ML17056A979

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Semiannual Radioactive Effluent Release Rept for Jan-June 1990.
ML17056A979
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/30/1990
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17056A978 List:
References
NUDOCS 9009120037
Download: ML17056A979 (48)
v • d • e


Text

NINE MILE POINT NUCLEAR STATION UNIT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990 DOCKET NO.: 50-410 LICENSE NO.: NPF-69 NIAGARA MOHAWK POWER CORPORATION 9009'f20037 9'00830 PDR ADOCK 050004io R PNU

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NINE MILE POINT NUCLEAR STATION UNIT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990 Facility: Nine Mile Point Unit 42 Licensee: Niagara Mohawk Power Corporation

1. Technical Specification Limits:

A) Fission and activation gases:

The dose rate limit of noble gases from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.

The air dose from noble gases released in gaseous effluents from the Nine Mile Point 2 Station to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, during any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

BEC) Tritium, Iodines and Particulates, half lives > 8 days:

The dose rate. limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released gaseous effluents from the site to areas at or beyond the site boundary, shall be less than or equal to 1500 mrem/year to any organ.

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 2 Station to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem 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 gases, the concentration shall be limited to 2E-04 microcuries/ml total activity,

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D. Liquid Effluents (Cont'd)

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

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

None specified D) Liquid Effluents:

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

Avg MPC ( Jan. - March ) = 1.83E-03

.Avg MPC ( April June ) = 2.56E-03

3. Average Energy (Fission and Activation gases Mev)

Jan. - March: E Q = 0.608; Eg - 1.11 Apr. - June: Ep = 0.799; Eg = 1.21

4. Measurements and Approximations of Total Radioactivity Described below are the normal 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) of an isokinetic sample stream.

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

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

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

E) Liquid Effluents: Isotopic Analysis of a representative sample of each batch.

F) Solid Effluents: Isotopic contents of waste shipments are determined by gamma spectroscopy analyses and water content estimates of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applie'd, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

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: 24
2. Total time period for batch releases: 81 hours 25 min.

3." 'Maximum time period for a batch release: 3 hours 28 min.

4. Average time period for a batch release: 3 hours 24 min.
5. Minimum time period for a batch release: 3 hours 17 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 4.46 E+08 liters

,8. ,Total volume of water available to dilute the liquid effluent during reporting period 2.16 E+10 liters B) Gaseous (Primary Containment Purge) 1., -Number. of batch releases: 12

2. Total time period for batch releases: 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> 52 min.
3. Maximum time period for a batch release: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 30 min.
4. Average time period for a batch release: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
5. Minimum time period for a batch release: 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 26 min.
6. Abnormal Releases A. Liquids none B. Gaseous none
  • Actual purge times are less than shown. The times presented are the sampling times, and represent a conservative approximation to actual purge times, (approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per purge).

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TABLE 1A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1990 1st 2nd EST.TOTAL UNIT gUARTER QUARTER ERROR '/

A. Fission 5 Activation ases

l. Total release Ci 2.01E+01 1.40E+02 5.0E+01
2. Average release rate for period uCi /sec 2.59E+00 1.80E+01
3. Percent of Technical Specification Limit B. Iodines
1. Total iodine 8.95E-04 3.10E-03 5.0E+01
2. Average release rate for period uCi/sec 1.15E-04 3.95E-04

'3. . Percent of'echnical Specification Limit Particulates ¹

1. Particulates with half-lives > 8 days Ci 9.48E-04 1.07E-03 5.0E+01
2. Average release rate for period uCi/sec 1.22E-04 1.36E-04
3. Percent of Technical Specification Limit
4. Gross alpha radio-activity Ci 5.72E-06 1.31E-05 5.0E+01 D. Tritium
1. Total release Ci 2.53E+00 4.84E+00 5.0E+01

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'2.'.Average'-'release rate for period uCi/sec 3.25E-01 6.16E-01 3 ~ Percent of Technical Specification Limit

¹* Include Mo-99 also Refer to Section E on next page

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TABLE 1A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY "- JUNE 1990 1st 2nd UNIT QUARTER QUARTER E. Percent of Technical S ecification Limits Fission and Activation Gases:

