IR 05000458/1988006

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Attachments 1,2,3,4,5 & 6 to Insp Rept 50-458/88-06
ML20151M794
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/18/1988
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151M763 List:
References
50-458-88-06, 50-458-88-6, NUDOCS 8804250130
Download: ML20151M794 (16)


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ATTACHMENT 1 Analvtical Measurements 1.

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 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 standards.

addition, the analyses of standards are used to evaluate the licensee's analytical procedures with respect to accuracy and precision.

The results of the measurements comparison are listed in Attachment 2.

Attachment 3 contains the criteria used to compare results.

All standards were analyzed in triplicate.

The licensee's original analytical results indicated that 26 of the 30 results were in agreement.

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 analyses.

The rerun result for chloride was in agreement, but the rerun result for fluoride remained in disagreement.

The licensee's original high concentration result for nickel was biased low and in disagreement.

The nickel quality control standard prepared in the same concentration range as the BNL standard read high.

The licensee prepared a new dilution of BNL standard 861 for the high concentration range and reran the nickel analysis.

The rerun 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 agreement.

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 compared.

As part of the inspection, actual inplant samples were split between the licensee and the NRC in order to verify the licensee's measurement capabilities on actual plant water samples.

The analyses will be 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 report.

8804250130 880419

{DR ADOCK 05000458 DCD

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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 intercomparisons.

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 stated in 10 CFR Part 20, Appendix B, Table II.

Attachment 5 contains the criteria used to compare results.

At the time of the inspection, the licensee utilized two detectors in The licensee radiochemistry for comparison with the NRC results.

performed the tritium analysis on their liquid scintillation counting system.

The individual sample analyses and comparison of analytical results of the confirmatory measurements are tabulated in Attachment 4, as detectors 1 and 2.

isotopic results from the listed sanples in The licensee's gamma showed 97 percent agreement with the NRC's analysis Attachment 4 results.

The licensee's tritium result was in agreement with the NRC's analysis result.

the licensee and a Confirmatory measurements were perforued by contractor laboratory on two liquid radiochemistry samples prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho j

Falls, Idahc.

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 activities.

Therefore, the licensee's overall results for the 1987 RESL samples were in 71 percent agreement.

Further review of River Bend Station's that RBS Fe-55 results hhve been performance on RESL samples indicated in disagreement on both the 1986 and 1987 RESL samples.

The disagreements were discussed with the licensee during the exit interview on February 26, 1988, and the licensee agreed to evaluate the performance of their contractor laboratory on analyzing samples I

for Fe-55.

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ATTACHMENT 2 Water Chemistry Confirmatory Measurements Results River Bend Nuclear Station NRC Inspection Report: 50-458/88-06 1.

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 2.

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 3.

Sul f ate Analysi s (5-40 ppb)

RBS Results NRC Results RBS/NRC Comparison Samale dethed

__1Rahl___

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_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 4.

Baron Anal ysi s (100-500 ppm)

RBS Results NRC Results RBS/NRC Comparison Saente detbed

__lanel___

__lunel___

_Bette_

_Dentstge_

86D PES 100.510.5 100.011.0 1.0010.01 Agreement 86E 306.Bil.O 302.414.6 1.0110.02 Agreement 86F 498.911.3 494.716.1 1.0110.01 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___

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_Batte_

_DeEtsten_

86G PES 126.811.8 122.3 8.8 1.0410.08 Agreement 86H 309.014.6 318.3 11.3 0.97iO.04 Agreement 861 466.214.0 490.0 14.0 0.95 0.03 Agreement 6.

Cooper Analysis (100-500 ppb)

RBS Results NRC Results RBS/NRC Compari son Seente detbed

__Innkl___

__Innkl___

_Bette_

_Dentsten_

86G PES 127.7 1.9 117.01 6.0 1.0910.06 Agreement 86H 312.312.2 322.0116.3 0.9710.05 Agreement 861 473.112.7 483.3120.0 0.9810.04 Agreement 7.

Chromium Anal ysi s (100-500 ppb)

RBS Results NRC Results RBS/NRC Comparison Seente dethed

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_gattg_

_Degtgige_

86G PES 125.111.8 127.51 7.5 0.9810.06 Agreement 86H 313.615.8 313.7110.0 1.0010.04 Agreement 861 460.1 1.5 476.7126.7 0.97 0.05 Agreement 8.

