ML17056B981
| ML17056B981 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1992 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056B982 | List: |
| References | |
| NUDOCS 9209080213 | |
| Download: ML17056B981 (42) | |
Text
Pi NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992 NIAGA RA MOHAWKPOWER CORPORA TION 9209080213 920827 r PDR ADOCK,05000220 PDR PP2767LL
'I 4
NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit ¹1 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.
BRC) Tritium, lodines and Particulates, half lives > 8 days:
- 1. Tahe 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 eight 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:
- 1. 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.
002757LL
I 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 1 to 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 rnrems 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 mrerns to any organ.
- 2. Measurements and Approximations of Total Radioactivity:
Described below are the 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 grab sample) of an isokinetic stack sample stream.
B) lodines:
Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges 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 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.
Batch release activities of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to activity concentrations of gamma emitters. The activity of tritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.
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:
Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
002767LL
~ Measurements and Approximations of Total Radioactivity (Cont'd):
F) Solid Effluents:
Isotopic contents of waste shipments are determined by gamma spectroscopy, 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 emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
002757LL (4)
ATTACHIVIENT1 Page 1 of 2 Summary Data Unit 1 X Unit 2 Reporting Period Janus - June 1992 Uquid Effluonts: THERE WERE NO LIQUID RELEASES DURING THIS REPORTING PERIOD 10CFR20, Appendix B, Table II, Column 2 NA NA Average Energy (Fission and Activation gases - Mev):
Qtr. 1 Ey a 2.47E-01 EP a 3.17E-01 Qtr. 2 Ey ~ 2.47E-01 EP ~ 3.17E-01 Uquid: THERE WERE NO LIQUID RELEASES DURING THE REPORTING PERIOD Number of batch releases ~NA Total time period for batch releases (hrs.) ~NA Maximum time period for a batch release (hrs.): N/A Average time period for a batch release (hrs.): ~NA Minimum time period for a batch release (hrs.): ~NA Total volumo of water used to dilute the liquid effluent during release period (L) NNIA Total volume of water availablo to dilute the liquid effluent during reporting period (L) 1.45E+ 11 UNIT 1 (ONLY) THERE WERE NO BATCH GROUND LEVEL RELEASES FROM THE EMERGENCY CONDENSER VENT DURING THE REPORTING PERIOD Gaseous (Emergency Condenser Vent):
Number of batch releases Total time period for batch releases (hrs.) ~NA Maximum time period for a batch release (hrs.): N/A Average time period for a batch release (hrs.): ~NA Minimum time period for a batch release (hrs.): N/A Gaseous (Primary Containment Purge):
Number of batch releases Total time period for batch releases (hrs.) 2.40E+ 01 Maximum time period for a batch release (hrs.): 8.00E+00 Average time period for a batch release (hrs.): 8.00E+00 Minimum time period for a batch release (hrs.): 8.00E+00 002757LL
ATTACHMENT 1 Page 2 of 2 Summary Data Unit 1 X Unit 2 Reporting Period Janua - June 1992 Abnormal Releases: THERE WERE NO ABNORMALRELEASES DURING THE REPORTING PERIOD A. Uquids Number of releases N/A Total activity released N/A Ci B. Gaseous Number of releases ~NA Total activity released N/A Ci 002757LL
0 ATTACHMENT2 Unit 1 X Unit 2 Reporting Period Janus - June 1992 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL EE 2~ EST. TOTAL QUARTER QUARTER ~ERROR Fission 8E Activation eses'
- 1. Total release Ci 6.77E-01 1.57E+00 5.00E+01
- 2. Average release rate uCi/sec. 8.61E-02 1.99E-01 lodines'.
Total iodine Ci 2.03E-02 3.85E-03 3.00E+01
- 2. Average release rate for period uCi/soc. 2.62E-03 4.72E-04 Particulates
- 1. Particulates with half. lives >8 days Ci 2.22E-04 1.25E-03 3.00E+01
- 2. Average release rate for period uCi/sec. 2.87E-05 1.53E-04
- 4. Gross alpha radioactivity Ci 3.42E-05 6.13E-05 2.50E+01 Tritiuin'.
