ML17056A963

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Semiannual Radioactive Effluent Release Rept Jan-June 1990.
ML17056A963
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/30/1990
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17056A964 List:
References
NUDOCS 9009110041
Download: ML17056A963 (68)
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Text

NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990 DOCKET NO.: 50-220 LICENSE NO.: DPR-63 NIAGARA MOHAWK POWER CORPORATION 9009ii004i 900830 05000220 PDR ADQCK R PNU

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N MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990

'SUPPLEMENTAL"INFORMATION Faci i ty:

1 Nine Mi 1 e Point Uni t ¹1 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 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

" '*=ite"boundary 1 Station to areas at and beyond the 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 milli roentgen for gamma radiation and less than or equal to 20 mrads 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 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 wi th 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'5 mrems to any'rgan.

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.

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D. Liquid Effluents (Con"

2. The dose

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t or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine

'ile Point Unit to unrestricted 'areas shall be limited during 1

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 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 ) = no discharges Avg MPC ( April June ) = 2.99E-3 uCi/ml

3. Average Energy (Fission and Activation gases - Mev)

Jan. Mar.  : No discharges Apr. June  : No discharges

4. 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 byon-line gamma spectroscopic monitoring (intrinsic

'ermanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample), of an isokinetic stack sample stream.

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

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4. (Cont'd) t C) Pa rticulates: 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.

0) 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.

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 appli'cation 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: 3
2. Total time period for batch releases: 14 hours 41 min.
3. Maximum time period for a batch release: 4 hours 56 min.
4. Average time period for a batch release: 4 hours 53 min.
5. Minimum time period for a batch release: 4 hours 49 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 8.81E+8 Liters
8. Total volume of water available to 'dilute the liquid effluent during reporting period 1.81E+ll Liters

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5. (Cont.)
8) Gaseous (Emergency Condenser Vent)
l. Number of batch releases: 0

'2.'otal time period for batch releases: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.

3. Maximum time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
4. Average time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
5. 'inimum time period for a batch release: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min ~
6. Abnormal Releases A. Liquids none B. Gaseous none

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TABLE lA SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE'POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1990 1st 2nd EST.TOTAL UNIT QUARTER QUARTER ERROR '/

A. Fis'sion 5 Activation ases

1. Total release Ci
2. Average release rate for period uCi/sec
3. Percent of Technical Specification Limit Prolonged Unit Outage B. Iodines
1. Total iodine-131 Ci
2. Average release rate for period uCi/sec
3. Percent of Technical Specification Limit Particulates'*
1. Particulates with half-lives >8 days Ci 6.92E-04 3.85E-04 2.5E+01
2. activityyrelease Average rate for period uCi/sec 8.90E-OS 4.80E-05
3. Percent of Technical Specification Limit
4. Gross alpha radio-Ci 3.57E-05 4.16E-05 2.5E+01 D. Tritium
1. Total release Ci 9.35E-01 1.40E+00 2.0E+01
2. Average. release rate for period 'Ci/sec, 1.20E-01 . 1.75E-01
3. Percent of Technical Specification Limit

'efer to E on next page.

    • Results were not received from the offsite vendor as of August 30, 1990.

These numbers include estimates for June 1990. Actual numbers will be provided in the next semi-annual report.

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1

'ASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES t

ELEVATED AND GROUND LEVEL

'ANUARY - JUNE 1990 1st 2nd UNIT gUARTER QUARTER E. Percent of Technical S ecification Limits (NMP-1 Elevated Release)

Fission and Activation Gases:

Percent of Quarterly Gamma Air Dose Limit O.OOE+00 O.OOE+00

2. Percent of Quarterly Beta Air Dose Limit O.OOE+00 O.OOE+00
3. Percent of Annual Gamma

'" Air Dose Limit to Date O.OOE+00 O.OOE+00

4. ""'Perce'nt<'of '>Annual 'Beta Air Dose Limi t to Date 0.00E+00 0.00E+00 Percent of Nhole Body Dose Rate Limit O.OOE+00 O.OOE+00 Percent of Skin Dose Rate Limit O.OOE+00 O.OOE+00

