ML17055C669

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Semiannual Radioactive Effluent Release Rept for Jan-June 1986.
ML17055C669
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/30/1986
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17055C670 List:
References
NUDOCS 8612090556
Download: ML17055C669 (40)
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Text

NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1986 DOCKET NO.: 50-220 LICENSE NO.: DPR-63 NIAGARA MOHAWK POWER CORPORATION 8612090556 860829 PDR *DOCK 05000220 R PDR

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NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1986 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit //1 Licensee: Niagara Mohawk Power

'Corporation

1. Technical Specification Limits:

A) Fission and activation gases:

1. The dose rate limit of noble gases from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.
2. The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation and, during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.

B&C) Tritium, Iodines and Particulates, half lives > 8 days:

1. The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site, shall be less than or equal to 1500 mrems/year to any organ.
2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half lives greater than 8 days as part of gaseous effluents released from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrems to any organ and, during any calendar year to less than or equal to 15 mrems to any organ.

D) 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 gases. For dissolved or entrained noble gas, the concentration shall be limited to 2E-04 microcuries/ml total activity.

D. Liquid Ef fluents (Cont ' )

2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
2. Maximum Permissible Concentrations A) Fission and activation gases:

None specified BGC) Iodines and particulates, half lives > 8 days:

None specified D) Liquid Effluents:

10CFR 20, Appendix B, Table II, Column 2.

Avg MPC ( Jan. March ) no discharges Avg MPC ( April - June ) 2.90E-03 pCi/ml

3. Average Energy (Fission and Activation gases Mev)

Jan. March: Ey 0.543; Eg 0.641 April June: Z~ 0.673; ZB'.920

4. Measurements and Approximations of Total Radioactivity Described below are the general methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A) Fission and Activation Gases: Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli sample) of an isokinetic stack sample stream.

B) Iodines: Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges manually or automatically sampled from an isokinetic stack sample stream.

C) Particulates: Activity released from main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters manually or automatically sampled from an isokinetic sample stream.

For emergency condenser vent batch releases, effluent curie quantities are estimated by subtracting activity remaining in the shell side of the emergency condenser after batch release from activity delivered to the shell from Make-Up sources. Actual isotopic concentrations are found via gamma spectroscopy. Activities of Sr-89, Sr-90 and H-3 are estimated by applying scaling factors or condensate storage activity concentrations.

D) Tritium: Tritium effluent activity is estimated by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.

E) Liquid Effluents: Gamma spectroscopic analysis of a representative sample of each batch and composite analysis of non"gamma emitters.

F) Solid Effluents: Isotopic contents of waste shipments are determined by gamma spectroscopic, gross alpha and water content analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emmitters. For low activity trash shipments, curie content may be estimated by dose rate measurement.

5. Batch Releases The following information relates to batch releases of radioactive materials in liquid and gaseous effluents.

A) Liquid

1. Number of batch releases: 6
2. Total time period for batch releases: 28 hours 20 min .
3. Maximum time period for a batch release: 4 hours 50 min.
4. Average time period for a batch release: 4 hours 43 min.
5. Minimum time period for a batch release: 4 hours 30 min.
6. Average stream flow during period of release of effluent into a flowing stream: Not Applicable
7. Total volume of water used to dilute the liquid effluent during release periods 1.74E+00 GL
8. Total volume of water available to dilute the liquid effluent during reporting period 1.43E+02 GL B) Gaseous (Emergency Condenser Vents)
1. Number of batch releases: 3
2. Total time period for batch releases: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 35 min.
3. Maximum time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 20 min.

4~ Average time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 12 min.

5~ Minimum time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 5 min.

6. Abnormal Releases A. Liquids none B. Gaseous none

TABLE lA SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1st 2nd EST.TOTAL UNIT QUARTER QUARTER ERROR, X A. Fission & Activation ases

1. Total release Ci 2.34E+02 8.78E+00 2.5E+Ol
2. Average release rate for period pCi/sec 3.02E+01 1.12E+00
3. Percent of Technical Specification Limit B. Iodines
1. Total iodine"131 Ci 5.54E-03 1.53E-04 2.0E+01
2. Average release rate for period uCi/sec 7.12E-04 1.95E-05
3. Percent of Technical Specification Limit C. Particulates
1. Particulates with half-lives >8 days 4.46E-03 2.30E-03 2.5E+01
2. Average release rate for period pCi/sec 5.74E-04 2.93E-04
3. Percent of Technical Specification Limit,
4. Gross alpha radio-activity Ci 2.83E-05 3.62E-05 2.5E+01 D. Tritium
1. Total release 2. 72E+01 6.37E+00 2.0E+01
2. Average release rate for period pCi/sec 3.50E+00 8.10E-01
3. Percent of Technical Specification Limit