Total release Ci 2.65E+ 00 1.45E+01 5.00E+01
- 2. Average release rate for period uCi/sec. 3.43E-01 1.78E+ 00 E. Percent of Tech. Spec. Limits Fission and Activation of Quarterly Gemma Air Dose 1.13E-03 2.62E-03 Gases'ercent Limit (5 mrem)
Percent of Quarterly Beta Air Dose Urnit 1.27E-03 2.94E-03 (10 mrem)
Percent of Annual. Gamma Air Dose Limit 5.63E-04 1.87E-03 to Date (10 mrem)
Percent of Annual Beta Air Dose Limit to 6.35E-04 2.11E-03 Date (20 mrem)
Percent of WhoIe Body Dose Rate Limit 4.31E-05 1.00E-04 (500 mrem/yr)
Percent of Skin Dose Rate Umit 2.1 1E-05 4.94E-05 (3000 mrem/yr)
Tritium lodines and Particulates with half.lives reater than 8 da s Percent of Quarterly Dose Limit 2.82E-01 4.89E-01 (7.5 mrem)
Percent of Annual Dose Limit 1.42E-01 4.35E-01 (15 mrem)
Percent of Organ Dose Rate Umit 5.77E-03 9.48E-03 (1500 mrem/yr)
Concentrations less than the lower limit of detection of 1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates, 1.00E-12 uCi/ml for lodines, and 1.00E-06 uCi/ml for Tritium as required by Technical Specifications are indicated with a double asterisk.
s Tritium, Iron-55, and Strontium results were not received from tho off-site vendor at tho time of this report. Those numbers include estimates and actual numbers will bo provided in tho next Semi-Annual Report.
002757LL
ATTACHMENT3 Unit 1 X Unit 2 Reporting Period Janus - June 1992 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODEs 1" gal Nuclides Released QUARTER QUARTER
- 1. Fission Gases'rgon-41 Ci ~0 ~0 Krypton-85 Ci ~0 ~0 Krypton-85m Ci ~0 0~
Krypton-87 Ci ~0 ~0 Krypton.88 Ci ~0 ~0 Xenon-127 Ci OO ~0 Xenon-133 Ci ~0 ~0 Xenon-135 Ci 6.77E-01 1.57E+00 Xenon-135m Ci ~0 ~0 Xenon-137 Ci 0~ ~0 Xenon-138 Ci 0~ ~0
- 2. I odin os'odine-131 Ci 4.69E-04 8.98E-05 iodine-'I 33 Ci 7.01E-03 1.34E-03 Iodine-'I 35 Ci 1.28E-02 2.42E-03
- 3. Particulates'trontium-89 Ci 3.35E-05 2.80E-04 Strontium-90 Ci ~0 3.25E-05 Cesium-134 Ci OO ~0 Cesium-137 Ci ~0 7.63E-06 Cobalt-60 Ci 1.67E-04 5.03E-04 Cobalt-58 Ci OO OO Manganese-54 Ci ~ I 6.62E-05 Barium-Lanthanum-140 Ci ~0 ~0 Antimony-125 Ci ~ t ~0 Niobium-95 Ci OO ~0 Cerium-141 Ci OO ~0 Cerium-144 Ci 0~ ~ t Iron-59 Ci ~0 ~0 Cesium-136 Ci OO ~0 Chromium.51 Ci 0~ OO Zinc-65 Ci ~0 ~0 Iron-55 Ci 2.10E-05 3.57E-04 Molybdenum-99 Ci ~0 ~0
- 4. Tritium Ci 5.81E-01 1.25E+01 Concentrations less then the lower limit of detection of 1.00E-04 uCi/ml for NobIs Gases, 1.00E-11 uCi/ml for particulates, 1.00E-12 uCi/ml for lodines, and 1.00E-06 uCi/ml for Tritium as required by Technical Specifications are indicated with a double asterisk.
- Tritium, Iron-55, and Strontium results were not received from the off-site vendor at the time of this report.