1. Percent of Quarterly Gamma Air Dose Limit 1. 80E-01 1. 22E+00 2.'ercent of Quarterly Beta Air Dose Limit 1.30E-03 1.19E-02
3. Percent of Annual Gamma Air Dose Limit to Date 9.01E-02 6.98E-01
4. Percent of Annual Beta

"' . Air Dose Limit to Date 6.50E-04 6.60E-03 5:"T Percent 'of- Nhole Body Dose Rate Limit 6.98E-03 4.66E-02

6. Percent of Skin Dose Rate Limi t 1.36E-03 9.10E-03 Tritium Iodines and Particulates (with half-lives reater than 8 da s):
1. Percent of Quarterly

. Dose Limit 4.76E-03 2.84E-02

2. Percent of Annual Dose Limit to Date 2.38E-03 1.66E-02
3. Percent of Organ Dose Rate Limit 1.94E-04 1.16E-03

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TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 GASEOUS EFFLUENTS-ELEVATED (STACK)

JANUARY JUNE 1990 Nuclides Released Fission Gases Ui CONTINUOUS MODE tll ~d ~t BATCH MODE

~d Argon-41 Ci 6.55E+00 5.25E+00 Krypton-85m Ci 2.25E+00 2.53E+00 Krypton-87 Ci 2.08E+00 Krypton-88 Ci 4.86E+00 6.56E+01 Xenon-133 Ci 1.09E-05 1.57E-06 Xenon-135 Ci ** 8.65E-01 Xenon-135m Ci 3.82E-01 3.38E+00 2.44E-01 Xenon-137 Ci 2.90E+00 3.91E+01 Xenon-13& Ci 1.95E+00 2.11E+01 9.12E-01

2. Iodines Iodine-131 Ci 4.93E-05 3.22E-04 Iodine-133 Ci 8.46E-04 2.78E-03 Iodine-135 Ci Particulates Strontium-89 Ci 4.06E-05 Strontium-90 Ci Strontium-91 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 3.61E-06 2.42E-06 Coba t-58 1 Ci Manganese-54 Ci 8.60E-07 6.80E-07 Barium-Lanthanum-140 Ci Antimony-125 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci 2.94E-05 Zinc-65 Ci 2.20E-06 Iron-55 Ci 3.22E-05 ¹ Molybdenum-99 Ci 4.10E-06 2.33E-05
4. Tri tium Ci 1.22E+00 3.50E+00 1.07E-02 5.39E-02
    • Less than sensi tivi ty of 1.00E-04 uCi /ml for noble gases, 1.00E-12 uCi /ml for iodines, 1.00E-ll uCi/ml for particulates and 1.00E-06 uCi/ml for tritium as applicable in Technical Specifications.

Results were not received from offsite vendor as of August l5, 1990. They will be included in the next Semi-Annual Report.

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TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 GASEOUS EFFLUENTS-COMBINED GROUND LEVEL-ELEVATED (REACTOR BUILDING VENT)

JANUARY JUNE 1990 t>>dtt I

CONTINUOUS MODE BATCH MODE Nuc 1 i des Re 1 eased Unit ~t dtt t t ttt t Fission Gases Argon-41 Ci Krypton-85 . Ci 4.25E-04 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci 7.74E-06 Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines Iodine-131 Ci 6.50E-07 Iodine-133 Ci Iodine-135 Ci

3. Particulates No batch releases Strontium-89 . Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 1.68E-05 3.50E-OS Cobalt-58 .Ci 2.85E-06 Manganese-54 Ci 1.16E-06 1.83E-OS Barium-Lanthanum-140 Ci

'Antimony-'125 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci 7.14E-04 8.39E-04 Zinc-65 Ci 3.10E-06 2.80E-05 Iron-55 Ci 2.49E-05 Molybdenum-99 Ci 1.07E-04 8.62E-OS

4. Tri tium Ci 1.30E+00 1.34E+00
    • Less than the sensitivity of 1.00E-04 uCi/ml for noble gases, 1.00E-12 uCi/ml for iodines, 1.00E-ll uCi'/ml for particulates and 1.00E-06 uCi/ml for tritium as applicable in Technical Specifications.