, Tritium 'odines and Particulates (with half-lives reater than 8 da s):

Percent of Quarterly Dose Limit 2.26E-01 1.03E-01 2 ~ Percent of Annual Dose Limit to Date 1.14E-01 1.77E-01

3. Percent of Organ Dose Rate Limit 4.60E-03 2.03E-03

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-ELEVATED RELEASE

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JANUARY JUNE 1990 Nuclides Released Fission Gases Uni t CONTINUOUS MODE¹ Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci "2. 'I'odines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci **

3. Parti cul ates Strontium-89* Ci 8.46E-06 7.12E-05 Strontium-90* Ci 1.93E-06 9.64E-06 Cesium-134 Ci Cesium-137 Ci 7.60E-05 7.92E-05 Cobalt-60 Ci 5.29E-04 1.47E-04 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 linc-65 Ci Iron-55* Ci 7.70E-05 7.78E-05 Molybdenum Ci

4. Tritium Ci 9.35E-01 1.40E+00 No batch mode release occurred during the reporting period.

Concentrations are less than lower limits of detection required by Technical Specification i.e., 1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates and 1.00E-12 uCi/ml for Iodines, respectively).

Results were not received from offsite vendor as of August 30, 1990.

These'numbers included estimates for June 1990. Actual numbers will be included in the next semi-annual report.

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-GROUND LEVEL (EMERGENCY CONDENSER VENT) RELEASES JANUARY JUNE 1990 Nuc 1 i des Released Fission Gases d t ~~dtCONTINUOUS MODE tll t ~dt BATCH MODE Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci "Xenon'-138 Ci No Releases

2. Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci
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 Chromiu'm-51 Ci Zinc-65 Ci Iron-55 Ci
4. Tritium Ci

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TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1990 1st 2nd Est. Total Unit guarter guarter Error A. Fission and activation roducts Total release (not including tritium, gases, alpha) Ci None 6.78E-04 2.5E+01 Average diluted con-centration during reporting period uCi/ml 8.13E-12 Percent of applicable 1 imi t B. Tritium

'1 . '".'"Tota'1"-re'lease Ci None 5.07E-01 2.0E+Ol

2. Average diluted con-centration during reporting period uCi/ml 6.08E-09
3. Percent of applicable 1 imi t C. Dissol.ved and entrained ases
1. Total release None None 3.0E+01
2. Average diluted con-centration during reporting period uCi/ml
3. Percent of applicable limit D. Gross al ha radioactivit Total release None 1.04E-09 3.0E+01 E. Volumes
l. Prior,to dilution .l,i ters . None 2.82E+05 1.0E+Ol

,2. . Volume of dilution water used during release period 1 i ters 8. 81E+08 2.0E+01

3. Volume of dilution water available during reporting period 1 i ters 9. 74E+10 8. 34E+10 2. OE+Ol
  • Refer to F on next page.

.a TABLE 2A (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REP RT NINE MILE POINT NUCLEAR STATION ¹1

'IQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1990 1st 2nd Unit quarter guarter F. Percent of Technical' ecification Limits

1. Percent of Quarterly Whole Body Dose Limit 8.62E-04
2. Percent of Quarterly Organ Dose Limit 4.91E-04
3. Percent of Annual Whole No Body Dose Limit to Date Discharges 4.30E-04
4. Percent of Annual Organ Dose Limit to Date 2.46E-04
5. Percent of 10CFR20 Concentration Limit 2.03E-04

'" '"Entrain'ed'-tNoble~Gas

6. Percent of Dissolved or Limi t None 10

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TABLE 28 RADIOACTIV EFFLUENT RELEASE SEMI-ANNUAL RE RT NINE MILE POINT NUCLEAR STATION ¹1 LIQUID EFFLUENTS RELEASED JANUARY JUNE 1990 BATCH MODE Unit ~~tt ~d Nuc1 i des Re 1 eased Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci

.Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci

" .""Mang'anese-"54 >> Ci Chromium-51 Ci Zirconium-niobium-95 Ci No Discharges Molybdenum-99 Ci Technetium-99m Ci

