ML20238C672
| ML20238C672 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/30/1987 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1588, NUDOCS 8709100292 | |
| Download: ML20238C672 (19) | |
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY - JUNE 1987 I
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jV B709100292 870630 PDR ADOCK 05000403 I
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4 TABLE OF CONTENTS l i
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0
SUMMARY
OF GASE0US RADIOACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTES SHIPMENTS 6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual i
6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation Table 1A Semiannual Summation of Gaseous Releases Table IB Semiannual Airborne Continuous and Batch Releases Table 2A Semiannual Summation of Liquid Releases Table 2B Semiannual Liquid Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments .
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1.0 INTRODUCTION
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' i This Semiannual Radioactive Effluent Release Report for Union Electric Company's Callaway Plant is submitted in accordance L with the requirements of Technical Specification 6.9.1.7. The )
report covers the period from January.1, 1987 through June 30, j 1987.
This report includes a summary of the quanities of radioactive
. liquid and gaseous effluents and solid waste released from the plant. The information is presented in accordance with the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, I June 1974.
All liquid and gaseous effluents discharged during this reporting period were in compliance with the limits of the Callaway Plant l Technical Specifications.
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b 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta l radiation and, j
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiat. ion and less than or equal to 20 mrad for beta radiction.
2.1.2 Radiciodine, Tritium, and Particulate The dose rate due to Iodine 131 and 133, tritium and all radionuclides in particulate form with half lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ.
The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
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,a 2.1.3 Liquid Effluents The concentration of radioactive material released in liquid i effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, ,
Column 2 for radionuclides other than dissolved or entrained noble 4 gases. . For dissolved or entrained noble gases, the concentration ? _g s hall be limited to 2.0E-04 microcuries/ml total activity. A
,i The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall !- ,
be limited-
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- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and 'l
- b. During any calendar year to less than or equal to 3 mrem to the ,
whole body and to less than or eqt.a1 to 10 mrem to any organ.
2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
2.2' Maximum Permissible Concentrations 2.2.1 The maximum permissible concentration values specified in 10CFR20,
' Appendix B, Table II, Column 2 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
2.2.2 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of' dose rate at the unrestricted area boundary.
2.3 Average Energy This is not applicable to the Callaway Plant's radiological effluent
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ted' specifications.
2.4 Measure..n. and Approximations of Total Radioactivity l The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Table 4.11-1 and Table 4.11-2 of the Callaway Plant Technical Specifications (See NUREG-1058, " Technical Specifications, Callaway Plant, Unit No. 1" (October, 1984)).
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Gar::ma spectroscopy was the primary analysis technique used to j determine the radionuclides composition and concentration of 9 liquid and pseous effluents. Cocposite samples were analy=ed l'
, , ' for Sr-89f Sr-90, and Fe-55 by an independent laboratory.
,-. Tritium 'aod alpha were measured for both liquid and gaseous l f.r . {!..
I effluit:s ur.,ing liquid scintillation counting and gas flow J '
/g 4, proportional counting techniques, respectively.
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,ji Th@ total radioactivity in effluent releases was determined
" 5 s from the measured concentrations of each radionuclides present
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Gross beta or
, and the total volume of effluents discharged.
gamma radioact.1vity measurement techniques were not. utilized / l a
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to approximate the total radioactivity in ef fluencs, ,
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~l 2.5 Hatch Releaseg ,
I 2.5.1 Liquia ' D 'h' '\
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2.5.1.1 '
Wumber of, hatch. releasen: ,146 ;)
Total time period for badri releases: 37426 minutes (
2.~5.1.2 i-a '
.h Maximum time period for a hatch releasea 1031 ninutes t
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2.$.123 t a s 2.5.1.4 Avehage time period for batch 2:eleases: ~ 322.6 minutes 2.5.1.5 Thhm time period for a bacch release: 148 minutes 2.5.1.6 Average,/ -
r .tream fl. ev during periods 'of release of effluent into a flowing. stream: 69,000 cf s
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Gaseous 2.5.2.1 Number of batch releases: 59' 2.5.3.1.1 Inludes 5 Spring Outage hatch releases 2.5.2.2 hochi time period for hatch rel' eases: 4E910 minutes
. Includes 41239 m'inutes of Spring Outage batch releases 2.5.2.1.2
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29482 minutes 2.5.2.3 Maximum time period for a batch t.elease:
2.5.2.3.1 Maximum tied period for,a bacciqrelease other than the Spring Oatage: 2 8 minutes .
2.5.2.4. Average time period. for batch oliases: 845.9 minutes the Spring 2.5.2.4.1 Average time penir.1 for batch releases without Catage: 155 minutes i i
2.2.2.5 Minimum time period f or a bate': release: 28 minutes ,
2.6 Abnormal Releases ,
2.6.1 Liquid <<
0 2.6.1.1 Number of releases:
Total Activity released: 0 2.6.1.2 T 4
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2.6.2 Gaseous l
'2.6.2.1 Number of releases: 2 2.6.2.2 Total Activity released: 1.93 Ci
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3.0
SUMMARY
OF GASEOUS RADI0 ACTIVE EFFLUENTS l l
3.1 The quantities of radioactive material released in gaseous effluents 3 are summarized in Table 1A and IB. Note that for this reporting l period no gaseous effluents were considered as elevated releases.
4.0
SUMMARY
OF LIQUID RADI0 ACTIVE EFFLUENTS 4.1 The quantities of radioactive material released in liquid effluents are summarized in Table 2A and 2B.
i 5.0 SOLID WASTES 5.1 The quantities 'of radioactive material released in shipments of ;
solid waste and irradiated fuel transported from the site during the i reporting period are summarized in Table 3. The activity and fractional abundance of each nuclide was determined for each vaste type by an independent laboratory based upon radiochemical analysis j of samples of that waste type. The curie amount of each nuclide l listed in Table 3 was determined as the product of the fractional l abundance and the total curies shipped. Those nuclides which j comprise at least 1% of the total activity for a particular waste {
type are presented in Table 3.
1 6.0 RELATED INFORMATION l l
6.1 Unplanned Releases a Unplarned releases are inadvertent or accidentti releases of !
radioactive material, or releases of radioactive material via normal j pathways without a release permit or proper authorization, or ;
without proper sampling and analysis, or reles.ses which are l conducted in such a manner as to result in significant deviation from the requirements of the release permit.
There were two unplanned releases during the reporting period, !
involving one instance of an inadvertent partial release of a Waste Gas Decay Tank (WGDT) to the Radwaste Bui161rg following maintenance 1 activities and one instance involving a minor deviation from the conditions stipulated on a Containment Purge release permit. In each instance, the release occurred throy,h the plant's normal j release point, and resulted in an insignificant offsite dose; the ;
health and safety of the public was not comp *;omised, l
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',s 6.1.1 On 6/25/87 caaintenance work was completed on Gaseous' kad Waste (GRW)
L Compressor "B"., At approximately;1345, the Rad / Chem Technician (RC Tech) was instr 0^.ted to clear the maintenance tags and to restore the compreseo:: to service. Upon returning to the Radwaste Contro!'
Ro?m, he dfscose[ed a decr(are in:WGDT %" of appror.imately 2 psig and ,an - incre's.te ,. in $ tl.e Radwaste Br..lldi4g Vent activit y. The R/C
- Tech Mwtediateli! isolated GRW comptrissc:: j'B". The Ra<Maste Building Vet,t ,nctivity 1 reached I
a pea % .:c tiuity of 1.2E-3 giCi/sec at appwximately 1210. The leak was later determ!ned to;be the result >
of a missing drain plug on the underside (,f thei cor. pressor housing
.which had been inadvertent 1y' 'lef t out folicwing' Ene maintenance work. ,This incident resulted in the release of a sruill quantity of nob a gases:
Xe-133 9.51E-1 C.f Xe-135 1.691C'.i ci Ga s.a Ali' Dose: 1.52E-6 mrad
,.Bc(na Air Done: 4.20E-6 mrad i i Total Bc0y 'liose Rate;: 2.lGE-3 mrem /yr
' Skin Dose Kate: 4.29E-3 mrem /yr -
These values are e stiell fraction cf Technical Specificaric a idmits. j This incident is dhcumented in Callaeay Plant Incidant RQort 87-114.
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~6.1.2 On 6/h3/7 a Containment Mini Purge was coddiacted under release ,
permit # W G-58:pi redrce containment pressure. Pre-release dose ' calculations wcre ; perikrued using 1-2 hcur release duration.