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TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1st 2nd Est. Total Uni t quarter guarter Error A. Fission and activation roducts Total release (not including tritium, gases, alpha) 2.29E-02 2.72E-03 2.50E+1

2. Average diluted con-centration during reporting period uCi/ml 1.83E-09 2.98E-10
3. Percent of applicable limit 2.60E-03 1.54E-04 B. Tritium
l. Total release Ci 1.47E+00 2.69E-01 2.50E+1
2. Average diluted con-centration during reporting period uCi /ml 1. 18E-07 2. 96E-08
3. Percent of applicable limit 3.92E-03 9.85E-04
c. Dissolved and entrained ases
l. Total release Ci 6.98E-05 1.52E-04 5.00E+1
2. Average diluted con-centration during reporting period uCi/ml 5.58E-12 1.67E-11 3 ~ Percent of applicable limit 2. 79E-06 8. 32E-06 D. Gross al ha radioactivit
1. Total release Ci E. Volumes
1. Prior to dilution liters 1..95E+06. 2.69E+05 2.50E+1
2. Volume of dilution water used during release period liters 4.05E+08 4.07E+07 2.50 E+1
3. Volume of dilution wa'ter available during reporting period 1 i ters 1. 25E+10 9. 11E+09 2. 50 E+1
    • <1.00E-07 uCi/ml sensitivity for gross alpha radioactivity.

'ABLE 2A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1990 1st 2nd Unit quarter gu'arter F. Percent of Technical S ecification Limits

1. Percent of Quarterly Whole Body Dose Limit 7.50E-01 3.27E-02
2. Percent of Quarterly Organ Dose Limit 5.01E-01 2.16E-02
3. Percent of Annual Whole Body Dose Limit to Date 3.75E-01 3 '1E-01 4; Percent of Annual Organ Dose Limit to Date 1. 2.50E-01 2 '1E-01
5. Percent of 10CFR20 Concentration Limit 6.52E-03 1.14E-03
6. Percent of Dissolved or

ntraine'd'Noble Gas Limit 2.79E-06 8.32E-06

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TABLE 28 RADIOACTIVE EFFLUENT RELEASE SEMI-ANNUAL REPORT NINE MILE POINT NUCLEAR STATION ¹2 LIQUID EFFLUENTS RELEASED Nuclides Released Strontium-89 Strontium-90 Ci Ci JANUARY JUNE 1990 CONTINUOUS MODE dll ~ BATCH MODE

~d Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci 1.87E-03 Cobalt-60 Ci 4.78E-03 2.59E-04 Iron-59 Ci 6.49E-04 Zinc-65 CI 1.01E-02 3 '7E-04 Manganese-54 Ci 2.99E-03 8.51E-05 Chromium-51 Ci 2.47E-03 2.03E-03 Zirconium-niobium-95Ci Molybdenum-99 Ci 1.01E-05 Technetium-99m Ci -9.84E-06 Barium-lanthanum-140Ci Cerium-141 Ci Hydrogen-3 Ci 1.47E+00 2.69E-01 Sodium-24 Ci Iron-55 Ci Manganese-56 Ci Nickel-65 Ci Arsenic-76 Ci Iodine-133 Ci Tungsten-187 Ci Xenon-133 Ci 1.05E-04 Xenon-135 Ci 6.98E-05 4.65E-05 Less than sensitivity of 5.00E-07 uCi/ml for gamma emitting nuclides, 1.00E-05 uCi/ml for dissolved and entrained noble gases and tritium, 5.00E-08 uCi/ml for Sr89 and Sr90 and 1.00E-06 uCi/ml for Fe55 as applicable in Technical Specifications.

Results were not received from offsi te vendor as of August 15, 1990. They will be included in the next Semi-Annual Report.

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TABLE 3A I ~

I SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1990 A. Solid Haste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel)

EST. TOTAL UNIT 6-MONTH PERIOD ERROR '/

a.'pent resins, filter sludge bottoms, etc. 1.70E+02 Ci 6.19E+02 2.50 E+01

b. Dry compressible waste, contaminated equip., etc. m3 2.80E+01 Ci 2.09E-01 5.00E+01
c. Irradiated components, control rods, etc. m3 None None
d. Other O.OOE+00 Ci 0.00E+00
  • All were solidified in cement as Class A waste in strong, tight containers. All were shipped as radioactive LSA.

