ML18153A294

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Annual Radioactive Effluent Release Rept for Surry Power Station for 970101-1231.
ML18153A294
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1997
From: Blount P
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18151A392 List:
References
NUDOCS 9804160356
Download: ML18153A294 (28)
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Text

ATTACHMENT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (January 1, 1997 Through December 31, 1997)

  • Prepared By: I~ ~ 7£'~j-

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Radiological Protection l

9804-160356 980408 PDR ADOCK 05000280 R PDR

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (January 1, 1997 Through December 31, 1997)

Index Section No. Subject Page 1 Executive Summary 1 2 Purpose and Scope 2 3 Discussion 3 & 4 4 Supplemental Information 5 Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM)

Attachment 4 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Analysis

FORWARD This report is submitted as required by Appendix A to Operating License No.' s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.B.3 .

  • EXECUTIVE

SUMMARY

ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT The Annual Radiological Effluent Release Report describes the radiological effluent control program conducted at the Surry Power Station during the 1997 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the Surry Power Station in accordance with R. G. 1.21 and includes an assessment of radiation doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents.

There were no unplanned gaseous effluent releases and two unplanned liquid effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual during this reporting period.

The releases are discussed in Attachment 6.

Based on the 1997 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

1. The total body dose due to liquid effluents was 8.25E-04 mrem, which is 1.38E-02% of the 6 mrem dose limit. The critical organ doses due to liquid effluents, GI-LLI and Thyroid respectively, were 2.lBE-03 mrem and 2.57E-04 mrem. These doses are 1.09E-02% and 1.29E-03% of the respective 20 mrem dose limit.
2. The air dose due to noble gases in gaseous effluents was 1.72E-01 mrad gamma, which is 8.60E-01% of the 20 mrad gamma dose limit, and 5.58E-01 mrad beta, which is 1.40E+OO% of the 40 mrad beta dose limit.
3. The critical organ dose from gaseous effluents due to I-131, I-133, H-3, and particulates with half-lives greater than 8 days is 7.42E-02 mrem, which is 2.47E-01%

of the 30 mrem dose limit.

There were no major changes to the radioactive liquid, gaseous and solid waste treatment systems during this reporting period.

There was one change to VPAP-2103, Offsite Dose Calculation Manual, during this reporting period. Attachment 3 provides the changes to VPAP-2103.

Based on the radioactivity measured and the dose calculations performed during this reporting period, the operation of Surry Nuclear Power Station has resulted in negligible radiation dose consequences to the maximum exposed member of the public in unrestricted areas .

  • 1
  • Purpose and Scope The Radioactive Effluent Release Report, Attachment 1, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly basis following the format of Tables 1, 2 and 3 of Appendix B thereof. Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6.

As required by Technical Specification 6. 8 .B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.

Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 10CFR50. 59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report .

  • 2

_ _J

  • Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM section, 6.3.1, which requires that the dose rate for iodine - 131, iodine - 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mRem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid, inhalation pathway.

The basis for the calculation of the percent of technical specification for the total body and skin in Table lA of Attachment 1, is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be 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 basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is the ODCM, section 6.2.1, which states that the concentration of radioactive material releases in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 10CFR2 0, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/ml.

Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being either the thyroid gland or gastrointestinal-lower large intestine. The total body dose was also determined for this individual .

  • 3
  • Presented in Attachment 6 is a list of unplanned gaseous and liquid releases as required by the ODCM, Section 6.7.2.

The typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis) . Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower level of detection, then the totals for this period will be designated as Not Applicable (N/A) .

  • 4
  • Supplemental Information Section 6.6.1.b.4 of the ODCM requires the identification of the cause (s) for the unavailability of milk or if required, leafy vegetation samples, and the identification for obtaining replacement samples. As all milk samples were available for collection during this reporting period, leafy vegetation sampling was not required.

As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program. Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the radiological environmental monitoring program .

