor Coolant Tritium Sample (Sampled: 17:05, CDT, June 8, 1989)

FCS Results NRC Results FCS/NRC Comparison Nuclide (uci/ml) (uC1/ml) Ratio pecision H-3 2.5110.02E-01 2.4310.07E-01 1.03 Agree.ent I

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i ATTACHMENT 6

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CRITERTA FOR COMPARING RADIOCHEMISTRY ANALYTICAL MEASUREMENTS

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l The following are the criteria used in comparing the results of )

capability tests and verification measurements. The criteria are l based on an empiriced relationship established through prior  !

experience and *his . program's analytical requirement )

)

In these criteria, the judgement limits vary in relation to the ]

j comparison of the resolutio =

"

Resolution i

NRC UNCER TAINTY

!

LICENSEE VALUE i Ratio = {

NRC VALUE Comparisons are made by first determining the resolution and then reading across the same lino to the corresponding ratio. The f ollowing tabic shows the acceptance value RESOLUTION AGREEMENT RATIO

<4 0.40 - 2.50 4-7 0.50 - 2.00 8- 15 0.60 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

>200 0.85 - 1.18 The above criteria are applied to the following analyses:

(1) Gamma Spectrometry (2) Tritium in liquid samples (3) Iodine on adsorbers (4) Gr and Sr determinations i

(5) Gross Beta where samples are counted on the same date using

! the same reference nuclid . -_____m--..._._.__m_____ _ _ _ . _ . _ _

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ATTACHMENT 7 DOCUMENTS REVIEWED

, Fort Calhoun Station NRC Inspection Report: 50-285/89-25 Title Revision Date '.,tanding Orders (50). ,

50 T-5, Primary Chemistry Summary Report 10 09/21/88 SO T-6, Chemistry Instruction' 6 07/25/88 50 T-7, Secondary Chemistry Summary Report 10 07/18/88 50 T-13, Quality Control Program for Chemistry and '37 11/15/88 Radiation Protection Equipment 50 T-18, Cleaning Agents for Use in the' Auxiliary 2 06/25/85

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Building 50 T-25, Quality Control Program for Evaluating t, 07/25/88 Chemistry Performance 50 T-27, Calibration Procedure /18/88 Chemistry Manual Procedures (CMP)

CMP-1, System Chemical Limits 33 12/15/88 CMP-2, Sample Collection 14 12/09/88 CMP-2.1, Grab Sampling 9 01/07/86-CMP-2.2, Waste Gas Sampling System 4- 11/23/87 CMP-2.3, Composite Sampling Procedure 2 03/02/87 CMP-2.4, Primary Sampling System - Normal Operation 8 12/17/88 CMP-2.5, Secondary Sampling System 4 10/29/88 ;

CMP-3.0, Laboratory Practices - Reagents 5 08/05/88 CMP-3.1, Evaporated Specific Activity Determination 6 10/11/88 CMP-3.5, Determination of Isotopic Specific Activity 5 03/09/87 CMP-3.8, Determination of Hydrogen, Nitrogen, Carbon 10 11/04/88 Dioxide, and Oxygen

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CMP-3.9, Determination of Tritium in Plant Atmospheres 7 09/10/88 CMP-3.10. Determination of Radioactive Particulate and 4 12/09/86 Radioactive Iodine in Air Samples.

i' >

CMP-3.13,l Determination 'of Tritium by Liquid - 12 06/13/88 Scintillation CMP-3.14,' Determination of E-Bar in the Reactor' 6 02/25/87 Coolant CMP-3.19, Determination of Boron 13 11/13/88 CMP-3.21' Determination of pH

, 7 08/08/88

.

CMP-3.22, Measurement of Conductivity 7 11/13/88 CMP-3.23, Determination of Chloride 10 04/20/87 CMP-3.34, Determination of. Dissolved Oxygen 6 01/31/84 CMP-3.36, Determination of Hydrazine 11 10/05/87 CMP-3.38, Determination of Crystallodial Silica 15 08/18/88 CMP-3.43, Determination of Ammonia 11 01/07/88 s' CMP-3.46, Sodium Determination by Flame Emission 8 09/02/88 CMP-3.48, Determination of Trace Metals Using Flameless 5 07/29/88 Atomic Absorption CMP-3.65, Strontium 89-90 Analysis 6 06/13/88 CMP-3.67 Determination of Trace Metals Using Fiame 7 11/26/88 Atomic Absorption CMP-3.87, Determination of Anions by Gradient Ion 0 11/29/88 Chromatography CMP-4.74, Chemistry Quality Control Charts 2 03/31/89 3. Instrument Calibration Procedures (CP)-LAB CP-LAB-19, Canberra Jupiter Ge-Li System 4 10/01/88

