ML20214L956

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Semiannual Radioactive Effluent Release Rept,Jan-June 1986
ML20214L956
Person / Time
Site: Callaway Ameren icon.png
Issue date: 06/30/1986
From: Schnell D
UNION ELECTRIC CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
ULNRC-1366, NUDOCS 8609100470
Download: ML20214L956 (39)
v • d • e


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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY - JUNE 1986 m, s 8609100470 860630 3 DR ADOCK 0500 (g t\'

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o TABLE OF CONTENTS

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 GASEOUS RADI0 ACTIVE 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 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

g TABLE OF CONTENTS (Continued)

Attachment 1 Radioactive Liquid Waste Sampling and Analysis Program

' Attachment 2 Radioactive Gaseous Waste Sampling and Analysis Program Attachment 3 Process Control Program Changes 1

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TABLE OF CONTENTS (Continued)

Attachment 1 - Radioactive Liquid Waste Sampling and Analysis Program l

Attachment 2 Radioactive Gaseous Waste Sampling and Analysis Program Attachment 3 Process Control Program Changes l

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1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for Union Electric Company's Callaway Plant and is submitted in accordance with the requirements of Technical Specification 6.9.1.7. The report covers the period from January 1, 1986 through June 30, 1986.

This report includes a summary of the quantities 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, June 1974.

All liquid and gaseous effluents discharged during this reporting period were in compliance with the limits of the Callaway Plant Technical Specifications.

I.

2.0' SUPPLEMENTAL INFORMATION i

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) l 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 I radiation and,
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.2 Radioiodine, Tritium, and Particulates The dose rate due to Iodine 131 and 133, tritium and +L1 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 ef fluents 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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2.1.3 Liquid Effluents The concentration of radioactive material released in liquid 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 j gases. For dissolved or entrained noble gases, the concentration shall be' limited to 2.0E-04 microcuries/ml total activity.

The dose or dose commitment' to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall 4 be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem i to the total body and less than or equal to 5 mrem to any organ, and

! b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal 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-i 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 i 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 total noble gas activity is used as the MFC 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 i limits are stated in terns of dose rate at the unrestricted area i boundary.

2.3 Average Energy

, This is not applicable to the Callaway Plant's radiological effluent technical specifications.

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S 2.4 Measurements and Approximations of Total Radioactivity 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 attachments 1 and 2).

Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, and Fe-55 by an independent laboratory. Tritium and alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.

The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of ef fluents discharged. Gros 5 beta or gamma radioactivity measurement techniques were not utillzed to approximate the total radioactivity in effluents.

2.5 Batch Releases 2.5.1 Liquid 2.5.1.1 Number of batch releases: 148 2.5.1.2 Total time period for batch releases: 36886.0 minutes 2.5.1.3 Maximum time period for a batch release: 1093.0 minutes 2.5.1.4 Average time period for batch releases: 249.2 minutes 2.5.1.5 Minimum time period for a batch release: 2.0 minutes 2.5.1.6 Average stream flow during periods of release of effluent into a flowing stream: 69,000 cfs 2.5.2 Gaseous 2.5.2.1 Number of batch releases: 78 2.5.2.2 Total time period for batch releases: 94759.0 minutes 2.5.2.3 Maximum time period for a batch release: 10436.0 minutes 2.5.2.4 Average time period for batch releases: 1214.0 minutes 2.5.2.5 Minimum time period for a batch release: 60.0 minutes

2.6 Abnormal Releases 2.6.1 Liquid 2.6.1.1 Number of releases: 0 2.6.1.2 Total Activity released: 0 2.6.2 Gaseous 2.6.2.1 Number of releases: 0 2.6.2.2 . Total Activity released: 0 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS 3.1 The quantities of radioactive material released in gaseous effluents are summarized in Table 1A and IB. Note that for this reporting period no gaseous effluents were considered as elevated releases.

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS 4.1 The quantities of radioactive material released in liquid effluents are summarized in Table 2A and 2B.

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 reporting period are summarized in Table 3. The activity and fractional abundance of each nuclide was determined for each waste type by an independent laboratory based upon radiochemical analysis of samples of that vaste type. The curie amount of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped. Those nuclides which comprise at least 1% of the total activity for a particular waste  ;

type are presented in Table 3.

6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.1.1 There were no unplanned releases during the reporting period.

6.2 Changes to the Process Control Program Two revisions to the Callaway Plant Process Control Program were issued during the reporting period. The first, Revision 5, issued March, 1986 provided for incorporation of vendor supplied updated solidification formulation nomograms and incorporated text changes and coversheet changes denoting that formulations contained within the document are considered proprietary. Additionally a section within the document dealing with specifications for solidification agents was removed as this information is addressed in purchase specifications for this material.

l On April 29, 1986 Revision 6 of the Process Control Program was issued. This revision was made to incorporate programmatic control for use of vendor services for the packaging of solid radioactive wastes. These controls provide assurance that vendor activities related to the packaging and documentation of solid radioactive waste processing are performed in a manner consistent with plant Technical Specifications. Vendor PCP's were reviewed and approved by the Onsite Review Committee prior to implementation.