~ Barium-lanthanum-140 Ci Cerium-141 Ci Tungsten-187 Ci Arsenic-76 Ci Iodine-133 Ci Iron-55 6.78E-04

Neptunium-239

'"Pras'e'odymium-"144 Iodine-135 Ci Ci Ci Ci Dissolved or Entrained Gases Ci Tri tium 5:07E-01

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1990 A. 10CFR61 Solid Haste Shi ed for Burial (Not irradiated fuel)

Est.Total

1. Class of Haste Januar June Error
a. Class A I

Spent Resins m3 1. 51E+01 Curies 1.44E+01 2.5E+01 Solidification Agent None Container HIC Package Type A Principle Isotopes Co60, Cs137 Fe55

"~Dry"A'ct 1 ve ~Has te m3 5.38E+00 Curies 1.41E+00 4.0E+01 Solidification Agent None Containers Steel LSA Box Package Strong Tight Package Principle Isotopes Co60, Csl37, Mn54, H3

b. Class B Filter Sludge m~ 1.36E+01 Curies 1.76E+02 2.5E+01 Solidification Agent Cement

'ontainer Steel liner Package Type A Principle Isotopes Co60, Csl37, H3 Mn54, Ni63, Fe55

c. Class C None 12

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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

JANUARY JUNE 1990

2. Estimate of Ma or Nuclide Com osition (b T e of Haste)
a. Resins Filter .Sjudges Percent Cobalt-60 6.76E+01 Cesium-137 1.86E+01 Iron-55 9.40E+00 Nickel-63 2.09E+00 Manganese-54 1.69E+00 Other 6.20E-01
b. Dry Active Haste Percent Cesium-137 5.94E+01 Cobalt-60 3.32E+01

.~ "-'Hydrogen-3 5.33E+00

'anganese-54 1.07E+00 Cesium-134 8.29E-01 Other 1.71E-01

3. Solid Haste Dis osition Number of Shi ments Mode Destination Truck Chem-Nuclear Systems Barnwell, South Carolina 13

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TABLE 3A SEMI-AN AL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

JANUARY - JUNE 1990 B. Irradiated Fuel Shi ments (Disposition)

Number'of Shi ments Mode Destination None C. ,Sol.,id Haste Shi ed to Vendors for Processin and Burial Below is a summary of Dry Active Haste that was shipped offsite for processing and burial by vendor facilities (i.e., ALARON, QUADREX and SCIENTIFIC ECOLOGY GROUP) during January June 1990. These totals were reported separately from "10CFR61 Solid Haste Shipped for Burial" (i.e., Section A of Table 3A) since (a) waste classification and burial was performed by the vendors and (b) NMP-1 Technical Specification 6.9.1 requires reporting of "information for each class

""of"sol'id waste'(as':defined by 10CFR61) shipped offsite during the reporting period." The information provided in this section, therefore, is in addition to "that required by the NMP-1 Technical Specifications.

1. Volume/Activit Summar m3 1.17E+02 Curies 3.03E+00 Principle Isotopes Co60, Cs137, Fe55, Cs134, Mn54, H3, C14
2. Estimate of Ma or Nuclide Com osition*

Cesium-137 4.82E+01 Cobalt-60 3.86E+01

'"Iron-55 7.61E+00 Nickel-63 1.85E+00 Hydrogen-3 1.03E+00 Manganese-54 1.05E+00 Carbon-14 9.87E-01 Cesium-134 1.65E-01 Other 5.08E-01

3. Solid Haste Dis osition Number of Shi ments Destination 27 Barnwell, South Carolina Hanford, Hashington

.::-*. The Alaron.activity data is being re-evaluated and may/may not need updated in the next semi-annual report. He conservatively assumed that all the activity sent to Alaron was buried. This may/may not be the case.

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TABLE 3A SEMI-AN AL RADIOACTIVE EFFLUENT RELEASE PORT NINE MILE POINT NUCLEAR STATION ¹1

"<< =SOLID WASTE AND IRRADIATED.FUEL SHIPMENTS (Continued)

JANUARY JUNE 1990 D. Sewa e Slud e Shi ed to a Treatment Facilit Center for Processin 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 2 activities also.