These numbers include estimates and actual numbers will be included in tho next Semi-Annual Report.
No batch mode release occurred during the reporting period.
002757 LL
ATTACHMENT4 THERE WERE NO GROUND LEVEL RELEASES DURING THE REPORTING PERIOD Unit 1 X Unit 2 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE THERE WERE NO BATCH RELEASES DURING THE REPORTING PERIOD tl 1 ot gal 2'UARTER QUARTER QUARTER QUARTER Nuclides Released Fission Gases' Argon-41 Ci ~0 ~0 Krypton-85 Ci ~0 0~
Krypton-85m Ci ~0 J~
Krypton.87 Ci ~0 OO Krypton.88 Ci ~0 OO Xenon-133 Ci 0~ 11 Xenon-135 Ci ~0 ~0 Xenon-135m Ci ~0 OO Xenon-137 Ci ~0 OO Xenon-138 Ci ~0 ~0 Xenon-127 Ci ~0 ~0 Iodines'.
Iodine-131 Ci ~0 ~0 Iodine-133 Ci ~0 ~0 Iodine-135 Ci ~0 ~0 Particulates Strontium-89 Ci ~0 ~0 Strontium-90 Ci ~0 ~0 Cesium-134 Ci ~0 0~
Cesium-137 Ci ~0 ~0 Cobalt-60 Ci ~0 ~0 Cobalt-59 Ci ~0 Manganese-54 Ci ~0 ~0 Barium-Lanthanum-140 Ci Antimony-125 Ci ~0 Niobium-95 Ci ~0 OO Cerium-141 Ci ~0 ~0 Cerium-144 Ci ~0 Iron-59 Ci ~0 ~0 Cesium-136 Ci ~~ OO Chromium-5'I Ci ~0 OO Zinc-65 Ci ~0 OO Iron-55 Ci ~~ ~0 Molybedenum.99 Ci ~ I OO Tritium Ci 2.07E+ 00 2.02E+ 00 Concentrations less than the lower limit of detection of 1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates, 1.00E-12 uCi/ml for lodines, and 1.00E-06 uCi/ml for Tritium as required by Technical Specifications are indicated with a double asterisk.
002757LL
ATTACHMENT5 Page 't Of 2 THERE WERE NO UQUID RELEASES DURING THE REPORTING PERIOD Unit 1 X Unit 2 Reporting Period JEEnua - June 1992 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES THERE WERE NO LIQUID RELEASES DURING THE REPORTING PERIOD 1>> 2~ EST. TOTAL QUARTER QUARTER ~ERROR A. Fission & Activation Products'.
Total release (not including tritium, Ci ~NA ~NA 5.00E+01 gases, alpha)
- 2. Average diluted concentration uCi/ml N/A during reporting period B. Tritium
- 1. Total release Ci ~NA ~NA 5.00E+01
- 2. Average diluted concentration uCi/ml ~NA N/A during reporting period C. Dissolved and Entrained Gasest
- 1. Total release Ci N/A N/A 5.00E+01
- 2. Average diluted concentration uCi/ml ~NA ~NA during reporting period D. Gross Al ha Radioactivit
- 1. Total release Ci N/A N/A 5.00E+01 E. Volumes
- 1. Prior to dilution Uters ~NA N/A 5.00E+01
- 2. Volume of dilution water used Utors ~NA ~NA 5.00E+01 during release period
- 3. Volume of dilution water available Uters 8.31E10 6.17510 5.00E+01 during reporting period Percent of Technical S ecification Limits Percent of Quarterly Whole Body Doss N/A Limit (1.5 mrem)
Percent of Quarterly Organ Dose Limit ~NA N/A (5 mrem)
Percent of Annual Whole Body Dose ~NA ~NA Limit to Date (3 mrem)
Percent of Annual Organ Dose Umit to N/A N/A Date (10 mrem)
Percent of 10CFR20 Concentration Umit Percent of Dissolved or Entrained N/A Noble Gas Umit (1.00E-5 uCi/ml)
Concentrations less than tho lower limit of detection of 5.00E-07 uCi/ml for gamma emitting nuclides, 1.00E-05 uCi/mi for dissolved and entrained noblo gases and tritium, 5.00E-08 uCi/ml for Sr-89/90, 1.00E-OS uCi/ml for Fo-55 and 1.00E-07 uCi/ml for gross alpha radioactivity as required by Technical Specifications are indicated with a double asterisk.
