ML17056A979
| ML17056A979 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1990 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056A978 | List: |
| References | |
| NUDOCS 9009120037 | |
| Download: ML17056A979 (48) | |
Text
NINE MILE POINT NUCLEAR STATION UNIT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990 DOCKET NO.:
LICENSE NO.:
50-410 NPF-69 NIAGARA MOHAWK POWER CORPORATION 9009'f20037 9'00830 PDR ADOCK 050004io R
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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)
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 3." 'Maximum time period for a batch release:
3 4.
Average time period for a batch release:
3 5.
Minimum time period for a batch release:
3 6.
Average stream flow during, period of release of effluent into a flowing stream:
7.
Total volume of water used to dilute the liquid effluent during release periods
,8.
,Total volume of water available to dilute the liquid effluent during reporting period hours hours hours hours 25 min.
28 min.
24 min.
17 min.
Not Applicable 4.46 E+08 liters 2.16 E+10 liters B)
Gaseous (Primary Containment Purge) 1.,
-Number. of batch releases:
12 2.
Total time period for batch releases:
121 3.
Maximum time period for a batch release:
12 4.
Average time period for a batch release:
12 5.
Minimum time period for a batch release:
11 6.
Abnormal Releases A.
Liquids none B.
Gaseous none hours 52 min.
hours 30 min.
hours hours 26 min.
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 A.
Fission 5 Activation ases UNIT 1st 2nd EST.TOTAL gUARTER QUARTER ERROR
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l.
2.
3.
Total release Average release rate for period Percent of Technical Specification Limit Ci uCi /sec 2.01E+01 1.40E+02 5.0E+01 2.59E+00 1.80E+01 B.
D.
Iodines 1.
Total iodine 2.
Average release rate for period
'3.
. Percent of'echnical Specification Limit Particulates ¹ 1.
Particulates with half-lives
> 8 days 2.
Average release rate for period 3.
Percent of Technical Specification Limit 4.
Gross alpha radio-activity Tritium 1.
Total release
~'2.'.Average'-'release rate for period 3
~
Percent of Technical Specification Limit uCi/sec Ci uCi/sec Ci Ci uCi/sec 8.95E-04 3.10E-03 5.0E+01 1.15E-04 3.95E-04 9.48E-04 1.07E-03 5.0E+01 1.22E-04 1.36E-04 5.72E-06 1.31E-05 5.0E+01 3.25E-01 6.16E-01 2.53E+00 4.84E+00 5.0E+01
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 UNIT E.
Percent of Technical S ecification Limits 1st QUARTER 2nd QUARTER Fission and Activation Gases:
1.
Percent of Quarterly Gamma Air Dose Limit 2.'ercent of Quarterly Beta Air Dose Limit 3.
Percent of Annual Gamma Air Dose Limit to Date 4.
Percent of Annual Beta
. Air Dose Limit to Date 5:"T Percent
'of-Nhole Body Dose Rate Limit 6.
Percent of Skin Dose Rate Limit
- 1. 80E-01
- 1. 22E+00 1.30E-03 1.19E-02 9.01E-02 6.98E-01 6.50E-04 6.60E-03 6.98E-03 4.66E-02 1.36E-03 9.10E-03 Tritium Iodines and Particulates (with half-lives reater than 8 da s):
1.
Percent of Quarterly
. Dose Limit 2.
Percent of Annual Dose Limit to Date 3.
Percent of Organ Dose Rate Limit 4.76E-03 2.84E-02 2.38E-03 1.66E-02 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)
Nuclides Released Fission Gases JANUARY JUNE 1990 CONTINUOUS MODE BATCH MODE Ui tll
~d
~t
~d 2.