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TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - JUNE 1990

2. Estimate of Ma or Nuclide Com osition (b T e of Waste)
a. Spent Resins, filter sludges, evaporator bottoms, etc.

Percent Chromium-51 6.81E+01 Zinc-65 1.97E+01 Cobalt-60 4.43E+00 Iron-55 2.56E+00 Manganese-54 2.24E+00 Cobalt-58 1.89E+00 Others 1.05E+00

b. Dry Compressible Haste, Contaminated Equips, Etc.

Percent Zinc-65 6.69E+Ol Cobalt-60 1.56E+01 Manganese-54 8.32E+00 Chromium-51 2.78E+00 Iron-55 1.94E+00 Cobalt-58 1.73E+00 Others 2.73E+00

c. Irradiated components, control rods, etc.

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TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT. NUCLEAR STATION ¹2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1990

3. Solid Waste Dis osition Number of Shi ments Mode of Trans ortation Destination 28 Truck Burial in Barnwell SC B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shi ment Mode of Trans ortation Destination None C. SOLID WASTE SHIPPED OFFSITE TO VENDORS FOR PROCESSING AND SUBSE VENT BURIAL Below is a summary of Dry Activated Waste that was shipped offsite for processing and burial by vendor facilities (i.e., ALARON, QUADREX and SCIENTIFIC ECOLOGY GROUP) during July December 1989. These 'totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" (i.e.,

Section A of Table 3A) since (a) waste classification and burial was performed by the vendors and (b) NMP-2 Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped offsite during the reporting period." The informatiuon provided in this section, therefore, is in addition to that required by the NMP-2 Technical Specifications.

The offsite data reported in the July December 1989 semi-annual report was an estimate from Quadrex. -The actual data. arrived too late to include in f

the last semi-annual report. Therefore, the following data represents the actual shipments made from Quadrex of our non-compacted commingled trash.

This trash was'shipped to Quadrex, commingled trash shipped Oakridge, TN p td to for processing prior to burial at Barnwell, SC for processing prior to burial.

Uni t Shipment 1989 8.20E+00 Est. Total Error Ci 1.12E-01 5.00E+01

2. Estimate of Ma'or Nuclide Com osition Percent Cobalt-58 3.25E+01 Cobalt-60 2.96E+01 2inc-65 2.27E+01 Manganese-54 8.29E+00 Cesium-137 4.74E+00 Iron-55 2.17E+00 13

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TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1990

3. Solid Haste Di s osi tion Number of Shi ments Mode of Trans ortation Destination 22 Truck -Processing in Oakridge, TN

-Burial in Barnwell, SC.

D. SEWAGE SLUDGE SENT TO A TREATMENT FACILITY CENTER FOR PROCESSING AND BURIAL Below is a summary of the sewage sludge which was removed from the site sanitary treatment facility and transferred to a municipal sewage treatment facility for subsequent drying and disposal by landfill. .This is a site release and, therefore, includes the results from Unit activities, also.

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1. Vo1'ume/Activi t Summar m3 9.08E+00 Curies 9.02E-06
2. Estimate of Ma or Nuclide Com osition Percent Cobalt-60 1.00E+02
3. Solid Haste Dis osition Number of Shipments Destination landfill 14

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T BLE 4 SEMI-ANNUAL RADIOAC EFFLUENT RELEASE REPORT NINE MILE POIN NUCLEAR STATION-¹ 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 U-2 ODCM Rev. 5 Descri tion of Chan e Affect on Accurac /Reliabilit Section Chan ed and Justification of Dose Calculations/Alarm Set oint Determination P. 1, section 1.0 Revised to include the None normal process for licensee initiated ODCM changes per Technical Specifications

p. 2, section 2.1.2.1 The text was reworded None to use common terminology for clarification purposes.
p. 3, section 2.1.2.1 Added the option of Improved reliability using a conservatively since monitor responds lower CR in calculating at a more conservative the monitor efficiency. setpoint.