1. Volume/Activit Summar Est. Total Error %

9.08E+00 5.00E+Ol Curies 9.02E-06 5.00E+01

'2. ""'Estimate 'of:Ma'or Nuclide Comosition Percent Cobalt-60 1.00E+02

3. Solid Waste Dis osition
Number of Shipments Destination 1 Landfill 15

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 7 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations Table of Contents Changed the section headings None page i to be more consistent concerning RAGEMS and OGESMS for clarification purposes.

page 19, . Added the option of using an Previous methods used grab samp~l section 3.1.1 off-gas isotopic distribution techniques to establish monito~

to determine monitor setpoints K-factors. The new method uses from continuous release points NBS traceable standards which is to improve conservatisms and inherently more accurate and accuracy of setpoint reliable.

calculations.

page 19, Changed the title for the None section 3.1.1 Chemistry & Radiation Protection Supervision (C8RP) to Chemistry L Radiation Management (CORM) page 21, Added a summation sign None, since previous methods section 3.1.2 to the monitor efficiency used the summation.

factor, to correct a previous oversight.

page 22A, Added a monitor efficiency This change improves the section 3.1.2 equation to determine accuracy and reliability of efficiencies when the stack alarm setpoint determinations release rates are near the by using the results from a lower limit of detection national standard as a basis for the calculation in lieu of low activity gas sample concentrations.

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TABLE 4 SERI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 7 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations page 22B, Added a summation sign. '-

None, since previous methods used section 3.1.3 the summation.

page 24, Rewrote the section to more None section, 3.1.5 clearly define the functions of the stack monitoring systems.

page 26; This section was revised to This change improves the accuracy section 3.1.5.3 more accurately describe of setpoint calculations since the intended functions of OGESMS uses four detectors each the stack monitoring system. of which alarm in the Control The OGESMS will be used to Room.

monitor stack effluents during normal operation and the RAGEMS will be used for accident monitoring.

page i,ii, Deleted the reference to pro- None Table of Contents cedures since we are rewri ting the chemistry procedures.

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 0'1 RECENT CHANGES TO-THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8* Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations 10 page iii, A. Revised the table numbers None Table of Contents to include additional liquid dose factors:

B. Added plume shine dose.

factor table.

C. Added immersion dose factor table.

D. Revised the appendices to include liquid dose factor derivation & plume shine dose factor derivation.

This change was done to be consistent with changes in liquid and gaseous dose methodology and, also, for clarification purposes.

pages 12-16, A. Clarified the canal Using 295ft3/sec. decreases section 2.3.1 discharge rate during canal dilution by a Factor of a radwaste liquid release. 2, but increases far field The C. T. Main report, dilution. The net affect on referenced in the ODCM, dose calculations is to used a discharge rate increase the result. This is assuming dilution from a more conservative approach in two circulating water case one circulating water pump pumps of 590ft~/sec. is inoperable.

Our dose calculations are based on 295ft3/sec.

which is based on dilution from one circulating water pump.

  • Revision 8 is submitted as partial fulfillment of the audit findings concerning dose calculations from the review of Revision 2 of the Unit Offsite Dose Calculation Manual. This review was completed on August 22, 1986 by the NRC and 1

its contractor, franklin Research Center.

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION Pl RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations-B. Added the drinking -water The net effect of adding new and sediment pathways to pathways is to increase the liquid dose methodology doses. However, we are still in lieu of using a in compliance with discharge conservative safety factor limits of 10CFR20 and 10CFR50, to account for these pathways Appendix I. By calculating to In addition, we are now a maximum individual we are calculating doses to all ensured that the highest dose organs instead of the is calculated. This is not liver and whole body, overly conservative since the only. However, instead dose factors did not vary much of calculating doses between the highest age groups for all age groups, we of Adult, Teen and Child.

are calculating for a maximum individual.

This maximum individual is a composite of the highest dose Factor of each age group for each organ and each nuclide.

12 page 18, Changed the immersion air This change improves the section 3.1.2 dose factor Mi to a plume accuracy of the setpoint shine whole body dose factor calculations.

Vi,to be consistent with NUREG-0133 methodology.

Previous methodology conservatively used immersion air factors.