These changes to the Process Control Program do not charge the overall conformance of the program to the requirements governing its intended use.

Documentation attesting to the review and approval of these changes by the On-Site Review committee is provided in Attachment 3.

6.3 Changes to the Offsite Dose Calculation Manual There were no changes to the ODCM during the reporting period.

6.4 Major Changes to Radwaste Treatment Systems There were no major changes to Radwaste Treatment Systems during the reporting period.

6.5 Land Use Census Changes There were no changes identified in critical receptor locations by the 1985 Land Use Census.

6.6 Inoperability of Effluent Monitoring Instrumentation All effluent monitoring instrumentat. ion was OPERABLE within the limits specified by Specifications 3.3.3.9 and 3.3.3.10 during the reporting period.

x TABLE 1A SEMIANNUAL SUMMATION OF GASE0US RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2, 1986 UNIT QUARTER 1 QUARTER 2 EST TOTAL TYPE OF EFFLUENT ERROR %

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES 7.49E 02 1.64E 03 3.50E 01
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 9.63E 01 '2.09E 02
3. PERCENT OF TECH SPEC LIMIT  % 5.53E-03 1.20E-02 B. RADIOI0 DINE 3
1. TOTAL 10 DINE-131 CURIES 1.11E-04 2.14E-04 3.50E01
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.43E-05 2.72E-05
3. PERCENT OF TECH SPEC LIMIT  % 1.36E-05 2.59E-05 C. PARTICULATES
1. PARTICULATES (HALF-LIVES > 8 DAYS) CURIES 7.43E-06 4.63E-06 3.50E 01
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 9.55E-07 5.89E-07
3. PERCENT OF TECH SPEC LIMIT  % 6.20E-08 3.83E-08
4. GROSS ALPHA RADIOACTIVITY CURIES 6.65E-06 6.73E-07 D. TRITIUM
1. TOTAL RELEASE CURIES 3.35E 00 9.01E 00 2.50E 01
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 4.31E-01 1.15E 00
3. PERCENT OF TECH SPEC LIMIT  % 2.83E-05 7.54E-05 PAGE 1 of 1

TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, 10 DINES, AND PARTICULATES QUARTERS 1 AND 2, 1986 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER ~2 _ QUARTER 1 QUARTER 2

1. FISSION GASES Kr-85M CURIES 3.05E 00 3.43E-01 3.44E-02 4.05E 00 Kr-85 CURIES 9.69E-05 0.00E 00 1.75E 00 1.27E 00 Kr-87 CURIES 0.00E 00 0.00E 00 0.00E 00 4.53E-01 Kr-88 CURIES 3.27E 00 0.00E 00 8.36E-03 3.86E 00 Xe-131M CURIES 6.27E 00 0.00E 00 2.18E 00 7.59E 00 Xe-133M CURIES 1.10E 01 0.00E 00 1.88E 00 2.70E 01 Xe-133 CURIES 4.37E 02 1.23E 02 2.45E 02 1.39E 03 Xe-135M CURIES 0.00E 00 0.00E 00 0.00E 00- 0.00E 00 Xe-135 CURIES 3.52E 01 9.93E 00 1.48E 00 6.07E 01 Xe-138 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ar-41 CURIES 0.00E 00 0.00E 00 7.31E-01 3.44E 00 TOTAL FOR PERIOD CURIES 4.95E 02 1.34E 02 2.54E 02 1.50E 03
2. 10 DINES I-131 CURIES 9.81E-05 1.97E-04 1.29E-05 1.67E-05 I-133 CURIES 5.44E-06 5.06E-06 0.00E 00 0.00E 00 I-135 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 1.04E-04 2.02E-04 1.29E-05 1.67E-05
3. PARTICULATES

--_-__-- -- ------_. -== . - -_-----------__.

H-3 CURIES 1.61E 00 5.11E 00 1.74E 00 3.89E 00 Na-24 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Mn-54 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Fe-59 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Co-58 CURIES 7.79E-07 3.96E-06 0.00E 00 0.00E 00 Co-60 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Zn-65 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Sr-89 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Mo-99 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Cs-134 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 PAGE 1 of 2 I

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9 TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, 10 DINES, AND PARTICULATES QUARTERS 1 AND 2, 1986 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 PARTICULATES CONTINUED Cs-137 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ba-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 La-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ce-141 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ce-144 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Sr-90 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 G ALPHA CURIES 4.46E-06 5.65E-07 2.19E-06 1.08E-07 UNIDENTIFIED CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 1.61E 00 5.11E 00 1.74E 00 3.89E 00 PAGE 2 0F 2

TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 1 AND 2, 1986 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 1.37E-03 2.96E-02 2.50E 01
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 2.84E-09 3.52E-08
3. PERCENT OF APPLICABLE LIMIT  % 5.24E-01 5.89E 00 B. TRITIUM