This option was added so that established procedures can use conservative values of CR thereby preventing repeated changeouts of the monitor calibration/

setpoints.

p. 3, section 2.1.2.1 Added the definition RDF None for clarification purposes.

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LE 4 SEMI-ANNUAL RADIOAC E EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹ 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 (Continued)

U-2 ODCM Rev. 5 Descri tion of Chan e Affect on Accurac /Reliabi lit Section Chan ed and Justification of Dose Calculations/Alarm Set oint Determination

p. 3, section 2.1.2.1 For clarification purposes None added text "...prior to alarm and termination of release", and also a reference to an alert alarm.
p. 5, section 2. 1.2.3 Change text to read None "potential contaminant" instead of "concentration in radwaste tank prior to dilution" to more accurately describe the variable as it is used in the equation.
p. 6, section 2.1.3.1 Inserted the word "gamma" None since equipment is only sensitive to gamma radiation.
p. 6, section 2.1.3.1 Deleted text since we None are operational to produce suffici ent activity.
p. 6, section 2.1.3.1 Deleted word initially. None
p. 6, section 2.1.3.1 Deleted spent fuel None pool analysis capability for tritium, since we do not use this option.

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LE 4 SEMI-ANNUAL RADIOA E EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹ 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 (Continued)

U-2 ODCM Rev. 5 Descri tion of Chan e Affect on Accurac /Reliabi lit Section Chan ed and Justification of Dose Calculations/Alarm Set oint Determination

p. 7, section 2.1.3.1 Revised flow rate None to correct misprint.
p. 7, section 2.1.3.1 Deleted last The change should not affect paragraph since the the accuracy/reliability of assumptions used setpoint determination since were overly conservative. the revised method will still ensure alarm response prior to exceeding canal MPC.
p. 8, section 2.1.3.1 Corrected misprints. None
p. 9, section 2.1.3.1 Deleted last part The change should not affect of paragraph since the accuracy/reliability of the assumptions used setpoint determination since were overly conservative. the revised method will still ensure alarm response prior to exceeding canal MPC.
p. 10, section 2.1.3.2 Corrected flows to None correct misprints.
p. 10, section 2.1.3.2 Changed text to None convey the use of reactor water each fuel cycle for detector response evaluation because the old wording was applicable prior to commercial operation.

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LE 4 SEMI-ANNUAL RADIOAC EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹ 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 (Continued)

~Ch . No. U-2 ODCM Rev. 5 Descri tion of Chan e Affect on Accurac /Reliabi lit Section Chan ed and Justification of Dose Calculations/Alarm Set oint Determination 17 p. 11, section 2.1.3.2 Corrected roundoff None and misprint errors.

18 p. 16, section 2. 5 Deleted paragraph concerning alert alarm setpoint for the liquid radwaste effluent alarm, since it was placed in the wrong section. It is now described in section 2.1.3.1.

19 p. 16, section 2.-5-. Deleted text reference None to adequate purge volume and placed in appropriate procedures.

20 p. 32, section 3.1.2.3 The equation was None rewritten so that alarm setpoint is in proper units of uCi/cc.

21 p. 33, section 3.1.3 Included Nine Mile None Point Uni t and 1

Fitzpatrick plant in notifications, so as not to exceed site limit.

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LE 4 SEMI-ANNUAL RADIOA E EFFLUENT RELEASE REPORT NINE NILE POINT NUCLEAR STATION ¹ 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 (Continued)

~Ch . No. U-2 ODCH Rev. 5 Descri tion of Chan e Affect on Accurac /Reliabilit Section Chan ed and Justification of Dose Calculations/Alarm Set oint Determination 22 p. 35, section 3.1.3.2 Corrected typographical None error.

23 P. 36, section 3.1.3.3 In Rev. 4 of the U-2 ODCN, The new method improves the accuracy the previous method of of the setpoint calculations since calculating detector actual plant offgas distribution is response was applicable used instead of an assumed. value.

prior to commercial operation. The new method is based on actual grab samples and uses a plant distribution typical of a recoil release mechanism.