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8 Description of Change

  • of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations jp This dose Factor was changed to comply with Reg. Guide 1.109 methodology in calculating doses from a free standing stack. This was an NRC audit finding in 1988.

13 page 28, Reworded the beginning None section 3.2 paragraph for clarification purposes.

14 page 29, Deleted the reference to The accuracy/rel i abi i ty 1

section 3.2 using real time meteorological of the dose/alarm setpoint data. This option was calculations is not affected deleted from our environmental by this change.

program due to difficulties in implementing.

15 page 30, Changed the methodology The accuracy/reliability is not section 3.2 from calculating dose for affected. The doses are all age groups to calculating conservatively higher but still dose for a maximum individual. within the limits of 10CFR.50 and This maximum individual is a 10CFR.20.

composite of the highest dose factor of each age group for each organ and total body and each nuclide.

This change was done to decrease the number of calculations needed while still being conservative and in compliance with Technical Specification Requirements.

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations 16 page 31, Reworded the text for None, emergency condenser vent section 3.2 ' clarification purposes releases were previously included and added the emergency in dose calculations, although condenser vent as a it was not clearly stated in the ground level release ODCM.

when calculating noble gas dose rates.

17 page 32, Changed the noble gas The revised equations are sectio'n 3.2.1 dose rate equations to more accurate.

be consistent with NUREG-0133.

18 page 33 Changed the tritium, The new equations are more section 3.2.1.2 iodines and particulate conservative and are more equations to be consistent easily, traceable to NUREG-0133 with NUREG-0133. Previous methodology. Again, no equations used Reg. Guide change to accuracy/reliability 1.109 methodology, which from adding a reference to was inconsistent with the the emergency condencer vent Unit 2 ODCM. In addition, since previous calculations the emergency condenser vent included the resultant dose.

calculation was included as a ground level release.

19 page 34, Recalculated ihe release rate None section 3.2.1.2 limit to reflect the new dose factors that resulted when we changed from Regulatory Guide 1.109 to NUREG-0133 methodology.

20 page 35, Reworded text for clarification None section 3.2.2 purposes.

21 page 36, Same description as change No. 16 section 3.2.2.1 22 page 37, Same description as change No. 17 section 3.2.2.2 21

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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations 23 page 38, Added the noble gas plume air The dose equations are more section 3.2.2.3 dose as a contribution to the accurate, because of consistency maximum individual dose=at the with NUREG-0133 methodology.

critical receptor to be with sectioris 3.2.1

'onsistent and 3.2.2, satisfying requirements of NUREG-0133. Previous calculations used immersion dose factors to be conservative.

In addition we reworded the text for clarification purposes.

24 page 39, Reworded the text for None section 3.3 clarification purposes.

25 page 40, Reworded the text to include an None section 3.3 explanation of a maximum individual and the corresponding critical receptors of site boundary and residence.

26 page 45-47, Capitalized the letter notation None section 4.1 "U" which represents the consumption rate of fish, for clarification purposes.

27 page 52, Deleted the reference to the None Previous section 4.4 use of real time meteorology calculations always used for calculating plume dispersion five year average annual parameters. This option is not dispersion parameters.

available at this time.

28 page 55, Deleted the reference to None section determining iodine in milk since this is not required by Tech'pecs.

22

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TABLE 4 SEMI-ANNUAL RADIOACTIVE.EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev. 8 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justification) Set oint Determinations 29 page 59, Changed the table number to None Table l-l be consistent with the section it pertains to.

30 page 60-66, Added the liquid dose parameters Improves the accuracy Tables 2-1 to 2-7 for radwaste discharges.and of the liquid dose liquid releases from the startup calculations, since minor-or testing of the emergency doses due to liquid discharges condenser vent. from the Emergency Condenser vent are now calculated.

31 page 68, Changed the location for the None Table 3-1 goat milk pathway, to be consistent with the cow milk location. This was done to be conservative and for ease of keeping locations current.

32 page 69, Added the gamma air and whole Improves the accuracy Table 3-2 body plume shine dose factors of the dose calculations, to keep consistent with sections because they are in compliance 3.2.1 and 3.2.2. with NUREG-0133.

page 70, Added the immersion dose factors Same as Change No. 32.