=_ -- ----- -

1. TOTAL RELEASE CURIES 6.73E 01 8.24E 01 2.50E 01
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.40E-04 9.81E-05
3. PERCENT OF APPLICABLE LIMIT  % 4.65E 00 3.27E 00 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CURIES 7.24E-01 1.68E-01 2.50E 01
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.50E-06 2.00E-07 j
3. PERCENT OF APPLICABLE LIMIT  % 7.51E-01 1.00E-01 D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CURIES 6.68E-04 7.54E-04 2.50E 01

- - = - - . ---- -- -----

E. WASTE VOL RELEASED (PRE-DILUTION) GAL 5.39E 06 9.85E 06 1.00E 01

_=- .._ .- - _ - _ _ -----

F. VOLUME OF DILUTION WATER USED CAL 1.22E 08 2.12E 08 1.00E 01 PAGE 1 0F 1

TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTER 1 AND 2, 1986 4

CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 1

ALL NUCLIDES l .-... . .

) H-3 CURIES 0.00E 00 5.01E-03 6.73E 01 8.24E 01 Na-24 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CURIES Cr-51 CURIES 0.00E 00 5.01E-05 0.00E 00 2.99E-03 Mn-54 CURIES 0.00E 00 9.60E-05 1.83E-04 3.08E-04 Fe-55 CURIES 0.00E 00 0.00E 00 1.21E-04 1.78E-06

. Fe-59 CURIES 0.00E 00 0.00E 00 0.00E 00 8.31E-05 l

Co-58 CURIES 0.00E 00 5.56E-04 2.66E-04 4.96E-03 Co-60 CURIES 0.00E 00 9.65E-05 2.12E-05 6.52E-04

, Zn-65 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 i Sr-89 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00

Zr-95 CURIES 0.00E 00 0.00E 00 0.00E 00 1.71E-04 j Nb-95 CURIES 0.00E 00 8.62E-06 0.00E 00 3.73E-04 Mo-99 CURIES 0.00E 00 0.00E 00 0.00E 00 5.34E-06 l Tc-99M CURIES 0.00E 00 0.00E 00 0.00E 00 2.52E-05 I-131 CURIES 0.00E 00 1.41E-05 7.56E-04 1.47E-02 i 1-133 CURIES. 0.00E 00 0.00E 00 0.00E 00 5.80E l I-135 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00

, Cs-134 CURIES 0.00E 00 1.24E-05 0.00E 00 1.84E-03 Cs-136 CURIES 0.00E 00 0.00E 00 0.00E 00 6.47E-05 Cs-137 CURIES 0.00E 00 1.73E-05 1.32E-05 2.55E-03 i La-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ce-141 CURIES 0.00E 00 0.00E 00 1.13E-05 0.00E 00 4

Ce-144 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 i W-187 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00

Kr-85 CURIES 0.00E 00 0.00E 00 1.08E-03 0.00E 00 i Kr-85M CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Xe-131M CURIES 0.00E 00 0.00E 00 6.31E-03 1.37E-03 i Xe-133 CURIES 0.00E 00 7.01E-05 6.98E-01 1.64E-01 Xe-133M CURIES 0.00E 00 0.00E 00 9.49E-03 1.64E-03 4

Xe-135 CURIES 0.00E 00 0.00E 00 8.46E-03 1.11E-03

{ Xe-135M CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Ba-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Sr-90 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 G ALPHA CURIES 0.00E 00 7.16E-05 6.68E-04 6.82E-04 l UNIDENTIFIED CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 0.00E 00 6.00E-03 6.81E 01 8.26E 01 l

l PAGE 1 0F 1 i

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TABLE 3 SOLID WASTE & IRRADIATED FUEL SHIPMENTS QUARTERS 1 & 2, 1986 A.~ SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (DOES NOT INCLUDE IRRADIATED FUEL)

TYPE OF WASTE UNIT 6-MONTH EST. TOTAL PERIOD ERROR (%)

a. Spent resins, filter sludges

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m3 4.16E 01 2.5E 01 evaporator bottoms, etc. C1 1.04E 01 H-3 23% 2.4E 00 C1 Co-58 21% 2.2E 00 Cs-137 20% 2.1E 00 Mn-54 13% 1.3E 00 Co-6a 6% 5.9E-01 1-129 5% 4.8E-01 C-14 4% 4.1E-01

h. Dry compressible waste, m3 2.65E 01 2.5E 01 contaiminated equipment, etc. Ci 1.31E 00 Fe-55 44% 5.8E-01 C1 Co-58 25% 3.3E-01 NE-95 7% 9.2E-02 Co-60 6% 8.5E-02 C-14 6% 8.1E-02 Zr-95 4% 5.2E-02

'Mn-54 4% 5.2E-02 Ni-63 1% 1.1E-02 Fe-59 1% 1.3E-02

c. Irradiated components, control m 3 0.00E 00 rods, etc. Ci 0.00E 00 ,
d. Other m3 0.00E 00 Ci 0.00E 00 Solid' Waste' Disposition Number of Shipments Mode of Transportation Dest ination 5 Truck Richland, WA Class of Solid Waste Shipped Class A Type of Container LSA

TABLE 3 (cont.)

