ML17250A954
| ML17250A954 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1989 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909060292 | |
| Download: ML17250A954 (34) | |
Text
,ACCZEZMTZO 31 BUTION DEMONSTR TION SYrrEX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8909060292 DOC.DATE: 89/06/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION R
SUBJECT:
"Semiannual Radioactive Effluent Release Rept." W/890828 ltr. I DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports S
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 3 3 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 IRM TECH ADV 1 1 2 2 NUDOCS-ABSTRACT 1 1 1 1 RGN1 DRSS/RPB 2 2 1 1 EXTERNAL I BNL T CHLER g J0 3 1 1 EGGG SIMPSONi F NRC PDR 2
1 2
1 LPDR 1 1 h
TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19
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Ill IIIIIIII II)IIIIIII III IIIIIIIIIII t /LID Oa ( ~ 1 STATIC ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 ZCLCpHONE AeL*cooa7ie 546-2700 August 28, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Semiannual Radioactive Effluent Release Report R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Sirs:
This Semiannual Radioactive Effluent Release Report is being submitted in accordance with the requirements of Technical Specification Section 6.9.1.4.
Very truly yours, Robert C. ec y 85'09060292 890630 Foe eDOCK oa0002~Z
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Copies to:
Mr. William T. Russell Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA l9406 Resident NRC Inspector Ginna Station Ms. Donna Ross New York State Energy Office Empire State Plaza Albany, NY l2223 American Nuclear Insurers MAELU The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 ATTN: Winthrop Hayes Central Records, Ginna Station Category 2.22.2
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244
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TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 REGULATORY LIMITS 2.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2.3 RELEASE RATE LIMITS 2.4 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 2.5 BATCH RELEASES 2.6 ABNORMAL RELEASES 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTE 6.0 LOWER LIMIT OF DETECTION 7.0 RADIOLOGICAL IMPACT 8.0 METEOROLOGICAL DATA 9 ' LAND USE CENSUS CHANGES 10.0 ANNUAL TABULATION OF PERSONNEL EXPOSURE 11.0 LEAK TEST OF SEALED SOURCES 12.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL 13.0 CHANGES TO THE PROCESS CONTROL PROGRAM 14.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS
LIST OF TABLES Table lA Gaseous Effluents Gaseous Summation of all Releases Table 1B Gaseous Effluents Continuous and Batch Releases Table 2A Liquid Effluents Summation of all Releases Table 2B Liquid Effluents Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4 Release Permits Not Meeting LLD Requirements
1.0 INTRODUCTION
This Semiannual Radioactive Effluent Release Report is for Rochester Gas and Electric Corporation's R.E. Ginna plant and is submitted in accordance with the require-ments of Technical Specification Section 6.9.1.4. The report covers the period from January 1, 1989 through June 30, '1989.
This report includes a summary o f the quantities o f radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.
All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications.
2.0 SUPPLEMENTAL INFORMATION 2.1 Re ulator Limits The Technical Specification limits applicable to release of radioactive material in liquid and gaseous effluents are:
2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield
< 500 mrem/yr to the total body and < 3000 mrem/yr to the skin if allowed to continue for a full year.
The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:
(i) During any calendar quarter to < 10 mrad for gamma radiation and to < 20 mrad for beta radiation.
2 ' ~ 2 Radioiodine Tritium and Particulates The instantaneous dose rate, as calculated in the ODCMg due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and.radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield <
1500 mrem/yr to any organ if allowed to continue for a full year.
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The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:
(i) During any calendar quarter to < 7.5 mrem to any organ.
(ii) During any calendar year to < 15 mrem to any organ.
2 ' ' Li id Effluents The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20. For dissolved or entrained noble gases the total activity due to dissolved or entrained'oble gases shall not exceed 2 E-04 uCi/ml.
The dose or dose commitment. to an individual as calcu-lated in the ODCM from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
(i) During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and (ii) During anyto calendar year to < 3 mrem to the total body and < 10 mrem to any organ.
2.2 Maximum Permissible Concentrations MPC 2.2.1 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 ' ' For liquid effluents, the maximum permissible concen-tration values specified in 10CFR20, Appendix B, Table II, column 2 are used to calculate release rates and permissible concentrations at the unrestricted area boundary. A value of 2E-04 uCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
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2 ' Release Rate Limits The release rate limits for fission and activation gases from the R.G.&E Ginna plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable. However, the average energy of the radionuclide mixture was 0.448 Mev.