Argon-41 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-13&
Iodines Ci Ci Ci Ci Ci Ci Ci Ci Ci 6.55E+00 2.25E+00 4.86E+00 1.09E-05 3.82E-01 2.90E+00 1.95E+00 5.25E+00 2.53E+00 2.08E+00 6.56E+01 1.57E-06 8.65E-01 3.38E+00 3.91E+01 2.11E+01 2.44E-01 9.12E-01 Iodine-131 Iodine-133 Iodine-135 Particulates Ci Ci Ci 4.93E-05 3.22E-04 8.46E-04 2.78E-03 Strontium-89 Ci Strontium-90 Ci Strontium-91 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Coba 1 t-58 Ci Manganese-54 Ci 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 Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci 4.06E-05 3.61E-06 8.60E-07 3.22E-05 4.10E-06 2.42E-06 6.80E-07 2.94E-05 2.20E-06
¹ 2.33E-05 4.
Tri tium Ci 1.22E+00 3.50E+00 1.07E-02 5.39E-02
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 I
Nuc 1 i des Re 1 eased Fission Gases Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Iodines Iodine-131 Iodine-133 Iodine-135 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CONTINUOUS MODE BATCH MODE
~t dtt t
t ttt t>>dtt t
4.25E-04 7.74E-06 6.50E-07 3.
Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58
.Ci Manganese-54 Ci 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 Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci 1.68E-05 1.16E-06 7.14E-04 3.10E-06 2.49E-05 1.07E-04 3.50E-OS 2.85E-06 1.83E-OS 8.39E-04 2.80E-05 8.62E-OS No batch releases 4.
Tritium Ci 1.30E+00 1.34E+00
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TABLE 2A Uni t A.
Fission and activation roducts 1st 2nd quarter guarter SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE Est. Total Error 2.
3.
Total release (not including tritium,
- gases, alpha)
Average diluted con-centration during reporting period Percent of applicable limit 2.29E-02 2.72E-03 2.50E+1 uCi/ml 1.83E-09 2.98E-10 2.60E-03 1.54E-04 B.
Tritium l.
2.
3.
Total release Average diluted con-centration during reporting period Percent of applicable limit Ci uCi /ml
- 1. 18E-07
- 2. 96E-08 3.92E-03 9.85E-04 1.47E+00 2.69E-01 2.50E+1 c.
l.
2.
3
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Total release Average diluted con-centration during reporting period Percent of applicable limit Dissolved and entrained ases Ci uCi/ml 5.58E-12 1.67E-11
- 2. 79E-06
- 8. 32E-06 6.98E-05 1.52E-04 5.00E+1 D.
Gross al ha radioactivit 1.
Total release E.
Volumes Ci 1.
2.
3.
Prior to dilution Volume of dilution water used during release period Volume of dilution wa'ter available during reporting period liters 1..95E+06.
2.69E+05 2.50E+1 liters 4.05E+08 4.07E+07 2.50 E+1 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 Unit F.
Percent of Technical S ecification Limits 1.
Percent of Quarterly Whole Body Dose Limit 2.
Percent of Quarterly Organ Dose Limit 3.
Percent of Annual Whole Body Dose Limit to Date 4;
Percent of Annual Organ Dose Limit to Date 1.
5.
Percent of 10CFR20 Concentration Limit 6.
Percent of Dissolved or
ntraine'd'Noble Gas Limit 1st quarter 7.50E-01 5.01E-01 3.75E-01 2.50E-01 6.52E-03 2.79E-06 2nd gu'arter 3.27E-02 2.16E-02 3 '1E-01 2 '1E-01 1.14E-03 8.32E-06
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TABLE 28 RADIOACTIVE EFFLUENT RELEASE SEMI-ANNUAL REPORT NINE MILE POINT NUCLEAR STATION ¹2 LIQUID EFFLUENTS RELEASED JANUARY JUNE 1990 Nuclides Released Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci CONTINUOUS MODE BATCH MODE dll ~
~d Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Ci Ci Ci CI Ci Ci 1.87E-03 4.78E-03 6.49E-04 1.01E-02 2.99E-03 2.47E-03 2.59E-04 3 '7E-04 8.51E-05 2.03E-03 Zirconium-niobium-95Ci Molybdenum-99 Ci Technetium-99m Ci Barium-lanthanum-140Ci Cerium-141 Ci 1.01E-05
-9.84E-06 Hydrogen-3 Sodium-24 Iron-55 Manganese-56 Nickel-65 Arsenic-76 Iodine-133 Tungsten-187 Xenon-133 Xenon-135 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.47E+00 6.98E-05 2.69E-01 1.05E-04 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.