As shown in the plant procedures the actual offgas distribution will change with fuel integrity.

24 p. 59, section 3.7 Corrected inaccuracies and None rewritten to reflect the true constraints imposed on offgas system operation in accordance with plant technical specifications.

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'ABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 EXPLANATION OF INSTRUMENTATION INOPERABILITY JANUARY JUNE 1990 In accordance with NMP Unit 2 Technical Specifications, Radioactive Effluent Instrumentation which is inoperable for 30 consecutive days within the reporting period must be reported in the Semi-Annual Radioactive Effluent Release Report. Below is a listing of monitors which technically fall into this category during the January June 1990 reporting period along with a description of causes for the inoperability and, as appropriate, corrective actions taken to resolve the problems.

Date of Instrument Date Returned Cause of Inoperability/

Instrument Ino erabilit to Service Corrective Actions Service Hater A June 1989 May 6, 1990 Initial pump became Radiation Monitor inoperable. The pump was replaced.

May 10, 1990 Not returned The new pump had a to service as bad motor. He are of June 30, 1990 awaiting a replace-ment.

Service Hater B* Dec. 23, 1989 Not returned to The pump tripped on Radiation Monitors service as of a low flow signal June 30, 1990 and could not be restarted. He are awaiting a replacement pump.

To comply with Technical Specifications we are taking 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples for

"'ervice water.

  • Note: Service Hater B radiation monitor was returned to service on 8-18-90.

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TABLE '5 (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 EXPLANATION OF INSTRUMENTATION INOPERABILITY JANUARY JUNE 1990 Date of Instrument Date Returned Cause of Inoperabi 1 i ty Instrument Ino erabilit to Service Corrective Actions Reactor/Radwaste Jan. 10, 1989 Feb. 23, 1990 Vent Sample flow device Reactor/Radwaste Jan. 10, 1989 Feb. 23, 1990 Vent effluent flow device Reactor/Radwaste Jan. 10, 1989 Feb. 23, 1990 The vent skid was Vent, Noble Gas taken apart to fix Monitor a flow control module and we were Reactor/Radwaste Jan. 10,'989 Feb. 23, 1990 unsuccessful in Vent, Iodine re-instating Sampler system operability, until the date indicated.

Reactor/Radwaste Jan. 10, 1989 Feb. 23, 1990 Vent, Particulate Sampler To comply with technical specifications for gaseous effluents, we were taking 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples to analyze for noble gases and estimating flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Iodine and particulates were analyzed from a cartridge on the auxiliary sampling station.

Liquid Radwaste Nov., 1987 Not returned The monitor Effluent Radiation to service became inoperable Monitor as of due to continuous June 30, 1990 alarming from a contaminated detector.

Applicable ODCM changes have been made to permit increasing the alarm setpoint thereby eliminating the cause of failure. We are scheduled to return to service in 1990.

To comply with technical specifications for liquid radwaste discharge we are taking two samples for each discharge for dual analysis and verification.

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'TABLE 6

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 CHANGES TO THE PROCESS CONTROL PROGRAM JANUARY JUNE 1990 During the reporting period of January thru June 1990 there were no changes to the PCP or Process Control Program.

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TABLE 7 1

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT a

NINE MILE POINT NUCLEAR STATION ¹2 CIRCULATING WATER DISCHARGED THROUGH THE UNIT 1 DISCHARGE CANAL JANUARY JUNE 1990 During the period of Jan. - June 1990, the circulating water blowdown at Unit 2 was sent through the Unit 1 discharge canal to obtain the reguired dilution for copper concentration in the Unit 2 circulating water. This copper concentration is now being controlled through the use of chemical addition, and we are not currently sending the circulating water to the Unit 1 discharge canal. While the normal blowdown line could not be used, Unit 2 blowdown water which was sent to Unit 1 was analyzed for radioactivity every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using.,gamma spectroscopy. No activity was.detected.

1st tr. ~2nd tr.

TOTAL VOLUME DISCHARGED (Li ters) 2.33E+09 2.92E+09 TOTAL VOLUME OF DILUTION WATER 9.74E+10 8.34E+10 USED DURING THE REPORTING PERIOD

<Liters) 23

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