CP-LAB-23, Fisher /Titrimeter II - 8oron Titrator 4 03/09/87

CP-LAB-27, Atomic Absorption Spectrophotometer 2 04/11/89 Perkin-Elmer Model 2380

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CP-LAB-42, Hach DR/3000 Spectrophotometer Calibration 7 09/02/88 CP-LAB-48, Perkin-Elmer 5100 Atomic Abs'orption 1 01/22/89 Spectrophotometer Graphite Furnace Calibration CP-LAB-80,- Ion Chromatograph - Dionex 2120i 4 08/25/88 CP-LAB-81, Beckman Liquid Scintillation Spectrometer 2 08/24/87 Series LS 5801 n

CP-LAB-87, Ion Chromatograph;- Dionex 2120i and 4000i 3 03/31/89 CP-LAB-90, Perkin-Elmer 5100 Atomic Absorption -0 04/12/89 Spectrophotometer Flame Section Calibration Chemistry Record Forms FC-214, Reactor' Coolant Summary Report 8 03/30/89 FC-215, Secondary Chemistry Summary Report 7 02/12/88 FC-254, Monthig Chemical Analysis 4 06/30/88 5. Quality Assurance (QA) Surveillance and Audit QA Surveillance Report (QASR), Q-35, C3-88-2, Chemistry Sampling Surveillance Tour, conducted March 24, 1988 QASR, A-11, Diesel Generator Fuel 01i Sa:nple, conducted March 15-30, 1988 QASR, Q-34, C4-88-1, Chemistry Laboratory Surveillance Tour, conducted April 21, 1988 QASR, Q-35, C6-88-3, Chemistry Sampling Surveillance Tour, conducted June 21, 1988 QASR, Q-35, C10-88-7, Chemistry Sampling Surveillance Tour, conducted October 12-13, 1988 QASR, Q-34, Cl-89-2, Chemistry Laboratory and Sampling Tour, conducted January 9-10, 1989 QASR, A-11, P3-89-1, Diesel Generator Fuel Oil Analysis, conducted March 14-16, 1989 QASR, C-1, C1-89-2, Chemistry Laboratory and Sampling Surveillance Tour, conducted May 10 and 16, 198 Safety Audit Review Committee Audit Report 5-88, Chemistry Control Program, conducted August 15-19, 1988.

l

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PRINCIPAL INSPECTOR (Neme. Est. hast gnd frNDOfe mtfril)

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U.S. NUCLEAR REGULATORY COMMISSION

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?E E m S . INSPECTOR,S REPORT ,, y,, ,g  ;

Office of Inspection and Enforcement g,p, yg tN Vt C TOhb L. wlL Bond ,

REPORT W WE M LICENSEE VENDOR $$'[

y DOCKET NO (8 0. gas > 0R LICENSE NO IBY PRODUCTH13 ay, NO SEO MO Y Oh t et b m b l'C O u)w . . X o C o o o AF f Y 9 1 E'^

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FROM TO X 1 - REG'DNAL OFFICE STAFF OTHER mg-WeekN Manpower Reportung ' for Cod)e JEGION DIVISON BRANCH

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MO DAY VR MO DAV YR ' - RESIDENT INSPECTOR 014 olr Tl 4 ol4 ol9 F!9 '-"' ""^*C'^"'"^'S''^* N J f 25 26 31 32 33 84 35

TV PE OF ACTIVITY CONDUCTED (Check one por onev REGIONAL ACTION

'Cwone no. oa+ X 02 - SAFETY 10 PLANT SE INOUIRY J 06 - MGMT. Vimi _ _

03 - INCIDENT 07 - SPECIAL 11 - INVENT. VER IS - INVESTIGATION 1 - NRC FORM 591 08-vfNDOR 12 - SHIPMENT /EXPOR T X 2 REGIONAL OFFICE LE TTER 04 - ENFORCEMENT 05 - MGMT AUDIT 09 - MAT ACCT 13 - tMPOR T 3 B

.N 5F'E CT ION nN v E b T sG A T evN F iNDiN u h iOT AL NUMBER ENFORCEMENT CONFERENCE REPORT CONT AIN 2 790 LETTER OR REPORT TR ANSMITTAL DATE

^*r* aaa has aa'v' INFORMATION OF vlOLATONS AND HELD A D DEV;ATONS BlC NRC FORM S91 REPORT SENT OR REG TO HO FOR X t - CLE AR LETTER ISSUED ACTION 2 - VIOLATION A D MQ DAY YR VR 3 - DEVIATIO'd A B C D Al8 lC lD B C MO.! DAY 4 - VOLATON S DEVIATION gg , , , j l l 1 - YES 1 - VES _ R IN 3U 1% II I I 43 d4 49 SS m 40-d 3 42 SO MODU (E INFDPMA TION MODUlf lN&ORMATiON [, h , N ,

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