Nickel Anal ysi s (100-500 ppb)

RBS Results NRC Results RBS/NRC Comparison

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Seente detbed

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_Bette_

_DenteL90_

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86G PES 131.110.6 127.31 6.5 1.03 0.05 Agreement

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B6H 319.3 1.5 340.0110.0 0.9410.03 Agreement 86I 472.712.1 510.0113.3 0.9310.02 Disagreement Rerun 86I 475.311.03 510.0 13.3 0.93io.02 Disagreement 9.

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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Silica Anal ysi s (5-500 ppb).

RBS Results NRC Results RBS/NRC Comparison

Samele Methed

__lankl___

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_Batte_

_Dectsten_

86S SPEC 25.8 0.70 27,2 2.8 0.95i0.10 Agreement 86T 108.310.60 109.01 7.0 0.99iO.06 Agreement

86U 323.3 2.56 35).O 10.0 1.01 0.03 Agreement

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Analysis Method Definitions:

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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 provides criteria f or comparing results of capability This attachment tests.

In these criteria the judgement limits are based on the uncertainty of the ratio of the licensee's value to the NRC value.

The f ollowing steps are perf ormed (1)

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

); and (ratio

=

NRC VALUE (2)

the uncertainty of the ratio is propagated.

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 1 2 x uncertainty)

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Data Reduction and Error Analysis f or the 1(From:

Bevington, P.

R.,

Physical Sciences, McGraw-Hill, New York, 1969)

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eII8GddENI_4 Radiolooical Confirmatory Measuresment Results River Bend Nucl ear Station

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NRC Inspection Report: 50-458/88-06 1.

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 2.

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

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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__

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_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 5.

Off Gas Samole (15cc Off Gas Vi all (Sampled:

10:48, CST, February 25, 1988)

RBS Results NRC Results RBS/NRC Comparison Nygilde

_Jygifggi__

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_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 6.

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 7.

RESL Unknown Liould Samole (Standardized:

12:00, MST, January 11, 1987)

l RBS Results NRC Results RBS/NRC Comparison Nuclide

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l Mn-54 2.33E-5 2.0810.04E-5 1.12 Agreement Co-60 2.18E-5 2.00 0.04E-5 1.09 Agreement l

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Cs-137 3.30E-5 2.9310.09E-5 1.13 Agreement Fe-55 8.80 0.2E-5 6.26iO.13E-5 1.41 Disagreement j

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 Standards.

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BIIOCUDESI_b CB1IEB10_E0B_CQbB0810G_0NOLYIICOL_DEOSUBEdENIE The f ollowing are the criteria used in comparang the results of The criteria are ccpability tests and verification measurements.

boced on an empirical relationship established through prior oxperience and this program's analytical requirements.

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

i comparison of the resolution.

R ALUE Resolution

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NRC UNCERTAINTY LICENSEE VALUE Ratio

=

NRC VALUE Ccmparisons are made by first determining the resolution and then The reading across the same line to the corresponding ratio.

f ollowing table shows the acceptance values.

AGREEMENT RATIO RESOLUTION 0.40 - 2.50

<4 0.50 - 2.00 4-7 0.60 - 1.66 0- 15 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

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

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ATTACHMENT 6 Documents Reviewed River Bend Nuclear Station NRC Inspection Report 50-458/88-06 Title Revision Date 1.

Administrative Procedures (ADM)

ADM-0001, Station Staff Organization,

05/03/85 Responsibilities and Authorities ADM-0007, Selection, Training, Qualification,

01/10/86 and Evaluation of Plant Staff Personnel ADM-0015, Station Surveillance Test Program

09/14/87 ADM-0042, Conduct of Chemistry

10/21/87 2.

Chemistry Section Procedures (CSP)

CSP-0003, Chemistry Personnel Qualifications

12/10/87 CSP 0100, Chemical / Radiochemical Technical

02/12/88 Specification Surveillances CSP-0101, Chemical / Radiochemical Non-Technical

09/25/87 Specification Surveillancec CSP-0102, Chemistry Analytical and Instrument

02/12/88 Performance Control Program CSP-0104, Preparation of Reagents

06/24/86 CSP-0120, Counting Room Instrument Surveillance

09/16/87 CSP-0121, Chemistry Laboratory Instrument

06/15/87 Surveillance CSP-0127, Analytical Methods Performance

06/15/87 Surveillance 3.