002757LL
CI ATTACHMENT5 Page 2of 2 THERE WERE NO LIQUID RELEASES DURING THE REPORTING PERIOD Unit 1 X Unit 2 Reporting Period Januar - June 1992 LIQUID EFFLUENTS RELEASED BATCH MODE gal Nuclides QUARTER QUARTER Released'trontium-89 Ci NIA N/A Strontium-90 Ci NIA NIA Cesium-134 Ci ~NA NIA Cesium-137 Ci ~NA ~NA iodine-131 Ci NIA ~NA Cobalt-58 Ci ~NA ~NA Cobalt-60 Ci NIA NIA Iron-59 Ci NIA NIA Zinc-65 Ci N/A N/A Manganese-54 Ci N/A NIA Chromium-51 Ci NIA NIA Zirconium-Niobium-95 Ci N/A N/A Molybdenum-99 Ci NIA N/A Technetium-99m Ci ~NA ~NA Barium-Lanthanum-140 Ci ~NA ~NA Cerium-141 Ci NIA NIA Tungsten-187 Ci NIA NIA Arsenic-76 Ci N/A NIA iodine-133 Ci NIA ~NA Iron-55 Ci ~NA N/A Neptunium-239 Ci N/A NIA Praseodymium-144 Ci NIA NIA Iodine-135 Ci N/A N/A Dissolved or Entrained Gases Ci ~NA ~NA Tritium Ci NIA ~NA Concentrations less than the lower limit of detection of 5.00E-07 uCi/ml for gama emitting nuclides, 1.00E-05 uCi/ml for dissolved and entrained noble gases and tritium, 5.00E-08 uCi/ml for Sr-89/90, 1.00E-06 uCi/ml for Fe.55 and 1.00-07 uCi/ml for gross alpha radioactivity as required by Technical Specifications are indicated with a double asterisk.
002757LL
ATTACHMENT6 Page 1 Of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.l TYPE Volume ~Activit
{ms) 'Ci)
Class Class
- 1. Spent Resin 2.82E+ 01 1.37+ 01 1.00E+ 01 7.25E+01 Filter Sludge 5.50E+ 00 5.50E+ 00 1.78E-01 2.46E+ 01 Concentrated Waste 2.20E+ 01 5.72E+ 01 Evaporator Bottoms Total 3.37E+ 01 2.75E+ 01 1.37E+ 01 1.02E+ 01 8.18E-01 7.25E+ 01
- 2. Dry Compressible Waste, Dry Non-Compressible Waste {Contaminated 5.69E+ 00 8.54E-01 Equipment)s Total 5.69E+ 00 8.54E-01
- 3. Irradiated Components, Control Rods 4.08E+ 00 5.25E+ 04 The estimated total error is 5.00E+01%.
s Since there were non-compressible tools and compressible trash combined in the waste shipments, the non.compressible and compressible waste categories were combined.
~ THERE WERE NO SHIPMENTS DURING THE REPORTING PERIOD.