TABLE 1A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE (Cont'd) 1st 2nd UNIT QUARTER QUARTER E.* Percent of Technical S ecification Limits (NMP-1 Elevated Release)

Fission and Activation Gases:

1. Percent of Quarterly Gamma Air Dose Limit 9.48E-01 7.00E-02
2. Percent of Quarterly Beta Air Dose Limit 5.52E-01 4.77E-02
3. Percent of Annual Gamma Air Dose Limit to Date 4.74E-01 5.09E-01
4. Percent of Annual Beta Air Dose Limit to Date 2.76E-01 3.00E-01
5. Percent of Whole Body Dose Rate Limit 9.48E-03 7.00E-04.
6. Percent of Skin Dose Rate Limit 1.84E-03 1.59E-04 Tritium, Iodines and Particulates (with half-lives reater than 8 days):

Percent of Quarterly Dose Limit 2. 68E+00 7. 54E-01

2. Percent of Annual Dose Limit to Date 1.35E+00 1.37E+00
3. Percent of Organ Dose Rate Limit 1.34E-02 3. 78E-03

TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-ELEVATED RELEASE JANUARY JUNE CONTINUOUS MOD E Nuclides Released Unit

1. Fission Gases Argon-41 Ci lo93E+00 1.23E-01 Krypton-85m Ci 4.16E+00 2.99E-01 Krypton-87 Ci 2.52E+00 Krypton-88 Ci 1.38E+00 Xenon-133 Ci 3.63E+01 Xenon-135 Ci 1.41E+Ol 5.79E-01 Xenon-135m Ci 1.85E+01 5.88E-01 Xenon-137 Ci 7.82E+Ol 3.22E+00 Xenon-138 Ci 7.74E+01 3.97E+00
2. Iodines Iodine-131 5.54E-03 1.53E-04 Iodine-133 3.92E-02 <1.45E-03 Iodine-135 7.22E-02 <3.17E-03
3. Particulates Strontium-89 Ci 1.31E-03 7.14E-05 Strontium-90 Ci 4.90E-06 9.10E-07 Cesium-134 Ci 1.26E-05 4.67E-06 Cesium-137 Ci 4.28E-04 3.57E-04 Cobalt-60 Ci 1.50E-03 1.41E-03 Cobalt-58 Ci 1.41E-05 1.29E-05 Manganese-54 Ci 6.84E-06 5.21E-05 Barium-Lanthanum-140 Ci 1.15E-03 2.06E-05 Antimony-125 Ci Niobium-95 Ci Cerium-141 Ci 2. 36E-05 Cerium-144 Ci Iron-59 Ci Cesium-136 Ci 8.96E-06 3. 28E-06 Chromium-51 Ci 2.07E-05 Zine-65 Ci 3.28E-06 9.15E-06
4. Tritium Ci 1.16E+01 2.58E+00

TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-GROUND LEVEL (EMERGENCY CONDENSER VENT) RELEASES JANUARY JUNE CONTINUOUS MODE BATCH MODE Nuclides Released Fission Gases Argon-41 Ci Krypton-85m Krypton-87 Ci Krypton-88 C Xenon-133 Ci Xenon-135 Ci Xenon-135m Xenon-137 Xenon-138 C i Ci 2~ Iodines Iodine-131 Ci Iodine-133 Iodine-135 C

C ii

3. Particulates Strontium-89 C i 1.10E-04 Strontium-90 Cesium-134 C

Ci i 2.75E-06 Cesium-137 Ci 2.75E-05 Cobalt-60 Ci 1.77E-04 Cobalt-58 Manganese-54 2.15E-05 Barium-Lanthanum-140 Antimony-125 C

C ii Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 C Chromium-51 Ci Zinc-65 C i 4, Tritium Ci 1.56E+01 2. 74E+00 1.05E+00

TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION //1 LIQUID EPFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1st 2nd Est. Total Unit ~artery ~artery Error X A. Pission and activation roducts Total release (not including tritium, gases, alpha) Ci None <6.70-04 2.5E+Ol

2. Average diluted con-centration during reporting period pCi/ml <1.17E-ll
3. Percent of applicable limit B . Tritium 1~ Total release Ci None 2.19E+00 2.0E+01
2. Average diluted con-3.

centration during reporting period Percent of applicable p Ci/ml 3. 83E" 08 limit C. Dissolved and entrained ases 1~ Total release Ci None <2.05E-,03 3.0E+01

2. Average diluted con-centration during reporting period uCi/ml <3.58E-11
3. Percent of applicable limit D. Gross al ha radioactivit
1. Total release Ci None 3.35E-07 3.0E+01 E. Volumes
1. Prior to dilution liters None 5.20E+05 1.0E+01 2~ Volume of dilution water used during release period liters 1.74E+09 2.0E+01 3~ Volume of dilution water used during reporting period liters 8. 56E+10 5. 72E+10 2. OE+01

TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE (Cont.)