  • 5
  • EFFLUENT RELEASE DATA Attachment 1 (January 1, 1997 Through December 31, 1997)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B .

Attachment 1 TABLE lA Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • PERIOD 1/1/97 TO 12/31/97 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND  % EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES
1. TOT AL RELEASE Ci 4.66E+02 l.89E+Ol l.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec 5.99E+Ol 2.41E+OO B. IODINE
1. TOTAL 1-131 Ci 3.54E-03 l.29E-04 2.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec 4.55E-04 l.64E-05 C. PARTICULATE
1. HALF-LIFE >8 DAYS Ci l.32E-05 2.76E-05 2.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec l.70E-06 3.51E-06 3 . GROSS ALPHA RADIOACTIVITY Ci N/D N/D
1. TOT AL RELEASE Ci 7.0lE+OO 7.77E+OO 3.lOE+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec 9.02E-01 9.89E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 3.41E-02 5.51E-03 TOTAL BODY DOSE RATE  % l.18E-01 3.98E-04 SKIN DOSE RATE  % 4.96E-02 l.63E-04 I_

Attachment 1 TABLE lA Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • SURRY POWER STATION UNITS 1&2 PERIOD 1/1/97 TO 12/31/97 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES
1. TOTAL RELEASE Ci 4.59E+OO 7.82E+OO l.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec 5.78E-01 9.83E-01 B. IODINE
l. TOTAL 1-131 Ci N/D 7.46E-06 2.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec NIA 9.38E-07 C. PARTICULATE
1. HALF-LIFE > 8 DAYS Ci l .33E-06 l.85E-05 2.80E+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec l.67E-07 2.33E-06
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
  • 1. TOTAL RELEASE Ci 9.96E+OO l.51E+Ol 3.lOE+Ol
2. AVE RELEASE RATE FOR PERIOD µCi/sec l.25E+OO l.89E+OO PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 5.55E-03 8.54E-03 TOT AL BODY DOSE RATE  % 5.05E-05 7.86E-05 SKIN DOSE RATE  % l.89E-05 3.02E-05

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • PERIOD: 1/1/97 TO 12/31/97 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER
1. FISSION & ACTIVATION GASES Kr-85 Ci 3.08E-01 NID 2.18E+OO 8.75E-01 Kr-85m Ci l .19E-03 NID 8.12E-04 l.17E-04 Kr-87 Ci N/D NID N/D N/D Kr-88 Ci NID N/D N!D N!D Xe-133 Ci l.05E+Ol 2.39E-02 l.85E+02 l.62E+Ol Xe-135 Ci 2.88E-02 NID 7.36E-04 l.31E-02 Xe-135m Ci NID NID N!D NID Xe-138 Ci NID NID N/D NID Xe-131m Ci l.58E-01 3.05E-02 3.70E+OO 1.20E+OO Xe-133m Ci 8.31E-02 NID 5.88E-01 6.78E-03 Ar-41 Ci l.51E-05 N/D 7.33E-05 N/D TOT AL FOR PERIOD Ci l.llE+Ol 5.44E-02 l.92E+02 l.83E+Ol
  • 2. IODINES 1-131 1-133 1-135 Ci Ci Ci 5.54E-08 N/D N/D 2.88E-08 NID N/D N!D N!D N/D NID NID NID TOT AL FOR PERIOD Ci 5.54E-08 2.88E-08 NIA NIA
3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci N/D NID NID NID Cs-134 Ci NID NID NID NID Cs-137 Ci 8.44E-09 5.38E-09 N!D NID Co-58 Ci NID NID N/D NID Co-60 Ci NID 5.45E-09 NID NID Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID N!D NID Zn-65 Ci NID NID N!D NID Mo-99 Ci N!D NID NID N!D Ce-141 Ci N/D NID NID NID Ce-144 Ci N/D N!D N!D NID Ba-140 Ci NID NID N!D NID NID La-140 Ci NID NID NID TOTAL FOR PERIOD Ci 8.44E-09 l.08E-08 NIA NIA