Table 3-3 for gamma whole body and beta skin dose calculations to keep consistent with sections 3.2.1 and 3.2.2.

pages 71-89, Changed the dose factors to None Tables 3-4 to 3-22 reflect changes in sections 3.2.1 and 3.2.2.

35 pages 92-93 Updated the sampling -locations None Tables 5-1 to reflect changes in the land use census.

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION,¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Affect on Accuracy/Reliability Change ODCM Rev; 8 Description of Change of Dose Calculations/Alarm No. Section Chan ed (Justi fication) Set oint Determinations 36 pages 97-99 Added Appendix A to describe None the derivation of the equation used to calculate the liquid dose factors presented in tables 2-1 to 2-7.

37 pages 100-103 Added Appendix B to describe None the derivation of the plume shine dose factors presented in Table 3-2.

38 pages 104-114 Changed the location for None Appendix A to Appendix C and revised the text to reflect changes to the equation used to calculate the particulate, iodine and tritium dose factors presented in Tables 3-4 thru 3-22.

39 pages 115-129 Changed the location of Appendix None B to Appendix D, and revised the diagrams for the stack sample and return, RAGEMS dilution, RAGEMS Schematic, and OGESMS schematic. These reflect changes to sections 3.1.5 in Revision 7 of the U-1 ODCM ~

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TABLE 5 t

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 EXPLANATION OF 'INSTRUMENTATION INOPERABILITY JANUARY JUNE 1990 Instrument Cause of Ino erabilit /Corrective Actions Offgas 'Radiation Monitor These monitors were not required Offgas System Flow Rate Devices to be operable during outage Sampler Flow Rate Device periods as specified by Unit Technical 1

Specifications. New monitors were installed in the main control room during the period.

No flow for the period due to an extended outage.

Service Hater System A modification has been completed to provide Monitor annunciation along with a computer point to the control room when total power is lost to the service water monitor micro-computer skid.

On 4/9/90 the LCO was cleared.

Stack Flow Rate Measuring In conjunction with modifications to the Device Radioactive Gaseous Effluent Monitoring System (RAGEMS), the stack flow device was inoperable during the entire reporting Sample Flow Rate Measuring period. Total stack flow was estimated by Device fan configuration in accordance with Technical Specification Table 3.6.14-2, Footnote (d).

The sample flow rate was manually set on an auxiliary skid to maintain conditions isokinetic with stack flow. This ensures a representative sample.

'OGESMS The monitors were recalibrated in June 1990, with operability in July 1990 after several system modifications were completed (see Attachment 1).

Stack noble gas grab samples were taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to comply with Technical Specifications.

Stack flow taken 'from fan configuration.

High Range Stack Modification being performed to upgrade Monitor (RAGEMS) system to be more reliable (See Attachment 1) 25

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1

SUMMARY

OF CHANGES .TO THE PROCESS CONTROL PROGRAM JANUARY JUNE 1990 The Nine Mile Point ¹1 Process Control Program (PCP) for waste solidification, as described in Administrative Procedure 3.7, Revision 3, was not revised during the January June 1990 reporting period.

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TABLE 7 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY - DECEMBER 1989 3rd 4th EST.TOTAL UNIT QUARTER QUARTER ERROR A. Fission 5 Activation ases

1. Total release Ci
2. Average release rate for period uCi /sec

'3."~Percent"of .Technical Specification Limit Prolonged Unit Outage B. Iodines

1. Total iodine-131 Ci
2. Average release rate for period uCi/sec
3. Percent of'echnical Specification Limit C. Particulates
1. Particulates with half-lives >8 days Ci 8.61E-04 5.41E-04 3.0E+01
2. Average release rate

"'for"period uCi/sec 1.08E-04 6.80E-05

3. Percent of Technical Specification Limit
4. Gross alpha radio-activity Ci 7.17E.05 3.68E-05 D. Tritium
1. Total release Ci 2.86E+00 ,1.62E+00 2.5E+01
2. Average release rate for period 'uCi/sec 3.60E-01 2.03E-01
3. Percent of Technical Specification Limit
  • Refer to E on"next page.