1st 2nd Unit Quarter Quarter F.* Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Limit X <3.51E-03

2. Percent of Quarterly Organ Dose Limit x <1.36E-03
3. Percent of Annual Whole No Body Dose Limit to Date X Discharges <1.76E-03 4, Percent of Annual Organ Dose Limit X <6.82E-04
5. Percent of 10CFR20 Concentration Limit  %%d

<1.32E-03

6. Percent of Dissolved or Entrained Noble Gas Limit X <1.79E-05

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TABLE 2B RADIOACTIVE EFFLUENT RELEASE SEMI-ANNUAL REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 JANUARY JUNE BATCH MODE Unit Nuclides Released Strontium-89 Ci <2.34E-05 Strontium-90 Ci <3.85E-06 Cesium-134 Ci 2.87E-06 Cesium-137 Ci 3.14E-05 Iodine-131 Ci Cobalt-58 Cobalt-60 Ci, 8.83E-05 Manganese-54 Chromium-51 Ci.

Zirconiummiobium-95 Ci Barium-lanthanum-140 Ci Tungsten-187 Ci Arsenic-76 Ci Iodine-133 Ci Iron-59 Ci Iron-55 Ci <5.20E-04 Neptunium-239 Ci Praseodymium-144 Ci Iodine-135 Ci Z Dissolved or entrained gases Ci <2. 05E-03

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION gl SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel)

Est.Total

1. Class of Waste Januar June Error, X
a. Class A Spent Resins m3 8. 28K+01 Ci 5.24E+01 2.5E+Ol Solidification Agent Dewatered Container HIC Package Type A Principle Isotopes Co-60 Mn-54,Co-58, Cr-51 Filter Media m3 5.04E+00 Ci 1.61E+01 2. 5E+01 Solidification Agent Cement Container Steel Liner Package Type A Principle Isotopes Co-60, Cs-137, Fe-55, Mn-54, Cs-134 Evaporator Bottoms m3 2.97E+00 Ci 1.96E+00 2.5E+01 Solidification Agent Polymer (Dow)

Container 55 gallon drums Package Type A Principle Isotopes Co-60, Cs-137, Cs-134 Mn-54 Evaporator Bottoms m3 5. 01E+00 Ci 1.51E+00 2.5E+01 Solidification Agent Cement Container Steel Liner Package Type A Principle Isotopes Co-60, Cs-137, Cs-134, Mn-54 Dry Compresgible Waste m 3.25E+02 Ci 1.59E+00 4.0E+01 Solidification Agent None Container Strong Tight Container Package LSA Box Principle Isotopes Co-60, Mn-54,Co-58, Cr-51 ~

Cs-137

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

A. Solid Waste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel)

Est.Total

1. Class of Waste Januar June Error, X
a. Class A (Cont'd)

Dry Non-Compressed Waste m 1. 73E+01 Ci 3.09E+00 3.5E+01 Solidification Agent None Container Steel Liner Package Type A Principle Isotopes Cs-137, Co-60, Mn-54, Cs-134 Contaminated Charcoal m3 5.01K+00 Ci 3.20E-02 3.5E+Ol Solidification Agent Cement Container Steel Liner Package LSA Container Principle Isotopes H-3, Co-60, Cs-137, Co-58 Irraddated )cantor Components m 2. 55E+00 Ci 6.84E+00 2.5E+01 Solidification Agent None Container Steel Liner Package Type A Principle Isotopes Co-60, Fe-55, Ni-63 Contaminated Condenser Tubes*

m3 3. 48E+02 Ci 1.08E-01 3. 5E+Ol Solidification Agent None Container Strong Tight Container Package LSA Box Principle Isotopes Co-60, Ce-141, Ba-La-140, Zn-65

  • Condenser Tubes were shipped to Babcock and Wilcox for decontamination .

