IR 05000458/1988006

Attachments 1,2,3,4,5 & 6 to Insp Rept 50-458/88-06

ML20151M794
Person / Time
Site:	River Bend
Issue date:	04/18/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151M763	List: IR 05000458/1988006 ML20151M759
References
50-458-88-06, 50-458-88-6, NUDOCS 8804250130
Download: ML20151M794 (16)

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ATTACHMENT 1 Analvtical Measurements Water Chemistry Confirmatory Measurements During the inspection, standard chemical solutions were provided to the licensee for analysi The standard solutions were prepared by the Brookhaven National Laboratory (BNL), Safety and Environmental Protection Division, for the NR The standards were analyzed by the licensee using routine methods and equipment. The analysis of chemical standards is used to verify the licensee's capability to monitor chemical parameters in various plant systems with respect to In Technical Specification requirements and other industry standard addition, the analyses of standards are used to evaluate the licensee's analytical procedures with respect to accuracy and precisio The results of the measurements comparison are listed in Attachment Attachment 3 contains the criteria used to compare results. All standards were analyzed in triplicat The licensee's original analytical results indicated that 26 of the 30 results were in agreemen The low concentration chloride and fluoride results were orginally found in disagreement and biased low. The licensee's chloride quality control standard read high and the fluoride quality control standard read low. The licensee prepared a new dilution of BNL standard 868 for the low concentration range and reran the chloride and fluoride analyse The rerun result for chloride was in agreement, but the rerun result for fluoride remained in disagreemen The licensee's original high concentration result for nickel was biased low and in disagreemen The nickel quality control standard prepared in the same concentration range as the BNL standard read hig The licensee prepared a new dilution of BNL standard 861 for The rerun the high concentration range and reran the nickel analysi result for nickel showed no change from the original result and was still in disagreement. The licensee's original low concentration the sodium quality control result for sodium was biased low as was standard. The licensee prepared a new dilution of BNL standard 86L for the low concentration range and reran the sodium analysis. The rerun result for sodium was in agreemen The unresolved disagreements are not considered to indicate any significant programmatic problem. The licensee's final analytical results showed 93 percent agreement with the BNL results based on 28 agreement results out of 30 total results compare As part of the inspection, actual inplant samples were split between the licensee and the NRC in order to verify theThe licensee's measurement analyses will be capabilities on actual plant water sample performed by the licensee using their normal analytical methods and instrumentation and by BNL. Upon completion of the analyses by both laboratories, the results will be documented in a subsequent NRC inspection repor {DR ADOCK 05000458 DCD

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2 F3ad iol og ic a l _ Con f.i rma tory _ .Me,asu r_eme_n t s Confirmatory measurements were performed on the following standards and samples in the Region IV mobile laboratory at River Bend Nuclear Station during the inspections (1) Reactor Coolant Liquid Sample (1 liter Marinelli Beaker)

(2) Particulate Filter Standard (24838-109)

(3) Scott Charcoal Cartridge Standard (24841-109)

(4) Liquid Waste Sample (1 liter Marinelli Beaker)

(5) Off Gas Sample (15 cc Off Gas Vial)

(7) Reactor Coolant Tritium Sample The confirmatory measurements tests consisted of comparing measurements made by the licensee and the NRC mobile laboratory. The NRC's mobile laboratory measurements are referenced to the National Bureau of Standards (NBS) by laboratory intercomparison Confirmatory measurements are made only for those 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 Attachment 5 stated in 10 CFR Part 20, Appendix B, Table I contains the criteria used to compare result At the time of the inspection, the licensee utilized two detectors in radiochemistry for comparison with the NRC results. The licensee performed the tritium analysis on their liquid scintillation counting syste The individual sample analyses and comparison of analytical results of the confirmatory measurements are tabulated in Attachment 4, as detectors 1 and The licensee's gamma isotopic results from the listed sanples in Attachment 4 showed 97 percent agreement with the NRC's analysis results. The licensee's tritium result was in agreement with the NRC's analysis resul Confirmatory measurements were perforued by the licensee and a contractor laboratory on two liquid radiochemistry samples prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho j Falls, Idah The samples were provided to the licensee in July 1987.