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

,TE NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS'EFFLUENTS-SUMMATION OF ALL RELEASES t

ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING

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ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY DECEMBER 1989 3rd 4th UNIT gUARTER gUARTER E. Percent of Technical S ecification Limits (NMP-1 Elevated Release)

Fission and Activation Gases

1. Percent of Quarterly Gamma Air Dose Limit O.OOE+00 O.OOE+00
2. Percent of Quarterly Beta Air Dose Limit O.OOE+00 O.OOE+00
3. Percent of Annual Gamma
  • ,""'~Air'~Dose";Limi t;to Date 7.39E-09 7.39E-09
4. Percent of Annual Beta Air Dose Limit to Date 1.06E-07 1.06E-07
5. Percent of Whole Body Dose Rate Limit O.OOE+00 O.OOE+00
6. Percent of Skin Dose Rate Limit 0:OOE+00 O.OOE+00 Tritium Iodines and Particulates (with half-lives reater than 8 da s):
1. Percent of Quarterly Dose Limit 2. 47E-01 1. 57E-01
2. Percent of Annual Dose Limit to Date 3.77E-01 4.56E-01
3. Percent of Organ Dose Rate Limit 4.89E-03 1.80E-02 28

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-ELEVATED RELEASE t

ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY DECEMBER 1989 CONTINUOUS MODE¹ Nuc 1 i des Re 1 eased Uni t ~3dtd ' thlh t Fission Gases Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-133 Ci

-" ""Xe'non-'.1 35 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci

3. Particulates Strontium-89 Ci 8.29E-06 6.83E-06 Strontium-90 Ci 1.80E-06 2.32E-06

'e's i um-'.1 34 Ci Cesium-137 Ci 3.12E-04 1.34E-04 Cobalt-60 Ci 4.60E-04 3.24E-04 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 7.87E-05 7.39E-05 Molybdenum Ci Tritium Ci 2.86E+00 1.62E+00 No batch mode release occurred during the reporting period.

concentrations are less than lower limits of detection required by Technical Specification i.e., 1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates and 1.00E-12 uCi/ml for Iodines, respectively).

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ATTACHMENT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

" PROBLEMS WITH THE NMP1 STACK EFFLUENT MONITORING SYSTEM: CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990 The previous Semi-Annual Effluent Release Reports provided a status update for each of the specific modifications and changes associated with NMP-1's high range Radioactigve Gaseous Effluent Monitoring System (RAGEMS) and normal operation (lower range) Old General Electric (GE) Stack Monitoring System (OGESMS). Progress continues to be made toward the resolution of the system's

.design deficiencies so that a more reliable stack monitoring system can be obtained. During the period of RAGEMS inoperability, all stack radiological monitoring requirements, as defined in section 3.6.14b of the Technical Specifications, were met using the Old General Electric Stack Monitoring System (OGESMS) or an auxiliary sampling system as allowed by Technical Specifications Limiting Conditions of Operation.

Installation of all modifications to RAGEMS and OGESMS* is complete.

Current plans are to complete functional and pre-operational testing of the

,.RAGEMS in 1990. Additionally, it is the intent to maintain RAGEMS available

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'sing 'b'acku'p "gr'ab ~sample methods du'ring most periods of commercial operation to meet NUREG 0737 monitoring requirements. OGESMS modifications necessary

'or system-operability will be completed prior to restarts STACK MONITORING SYSTEM Modification U date The following is an update of recent modifications and design changes made to date on RAGEMS and OGESMS, and a summary of modifications needed to complete the entire system upgrade:

1. Developed a new Piping and Instrument Diagram (PAID) to convey more detailed information on a complex system to enhance system operation.

P8 ID was updated to reflect the final modification, and issued 7/17/90 for Operations Acceptance of OGESMS per DCR's and field walkdown.

2.'Revise'he "'sye .radiation alarming logic to include both the RAGEMS and the OGESMS to facilitate operator response. This design package was reworked to incorporate a valve and logic alignment switch to remotely place either unit into service. Installation is complete and was pre-operationally tested via Nl-POT-288 dated 6/90.