The release. was initiated at 15:52+ and terminated at 19:00; e.xceedir.g the 2 b'our reluase duration; utipulated by the releare permit. Total activity rtlenced and'offeite dosen were:
11 - 3 J 2.58E-3 Ci Kr-85m 6,69E-4 Ci Xe-131m 1.50E-2 C1 Xe-13?m , 1.34E-2 Ci Xe-13Y 1.77E0 C1 ,
Xe-1351 8.19E-3 Ci Ar-41' 3.56n-2 Ci Gamma Air Dose: 3.17E-5 mrad Beta Air Dor,e: 6.33E 5 mrad Total Body Dose Rete: 7.77E-2 mrem /yr Skin Dose Rates 1.56E-1 mrem /yr Maximum Organ Dose: 2.27E-4 mrem These values a:e a email fraction cliTechnical Specific:. tion limits.
This incident da ddomier.t sd in Callaway Plant Incident Report 37-108.
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6 '. 2 Changes to the Process Control Program There were no changes to the PCP during the reporting period.
( , b.3 _ Changes to the Offsite' Dose Calculation Manual
- / , There were no changes to the ODCM during the reporting period.
1 o 624 Ma gr_ Changes to Radwaste Treatment Systems
'There were no major changes to Radwaste Treatment Systems during the reporting period.
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[ i 6.5 Land i}e Census Changes
,[ t There were no changes in critical receptor locations for dose
,. ( calculations during the reporting period.
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l 6.6 Inoperability of Effluent Monitoring Instrumentation All effluent monitoring instrumentation was OPERABLE within the limits specified by Specifications 3.3.3.9 and 3.3.3.10 during the reporting period.
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I TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1.AND 2, 1987 UNIT QUARTER 1 QUARTER 2 EST TOTAL TYPE OF EFFLUENT ERROR %
'A . FISSION AND ACTIVATION GASES
'1. TOTAL = RELEASE CURIES 6.32E2 1.22E3 35
- 2. AVERACE RELEASE RATE FOR PERIOD UCI/SEC 81.3 155
- 3. PERCENT OF TECH SPEC LIMIT % 4.7E-3 8.9E-3 B. RADIOI0 DINES 1.- TOTAL 10 DINE-131 CURIES 6.54E-5 2.24E-4 35
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.41E-6 2.85E-5
- 3. PERCENT OF TECH SPEC LIMIT % 8.0E-6 2.7E-5 C. PARTICULATE
- 1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 9.88E-7 2.00E-5 35
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.27E-7 2.54E-6
- 3. PERCENT OF TECH SPEC LIMIT % 8.3E-9 1.6E-7
- 4. CROSS ALPHA RADI0 ACTIVITY CURIES 6.73E-7 2.69E-6 D. TRITIUM
- 1. TOTAL RELEASE CURIES 3.39E0 5.92E0 25 2.- AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 4.36E-1 7.53E-1
- 3. PERCENT OF TECH SPEC LIMIT % 2.9E-5 5.0E-5 ,
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1 I-TABLE IB' SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES CROUND LEVEL RELEASES FISSION GASES, 10 DINES, AND PARTICULATE QUARTERS 1 AND 2, 1987 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT OUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 1.: FISSION GASES Kr-85M CURIES 1.03E0 5.84E0 1.50E-1 4.26E-2 Kr-85 CURIES 0 0 5.47E0 5.58E0 Kr-87 CURIES 1.40E-1 1.56E0 1.58E-2 0 Kr-88 CURIES 6.11E-1 6.98E0 1.44E-1 4.52E-3 Xc-131M CURIES 5.39E-1 3.01E-1 2.54E0 8.34E0 Xe-133M CURIES 1.75E0 1.01El 2.29E0 6.70E0 Xe-133 CURIES 3.73E2 4.52E2 2.21E2 6.67E2 Xe-135M CURIES 0 5.05E-1 0 0 Xe-13; CURIES 2.01El 5.51El 2.52E0 1.66E0