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The analytical results were compared to the known sample activities and the results of the comparisons are presented in Attachment 4, sample 7. The licensee's results were in agreement with the certified activities for Mn-54, Co-60, Cs-137, and H-3. The contractor laboratory's Sr-90 result was in agreement and the Fe-55 and Sr-89 results were in disagreement with the certified activitie Therefore, the licensee's overall results for the 1987 RESL samples were in 71 percent agreement. Further review of River Bend Station's performance on RESL samples indicated that RBS Fe-55 results The hhve been in disagreement on both the 1986 and 1987 RESL sample disagreements were discussed with the licensee during the exit interview on February 26, 1988, and the licensee agreed to evaluate I the performance of their contractor laboratory on analyzing samples for Fe-5 _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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ATTACHMENT 2 Water Chemistry Confirmatory Measurements Results River Bend Nuclear Station NRC Inspection Report: 50-458/88-06 Chl oride Analysis (5-40 ppb)

RBS Results NRC Resul.ts RBS/NRC Comparison samale detted __1gabt___ __1gabt___ _Bettg_ _Degtatge_

86A IC 8.8710.15 12.10!1.60 0.73 0.10 Disagreement 86B 19.5010.10 18.7010.60 1.0410.03 Agreement 86C 37.5011.10 40.30 1.10 0.9310.04 Agreement Rerun 86B 9.6010.40 9.4010.30 0.9810.05 Agreement Fluoride An al ysi s (5-40 ppb)

RBS Results NRC Results RBS/NRC Comparison Seente Methed __lankl___ __Inakl___ _Bette_ _Dettsten_

86A IC 10.30 0.10 11.6010.30 0.8910.02 Disagreement 86B 20.4010.60 21.80 1.00 0.9410.05 Agreement 86C 39.5010.70 41.80 1.40 0.9410.04 Agreement Rerun 86B 8.2010.20 10.9010.50 0.7510.04 Disagreement Sul f ate Analysi s (5-40 ppb)

RBS Results NRC Results RBS/NRC Comparison Samale dethed __1Rahl___ __innkl___ _Batio_ _DeEtsL90_

86A IC 9.8010.72 10.0010.50 0.9810.09 Agreement 86B 18.17il.20 20.5011.20 0.89 0.08 Agreement 86C 37.80il.50 40.4011.50 0.9310.05 Agreement Baron Anal ysi s (100-500 ppm)

RBS Results NRC Results RBS/NRC Comparison detbed __lanel___ __lunel___ _Bette_ _Dentstge_

Saente 86D PES 100.51 .01 .0010.01 Agreement 86E 306.Bi .41 .0110.02 Agreement 86F 498.91 .71 .0110.01 Agreement IE

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? Iron Analysis (100-500 ppb)

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RBS Results NRC Results RBS/NRC Comparison Esente detben __inabl___ __Innbl___ _Batte_ _DeEtsten_

86G PES 126.81 .3 .0410.08 Agreement 86H 309.01 .3 1 .97iO.04 Agreement 861 466.21 .0 1 .95 0.03 Agreement Cooper Analysis (100-500 ppb)

RBS Results NRC Results RBS/NRC Compari son Seente detbed __Innkl___ __Innkl___ _Bette_ _Dentsten_

86G PES 127.7 .01 .0910.06 Agreement 86H 312.31 .011 .9710.05 Agreement 861 473.11 .312 .9810.04 Agreement Chromium Anal ysi s (100-500 ppb)

RBS Results NRC Results RBS/NRC Comparison Seente dethed __inakt___ __Innb1___ _gattg_ _Degtgige_

86G PES 125.11 .51 7.5 0.9810.06 Agreement 86H 313.61 .711 .0010.04 Agreement 861 460.1 .712 .97 0.05 Agreement Nickel Anal ysi s (100-500 ppb)

RBS Results NRC Results RBS/NRC Comparison

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l l 86G PES 131.11 .31 6.5 1.03 0.05 Agreement

! B6H 319.3 .011 .9410.03 Agreement 86I 472.71 .011 .9310.02 Disagreement Rerun 86I 475.311.03 510.0 1 .93io.02 Disagreement Sodium Anal vsi s (10-50 ppb)

RBS Results NRC Results RBS/NRC Comparison Seente dethed __innkl___ __lankt___ _Battg_ _DegLsige_

86J IC 4.87 0.35 9.20 1.00 O.53io.07 Disagreement 86K 19.3011.60 18.5011.60 1.0410.12 Agreement 86L 49.60iO.30 48.0012.70 1.03 0.06 Agreement Rerun 86L 12.9010.90 11.5011.30 1.1210.15 Agreement

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1 Silica Anal ysi s (5-500 ppb).