002767LL
It
~ ~
ATTACHMENT6 Page 2 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container ~Peaks
- AAA at
- 3. Irradiated Components Control Rods Steel Liner ~Te B ~NA 002757LL
k ATTACHMENT6 Page 3 Of 6 Unit1 X Unit 2 Reporting Period Jenusr - June 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 Estiinate of Ma or Nuclide Com osition b T e of Waste
- a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Co-60 4.98E+ 01 C6-137 2.37E+01 Fe-55 8.86E+00 Mn.54 7.08E+00 Pu-241 6.93E+00 Co.58 'I.81E+00 Cr-51 1.06E+00 Other 7.60E-01
- b. Dry Compressible Waste, Dry Non-Compressible Waste {Contaminated Equipment)
Nuclide Percent Co-60 5.34E+01 Cs-137 3.51E+01 Mn-54 5.43 E+ 00 Co-58 3.18E+00 Fe-59 1.83E+00 Other 1.06E+00
- c. Irradiated Components, Control Rods Nuclide Percent Co-60 8.58E+01 Fe-55 7.08E+00 Ni-63 5.97E+00 H-3 1.01E+00 Other 1.40E-01
- d. Other THERE WERE NO OTHER SHIPMENTS DURING THE REPORTING PERIOD 002757LL
ATTACHMENT6 Page 4 of 6 Unit 1 X Unit 2 Reporting Period Jenuer - June 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. Soiid Waste Dis osition Number of Shi ments Mode of Trans ortation Destination 18 Truck B wllSC Train Rl hI nd WA B. IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shi ments Mode of Trans ortation Destination 0
002757LL
ATTACHMENT6 Page 50f 6 Unit 1 X Unit 2 Reporting Period Jenua - June 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e., ALARON, QUADREX, and/or SCIENTIFIC ECOLOGY GROUP) during Janus - June 1992. 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) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period". The information provided in this section, therefore, is in addition to that required by tho Technical Specifications. The following data represents tho actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.
d.t. ~Te ot Waste- noneompseted oommingted trash end contaminated fuel pool equipment shipped to Oakridgo, TN Buriai Volume Activity Est. Total for processing prior to burial at Barnwell, SC ~me ~CI ~dror 7.96E+ 00 2.25E+ 00 5.00E+01 C.2. Estimate of Ma or Nuclide Com osition Nuclide Percent 1 Co-60 5.38E+01 2 Cs-137 3.55E+01 3 Mn-54 5.05E+00 4 Co-58 2.94E+00 5 Fe-59 1.69E+ 00 10 Other 2.22E-01 C.3. Solid Waste Dis ositionr Number of Shi ments Mode of Trans ortation Destination 14 Truck 8 wtrsc The number of shipments reported hero represents tho total number that was shipped from tho offsite vendor for burial. This does not represent the number of shipments Niagara Mohawk sent to bo processed.
002757LL
N I
ATTACHMENT 6 Page 6 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE SLUDGE SHIPPED 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 to a landfill. This is a site release, and therefore includes the results from Unit 2 activities, also.
D.l. T~eaf waste- sewage Burial Volume Activity sludge ~L ~CI 7.95E+ 03 2.29E-07 D.2. Estimate of Ma or Nuclide Com osition Nuclide Percent Co-60 1.00E+02 D.3. Solid Waste Dis osition Number of Shi ments Mode of Trans ortation Destination Landfill Thore were three shipments of sowago sludgo with quantified Co-60 that wore sont by vendor vacuum tank truck from NMP to the treatment facility. The number of shipments sent from NMP does not reflect tho number of shipments to the ultimate destination (i.o., landfill). Sludge is mixed with municipal sludge, dried and subsequently transferred to a state approved landfill by municipal personnel.
002757LL
ATTACHMENT7 Unit 1 X Unit 2 Reporting Period Jenuer - June 1992 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS EFFLUENTS ~ ELEVATED ANO GROUND LEVEL UOUID EFFLUENTS Update of data using actual results from the off-site vendors for Strontium, Tritium, and Iron-55, for the Founh Quarter of 1991.
GASEOUS LIQUID (Quarter) 4>> (Quarter) 4>>
THERE WERE NO LIQUID RELEASES Activit Ci DURING THE REPORTING PERIOD Nuclide'r-89 6.41E-05 Sr-90 H-3 7.19E+ 00 Fe-55 7.04E-05 GASEOUS LIQUID Particulates'ritium'. Particulates with Ci 3.02E-04
)
half-lives 8 days
- 2. Average release rate uCi/sec 3.75E-05 for period
'I. Total roleaso Ci 7.19E+ 00 ~NA
- 2. Avorago reloaso rate UCi/sec 8.95E-01 ~NA for period Tritium lcdines and GASEOUS LIQUID Particulates with half-lives rester than 8
- 1. Percent of Quarterly 3.75E-01 ~NA Dose Umit (Quarterly) (Quarterly)
- 2. Percent of Annual 1.09E+ 00 ~NA Dose Limit to Date (Annual) (Annual)
- 3. Percent of Organ 7.37E-03 ~NA
- Dose Rate Umit (Quarterly) (Quarterly)
(Gaseous)(Quarterly) N/A N/A
- Dose Umit (Uquid) (Annual) (Annual)
(Annual fk Quarterly)
- 4. Percent of 10CFR20 N/A N/A Concentration Umit (U quid)
- 5. Percent of Dissolved N/A N/A or Entrained Noble Gas (Liquid)
Concentrations less than tho lower limit of detection, as required by Technical Specifications are indicated with a double asterisk.