10
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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹2 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS 6-MONTH PERIOD UNIT JANUARY JUNE 1990 A.
Solid Haste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel)
EST.
TOTAL ERROR
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a.'pent resins, filter sludge bottoms, etc.
b.
Dry compressible
- waste, contaminated equip., etc.
Ci m3 Ci 1.70E+02 6.19E+02 2.80E+01 2.09E-01 2.50 E+01 5.00E+01 c.
Irradiated components, control rods, etc.
m3 None None d.
Other Ci O.OOE+00 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.
Chromium-51 Zinc-65 Cobalt-60 Iron-55 Manganese-54 Cobalt-58 Others Percent 6.81E+01 1.97E+01 4.43E+00 2.56E+00 2.24E+00 1.89E+00 1.05E+00 b.
Dry Compressible
- Haste, Contaminated
- Equips, Etc.
Zinc-65 Cobalt-60 Manganese-54 Chromium-51 Iron-55 Cobalt-58 Others Percent 6.69E+Ol 1.56E+01 8.32E+00 2.78E+00 1.94E+00 1.73E+00 2.73E+00 c.
Irradiated components, control rods, etc.
NONE 12
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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 28 Mode of Trans ortation Truck Destination Burial in Barnwell SC B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shi ment None Mode of Trans ortation Destination 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 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, for processing prior to burial.
f
p td commingled trash shipped to
- Oakridge, TN for processing prior to burial at Barnwell, SC 2.
Estimate of Ma'or Nuclide Com osition Unit Ci 8.20E+00 1.12E-01 5.00E+01 Shipment Est.
Total 1989 Error Cobalt-58 Cobalt-60 2inc-65 Manganese-54 Cesium-137 Iron-55 Percent 3.25E+01 2.96E+01 2.27E+01 8.29E+00 4.74E+00 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 22 Mode of Trans ortation Truck Destination
-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 1 activities, also.
1.
Vo1'ume/Activi t Summar m3 Curies 2.
Estimate of Ma or Nuclide Com osition Cobalt-60 3.
Solid Haste Dis osition Number of Shipments 9.08E+00 9.02E-06 Percent 1.00E+02 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 Section Chan ed Descri tion of Chan e
and Justification Affect on Accurac /Reliabilit of Dose Calculations/Alarm Set oint Determination P.
1, section 1.0
- p. 2, section 2.1.2.1
- p. 3, section 2.1.2.1
- p. 3, section 2.1.2.1 Revised to include the normal process for licensee initiated ODCM changes per Technical Specifications The text was reworded to use common terminology for clarification purposes.
Added the option of using a conservatively lower CR in calculating the monitor efficiency.
This option was added so that established procedures can use conservative values of CR thereby preventing repeated changeouts of the monitor calibration/
setpoints.
Added the definition RDF for clarification purposes.
None None Improved reliability since monitor responds at a more conservative setpoint.
None 15
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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 Section Chan ed Descri tion of Chan e
and Justification Affect on Accurac /Reliabi lit of Dose Calculations/Alarm Set oint Determination
- p. 3, section 2.1.2.1 For clarification purposes added text "...prior to alarm and termination of release",
and also a
reference to an alert alarm.
None
- p. 5, section
- 2. 1.2.3
- p. 6, section 2.1.3.1
- p. 6, section 2.1.3.1 p.
6, section 2.1.3.1
- p. 6, section 2.1.3.1 Change text to read "potential contaminant" instead of "concentration in radwaste tank prior to dilution" to more accurately describe the variable as it is used in the equation.
Inserted the word "gamma" since equipment is only sensitive to gamma radiation.
Deleted text since we are operational to produce sufficient activity.
Deleted word initially.