RBS Results NRC Results RBS/NRC Comparison 4 Samele Methed __lankl___ __innkl___ _Batte_ _Dectsten_ l 86S SPEC 25.8 0.70 27,2 2.8 0.95i0.10 Agreement 86T 108.310.60 109.01 .99iO.06 Agreement 1 86U 323.3 2.56 35).O 1 .01 0.03 Agreement

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Analysis Method Definitions:

Ion Chromatograph - IC Plazma Emission Spectroscopy - PES Atomic Absorption Graphite Furnace - AAGF Atomic. Absorption Flame - AAF Selective Ion Electrode - SIE Manitol Titration - MT Spectroscopy - SPEC

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CB1IEB10_EQB_CQUEBB100_8096YIIC9L_DEeSUSEdENIS This attachment provides criteria f or comparing results of capability test In these criteria the judgement limits are based on the uncertainty of the ratio of the licensee's value to the NRC valu The f ollowing steps are perf ormed (1)

The ratio of the licensee's value to the NRC value i s cooputed

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Licensee's Value ); and (ratio 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 agreemen (l1-ratio l 1 2 x uncertainty)

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z- , enen y2 y Z2 x2 1(From: Bevington, P. R., Data Reduction and Error Analysis f or the Physical Sciences, McGraw-Hill, New York, 1969)

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L eII8GddENI_4 Radiolooical Confirmatory Measuresment Results River Bend Nucl ear Station

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NRC Inspection Report: 50-458/88-06 Reactor Coolant Licuid Samole (1 liter Marinelli Beaker)

(Sampled: 08:00, CST, February 25, 1988)

RBS Results NRC Results RBS/NRC Comparison Nyglidg _J991/911__ _Jygiggll__ _Sailg_ _pggisige_

Na-24 5.962E-3 5.60910.025E-3 1.06 Agreement 5.717E-3 1.02 Agreement Cr-51 4.053E-3 3.547dO.072E-3 1.14 Agreement 3.614E-3 1.02 Agreement Mo-99 2.563E-4 2.471io.382E-4 1.04 Agreement 2.179E-4 0.88 Agreement Tc-99m 4.343E-3 4.28810.012E-3 1.01 Agreement 3.909E-3 0.91 Agreement Rh-105 2.093E-3 1.84110.038E-3 1.14 Agreement 1.889E-3 1.03 Agreement I-132 3.556E-4 3.346tO.148E-4 1.06 Agreement 3.249E-4 0.97 Agreement I-133 2.408E-4 2.21010.053E-4 1.09 Agreement 2.218E-4 1.00 Agreement 1-134 1.145E-3 1.360iO.064E-3 0.84 Agreement 1.069E-3 0.79 Agreement I-135 5.OO4E-4 a.84110.349E-4 1. ' 3 Agreement 4.951E-4 1.02 Agreement Particulate Filter Standard (47 mm Filter 24838-109)

(Standardized: 08:00, CST, February 22, 1988)

RBS Results NRC Results RBS/NRC Comparison Uus11de lyGileamalel lyGilSeenlel _Bati9_ _Desisi90_

Cd-109 1.227E+0 1.04110.OO3E+0 1.18 Agreement 1.180E+O 1.13 Agreement Co-57 3.OO9E-2 2.43110.010E-2 1.24 Disagreement 2.826E-2 1.16 Agreement ,

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Particulate Filter Standard Cont'd RBS Results NRC Results .RBS/NRC Comparison NugLtde fuGLL@gmRLEl IWGLdEEGELEl _BatLg_ _Qegistgg_

Ce-139 1.849E-2 1.59110.OO9E-2 1.16 Agreement 1.771E-2 1.11 Agreement Hg-203 1.190E-2 9.90110.107E-3 1.20 Agreement 1.115E-2 1.13 Agreement Sn-113 2.848E-2 2.45810.022E-2 1.16 Agreement 2.7BOE-2 1.13 Agreement l Cs-137 5.374E-2 4.546 0.031E-2 1.18 Agreement 5.232E-2 1.15 Agreement Y-88 3.579E-2 3.09510.n31E-2 1.16 Agreement 3.516E-2 1.14 Agreement Co-60 4.542E-2 4.01410.036E-2 1.13 Agreement 4.517E-2 1.13 Agreement 1 Scott Charcoal Cartridae Standard (Cartridae 24841-109)

(Standardized: 08:00, CST, February 22, 1988)