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Solidification Agent Cement (applicable to waste type "a" only)

, B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments Mode of Transportation Destination 4

0 N/A N/A

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O ATTACHMENT 1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

  • 8 SON $ *

[' 3/4.L1 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENIRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrair.ed noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /ml total activity. .

. APPLICABILITY: At all times.

AC110N:

With the concentration of radioactive material released in liquid effluents to

- UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen-tration to within the above limits.

r SilRVEllLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1. .

4.11.1.1.2 The results of the radi'oactivity analysis shall be used in accordance with the methodology and parameters in the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification

3. I 1. l .1.

Call AWAY - IINI1 1 3/4 11-1

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,, TABLE 4.11-1

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RAOI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i LOWER LIMIT MINIMUM SAMPLING OFDETECTgg LIQUID RELEASE ANALYSIS TYPE OF ACTIVITY (LLO)

TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)

1. Batch Waste P P -

Release Each Batch 7 i Each Batch Principal Gamma 5x10 Tanks (2) . Emitters (3)

I-131 -6 1x10

a. Waste Monitor Tank P M Ofssolved ande lx10 -5 One Batch /M Entrained Gases (Gamma Emitters)
b. Secondary Liquid Waste P M H-3 1x10

-5 Monitor Each Satch Composite {4)

,7 Tank Gross Alpha 1x10

c. Discharge P Q Sr-89, Sr-90 5x10

-8 Monitor Each Batch Composite (4)

. Tank Fe-55 1x10

-6

2. Continuous W Principal Gamma -7 5x10 Releases (5) Daily (6) Composite (4) Emitters (2)

Grab Sample I-131 -6 1x10 1 Steam Generator Blowdown M Dissolved and -5 M 1x10 Grab Sample Entrained Gases (Gamma Emitters)

M H-3

-5 1x10 Daily (6) Composite (#)

7 Grab Sample Gross Alpha 1x10 Q Sr-89, Sr-90 5x10'8 Daily (6) Composite (4)

Grab Sample Fe-55 4

. 1x10 s

e CALLAWAY - UNIT 1 -

3/4 11-2

?

s REVISlon 1

'~~ 1 AHLE 4.11-1 (Continued)

TABLE NOTATIONS -

(1)The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only $5 probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

D LLD =

E V 2.22 x 108 Y exp (-Aat)

Where:

LLD = the "a priori" lower limit of detection (microcuries per unit mass or volume),

J

! sb = the standard deviation of the background counting rate or of

( the counting rate of a blank sample as appropriate (counts per minute), .

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 108.= the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield *, when applicable, A = the radioactive decay constant for the particular radionuclide (s 8), and at = the elapsed time between the midpoint of sample collection

. and the time of counting (s).

Typical values of E, V, Y, and at should be used in the calculation.

It shuuld be recognized that the LLD is defined as an a priori (before

. the fact) limit representing the capability of a measurement system and

. not as an a posteriori (af ter the fact) limit for a particular measurement.

i

(?)A batch release is the discharge of liquid wastes of a discrete volume, l'rior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the 00CM to assure representative sampling.

~

CALLOWAY - UNIT 1 3/4 11-3 i

4

- - - - , - , - - - - , - . _ . - - ~ . . - . - - , - , - - - . , - , - . - - , - - - - - - - , , - -

REVISION I TABLE 4.11-1 (Continued) ~'s TABLE NOTATIONS (Continued)

(3)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, In-65, Ho-99, Cs-134. Cs-137, Ce-141, and Ce-144. This list does not mean that

! only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21 Appendix B, Revision 1, June 1974.

(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g. , from a volume of a system that has an input flow during the continuous release.

.(6) Samples shall be taken at the initiation of effluent flow and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter while the release is occurring. To be representa- s tive of the liquid effluent, the sample volume shall be proportioned to the .')

effluent stream discharge volume. The ratio of sample volume to effluent /

discharge volume shall be maintained constant for all samples taken for

  • the composite sample.

i

,CALLAWAY - UNIT 1 3/4 11-4 ./

, _ _ _ _ . _ _ _ ~ , . _ _ . - _ _ _c , . . _,

w _ , - _ . _ , , __ _m_.- . . . - _ _ . _

O O

e ATTACHMENT 2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l

, REVISlon 1 ~ ~

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS e' N ,

DOSE RATE LIMITING CONDITION FOR OPERATION i

3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 arems/yr to the whole body and less than or equal to 3000 mress/yr to the skin, and
b. For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s). . .