Chemistry Operating Pr(cedures (COP)

COP-0001, Sampling via Various Balance-of-Plant

08/20/87 (

Sample Panels COP-0007, Sampling the Off-Gas Treatment Sample

07/16/87 Panels

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COP-0032, Sampling via the Reactor Water Sample

04/09/86 Panel 1G33-PNLZ020 COP-C202, Operation of the Beckman Visible

11/15/85 Spectrophotometer, Model DU-6 COP-0203, Operation of Dionex High Performance

06/17/87 Ion Chromatograph Series 2000 COP-0223, Operation of Beckman Direct Current

09/22/87 Plazma Spectrometer, Spectro-Span VI COP-0301, Operation of the Beckman Liquid

07/02/85 Scintillation Counter, Series LS-3800 COP-0303, Operation of the Canberra Multichannel

03/10/87 Analyzer, Series 90 C0P-0415, Determination of Low-Range Chloride-

08/18/87 Specific Ion Electrode Method

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COP-0416, Determination of Fluoride - Electrode

09/10/87 Method COP-0420, Determination of Silica - Photometric

03/18/87 Method COP-0424, Determination of Elements - Plazma

04/07/87 Emission Method COP-0602, Analysis of Aqueous Samples for Tritium

01/06/88 COP-0608, Determination of Radioiodines - Iodine

06/18/87 Separation Method COP-0612, Cetermination of Beta Activity

09/02/87 COP-0613, Determination of Alpha Activity

09/05/87 COP-0619, Gama Isotopic Analysis Sample

01/28/87 Preparation COP-0803, Energy Calibration of the Gamma

07/15/87 Spectroscopy MCA System (Stand Alone)

COP-0804, Determination of Gamma Spectroscopy

04/22/87

"a Priori" Lower Limits of Detection (LLD)

COP-0805, Verification of the Gamma Spectrometer

09/10/87 Efficiency Calibration a

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C0P 0806, Energy Calibration of the Gamma

01/28/87 Spectroscopy MCA System (APOGEE)

COP-0807, Efficiency Calibration of the Gamma

07/16/87 Spectroscopy MCA System (Stand Alone)

COP-0808, Efficiency Calibration of the Gamma

01/20/88 Spectroscopy MCA System (APOGEE)

COP-1000, Post Accident Sampling System

09/16/87 Operability verification COP-1001, Post Accident Sampling of Liquid

10/01/87 Samples COP-1002, Post Accident Sampling of

09/16/87 Containment /Drywell Atmosphere COP-1003, Post Accident Sampling of Gaseous

09/17/87 Effluents COP-1004, Post Accident Sampling of Liquid

12/19/87 Effluents COP-1006, Post Accident Transportation of Large

09/11/87 Volume Cask COP-1010, Preparation of Primary Coolant Sample

01/18/88 for Post Accident Analysis COP-1011, Preparation of PAS Containment

01/15/88 Atmosphere for Post Accident Analysis COP-1012, Preparation of Gaseous Effluent Sample

01/08/88 for Post Accident Analysis COP-1013, Preparation of Liquid Effluent Sample

01/06/88 for Post Accident Analysis COP-1020, Post Accident Boron Analysis - Plazma

01/25/88 Emission Method COP-1021, Post Accident Chloride Analysis

01/15/88 COP-1022, Post Accident Hydrogen Analysis of the

07/02/85 Containment Atmosphere COP-1023, Post Accident pH Analysis

12/16/87 COP-1030, Post Accident Isotopic Analysis for

10/19/87 Particulate, Iodine Gaseous Activity Lm

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COP-1031, Post t.ccident Dissovled Gas Analysis

02/02/88 COP-1033, Post Accident Liquid Isotopic Analysis

10/05/87 COP-1047, Post Accident Initiation of Site and

01/18/88 Backup Laboratory Facilitics COP-1048, Post Accident Sample Transoort to the

01/12/88 Backup Facility COP-1050, Post Accident Estimation of Fuel Core

05/19/85 Damage 4.

Nuclear Trainin_q Department TTP-7-017, Nuclear Chemistry Technician Training

99/17/87 Program 1988 Chemistry Training Schedule

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

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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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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

July 3, 1987

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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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