RBS Results NRC Results RBS/NRC Comparison Ngglidg lygid@geglel iggif@gegLgl _Bellg_ _QggLstge_

Cd-!O9 1.120C+O 1.02610.OO4E+0 1.09 Agreement 1.228E+0 1.20 Agreement l

l Co-57 2.678E-2 2.376 0.014E-2 1.13 Agreement l 2.897E-2 1.22 Agreement l

Ce-139 1.713E-2 1.55910.012E-2 1.10 Agreement 1.835E-2 1.18 Agreement l

Hg-203 1.201E-2 1.01010.015E-2 1.19 Agreenent 1.207E-2 1.20 Agreement Sn-113 2.618E-2 2.38110.025E-2 1.10 Agreement 2.741E-2 1.15 Agreement t Cs-137 4.925E-2 4.458 0.036E-2 1.10 Agreement l

5.198E-2 1.17 Agreement Y-88 3.327E-2 3.00710.037E-2 1.11 Agreement

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3.427E-2 1.14 Aqreement Co-60 4.212E-2 3.835 0.041E-2 1.10 Agreement 4.503E-2 1.17 Agreement

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! Licuid Waste Sample (1 liter Marinelli Beaker)

(Sampled: 02:07, CST, February 26, 1988)

RBS Results NRC Results RBS/NRC Comparison Nyclide- _Jugifmii__ _JyCifmii__ _Bgilg_ _Deg131gn_

Na-24 1.152E-1 1.12610.OO9E-1 1.02 Agreement 1.114E-1 0.99 Agreement Cr-51 3.672E-2 3.434to.128E-2 1.07 Agreement 3.290E-2 0.96 Agreement Mn-54 2.OO9E-2 2.112 0.037E-2 0.95 Agreement 1.681E-2 0.80 Agreement Co-58 6,247E-3 6.052io.254E-3 1.03 Agreement 5.130E-3 0.85 Agreement Fe-59 1.849E-3 2.400io.564E-3 0.77 Agreement 1.515E-3 0.63 Agreement Co-60 5.211E-2 5.43310.055E-2 0.96 Agreement 4.427E-2 0.81 Agreement Zn-65 1.205E-2 1.209 0.083E-2 1.00 Agreement 1.089E-2 0.90 Agreement Tc-99m 3.051E-2 3.42010.033E-2 0.89 Agreement 3.056E-2 0.89 Agreement Sb-122 1.093E-3 9.73212.110E-4 1.12 Agreement 8.036E-4 0.83 Agreement I-133 3.558E-3 3.06410.213E-3 1.16 Agreement 3.262E-3 1.06 Agreement Off Gas Samole (15cc Off Gas Vi all (Sampled: 10:48, CST, February 25, 1988)

RBS Results NRC Results RBS/NRC Comparison Nygilde _Jygifggi__ _Jygifggi__ _Sglig_ _Degigigg, Ar-41 1.183E-4 1.040iO.167E-4 1.14 Agreement 9.779E-5 0.94 Agreement i

Kr -85m 2.07BE-4 2.40810.053E-9 0.86 Agreement 1.898E-4 0.74 Agreement I

Kr-87 1.309E-3 1.52510.049E-3 0.86 Agreement 1.185E-3 0.70 Agreement l

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Kr-88 8.120E-4 8.55710.219E-4 0.95 Agreement 6.849E-4 0.80 Agreement

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Off Gas Sample Cont'd RBS Results NRC Results RBS/NRC Comparison UustLde luGLLgamalet lugi Lgamalet _gattg_ _Decistgg_

Xe-133 4.752E-5 4.172 0.476E-5 1.14 Agreement C.526E-5 0.85 Agreement Xe-135 6.254E-4 7.622 0.077E-4 0.82 Agreement 5.839E-4 0.77 Disagreement Bea c tet_Qggl get_T;i t ium_ga mgle _12O_m L_Sc Lat i lla t i gg_Vlall (Sampled: 08:00, CST, February 25, 1988)

RBS Results NRC Results RBS/NRC Comparison UusLtde _lugLLett__ _lugitmLt__ _Bette_ _Degtglgg_

H-3 3.29iO.09E-4 4.0410.05E-4 0.81 Agreement RESL Unknown Liould Samole (Standardized: 12:00, MST, January 11, 1987)

l RBS Results NRC Results RBS/NRC Comparison Nuclide _lugilmil__ _1gCitmil__ _Batig_ _Degisigg_