SURVEILLANCE' REQUIREMENfS i

i

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous offluents shall be determined to be within the above limits in.accordance with

'; the methodology and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

i J

~-

Call AWAY - UNil 1 3/4 11-8 4

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TABLE 4.11-2 E

RADI0 ACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM E

l

  • IMINIMUM LOWER.LIMI c SAMPLING ANALYSIS TYPE OF lETECTION(LLD)yf O

GASEOUS RELEASE TYPE ACTIVITY ANALYSIS (pCi/ml)

$ FREQUENCY FREQUENCY

" 4

1. Waste Gas Decay Each Tank Each Tank Principal Gamma Emitters (2) 3,3g Tank . Grab 8 Sample ,

~4 a 2. Contai g t Purge Each PURCE I} Eac PURGE (3) Principal Gamma Emitters (2) 1x10 or Vent u

l . hkie M H-3 (oxide) 1x10

-6 *

~4 4

3. Unit vent 'M I3)*I4) M I3) Principal Gamma Emitters (2) 1x10 Grab -6 M Sample M ) H-3 (oxide) 1x10
4. Spent Fuel Building M(5) M Principal Gamma Emitters II 1x10'4 7

Exhaust Grab Sample -6 M(5) H-3 (oxide) 1x10 Principal Gamma Emitters (2) - 3,39

-4

5. Radwaste Building M Vent Grab Sample M g(7) -12
6. All Release Types Continuous (6) (8) 1-131 1x10 as listed in 1.. Charcoal -10 2., 3. 4., and Sample I-333 1x10
5. above g(7) Principal Gamma Emitters (2) 1x10'll ' '

Continuous (6) (8)

Particulate r Sample I g

~II Continuous (6) (8) M ,

Gross Alpha 1x10 Composite -

Particulate Sample C)

Continuous (6) (8) Q Sr-89, Sr-90 1x10

~II I Composite Particulate M Sample

o e o -

REVISloN 1 TABIf 4.11-2 (Continued) 9  ;

1ABLE NOTATIONS (1)lh TTD s defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which ma'y include radiochemical separation:

4.66 s b '

E V 2.22 x 108 Y exp (-Aat)

Where:

tLD = the "a priori" lower limit of detection (microCuries per unit mass or volume),

s = the standard deviation of the background counting rate or of b

the counting rate of a blank sample as appropriate (counts per minute),

' E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume), .

2.22 x 108 = the number of disintegrations per minute per microcurie, Y

  • the fractional radiochemical yield, when applicable, .

Az the radioactive decay constant for the particular radionuclide (S 8), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

CAL 1AWAY - UNIT I 3/4 11-10

REVisgoy 3-.

TA8LE 4.11-2 (Continued)

TA8LE NOTATIONS (Continued)

(2)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58 Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137 Ce-141, and Ce-144 in lodine and particulate releases. This It'st does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21 Appendix B. Revision 1, June 1974.

('l) Sampling and analysis shall also be performed following shutdown, startup,

! or a litLRMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 4

hour period.

i (4)fritium grab samples shall be taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

(5) Tritium grab samples shall be taken and analyzed at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. Grab samples need to be taken only when

[ spent fuel is in the spent fuel pool. .

(6)The ratio of the sample flow rate to the sampled stream flow rate shall

! be known for the time period cover'ed by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

1

(/) Samples shall he changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing, or af ter removal from sampler.

l for unit vent, sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i n c a t. least / days following each shutdown, STARTUP or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LL0s may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows j that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that ef fluent activity has not increased more than a factor of 3.

(8) Continuous sampling of the spent fuel building exhaust needs to be performed i only when spent fuel is in the spent fuel pool.

4 i

Call AWAY - LINil I 3/4 11-11

, P-ATTACHMENT 3 PROCESS CONTROL PROGRAM CHANGES This Attachment contains the Callaway Plant ORC Meeting Minutes (applicable sections) providing documentation that Revisions 5 and 6 of the PCP have been reviewed and found acceptable by the ORC.

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CALLAWAY FLANT i ORC MEETING MINUTES

. Neeting Number 52L Date J M-85

'II . Attendees Chairman /'li- Ot.eir-- 6. L . RAMDot PH Messipee/ Alternate M. / If . u_, _ t ad

-Hesher/ Alternate h-[ MM

  • Member /Alsamente kkcut.1 '

Member /ALseeeese. ]

Member /A&eerneee- bA1AoN k a. ., ,

u.-- ia.-.- JiLik E %A /n SMkO '

u":r /!lte'-2t?- L$l .SLu .

Recommended Distosition 121. Frenosed Iteus_

Approva1 /d/ Disapproval /_/ Open /_/

[A. 494-72M [M 2[TUA/%e3.W) ipprovat g Disa,,rovat /_ / 0,en /_/

B. AF/1-12-cd530 #ea 5 Approval @ Disapproval /_/ Open /_/

4. N94-77-DOTlh [GO. 7

. .,D.FCP.Fod 5 _

Approval @ Disapproval,/_/ Open /_/

E. C/r19 R4-OI//, ( Ac/tl-05D Approval @ Disapprovat / _/ 'Open /_/'

T. Oy)F H-o'59/ol Ar Al 04) Approva1 / [

  • disapproval /_/ Open /_7 h Attached sist of Procedure Request Approval /[ Approval /_/ Identify exceptiens &

W/0 Exception W/E::ceptions forms and Safety Evaluations reason on NOTE: For items A through G. a recommendation for li' approval signifys that ORC found that the ite=s {EE* ar as did not constitute an unreviewed safety question. 9 "* ****

unless otherwise specifically stipulated in the ORO minutes.