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • PERIOD: 1/1/97 TO 12131/97 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER
1. FISSION & ACTIVATION GASES Kr-85 Ci NID N/D NID N/D Kr-85m Ci NID 2.llE-04 3.87E-03 4.34E-04 Kr-87 Ci NID N/D N/D 9.15E-05 Kr-88 Ci N/D N/D 2.26E-04 l.34E-04 Xe-133 Ci l.OOE+OO 3.20E-01 3.30E+00 7.26E+OO Xe-135 Ci 8.56E-02 3.77E-03 l.42E-01 l.48E-02 Xe-135m Ci NID NID NID N/D Xe-138 Ci N/D NID N/D N/D Xe-131m Ci NID 3.29E-04 l.61E-03 l.71E-01 Xe-133m Ci NID 2.0lE-03 5.81E-02 l.90E-02 Ar-41 Ci N/D N/D l.02E-03 9.55E-03 TOTAL FOR PERIOD Ci l.09E+OO 3.26E-01 3.50E+OO 7.48E+00
  • 2. IODINES 1-131 133 1-135 Ci Ci Ci NID NID NID N/D NID N/D N/D NID NID N/D N/D N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA
3. PARTICULATES Sr-:S9 Ci NID N/D NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci NID NID N/D NID Cs-137 Ci 5.71E-09 5.07E-09 NID N/D Co-58 Ci N/D NID NID NID Co-60 Ci 4.91E-09 4.39E-10 NID NID Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID NID N/D Zn-65 Ci NID NID N/D N/D Mo-99 Ci NID NID NID N/D Ce-141 Ci NID NID NID N/D Ce-144 Ci NID N/D N/D N/D Ba-140 Ci NID NID N/D N/D La-140 Ci N/D NID NID N/D
  • TOTAL FOR PERIOD Ci l.06E-08 5.51E-09 NIA NIA

Attachment 1 TABLElC Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • PERIOD:1/1/97 TO 12/31/97 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER
1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D l.25E+Ol N/D Kr-85m Ci 1.42E-03 NID N/D N/D Kr-87 Ci 1.48E-03 N/D NID NID Kr-88 Ci 8.64E-04 N/D NID NID Xe-133 Ci 3.65E+Ol 5.99E-01 2.11E+02 3.69E-03 Xe-135 Ci l.65E-02 l.26E-04 2.47E-01 N/D Xe-135m Ci 7.21E-03 2.67E-04 N/D N/D Xe-138 Ci l.96E-04 N/D NID N/D Xe-131m Ci NID NID l.15E+OO 3.0SE-03 Xe-133m Ci N/D N/D l.20E+00 NID Ar-41 Ci 2.03E-03 l.07E-04 N/D N/D TOT AL FOR PERIOD Ci 3.65E+Ol 6.00E-01 2.26E+02 6.73E-03

. 2 . IODINES 1-131 Ci 3.25E-03 l.21E-04 2.87E-04 8.23E-06 1-132 Ci N/D N/D l.14E-06 N/D 1-133 Ci 2.36E-04 N/D l.OlE-05 N/D 1-135 Ci N/D NID N/D N/D TOTAL FOR PERIOD Ci 3.49E-03 l.21E-04 2.98E-04 8.23E-06

3. PARTICULATES Sr-89 Ci NID N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci NID N/D N/D N/D Cs-137 Ci 4.69E-05 2.38E-05 N/D N/D Co-58 Ci l.07E-05 l.44E-05 N/D l.67E-08 Co-60 Ci 2.16E-05 l.53E-05 l.13E-08 NID Mn-54 Ci N/D N/D N/D NID Fe-59 Ci N/D NID NID N/D Zn-65 Ci N/D NID N/D N/D Mo-99 Ci N/D N/D N/D NID Ce-141 Ci N/D NID N/D N/D Ce-144 Ci NID NID N/D N/D Ba-140 Ci N/D NID N/D NID La-140 Ci N/D N/D NID N/D
  • TOTAL FOR PERIOD Ci 7.92E-05 5.35E-05 l.13E-08 l.67E-08