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

A. Solid Waste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel)

Est.Total

1. Class of Waste Januar June Error, X
b. Class B Spent Resins m3 1.42E+01 Ci 4.11E+02 2.5E+01 Solidification Agent Dewatered Container HIC Package Type A Principle Isotopes Co-60,Cs-137,Mn-54,Cs-134 Filter Media m3 1.49E+Ol Ci 9.62E+Ol 2.5E+01 Solidification Agent Cement Container Steel Liner Package Type A Principle Isotopes Co-60, Cs-137,Mn-54, Cs-134 c~ Class C None

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIBKNTS (Continued)

2. Estimate of Ma or Nuclide Com osition (b T e of Waste)
a. Evaporator Bottoms Resins Filter Media Cobalt-60 6.56E+01 Cesium-137 7.94E+00 Manganese-54 7.46E+00 Iron-55 4.59E+00 Cobalt-58 3.82E+00 Chromium-51 3.78E+00 Cesium-134 2.41E+00 Zinc-65 2.18E+00 Other 2.22E+00
b. Dry Compressible Waste, Contaminated Components Cesium-137 4.93E+01 Cobalt-60 4.21E+Ol Manganese-54 2.90E+00 Cesium-134 2.50E+00 Other 3.20E+00 C ~ Irradiated Components Cobalt-60 6.44E+01 Iron-55 3.30E+01 Nickel-63 2.35E+00 Other 2.50E-01
3. Solid Waste Dis osition
a. Number of Shi ments* Mode Destination Truck Barnwell, SC
  • Excludes condenser tubes shipped to Babcock and Wilcox for decontamination.

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'll TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION //1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

4. a. Irradiated Reactor Com onents Dis osition Number of Shi ments Mode Destination Truck Barnwell, SC
b. Irradiated Fuel Shi ments Dis osition Number of Shi ments Mode Destination None

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 CAUSE AND CORRECTIVE ACTIONS REGARDING LIQUID DISCHARGE EFFLUENT MONITOR INOPERABILITY JANUARY JUNE The NMP-1 Liquid Discharge Effluent monitors were declared inoperable prior to 6 liquid discharge batch releases in June of 1986 for two reasons: (1) monitor sensitivity was insufficient to ensure alarm activation prior to exceeding 10CFR20 release rate limits and (2) alarm setpoint formula specified in the ODCM did not adequately address the contribution of tritium to the calculated liquid discharge batch MPC.

Item (2) above can be resolved with a small change to the Offsite Dose Calculation Manual. This will be accomplished prior to the next liquid discharge at Unit 1. Details of the ODCM revision will be supplied in a future Semi-Annual Effluent Release Report in accordance with Section 6.9.1 of the Technical Specifications.

Ironically, monitor sensitivity problems are partly a function of the low radionuclide concentration of the batch tank requiring discharge. This is because the monitor setpoint is a function of the quantity:

[E(C ) ] - TDF

[ ~(Ci MPCi) totall '

Where: (Ci) is the radionuclide concentration of gamma emitter, i and: Ci is the radionuclide concentration of any isotope, i MPCi is.the MPC for isotope Ci TDF is the total dilution water flow during the discharge F is the flow from the tank being discharged.

Thus, lowering gamma emitting isotope concentrations while maintaining the quantities E (Ci/MPCi) and TDF/F essentially constant (as is the case at NMP-1 where tritium is the predominant isotope), results in lower monitor alarm setpoint requirements.

Calculated monitor Hi alarm setpoints for the batch releases in June 1986 were about 4E-04 uCi/ml gamma. This value was slightly lower than the current monitors would tolerate without alarming due to background radiation.

For future resolution of the current monitors'ensitivity problems, Niagara Mohawk has purchased a new Liquid Discharge Effluent Monitor and has included the monitor on the site modification priority list. The relative need for completing monitor installation will be evaluated. In the interim, NMP-1 will minimize liquid discharge occurrences. Should a discharge of a low activity tank become necessary, verification processes and additional sampling requirements specified in the Technical Specifications will be accomplished.

In the unlikely event the discharge of a relatively high activity tank becomes necessary, it should not be necessary to declare. monitor inoperability since calculated setpoints will be higher than the monitors'ensitivity threshold.

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TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION // 1 HOURS AT EACH WIND SPEED AND DIRECTION JANUARY JUNE In accordance with Amendment 66 of Nine Mile Point Unit 1 Technical Specifications, an annual summary of hourly meteorological data shall be included and submitted in the Semi-Annual Red',oactive Effluent Release Report within 60 days after January 1 of each year. Therefore, meteorological data has not been included in this report. Data will appear in the subsequent Semi-Annual Report.

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TABLE 6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION Pl

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE There were no changes to the NMP-1 ODCM during the period January June 1986.

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TABLE 7 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1986)

NINE MILE POINT NUCLEAR STATION 81 CHANGES TO THE PROCESS CONTROL PROGRAM JANUARY JUNE The Nine Mile Point /i'1 Process Control Program '(PCP) for waste solidification, as described in Administrative Procedure 3.7, Revision 0, has not been revised during the current reporting period. Some waste solidification procedure revisions have been made; how'ever, these changes have not affected the overall PCP.

Copies of waste solidification procedure revisions and explanations are available upon request.

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