2.4 Measurements and A roximations of Total Radioactivit Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concen-tration of gaseous and liquid effluents. Composite samples were analyzed for Sr-89, Sr-90 and Fe-55 by a contract laboratory. Tritium and alpha analysis were done using liquid scintillation and gas flow proportional counting respectively.
The total radioactivity in effluent releases were deter-mined from the measured concentration of each radio-nuclide present in grab or composite samples and the total volume of effluents released.
2.5 Batch Releases 2.5. 1 ~Li uid 1~
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Number of batch release:
Total time period for batch releases:
5 '3 E+02 5.78 E+04 3 ~ Maximum time period for a batch release: 4.96 E+03 4 ~ Average time period for batch releases: 1.15 E+02 5~ Minimum time period for a batch release: 1.1 E+Ol 6~ Average stream flow (LPM) during periods of release effluent into a flowing stream: 9.05 E+05 2.5.2 Gaseous 1~ Number of batch releases: l. 1E+01 2 ~ Total time period for batch releases: 5.18E+03 min 3 ~ Maximum time period for a batch release: 7.26E+02 min 4 ~ Average time period for batch releases: 4. 71E+02min 5 ~ Minimum time period for a batch release: 2. 31E+02 min 2~6 Abnormal Releases There were no abnormal releases of liquid or gaseous effluents during the reporting period.
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3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A and 1B.
The effluent release heights of the majority of releases were considered to be elevated. Gaseous effluent totals now include C-14 release quantities.
4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.
5.0 SOLID WASTES The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in Table 3.
Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type.
6 ' LOWER LIMIT OF DETECTION NOT MET There were 26 liquid releases for which 1 or more gamma emitting radionuclide did not meet the required lower limit for detection. These are listed by release number in Table 4.
7.0 RADIOLOGICAL IMPACT An assessment of doses to the maximally exposed indivi-dual from gaseous and liquid effluents will be performed and reported in the July - December, 1989 Semi-Annual Report for the year of 1989.
8~0 METEOROLOGICAL DATA Not applicable for this report.
9.0 LAND USE CHANGES Not applicable for this report.
10.0 ANNUAL TABULATION OF PERSONNEL EXPOSURE This data will be in the report issued for July-December, 1989.
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LEAK TEST OF SEALED SOURCES No sealed sources were found to be leaking when smeared by both wet and dry smears.
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
Minor typographical and wording changes as a result of a periodic review were made to the procedural documen-tation of the ODCM. Some of the tables were also replaced to improve legibility. These changes were made to improve readability and legibility. The changes do not affect the accuracy or reliability of the dose calculations or setpoint determinations. The procedure change was reviewed by PORC and approved on 3/8/89.
CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
The procedure documenting the Process Control Program was changed to include the Technical Specification reporting requirements to the procedure. This change does not affect any of the waste processing methods.
The procedure was review by PORC and approved on 6/28/89.
MAJOR CHANGES TO RADNASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.
Table 1A EFFZVENT AND WASTE DISPOSAL SZ2KEANNVAL REPORT GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January - June, 1989 Unit )Quarter )Quarter )Est. Total)
Error 0 A. Fission & activation gases
- 1. Total release Ci 1.51E+Ol 5.21E+00 7.0 E+00
- 2. Avera e release rate for eriod uCi sec 1.94E+00 6.55E-Ol
- 3. Percent of technical s ecification limit % 3.08E-04 6.18E-05 B. Iodines
- 1. Total iodine-131 Ci 2.29E-04 2.25E-05 4.3 E+01