Attachment 1 TABLE lC Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • PERIOD:1/1/97 TO 12131/97 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER
1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D NID NID Kr-85m Ci 7.91E-06 2.54E-04 NID N/D Kr-87 Ci NID 2.38E-04 NID NID Kr-88 Ci N/D N/D N/D NID Xe-133 Ci 2.56E-05 5.30E-03 NID 4.15E-03 Xe-135 Ci 7.89E-04 2.60E-03 NID NID Xe-135m Ci 7.13E-04 7.91E-04 NID N/D Xe-138 Ci NID NID NID NID Xe-131m Ci NID NID NID N/D Xe-133m Ci N/D N/D NID NID Ar-41 Ci l.42E-04 l.13E-04 NID NID TOT AL FOR PERIOD Ci l.68E-03 9.30E-03 NIA 4.15E-03

. 2 . IODINES 1-131 Ci N/D 7.45E-06 NID 7.23E-09 1-133 Ci N/D NID NID N/D 1-135 Ci N/D NID NID N/D TOT AL FOR PERIOD Ci NIA 7.45E-06 NIA 7.23E-09

3. PARTICULATES Sr-89 Ci NID NID NID N/D Sr-90 Ci NID N/D NID N/D Cs-134 Ci NID NID N/D N/D Cs-137 Ci 7.91E-07 6.19E-07 N/D N/D Co-58 Ci NID 4.54E-06 NID l.86E-08 Co-60 Ci NID 5.71E-06 NID NID Mn-54 Ci N/D N/D NID N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D
  • Cr-51 Se-75 TOTAL FOR PERIOD Ci Ci Ci N/D 5.30E-07 l.32E-06 7.64E-06 N/D l.85E-05 N/D N/D NIA N/D N/D 1.86E-08

Attachment 1 TABLE2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • SURRY POWER STATION UNITS 1&2 PERIOD: 1/1/97 TO 12/31/97 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES UNIT FIRST SECOND  % EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS
1. TOT AL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 3.06E-02 l.21E-01 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 4.94E-ll l.81E-I0
3. PERCENT OF APPLICABLE LIMIT  % l.31E-04 5.03E-04 B. TRITIUM
1. TOTAL RELEASE Ci 5.03E+02 l.35E+02 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 8.13E-07 2.02E-07
3. PERCENT OF APPLICABLE LIMIT  % 8.13E-04 2.02E-03 C. DISSOLVED AND ENTRAINED GASES
1. TOT AL RELEASE Ci 2.78E-03 9.17E-04 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 4.49E-11 l.37E-12
3. PERCENT OF APPLICABLE LIMIT  % 2.25E-06 6.86E-07 D. GROSS ALPHA RADIOACTIVITY
1. TOT AL RELEASE Ci N/D N/D 2.00E+Ol E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 4.94E+07 5.94E+07 3.00E+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.19E+ 11 6.68E+ll 3.00E+OO

Attachment 1 TABLE2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • SURRY POWER STATION UNITS 1&2 PERIOD: 1/1/97 TO 12/31/97 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS
1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci l.72E-01 8.14E-02 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 2.21E-10 l.22E-10
3. PERCENT OF APPLICABLE LIMIT  % 2.42E-04 5.14E-04 B. TRITIUM
1. TOT AL RELEASE Ci 2.79E+02 l.93E+02 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 3.59E-07 2.89E-07
3. PERCENT OF APPLICABLE LIMIT  % 3.59E-03 2.89E-03 C. DISSOLVED AND ENTRAINED GASES
1. TOT AL RELEASE Ci 3.24E-04 l.64E-04 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 4.16E-13 2.46E-13
3. PERCENT OF APPLICABLE LIMIT  % 2.0SE-07 l.23E-07 D. GROSS ALPHA RADIOACTIVITY
l. TOTAL RELEASE Ci N/D N/D 2.00E+Ol E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 6.64E+07 l.18E+08 3.00E+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.78E+ll 6.67E+ll 3.00E+OO