Mn-54 2.33E-5 2.0810.04E-5 1.12 Agreement l

l Co-60 2.18E-5 2.00 0.04E-5 1.09 Agreement l

l Cs-137 3.30E-5 2.9310.09E-5 1.13 Agreement j

Fe-55 8.80 0.2E-5 6.26iO.13E-5 1.41 Disagreement l

Sr-89 1.OOiO.1E-4 1.40iO.04E-4 0.71 Disagreement Sr-90 1.20io.1E-5 1.2710.05E-5 0.94 Agreement H-3 1.01E-4 1.02iO.02E-4 0.99 Agreement Fe-59 4.9810.20E-6 NRC results were taken from the standard certification supplied to the NRC Region IV office as prepared by RESL and traceable to the National Bureau of Standard l

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BIIOCUDESI_b CB1IEB10_E0B_CQbB0810G_0NOLYIICOL_DEOSUBEdENIE The f ollowing are the criteria used in comparangThe thecriteria results ofare ccpability tests and verification measurement boced on an empirical relationship established through prior oxperience and this program's analytical requirement In these criteria, the judgement limits vary in relation to the

i comparison of the resolutio R ALUE

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Resolution NRC UNCERTAINTY

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LICENSEE VALUE Ratio NRC VALUE Ccmparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio. The f ollowing table shows the acceptance value AGREEMENT RATIO RESOLUTION

<4 0.40 - 2.50 4-7 0.50 - 2.00 0- 15 0.60 - 1.66 0.75 - 1.33 16 - 50 0.80 - 1.25 51 - 200 0.95 - 1.18

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

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(1) Gamma Spectrometry

(2) Tritium in liquid samples (3) Iodine on adsorbers O

(4) Se and Sr determinations .

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

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ATTACHMENT 6 Documents Reviewed River Bend Nuclear Station NRC Inspection Report 50-458/88-06 Title Revision Date Administrative Procedures (ADM)

ADM-0001, Station Staff Organization, 2 05/03/85 Responsibilities and Authorities ADM-0007, Selection, Training, Qualification, 3 01/10/86 and Evaluation of Plant Staff Personnel ADM-0015, Station Surveillance Test Program 11 09/14/87 ADM-0042, Conduct of Chemistry 4 10/21/87 Chemistry Section Procedures (CSP)

CSP-0003, Chemistry Personnel Qualifications 4 12/10/87 CSP 0100, Chemical / Radiochemical Technical 6 02/12/88 Specification Surveillances CSP-0101, Chemical / Radiochemical Non-Technical 3 09/25/87 Specification Surveillancec CSP-0102, Chemistry Analytical and Instrument 4 02/12/88 Performance Control Program CSP-0104, Preparation of Reagents 0 06/24/86 CSP-0120, Counting Room Instrument Surveillance 3 09/16/87 CSP-0121, Chemistry Laboratory Instrument 2 06/15/87 Surveillance CSP-0127, Analytical Methods Performance 2 06/15/87 Surveillance Chemistry Operating Pr(cedures (COP)

COP-0001, Sampling via Various Balance-of-Plant 3 08/20/87 ( Sample Panels COP-0007, Sampling the Off-Gas Treatment Sample 5 07/16/87 Panels

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COP-0032, Sampling via the Reactor Water Sample 3 04/09/86 Panel 1G33-PNLZ020 COP-C202, Operation of the Beckman Visible 2 11/15/85 Spectrophotometer, Model DU-6 COP-0203, Operation of Dionex High Performance 2 06/17/87 Ion Chromatograph Series 2000 COP-0223, Operation of Beckman Direct Current 0 09/22/87 Plazma Spectrometer, Spectro-Span VI COP-0301, Operation of the Beckman Liquid 2 07/02/85 Scintillation Counter, Series LS-3800 COP-0303, Operation of the Canberra Multichannel 3 03/10/87 Analyzer, Series 90 C0P-0415, Determination of Low-Range Chloride- 3 08/18/87

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Specific Ion Electrode Method COP-0416, Determination of Fluoride - Electrode 4 09/10/87 Method COP-0420, Determination of Silica - Photometric 2 03/18/87 Method COP-0424, Determination of Elements - Plazma 1 04/07/87 Emission Method COP-0602, Analysis of Aqueous Samples for Tritium 5 01/06/88 COP-0608, Determination of Radioiodines - Iodine 0 06/18/87 Separation Method COP-0612, Cetermination of Beta Activity 3 09/02/87 COP-0613, Determination of Alpha Activity 3 09/05/87 COP-0619, Gama Isotopic Analysis Sample 3 01/28/87 Preparation COP-0803, Energy Calibration of the Gamma 3 07/15/87 Spectroscopy MCA System (Stand Alone)