- 2. Avera e release rate for eriod uCi sec 2.95E-05 2.83E-06
- 3. Percent of technical s ecification limit 4 6.47E-02 6.22E-03 C. Particulates
- 1. Particulates with half-lives > 8 da s Ci 5.00E-01 7.68E-01 3.0 E+01
- 2. Avera e release rate for eriod uCi sec 6.43E-02 9.66E-02
- 3. Percent of technical s ecification limit 4 3.42E-06 5.14E-06
- 4. Gross al ha radioactivit ci 2.24E-06 D. Tritium
- 1. Total release Ci 1.43E+01 3.16E+01 3.2 E+00
- 2. Avera e release rate for eriod uCi sec 1.84E+00 3.98E+00
- 3. Percent of technical s ecification limit 0 2.16E-04 4.68E-04
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Table 1B EFEXZH2lT AND HASTE DISPOSAL SEMIANKJAL REPORT GASEOUS EFFLUENTS EZZVATED RELEASE January June, 1989 CONTINUOUS MODE BATCH MODE Nuclides Released Unit uarter arter uarter arter
- 1. Fission gases k ton-85 Ci k ton-85m Ci 3.66E-02 8.69E-03 k ton-87 Ci 7.48E-02 1.25E-02 k ton-88 Ci 9.25E-02 2.00E-02 xenon-133 Ci 6.06E+00 2.77E+00 2.26E+00 xenon-135 Ci 4.74E+00 2.08E+00 5.50E-03 xenon-135m Ci 8.81E-01 1.15E-Ol xenon-138 Ci 3.05E-01 3.89E-02 Others s ecif Ci xenon-131m Ci 1.14E-01 2.19E-02 9.69E-04 xenon-133m Ci 6.94E-03 3.18E-03 3.25E-02 ar on-41 Ci 5.35E-Ol 1.40E-Ol Total for eriod Ci 1.28E+Ol 5.21E+00 2.30E+00
- 2. Iodines iodine-131 Ci 3.45E-05 1.72E-05 iodine-133 Ci 1.94E-04 5.31E-06 iodine-135 Ci Total for eriod Ci 2.29E-04 2.25E-05
- 3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci 3.63E-06 3.24E-06 barium-lanthanum-140 Ci Others s ecif Ci carbon-14 Ci 5.00E-Ol 7.68E-01 4.50E-Ol 5.40E-01 cobalt-58 Ci 2.18E-05 cobalt-60 Ci 3.99E-05 unidentified Ci 5.42E-06 2.10E-04 Note: Isotopes for which no value is given were not identified in applicable releases.
- Sample sent out for analysis but results not yet received. Data for identified isotopes will be included with next semi-annual report for July - December, 1989.
AI Table 2A EFEIDENT AND MSTE DISH3EBL LIQUID EPPIIJ12lTS SUMMATION OF ALL R1K2WBES January June, 1989 J
Unit (Quarter ]Quarter /Est.Total]
A. Fission and activation products
)1. Total release (not including tritium, ases al ha Ci 2.25E-02 4.25E-02 1.1 E+01 (2. Average diluted concentration I I I dur iod uCi ml 1.80E-10 3.83E-10
- 3. Percent of a licable limit 2.38E-02 5.31E-03 B. Tritium
- 1. Total release Ci 1.82E+02 1.72E+02 3.2 E+00 (2. Average diluted concentration I I I I dur icd uCi ml 1.48E-06 1.55E-06
- 3. Percent of a licable limit 4.93E-02 5.17E-02 C. Dissolved and entrained gases
- 1. Total release Ci 1.67E-04 3.0 E+01
]2. Average diluted concentration I I I dur iod uCi ml 1.34E-12
- 3. Percent of a licable limit 1.34E-06 D. Gross alpha radioactivity
- 1. Total release Ci E. Volume of waste released rior to dilution liters 3.05E+07 2.63E+07 5.0 E+00 F. Volume of dilution water used dur'od liters 1.25E+ll 1.11E+11 5.0 E+00
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Table 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS January June, 1989 CONTINUOUS MODE BATCH MODE Nuclides Released Unit uarter uarter uarter uarter 1 2 1 2 strontium-89 Ci 3.62E-05 strontium-90 ci cesium-134 Ci 2.53E-06 2.02E-04 1.33E-03 cesium-137 Ci 2.81E-04 1.20E-04 2.43E-03 5.03E-03 iodine-131 Ci 8.82E-06 5.35E-05 5.94E-03 2.38E-03 cobalt-58 Ci 5.05E-05 6.39E-05 1.40E-04 6.50E-03 cobalt-60 Ci 5.05E-07 1.92E-04 2.34E-03 iron-59 Ci zinc-65 Ci 9.29E-09 man anese-54 Ci 5.42E-07 2.43E-04 chromium-51 Ci 1.70E-06 6.25E-06 zirconium-niobium-95 Ci 7.36E-06 1.18E-04 mol bdenum-99 2.36E-05 5.80E-05 technetium-99m Ci barium-lanthanum-140 Ci 3.34E-06 1.79E-05 cerium-141 Ci 9.50E-06 1.44E-04 Other s ecif Ci silver-110m Ci 3.45E-05 4.95E-04 antimon -124 C1 2.40E-08 2.08E-05 1.17E-02 antimon -125 C1 5.35E-05 5.15E-06 5.94E-03 iodine-133 Ci 4.16E-05 8.89E-05 8.53E-03 4.08E-03 iodine-135 Ci 5.19E-05 2.20E-06 4.49E-03 1.69E-03 unidentified C1 Total for eriod above Ci 4.70E-04 3.85E-04 2.20E-02 4.21E-02 xenon-133 Ci 1.67E-04 xenon-135 Ci NOTE: Isotopes for which no value is given were not, identified in applicable releases.