Deleted spent fuel 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 Section Chan ed Descri tion of Chan e
and Justification Affect on Accurac /Reliabi lit of Dose Calculations/Alarm Set oint Determination
- p. 7, section 2.1.3.1
- p. 7, section 2.1.3.1
- p. 8, section 2.1.3.1
- p. 9, section 2.1.3.1 p.
10, section 2.1.3.2 p.
10, section 2.1.3.2 Revised flow rate to correct misprint.
Deleted last paragraph since the assumptions used were overly conservative.
Corrected misprints.
Deleted last part of paragraph since the assumptions used were overly conservative.
Corrected flows to correct misprints.
Changed text to convey the use of reactor water each fuel cycle for detector response evaluation because the old wording was applicable prior to commercial operation.
None The change should not affect the accuracy/reliability of setpoint determination since the revised method will still ensure alarm response prior to exceeding canal MPC.
None The change should not affect the accuracy/reliability of setpoint determination since the revised method will still ensure alarm response prior to exceeding canal MPC.
None None 17
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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 Section Chan ed Descri tion of Chan e
and Justification Affect on Accurac /Reliabi lit of Dose Calculations/Alarm Set oint Determination 17 18 19 20 21 p.
11, section 2.1.3.2 p.
16, section
- 2. 5 p.
16, section 2.-5-.
- p. 32, section 3.1.2.3
- p. 33, section 3.1.3 Corrected roundoff and misprint errors.
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.
Deleted text reference to adequate purge volume and placed in appropriate procedures.
The equation was rewritten so that alarm setpoint is in proper units of uCi/cc.
Included Nine Mile Point Uni t 1
and Fitzpatrick plant in notifications, so as not to exceed site limit.
None None None None 18
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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 Section Chan ed Descri tion of Chan e
and Justification Affect on Accurac /Reliabilit of Dose Calculations/Alarm Set oint Determination 22 23 24
- p. 35, section 3.1.3.2 P. 36, section 3.1.3.3
- p. 59, section 3.7 Corrected typographical error.
In Rev.
4 of the U-2 ODCN, the previous method of calculating detector response was applicable 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.
Corrected inaccuracies and rewritten to reflect the true constraints imposed on offgas system operation in accordance with plant technical specifications.
None The new method improves the accuracy of the setpoint calculations since actual plant offgas distribution is used instead of an assumed.
value.
None 19
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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.
Instrument Service Hater A
Radiation Monitor Date of Instrument Ino erabilit June 1989 May 10, 1990 May 6, 1990 Initial pump became inoperable.
The pump was replaced.
Not returned The new pump had a
to service as bad motor.
He are of June 30, 1990 awaiting a replace-ment.
Date Returned Cause of Inoperability/
to Service Corrective Actions Service Hater B*
Radiation Monitors Dec.
23, 1989 Not returned to service as of June 30, 1990 The pump tripped on a low flow signal 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 Instrument Reactor/Radwaste Vent Sample flow device Date of Instrument Ino erabilit Jan.
10, 1989 Date Returned Cause of Inoperabi 1 i ty to Service Corrective Actions Feb.
23, 1990 Reactor/Radwaste Vent effluent flow device Jan.
10, 1989 Feb.
23, 1990 Reactor/Radwaste
- Vent, Noble Gas Monitor Reactor/Radwaste Vent, Iodine Sampler Jan.
10, 1989 Jan.
10,'989 Feb.
23, 1990 Feb.
23, 1990 The vent skid was taken apart to fix a flow control module and we were unsuccessful in re-instating system operability, until the date indicated.
Feb.
23, 1990 Reactor/Radwaste Jan.
10, 1989 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 Effluent Radiation Monitor Nov.,
1987 Not returned to service as of June 30, 1990 The monitor became inoperable due to continuous 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 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 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 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.
TOTAL VOLUME DISCHARGED (Liters)
TOTAL VOLUME OF DILUTION WATER USED DURING THE REPORTING PERIOD
<Liters) 1st tr.
2.33E+09 9.74E+10
~2nd tr.
2.92E+09 8.34E+10 23
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