Attachment 1 Page 9 of 12 TABLE2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/97 TO 12131/97 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci NID NID N/D NID Sr-90 Ci NID NID N/D NID Cs-134 Ci 8.41E-06 N/D 3.78E-04 8.71E-03 Cs-137 Ci 2.94E-03 l.84E-04 2.47E-03 l.82E-02 I-131 Ci N/D NID 4.84E-04 9.27E-05 Co-58 Ci N/D l.21E-07 l.66E-02 4.37E-02 Co-60 Ci 3.97E-04 7.84E-05 1.82E-03 3.87E-03 Fe-59 Ci NID N/D 6.81E-05 9.61E-06 Zn-65 Ci NID NID N/D 3.56E-06 Mn-54 Ci NID NID 2.18E-05 l.79E-05 Cr-51 Ci NID NID 2.93E-04 l.lSE-03 Zr-95 Ci NID NID 2.46E-06 2.62E-06 Nb-95 Ci N/D NID 2.64E-05 2.97E-05 Mo-99 Ci N/D NID NID 3.86E-05 Tc-99m Ci N/D N/D 1.lSE-06 5.42E-06 Ba-140 Ci N/D NID NID NID La-140 Ci NID NID NID NID Ce-141 Ci NID NID 6.77E-07 3.71E-06 Sb-122 Ci NID NID 2.73E-06 l.70E-05 NID NID 8.67E-04 Sb-124 Ci 9.59E-04 Sb-125 Ci N/D NID 4.00E-03 4.38E-02 Co-57 Ci N/D N/D l.llE-05 8.SlE-05 Na-24 Ci N/D NID l.33E-06 2.39E~os Ce-139 Ci NID NID N/D 2.80E-06 Ru-103 Ci N/D NID l.44E-06 2.26E-06 Ag-llOm Ci N/D NID 2.33E-05 N/D Te-132 Ci N/D NID 3.71E-06 9.0lE-06 Cs-138 Ci N/D NID 5.86E-06 NID W-187 Ci N/D N/D N/D 4.90E-06 Np-239 Ci N/D NID 6.71E-06 1.40E-04 Ce-143 Ci NID N/D N/D 2.lOE-05 Mn-56 Ci NID NID l.52E-06 3.56E-06 Te-127m Ci N/D NID NID 2.75E-04 Ru-106 Ci N/D NID N/D 2.77E-05 Nd-147 Ci N/D N/D 3.41E-05 NID Am-241 Ci N/D NID NID 6.46E-06 I-132 Ci N/D N/D 4.29E-06 NID I-133 Ci N/D N/D 3.77E-06 NID Ce-144 Ci NID N/D N/D N/D Fe-55 Ci NID NID N/D NID TOTAL FOR PERIOD Ci 3.35E-03 2.63E-04 2.72E-02 l.21E-01 Xe-133 Ci NID NID 2.70E-03 4.lOE-05 Xe-135 Ci NID N/D 8.38E-06 2.78E-06 Xe-133m Ci N/D NID N/D 2.78E-05 Xe-135m Ci N/D NID N/D 8.34E-04 Kr-85m Ci N/D NID 1.00E-06 3.81E-06 Kr-87 Ci N/D NID N/D - 2.06E-06 Kr-88 Ci N/D N/D 7.93E-07 5.69E-06 Ar-41 Ci N/D N/D 6.93E-05 N/D TOTAL FOR PERIOD NIA NIA 2.78E-03 9.17E-04