COP-0804, Determination of Gamma Spectroscopy 2 04/22/87

"a Priori" Lower Limits of Detection (LLD)

COP-0805, Verification of the Gamma Spectrometer 3 09/10/87 Efficiency Calibration a

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C0P 0806, Energy Calibration of the Gamma 4 01/28/87 Spectroscopy MCA System (APOGEE)

COP-0807, Efficiency Calibration of the Gamma 2 07/16/87 Spectroscopy MCA System (Stand Alone)

COP-0808, Efficiency Calibration of the Gamma 4 01/20/88 Spectroscopy MCA System (APOGEE)

COP-1000, Post Accident Sampling System 1 09/16/87 Operability verification COP-1001, Post Accident Sampling of Liquid 4 10/01/87 Samples COP-1002, Post Accident Sampling of 5 09/16/87 Containment /Drywell Atmosphere COP-1003, Post Accident Sampling of Gaseous 2 09/17/87 Effluents COP-1004, Post Accident Sampling of Liquid 4 12/19/87 Effluents COP-1006, Post Accident Transportation of Large 3 09/11/87 Volume Cask COP-1010, Preparation of Primary Coolant Sample 3 01/18/88 for Post Accident Analysis COP-1011, Preparation of PAS Containment 3 01/15/88 Atmosphere for Post Accident Analysis COP-1012, Preparation of Gaseous Effluent Sample 3 01/08/88 for Post Accident Analysis COP-1013, Preparation of Liquid Effluent Sample 3 01/06/88 for Post Accident Analysis COP-1020, Post Accident Boron Analysis - Plazma 3 01/25/88 Emission Method COP-1021, Post Accident Chloride Analysis 4 01/15/88 COP-1022, Post Accident Hydrogen Analysis of the 1 07/02/85 Containment Atmosphere COP-1023, Post Accident pH Analysis 4 12/16/87 COP-1030, Post Accident Isotopic Analysis for 3 10/19/87 Particulate, Iodine Gaseous Activity Lm -

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COP-1031, Post t.ccident Dissovled Gas Analysis 3 02/02/88 COP-1033, Post Accident Liquid Isotopic Analysis 3 10/05/87 COP-1047, Post Accident Initiation of Site and 4 01/18/88 Backup Laboratory Facilitics COP-1048, Post Accident Sample Transoort to the 3 01/12/88 Backup Facility COP-1050, Post Accident Estimation of Fuel Core 2 05/19/85 Damage 4. Nuclear Trainin_q Department TTP-7-017, Nuclear Chemistry Technician Training 1 99/17/87 Program 1988 Chemistry Training Schedule 5 01/05/88 CT-018-0, Lesson Plan - Chenistry Department 02/08/88 Policies and Procedures CT-040-0, Lesson Plan - Post Accident Gaseous 10/06/87 Sample Collection CT-041-0, Lesson Plan - Post Accident Large 10/06/87 Volume Sample Collection CT-042-0, Lesson Plan - Post Accident Small 10/06/87 Volume Sample Collection CT-089-1, lesson Plan - Post Accident Sampling 01/11/88 System Overview 5. Quality Assurance Audits and Surveillances QA Audit Report: Eberline Corporation Instrument Division, dated July 9, 1984

! QA Audit Report: 87-05-I-CHEM, "Chemistry Program," dated May 15, 1987 QA Surveillance Report: 05-87-02-04, "Conduct of Chemistry," dated February 6, 1987 QA Surveillance Report: 05-87-03-08, "Standby Cooling Tower Water,"

dated March 12, 1987 QA Surveillance Report: 05-87-03-06, "Plant Chemistry," dated March M ,

1987

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l QA Surveillance Report: 05-87-05-03, "PAS System Training," dated May 5, (. 1987 l

l QA_ Surveillance Report: 05-87-06-26, "0; erability of PASS to Obtain l

Reactor Water Sample," dated June 18, 1987 QA Surveillance Report: '05-87-06-30, "Conduct of Chemistry," dated l

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QA Surveillance Report: 05-87-09-31, "PASS Operability," dated September 16, 1987 i QA Surveillance Report: 05-88-01-36, "Conduct of Chemistry," dated January 28, 1988 l

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