002757LL
r ATTACHMENT8 Unit 1 X Unit 2 Reporting Period Janus - June 1992
SUMMARY
OF CHANGES TO THE OFFNITE DOSE CALCULATIONMANUAL The Unit 1 ODCM Revision 9 was implemented in June 1992. Copies of Revisions 8 and 9 are attached.
The following sampling locations have been changed or added to the environmental monitoring program as a result of a change from the land use census, except locations ¹30 and 52, which were typographical errors. The land use census showed potential alternate sample locations that could be used since garden locations can change significantly from year to year. The locations include numbers 59, 61 and 63. In addition, milk sample location numbers 64, 65 and 66 were added to show potential locations that have been used in the past and that are also currently used. These locations are not Technical Specification locations.
5L'o'catl6n'.: ;'. (Eny.",'. Pr'o'gr'a'm",¹)':,:;::;::::,::::::ll:,"':;::;:::,::::,'.:;..":',::,::;:Old Lroc :.,'New, Lccatiori,::,::.:':;:lli:,'..:,'::,'.:
30 Phoenix, NY Control (49) 19.8 mi. 8 170' No chango 19.8 mi. 6 163' (typographical error)
Produce Location (3) (C. Produce Location (3) (C.
52 Narewski) 1.6 mi. 9 84' Narewski) (NA) No change, (typographical error)
Produce Location (12) Produce Location (12) 59 (Johnson) (NA) 1.9 mi. 6 103'SE (Barton) (NA) 1.9 mi. 9 115'SE Provide Location (14) Produce Location (14) 61 (Dickenson) (NA) 1.7 mi. 6 82' (Koeneke)(NA) 1.9 mi. 6 95'E Produce Location (16) 63 NIA N/A (Murray) (NA) 1.2 mi. 9 207'SW 64 NIA N/A Milk Location (55) 9.0 mi. 9 95' 65 NIA NIA Milk Location (60) 9.5 mi. 9 90' NIA NIA Milk Location (4) 7.8 mi. 9 113'SE N/A ~ Not Applicable The changes noted above do not reduce the accuracy or reliability of dose calculations or sotpoint determinations. The changes noted above do not involve dose calculations or setpoint determinations. The changes more accurately show the Technical Specification and optional environmental sample locations.
002767LL
ATTACHMENT9 Unit 1 X Unit 2 Reporting Period Janus - June 1992
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the PCP during the Reporting Period.
002757 LL
ATTACHMENT 10 Unit 1 X Unit 2 Reporting Period Janus - June 1992
SUMMARY
OF INOPERABLE MONITORS Monitor Dates of Inoperability Cause and Corrective Actions RAGEMS Entire Reporting Period The Radioactive Gaseous Effluent Monitoring System (RAGEMS) modifications have been completed and successfully tested. The pre-operational test was executed and signed on June 5, 1992 and SORC approved on June 16, 1992. No test exceptions were taken and all acceptance criteria were met. Efforts to complete the testing by March 31, 1992 as committed, were delayed by the forced outages. All items identified in previous reports have been addressed and are proven by manual, automatic and semi-automatic operation. In addition, the operational system has many software program user enhancements and troubleshooting aids. Radiation detector rebuilds and calibrations and chemistry personnel training is in progress. RAGEMS is intended to be used as an emergency stack gas monitoring system.
002757LL
a l