1-Attachment 1 TABLE2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

  • SURRY POWER STATION UNITS 1&2 PERIOD: 1/1/97 TO 12131/97 LIQUID EFFLUENTS UNIT CONTINUOUS MODE THIRD QUARTER FOURTH QUARTER BATCH MODE THIRD QUARTER FOURTH QUARTER Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci 5.80E-06 2.70E-04 6.lOE-04 1.13E-02 Cs-137 Ci 6.12E-03 5.41E-03 1.14E-03 1.25E-02 1-131 Ci NID NID 3.30E-05 2.72E-05 Co-58 Ci N/D 8.30E-05 6.95E-02 l.95E-02 Co-60 Ci 2.23E-03 6.56E-04 1.14E-02 3.73E-03 Fe-59 Ci NID NID NID N/D Zn-65 Ci N/D NID NID l.OSE-05 Mn-54 Ci NID NID 8.21E-06 2.18E-05 Cr-51 Ci NID NID 2.lSE-03 4.lOE-04 Zr-95 Ci N/D NID 8.21E-06 l.77E-05 Nb-95 Ci NID NID 2.02E-06 2.14E-05 Mo-99 Ci N/D N/D l.04E-05 5.70E-06 Tc-99m Ci N/D NID NID 2.69E-06 Ba-140 Ci N/D NID l.77E-05 1.00E-05 La-140 Ci N/D NID NID NID Ce-141 Ci NID N/D l.62E-06 N/D Sb-122 Ci NID NID 2.75E-06 NID Sb-124 Ci NID NID 7.0lE-04 8.18E-04 NID NID Sb-125 Ci 7.34E-02 2.52E-02 Co-57 Ci NID NID 3.89E-04 5.07E-05 Se-75 Ci NID NID l.OOE-05 5.49E-07 Ce-139 Ci N/D NID NID 3.59E-07 Ru-103 Ci N/D NID NID 2.96E-06 Ag-llOm Ci NID NID 9.62E-07 NID Te-132 Ci NID NID l.23E-05 l.96E-06 Na-24 Ci N/D NID l.19E-05 NID Ru-106 Ci NID NID 3.58E-05 NID Np-239 Ci NID NID 3.20E-04 3.52E-05 Cs-138 Ci NID N/D l.OlE-05 l.OlE-04 1-133 Ci NID NID l.41E-05 3.83E-06 Ce-144 Ci N/D NID 4.21E-05 NID Ce-143 Ci N/D NID l.26E-05 NID Nd-147 Ci NID NID 2.67E-05 l.30E-05 Te-125m Ci NID NID 2.88E-03 l.OlE-03 Te-127m Ci NID N/D 7.96E-04 2.03E-04 Te-129m Ci N/D NID 4.21E-05 l.25E-04 Te-131m Ci NID NID 4.21E-05 5.12E-06 Fe-55 Ci NID NID N/D NID TOTAL FOR PERIOD Ci 8.36E-03 6.42E-03 l.64E-01 7.SlE-02 Xe-133 Ci NID NID 6.43E-06 7.82E-06

' )

Xe-135 Xe-131m Xe-133m Kr-85m Kr-85 Kr-87 Ci Ci Ci Ci Ci Ci NID N/D N/D N/D N/D N/D N/D NID NID N/D N/D N/D 3.75E-06 2.39E-04 4.41E-05 l.65E-05 NID 1.40E-05 2.16E-06 NID NID NID 1.SOE-04 4.21E-06 TOT AL FOR PERIOD Ci NIA NIA 3.24E-04 1.64E-04

TABLE3 Attachment 1 Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/97 - 12/31/97

' SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste 12 month Est. Total Period Error,%
a. Spent resins, filter sludges, evaporator m3 8.28E+Ol* l.OOE+Ol bottoms, etc. Ci 2.34E+02 3.00E+Ol
b. Dry compressible waste, contaminated m3 2.70E+02** LOOE+Ol equip., etc. Ci 9.68E+00 3.00E+Ol
c. Irradiated components, control m3 O.OOE+OO l.OOE+Ol rods, etc. Ci O.OOE+OO 3.00E+Ol
d. Other (Waste Oil, Sump Bottoms) m3 l .OOE+Ol *** l.OOE+Ol Ci 7.26E-04 3.00E+Ol
2. Estimate of major nuclide composition (by type of waste)
a. Ni-63  % 2.13E+Ol Co-60  % l.79E+Ol Cs-134  % l.64E+Ol Cs-137  % 1.59E+Ol Co-58  % l.14E+Ol Fe-55  % 9.55E+OO H-3  % 2.02E+OO
b. Co-60  % 2.93E+Ol Fe-55  % 2.51E+Ol Ni-63  % l.37E+Ol Co-58  % l.05E+Ol Cs-137  % 4.66E+OO Fe-59  % 4.35E+OO Cr-51  % 2.97E+00 Cs-134  % 2.92E+OO Zr-95  % l.72E+OO Sb-125  % l.65E+00 Nb-95  % l.63E+OO

' c.  %

TABLE3 Attachment 1 Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SIIlPMENTS PERIOD: 1/1/97 - 12/31/97 CONT'D SURRY POWER STATION A. SOLID WASTE SIIlPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

2. Estimate of major nuclide composition (by type of waste)
d. Ce-144  % 7.llE+Ol Cs-137  % l.39E+Ol Fe-55  % 8.03E+OO Co-60  % 6.54E+OO
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7 Truck Barnwell, SC (WMF) 8 Truck Barnwell, SC (CNCF) 7 Truck Oak Ridge; TN

'IRRADIATED FUEL SHIPMENT (Disposition)

Number of Shipments Mode of Transportation Destination 0

  • NOTE 1: 6.78E+Ol m3 of this was liquid shipped to a licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 9.19E+OO m3.
    • NOTE 2: 2.59E+02 m3 of the DAW was shipped to licensed waste processors for processing and/or volume reduction.

Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 7.97E+OO m3.

      • NOTE 3: Waste oil and sump bottoms were shipped to a licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is O.OOE+OO m3.

WMF: Waste Management Facility CNCF: Chem-Nuclear Consolidation Facility

Attachment 2 Page 1 of 1 ANNUAL AND QUARTERLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant to the ODCM, section 6.7.2 requirement.

LIQUID GASEOUS Total Body Thyroid GI-LLI Gamma Beta Thyroid (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter l.57E-04 l.32E-04 3.78E-04 l.71E-01 5.55E-01 7.05E-02 2nd Quarter 2.38E-04 3.18E-05 5.57E-04 5.98E-04 l.85E-03 2.79E-03 3rd Quarter l.67E-04 4.74E-05. 8.67E-04 7.31E-05 l.70E-04 2.86E-04 4th Quarter 2.63E-04 4.51E-05 3.76E-04 l.64E-04 3.00E-04 5.84E-04 Annual 8.25E-04 2.57E-04 2.18E-03 l.72E-01 5.58E-01 7.42E-02

Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.

A complete revision, Revision 8, was implemented during the period January 1 to December 31, 1996.

Revision 8 incorporates the previously reported changes to Revision 7 of the ODCM as well as the following changes associated with Surry Power Station:

1. Updated section 3.0 References/Commitment Documents.
2. Changed the required presentation of solid waste data in the Annual Radiological Effluent Report from a quarterly format to an annual format.
3. Clarified that separate effluent release reports are to be submitted for the power station and the Independent Spent Fuel Storage Installation, ISFSI.

' 4. Corrected typographical error to dose factor, Attachment 5.

5. Revised isotope listing, Attachment 10.

Revision 8 of the ODCM is included with this attachment.

Attachment 4 Page 1 of 1 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to Surry's Radioactive Liquid, Gaseous or Solid Waste Treatment Systems this reporting period.

Attachment 5 Page 1 of 1 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitors required by the ODCM Attachments 1 and 14, which were determined inoperable, were not returned to operable status within 30 days. None of the above referenced monitors were inoperable for 30 days during this reporting period.