-Xe-138 CURIES 0 0 1.20E-3 0 1 Ar-41 CURIES 0 0 5.09E-1 8.35E-1 1 TOTAL FOR PERIOD CURIES 3.97E2 5.32E2 2.35E2 6.90E2
- 2. 10 DINES I-131 CURIES 6.49E-5 1.60E-4 4.80E-7 6.37E-5 I-133 CURIES 1.67F-6 0 1.79E-7 1.39E-7 I-135 CURIES 0 0 0 0 ,
TOTAL FOR PERIOD CURIES 6.66E-5 1.60E-4 6.59E-7 6.38E-5
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- 3. PARTICULATE H-3 CURIES 3.21E0 4.10E0 1.83E-1 1.82E0 Co-58 CURIES 0 1.37E-5 0 0 Co-60 CURIES 0 2.66E-7 0 0 Sr-89 CURIES 0 0 0 0 Cs-134 CURIES 0 1.57E-6 0 0 Cs-137 CURIES 3.15E-7 1.85E-6 0 0 Sr-90 CURIES 0 0 0 0 I G ALPHA CURIES 5.67E-7 8.68E-7 1.06E-7 1.83E-6 TOTAL FOR PERIOD CURIES 3.21E0 4.10E0 1.83E-1 1.82E0
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- l TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 1 AND 2, 1987 UNIT QUARTER 1 QUARTER 2 EST TOTAL TYPE OF EFFLUENT ERROR %
A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.89E-3 2.93E-2 25
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 7.63E-9 7.83E-8
- 3. PERCENT OF APPLICABLE LIMIT % 1.60E0 3.0E0 B. ' TRITIUM
- 1. TOTAL RELEASE CURIES 1.77E2 1.22E2 25
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOb UCI/KL 3.47E-4 3.25E-4
' 3. PERCENT OF APPLICABLE LIMIT %' 1.2E1 1.1El i C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.23E0 6.57E-1 25
- 2. AVERAGE DILUTED CONCENTRATION !
DURING PERIOD UC1/ML 2.41E-6 1.75E-6
- 3. PERCENT OF APPLICABLE LIMIT % 1.2E0 8.7E-1 D. GROSS ALPHA RADIOACTIVITY
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- 1. TOTAL RELEASE CURIES 1.02E-3 7.40E-4 25 E. WASTE VOL RELEASED (PRE-DILUTION) GAL 5.83E6 4.86E6 10
. F. VOLUME OF DILUTION WATER USED GAL 1.29E8 9.43E7 10 PAGE 1 0F 1
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! SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED l
QUARTER 1 AND 2, 1987 CONTINUOUS RELFASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 l ALL NUCLIDES H-3 CURIES 0 0 1.77E2 1.22E2 Na-24 CURIES 0 0 0 0 Cr-51 CURIES 0 0 0 4.07E-3 l Mn-54 CURIES 0 0 3.41E-5 7.69E-4 >
Fe-55 CURIES 0 0 0 0 i Fe-59 CURIES 0 0 0 1.66E-4 ;
Co-58 CURIES 0 0 1.18E-4 1.58E-2 l Co-60 CURIES 0 0 2.23E-4 1.98E-3 )
Zn-65 CURIES 0 0 s 0 l Rb-88 CURIES 0 0 0 8.93E-5 l Sr-89 CURIES 0 0 0 0 Zr-95 CURIES 0 0 0 5.23E-4 !
Nb-95 CURIES 0 0 0 8.91E-4 l Mo-99 CURIES 0 0 0 0 Tc-99M CURIES 0 0 0 0 Ag-110M CURIES 0 0 0 3.55E-4 I-131 CURIES 0 0 2.32E-3 3.24E-3 1-133 CURIES 0- 0 4.32E-4 2.15E-5 1-135 CURIES 0 0 0 0 Cs-134 CURIES 0 0 3.43E-4 5.69E-4 :
Cs-136 CURIES 0 0 0 0 ;
Cs-137 CURIES 0 0 4.13E-4 8.01E-4 !
La-140 CURIES 0 0 0 0 Cc-141 CURIES 0 0 4.33E-6 0 !
Cc-144 CURIES 0 0 0 7.24E-5 '
W-187 CURIES 0 0 0 0 ;
Kr-85 CURIES 0 0 0 0 l '
Kr-85M CURIES 0 0 0 1.16E-4 Xe-131M CURIES 0 0 1.13E-2 6.30E-3 Xe-133 CURIES 0 0 1.20E0 6.32E-1 !