Disapproval and NOTE: Open Items must be rescheduled for future meetings.

Open categories must have supporting rationale attached in writing.

Dissenting opinions require an attached statement of reason.

Attached pages shalt be uniquely identified by indicating in a preminent manner the meeting number, the date and page number of the attachment to this form.

3RC Chairman /"ica Ch d x = /

Distribution Members - w/ Attachments ORC File - w/ Attachments (QA Record) Supt. Training - w/Actachments NSR3 - w/ Attachments ISEG - w/ Attachments CA-#138 02/11/84 APA-Z:-00050 k

This is page 1 of of S.he minutes f or this meeting; 24We

  • J' ..

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\ rDa u-QW PRO 4 'b

1. Pro R Number A - F L oco"CEDURE REQUEST Revision Number FORM dure Tit - 3Mav- MI' rou.ss b>t1Yrcl Pre-am o Procedure Deletion Procedu t'. o Removing Deficiencies 1 cedur v , Ned Revision Number D

)

o Tempor re Change, effective until to next revision. TCN # )

incor o One  ;

g_ aryo Procedure. .Change,TCN # effective from UPERCEDED

2. ange Summary 2.1 Numbers Affected by Proposed Change ehd dbd ription of 'ew Pro NeshNeynds% d e/Cha es/ Deficiencies nemmrams Rekrved boeddL canestufes d V O 3 (

g* hcit acIA mArMww nu& h.a.L .dnhM s rivisd du.,sL.-t rXpedu eergen ,+d eumaf. , -

r mavd stNea A.2N. '

fith solidih%n "WM ermramut male %,' mum %lrs oreerMxco' Le rt ---

. (Use additional pages if required.) --- - - - - - -

2.3'ReasonforNewProMv Rue dure /Ch /Deficie ruisc Y gb M by Removalv 4 mtdA b 1hskr d

  • 21sAtht.'na shows iMmuMons rtouthh taas&mA owrktus 6%m. Gw.s mat te plant- fte to roteA- 47s . Rmt d sceht e.ous ,nA .L, b AS. m.are n.J u..cd b cdtAIMbA omcumt docu.ats. Geb., .AMWAa.u "

hhm%f6,ahk h a uAta st-duumant.

(Us's additional%. &pages if required.)Q 3h3b(8

3. Prepared by A-Date Q Signature Tic 1W -

~

Qualified Review (Check appropriate boxes)

(1) 4. 4.a Cross Disciplinary Review Required? No o YES X (If Yes, complete 4.b below)

ORC Review Re resi?/ t N0/J o YT

? - J O - r(>)( RJ d. Kr.- - .,- ir - m Tit Date Reviewedby/ Signature 4.b Cross Disciplinary Review Required (Signature /Date): te ue e

/ o P&S / XQ M /2 6 ,h -_

o Eng c H.P. / c Admin-S / c Mat' ." -/

s R.W.- / o Trng. / o Admin R /

/ o Sec. / o ISC /

- X Ch u)lJdEK c Comp. / o /

o Opsf /

c /

o Maint. / c Outages /

5. Responsible Department Head (Check appropriate box and sign):

5.a c Approved for Issue / /

5.b a Approved for ORC Review ( -3 AV W / 3 -d i-e '

(_# 4 (2) 6. Temporary Procedure Change Preliminary Approval (Signature /Date)

Member Management Staff /

Senior Reactor Operator /

(2) 7. Temporary Procedure Change Final Approval (Signature /Date; required within 14 days of Preliminary Approval.)

Responsible Dept. Head /

Manager, Callaway Plant -/

(1) 8. Procedure Approval (Signature /Date Manager, Callaway Plant /

(1) Applicable for new procedures and prdicedure revisiens only.

(2) Applicable for Temporary Procedure changes only; not all signatures are required in these sections. See APA-Z -00101 Section 5.1 for approval requirements.

CA-#33 02/24/86

('D APA- Z-00101

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'.I . M (1) 10ct's.Sc.S $ Af rLIC.A31LITT DLTD.'sthAttor ~

The precedura, precedure revision er chasse, or e.edificaties to which this evalu.attaa is syy11 tab seyresseats: ,

(2.1) Yes ye _ A cEmage to the plaat described 1.s t.he FSAR including t.he .

RI.3.P and Security Flaat ,

(2.2) Yes De A ebsage to precedures as described La the TSAR including the RD.P and Security Flaat .

(2.3) Yes Be A test er experLaent not described sa the TsAP. including ,.

. the RI.J.P and Security Flaat - -

(2.&) Yes No A ch.acge to t.be Technical $pecificettoas?

(2.5) Tas ye A ct.asse to plant structures system.s. er components. .

If any guestsea above is an.swered "Tes", this Checklist shall be forwarded to

. t.b e Superantendent. Engineering, for corpletion of a Nuclear Safety Evaluaties (CA= f 1041) p e r' AF A-12-001&O. .