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Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total
- l. T e of waste Unit Period
(
Error (a. Spent. resins, filter sludges, m 3.41E+00i 2E+00 eva orator bottoms etc. Ci 3.22E+01 5E+00
[b. Dry compressible waste, con- m 9.15E+Oli 2E+00 taminated e ui etc. Ci 1.06E+Ol 5E+00
)c. Irradiated components, control m rods etc. Ci (d. Other (describe) m Ci
- 2. Estimate of major nuclide composition (by type of waste)
- a. Co-60 3.7E+01 Cs-137 2.5E+01 Fe-55 1.1E+Ol Ni-63 1.0E+Ol Cs-134 5.9E+00 Mn-54 3.0E+00 Co-58 2.4E+00 H-3 1 ~ 6E+00 Sb-125 1.3E+00
- b. Fe-55 3.9E+01 Ni-63 3.3E+01 Co-60 1.6E+Ol Co-58 6.0E+00 Sr-90 2.0E+00 C-14 2.0E+00 Cs-137 1.0E+00
- 3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 50 Highway Vehicle Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shi ments Mode of Trans ortation Destination NONE 13
~ I Table 4 RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No. Date Isoto es Cause I I 240 13/29/89 (Fe-59, Zn-65, Ce-141 a ~
241 13/29/89 (Fe-59, Zn-65, Ce-141 a~
243 13/29/89 I Ce-141 a~
287 I 4/15/89 (Fe-59, Zn-65, Ce-141 a~
288 I 4/15/89 (Ce-141 a ~
306 (4/23/89 (Fe-59, Zn-65, Ce-141 a ~
307 (4/23/89 (Fe-59, Zn-65, Ce-141 a~
336 15/4/89 (Fe-59, Zn-65 a ~
341 I 5/5/89 (Fe-59, Zn-65, Cs-134, Ce-141 a ~
347 I 5/8/89 (Cs-134 a ~
375 I 5/19/89 IFe-59, Zn-65, Ce-141 a ~
376 I 5/19/89 (Fe-59, Co-60, Zn-65, Cs-134, Ce-141 'a ~
378 I 5/19/89 (Mn-54, Fe-59, Zn-65, Cs-134, Ce-141, I I I-131 a0 379 I 5/20/89 (Cs-134 a ~
382 I 5/2 0/89 (Mn-54, Fe-59, Co-60, Zn-65, I-131, I
Cs-13 4, Cs-137 a ~
413 (5/29/89 IFe-59, Zn-65, Cs-134 a ~
417 (5/30/89 (Cs-134 a ~
462 I 6/17/89 IFe-59, Zn-65, Ce-141, Ce-144 a ~
464 I 6/17/89 (Fe-59, Zn-65 a ~
466 I 6/17/89 (Fe-59, Zn-65, Ce-141 a ~
495 16/23/89 (Zn-65 a ~
507 (6/26/89 (Fe-59, Zn-65 a ~
512 16/27/89 (Fe-59, Zn-65, Cs-134 a ~
514 (6/27/89 (Fe-59, Zn-65 'a ~
518 (6/28/89 (Fe-59, Zn-65, Cs-134, Ce-141 a ~
522 16/29/89 (Fe-59, Zn-65 a ~
- a. Activity from other isotopes caused an increased background resulting in the LLD calculation exceeding 5E-07 uCi/ml for the listed isotopes.
The higher than normal occurrences of exceeding LLD requirements were due to the following:
Due to the 10 Year ISI program, the reactor cavity was flooded for 21 days instead of the normal 7 days. This significantly increased the amount of liquid waste water which required processing.
2 ~ The increased quantity of waste water required the use of the recycle evaporator to process waste water. This evapora-tor system is not as efficient as the waste evaporator system which resulted in an increased concentration of contaminants in the releases.
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