Attachment 6 Page 1 of 1

' UNPLANNED RELEASES There were no unplanned gaseous releases and two unplanned liquid releases for this reporting period. The liquid releases originated from the overpressure relief valve on the heater to the lA

  • Primary Grade Water Tank. The release pathway to the discharge canal was through the storm drain adjacent to the lA Primary Grade Water Tank. The releases, summarized below, occurred 11/25/97 and 12/17/97.

Release Release Isotopes Concentration Curies Date Duration Released uCi/ml Released 11/25/97 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> H-3 l.23E-06 8.38E-06 Co-58 l.79E-08 l.22E-07 Cs-137 2.70E-08 1.84E-07 12/17/97 55 minutes H-3 3.06E-06 1.16E-05 Co-60 4.49E-08 l.70E-07 Cs-134 2.13E-08 8.06E-08

Attachment 7 Page 1 of 1 LOWER LEVEL OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS GASEOUS: Isotope Reguired LLD Typical LLD Kr-87 l.OOE-04 l.12E l.61E-07 Kr-88 1.00E-04 2.03E 2.21E-07 Xe-133 l.OOE-04 1.59E 1.70E-07 Xe-133m l.OOE-04 4.19E 6.18E-07 Xe-135 l.OOE-04 5.77E 8.03E-08 Xe-135m l.OOE-04 2.78E 3.06E-07 Xe-138 l.OOE-04 5.02E 7.13E-07 1-131 l.OOE-12 8.65E l.18E-13 1-133 l.OOE-10 9.51E-14 l.30E-13 Sr-89 l.OOE-11 1.00E 4.00E-13 Sr-90 1.00E-11 2.00E 6.00E-14 Cs-134 1.00E-11 5.58E 1.23E-13 Cs-137 1.00E-11 7.55E 1.59E-13 Mn-54 l.OOE-11 7.58E l.42E-13 Fe-59 1.00E-11 1.63E 2.66E-13 Co-58 l.OOE-11 5.19E 1.14E-13 Co-60 1.00E-11 8.93E 1.54E-13 Zn-65 l.OOE-11 1.51E 3.60E-13 Mo-99 l.OOE-11 4.22E 8.lOE-13 Ce-141 l.OOE-11 5.69E l.07E-13 Ce-144 1.00E-11 2.06E 4.21E-13 Alpha l.OOE-11 1.0SE 2.75E-12 Tritium l.OOE-06 5.02E 5.47E-08 LIQUID Sr-89 5.00E-08 1.00E 5.00E-08 Sr-90 5.00E-08 4.00E 3.00E-08 Cs-134 5.00E-07 1.08E 2.03E-08 Cs-137 5.00E-07 1.42E 2.61E-08.

1-131 l.OOE-06 l.12E 1.67E-08 Co-58 5.00E-07 1.08E 1.93E-08 Co-60 5.00E-07 l.30E 2.55E-08 Fe-59 5.00E-07 2.70E 4.08E-08 Zn-65 5.00E-07 2.61E 5.45E-08 Mn-54 5.00E-07 1.23E 2.29E-08 Mo-99 5.00E-07 6.93E 1.33E-07 Ce-141 5.00E-07 l.48E 1.97E-08 Ce-144 5.00E-07 5.26E 8.74E-08 Fe-55 l.OOE-06 3.00E 7.00E-07 Alpha 1.00E-07 5.94E 1.56E-08 Tritium 1.00E-05 2.14E 1.58E-06 Xe-133 1.00E-05 2.26E 3.78E-08 Xe-135 1.00E-05 7.64E 1.56E-08 Xe-133m 1.00E-05 5.79E 1.17E-07 Xe-135m 1.00E-05 3.38E 5.24E-08 Xe-138 1.00E-05 6.57E 1.33E-07 Kr-87 1.00E-05 1.46E 2.83E-08 Kr-88 1.00E-05 2.87E 4.29E-08

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