(3) Fee eksages se perussent plant equip =cet, provide . justification below (Using the tarevsewed Safety Qaesties Deterniastion Cuidelines - Attachaeot 7) as to why the chacge does set constitute a yetentist ucreviewed safety .questies and why .

  • the responses to thea above guestions are "as". ' If a CA-#1041 form is required as indicated by a yes' response to any et tie guestions of section (2), thta 3 meed met be corpleted. I I

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AfA.2.2 00164

m OQR- 205/ Page 1 of I To: C.h. kb DATE: 3 s1 h rROa: s.g.e d PROCEDURE NO.: inuss dk Rev. NO.: 5

REFERENCES:

PCP h.) N, L7TO - HC - Pr# o f , oz. 4 o 3 PROCEDURE COM.41ENT SHEET Note: For any comment listed, there must be an Action and Approval.

COMMENTS ACTION TAKEN ' ACTION ACCEPTABLE q,3 4.Y.hkW.,pt\.1 " a...hyi# N' T 4/,4 s

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its. d p eAWu'M*' A. -utiddit tW . Itis c4. in ATTACH TO PROCEDyRE ECUEST FORM tepus M. neQLig a&w cc: ADSR 'Nb N'% - TN.h AD J7PO/ / (w/ comments) Line '

L-

"PCP" Date March 13, 1986 Revision 5 4

I

  1. +# sw INFORMAT10M uMCON7goLLED ONW
"y .,. l Ysp ! C UNION ELECTRIC COMPANY CALLAWAY PLANT PROCESS CONTROL PROGRAM Approved: O!M/J% IAb Chariman, ORC Date ORC Meeting number Reviewed: 3 -at- 6 6 erint(Adent, Radwaste Date Prepared by  % 3 l3 2(o Q 'Date

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  • A S%o f CALLAWAY PLANT me ~%

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" " --/ Alternate /M- /. Im_L._f_1 Member / Alternate 8

Recommended Disposition

^

~III. 'Freposed Items _

A. Pep - (bh //e- t / D b Approval /g Disapproval /_/ Open /_/

Nv5 /5( 55-oo/ N eJ Approval /3 Disapproval /_/ Open /_/

3.

  1. c.- /' Approval @ Disapproval /_/ Open /_/

C. Nd5 #fc #f-d/J Approval /_/ Disapproval /_/ Open /_/

D.

Approval /_/ Disapproval /_/ Open /_/

E.

Approval /_/ Disapproval /_/ Open /_/

F.

G. Attached list of Procedure Request Approva1 /_/ Approval /_/ Identify W/0 Exception W/Esceeptions exceptions &

for s and Safety Evaluations #*** " "

NOTE: For items A through G a reco=mendation for attached list approval signifys that ORC found that the ita=s *** 7 **

did not constitute an unreviewed safety question *E" ***

unless_ otherwise specifically stipulated in the ORC sinutes.

Disapproval and NOTE: Open Items must be rescheduled for future meetings.

Open categories must have supporting rationale attached in writing.

Dissenting opinions require an attached statement of reason.

Attached pages shall be uniquely identified by indicating in a prominent manner the meeting number, the date and page number of the attachment to this form.

CRC Chairman /Yict.=ChatrtTn b

Distributioq Members - v/ Attachments CRC File - v/ Attachments (QA Record) Sept., Training - v/Actachments l 55R3 - v/ Attachments

( ISEG - v/ Attachments CA-#138 02/11/84 APA-ZZ-000 ;C Y W ~.

This is page 1 of of the minutes for this meeting a garp.

O

PROCEDURE REQUEST FORM

&  % 0.01

1. Procedure Number Revision Number _

Procedure Title Paav Plant Pmm Gns) 6.

o New Procedure Request I o Removing Deficiencies o Procedure Deletion X Procedure Revision, New Revision Number 6 ., f i o Temporary Procedure Change, effective until incorporated into next revision. TCN # A 1,

%# t Q( Q

,E oOneTimeTemporaryProcedureChange,effectivefromh to , TCN # -y .g

2. New Procedure / Change Summary 2.1 Procedure Page, Numbers Affected by Proposed Cha Pup t , th , ! , Z . 7,10 ; 11, med 17 W -

CO{Qhv a 2.2 Description of New Rroced l ure/ Changes KwA5 ourcesa_ /Deficienk es an& se2on_. tw Removedwith dd;ir4-;en 8 DS5 CCA) TROL ftCG,PMY1 in T A Ah'l Saar.144uMEnr. (T:5. 't.22T s eM= A new ection meh c.z del J votlac nevke.s 4or p%'y Gilawsy flart watd .' ~

(Use additional pages if required.)

2.3 Reason for New Procedure / Change / Deficiency Removal

% dorm 211o tricacrerita. tL_ em%l # cutrudg1 wh. mm 4 c pad:uig 6627 flut uwk' (-r s.'+.ll.3 A (Use additional pages if required.)

3. ~ Prepared by * -

d 6 Signature Tith -

Date l (1) 4.