Xe-133M CURIES 0 0 1.16E-2 6.69E-3 1 l
Xe-135 CURIES 0 0 4.67E-3 1.13E-2 0
Xe-135M CURIES 0 0 0 Ba-140 CURIES 0 0 0 0 St-90 CURIES 0 0 0 0 l G ALPHA CURIES 0 0 1.02E-3 7.04E-4 UNIDENTIFIED CURIES 0 0 0 0 a
_ ---- ---------- l TOTAL FOR PERIOD CURIES 0 0 1.78E2 1.22E2 PAGE 1 0F 1 1
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TABLE 3 SOLID WASTE 6 IRRADIATED FUEL SHIPMENTS QUARTERS 1 & 2, 1987 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (DOES NOT INCLUDE IRRADIATED FUEL)
TYPE OF WASTE 6-MONTH EST. TOTAL PERIOD ERROR (%)
- a. Spent resins, filter sludges 29.5 m8 25%
evaporator bottoms, etc. 2.77E2 Ci Fe-55 26.6% 7.38E1 C1 Co-60 18.7% 5.2E1 Ci Cs-137 13.4% 3.71El Ci Mn-54 11.6% 3.21El C1 Co-58 10.1% 2.81El Ci Ni-63 9.2% 2.55El Ci Cs-134 7.4% 2.06El C1 C-14 1.4% 3.88E0 Ci H-3 0.6% 1.74E0 Ci
- b. Dry compressible waste, 11.9 ms 25%
contaminated equipment, etc. 2.03E-1 C1 Fe-55 45.2% 9.16E-2 C1 Co-58 25.8% 5.23E-2 Ci Nb-95 7.0% 1.42E-2 C1 Co-60 6.6% 1.34E-2 C1 C-14 6.3% 1.29E-2 Ci Mn-54 3.8% 7.65E-3 Ci Zr-95 3.6% 7.39E-3 C1 Cs-134 1.6% 3.25E-3 Ci
- c. Irradiated components, control 0 m8 rods, etc. O Ci
- d. Other 0 m8 0 Ci Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Class Container 1 Truck Barnwell, SC C LSA 3 Truck Richland, WA A LSA Page 1 of 2
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TABLE 3 (cont.)
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n Solidification Agent . . .
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Cement (applicable to waste type "a" (evaporator bottoms) only) ...
B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) ,.
Number of Shipments Mode of Transportation Destination 0 N/A N/A I
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^ Donald F. Schnell Vice President August 31, 1987 U. S. Nuclear Regulatory Commission Attn: . Document Control Desk Washington, DC 20555-Gentlemen: ULNRC- 1588 DOCKET NUMBER 50-483 CALLAWAY PLANT FACILITY OPERATING LICENSE NPF-30 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The enclosed Semi-Annual Effluent Release Report for the first half of 1987 is submitted pursuant to Section 6.9.1.7 of the Cal'laway Plant Technical Specifications.
Very truly yours, p
Donald F. Schnell JMC/plh Enclosure
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Maihng Address: P.O. Box 149, St. Louis, MO 63166
1 cc': Director, Resource Management U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Bill-Kesler Regional' Administrator Jefferson City Regional-Office Department of Natural Resources P.O' Box 1368 Jefferson City, MO 65102 W. L. Forney .
Chief, Reactor Project Branch 1-U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission R.R.#1 Steedman, MO 63077 Tom Alexion (2):
Office of Nuclear. Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014.
bec: Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 (with enclosure)
America Nuclear Insurers Library c/o Dottie Sherman The Exchange Suite 245 270 Farmington, CT 06032 (with enclosure)
G. L. Randolph J. F. McLaughlin J. E. Davis (Z40 ULNRC) (with enclosure)
A. P. Neuhalfen W. R. Campbell A. C. Passwater/D. E. Shafer/D. J. Walker R. R. Roselius J. R. Peevy, (with enclosure)
R. A. McAlleean N. G. Slaten (with enclosure)
J. C. Pozzo M. F. Bollinger DFS Chrono (with enclosure) 3456-0021.6 G56.37 N. Date 3456-8561.9 (with enclosure)
NSRB (S. L. Auston) (with enclosure) i