Qualified Review (Check appropriate boxes) 4.a Cross Disciplinary Review Required? NO a YES [ (If Yes, complete 4.b below)

ORC Review Re ired O /JES X Reviewedby[/

-- -E Signature b b a-< d u m - '/-M - h.

, Titlp Date 4.b Cross Disciplinary Review Required (Signature /Date): E7e e o fa o Ene / o P&S / X QA M / Vl2/l&

c H . E' .

o R.W.

/ o Admin-S / o Mat .' /

/ o Trng. / o Admin /

o Chim. / o Sec. / o I&C /

I o Opa. / o Comp. / o /

o Maint. /- o Outages / o /

5. Responsible Department Head (Check appropriate box and sign):

5.a o Approved for Issue - / / _

5.b at Approved for ORC Review Q A4L/"/ /4-M-%

.y J' (2) 6. Temporary Procedure Change Preliminary Approval (Signature /Date)

Member Management Staff /

Senior Reactor Operator /

(2) 7. Temporary Procedure Change Final Approval (Signature /Date; required within 14 days of Preliminary Approval.) -

Responsible Dept. Head /

Manager, Callaway Plant /

(1) 8. Procedure Approval (Signature /Date)

Manager, Callaway Plant (1) Applicable for new procedures and [rocedure revisions only.

/ '/kdi-(2) Applicable for Temporary Procedure c.hanges only; not all signatures are required in these sections. See APA-ZZ-00101 Section 5.1 for approval requirements.

( CA-#33 02/24/86 L APA-ZZ-00101

O s

CALIAWAT PIANT NUCIEAA SATETT EVALUATION CHECELIST (10 CIR50.59-APPLICABILITT DETERMINATION)

O No,-

(1) CHECELIST APPLICABLE TO: I REV. (o TCN (2) 10CTR50.59 APPLICABILITY DETERfiINATION The procedure, procedure revision or change, or modification to which this evaluation is applicable represeents:

(2.1) Yes No A change to the plaat described in the TSAR including the RERP and Security Plant (2.2) Yes No A change to procedures as described in the TSAR including ,

the RERP and Security Plan? l (2.3) Yes No A test or experiment not described in the TSAR including the RERP and Security Plan?

(2.4) Yes No A change to the Technical Specifications?

(2.5) Yes No A change to plant structures, systems, or components.

If any question above is answered "Tes", this Checklist shall be forwarded to the Superintendent, Engineering, for completion of a Nuclear Safety Evaluation (CA-d1041) per APA-ZZ-00140.

(3) For changes to permanent plant equipment, provide justification below (Using the Unreviewed Safety Question Determination Guidelines - Attachment 7) as to why the change does not constitute a potential unreviewed safety question and why the responses to the above questions are "no". If a CA-fl041 form is required as indicated by a "yes" response to any of the questions of section (2), t.his need not be completed.

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CA-f133 12/03/85 APA-ZZ-00140

I OQR 8/8M Pago 1 of I m [, .ld \ DATE: S 1 /157, FRCM: b-PROCEDURE NO.: /ectsr T Rev. NO.: (

REFERENCES:

PROCEDURE COMM.ENT SHEET Note: For any comment listed, there must be an Action and Approval.

COMMENTS ACTION TAKEN ACTION ACCEPTABLE M b'N) .

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N N Submitted by: W w$ .:OI* *lll)h ATTACH TO PROCED UEST NORM h@SO cc: AD5R AD ufol (w/ comments) i l

e "PCP" Date April 29, 1986 Revision 6 UNION ELECTRIC COMPANY CALLAWAY PLANT PROCESS CONTROL PROGRAM Approved: u 4/>+/m 539-S Chariman, ORC' Date ORC Meeting number Reviewed: b Med

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' pdrintehdent, Radwaste 4 -M-8 6 Date  ;

Prepared by '

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' UNION C'hh[hh se PRIORITY ROUTING First H

Sec>nd RC

.s 1901 Gratiot Street. St. Louis 03 s E-At

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Donald F. Schnell Vce President

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FILGA August 27, 1986 Mr. James G. Keppler Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 ULNRC- 1366

Dear Mr. Keppler:

DOCKET NUMBER 50-483 CALLAWAY PLANT FACILITY OPERATING LICENSE NPF-30 SEMI-ANNUAL RADIOACTIVE EFFLUENT REPORT The enclosed Semi-Annual Effluent Report for the first half of 1986 is submitted pursuant to section 6.9.1.7 of the Callaway Plant Technical Specifications.

Very truly yours, Donald F. Schnell DES /sjk Enclosure

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M SEP 2 1986 ,

Maihng Address: P.O. Box 14% St. Louis, MO 03100 l I

T l 1F' o cc distribution for ULNRC-1265 with enclosures Director, Resource Management U.S. Nuclear Regulatory Commission Washington, DC 20555 Director Office of Inspection & Enforcement U.S. Nuclear Regs11atory Commission Washington, DC 20555 Mr. Bill Kesler Regional Administrator '

Jefferson City Regional Office Department of Natural Resources P.O. Box 1368 Jefferson City, MO 65102 NRC Resident Inspector Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 (18 enclosures)

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