  • NOTE: Operations Acceptance of OGESMS on"'7'/13/90.

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ATTACHMENT 1 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t

PROBLEMS NITH THE NMPl STACK EFFLUENT MONITORING SYSTEM: CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990

3. Design and install flow alarming capabilities from the RAGEMS unit to the plant's main Control Room. This design was reworked to incorporate the logic switch identified earlier. Installation is complete. Functional testing was completed via Nl-ISP-112-A006.
4. Replace RAGEMS'ennelec Count Rate Meter to eliminate the periodic spiking signals. The new count rate meter was returned to the manufacturer to resolve signal interface concerns with the unit's programmable controller. It has subsequently been reinstalled. The spiking problem has been further addressed by evaluating and redesigning the power supplies to RAGEMS. Installation is complete and was tested via Nl-ISP-201-A036.

.5. Improve operator, interface with the system's parameters by increasing the abi'1'i'ty"'to'char't'/record the system's operation. Installation is complete.

A. Placing 'the existing"OGESMS radiation signals (counts per second or counts per minute) on new recorders.

B. Addition of new parameters to be recorded (e.g., the RAGEMS radiation release rate, OGESMS system flow, RAGEMS system flow and total stack

'low). During the reporting period, total stack flow value was estimated by fan configuration in accordance with Technical Specification Table 3.6.14-2, footnote (d).

6. Install a permanent power supply for the air conditioner in cabinet 44 of RAGEMS. Installation is complete.

, .7. ,Install cables for future expansion of the system. Installation is compTete". "Design 'packages which use these cables have been completed and issued. Installation is complete.

8. Install remote manual switches to the RAGEMS dilution system to manually override the RAGEMS process computer. The design of this work is complete. Installation of manually activated program to remotely control dilution is complete and functional testing is in progress.
9. Provide RAGEMS with the capability 'to .isolate 'the 'plant' contai nment vent and purge valves . OGESMS currently has this isolation capability. The design of this modification is complete. Installation is completed and pre-op tested in Nl-POT-288 in 6/90.
10. Replace the flow control valves in RAGEMS. The design of this work is complete. Installation is complete and functional testing is in progress'1

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ATTACHMENT 1 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t

PROBLEMS HITH THE NMP1 STACK EFFLUENT MONITORING SYSTEM: CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990 ll. Replace the flow control valve and associated controller on OGESMS.

Installation is complete and pre-op tested via Nl-POT-288 in 6/90.

12. Install calibration valves, leak test valves and gauges on both RAGEMS and OGESMS. 'RAGEMS valves have been installed. Installation of hardware for OGESMS is complete . Additional valves are being installed to facilitate remotely aligning each unit (RAGEMS/OGESMS) from the control room.

Installation is complete and leak checked via Nl-ISP-201-R531.

13. Redesign particulate and iodine filtration portion of OGESMS to provide filtration redundancy. Installation is complete and pre-op tested via Nl-POT-288 in 6/90.

1,4.,Install additional shielding designed to eliminate periodic spikes in the background r'adiation levels on the OGESMS monitors. Installation is complete.

15. Resolve computer software and hardware problems. This work includes the upgrade of the computer's modem capability. Hardware installation is complete. Software functional testing is in progress.
16. Modify RAGEMS/OGESMS computer input and output signals to provide additional essential input to the Safety Parameter Display System (SPDS).

Modification is complete and software tested.

17. Revise the plant's process computer's descriptions and setpoints as they apply to the Stack Gas Monitoring System (OGESMS and RAGEMS). Revision is complete and pre-op tested via Nl-POT-288 in 6/90.
18. Correct leakage pr'oblems with RAGEMS 3-way solenoid valves. Installation is complete and leak checked via Nl-ISP-201-R531.

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l' TECHllICRL.REVIE V 8119 CGllTROL REVIEW GHEGK LIST TO SE PREPARED BT AUTHOR JOCK CHECK LIST FOR DOCUMENT NO.............................,...... Gt r 7 REV................... DATE....../f........z....

OILY BOXES THAT hPPLY YES NA All references needed to implement the procedure are clearly identified and available........... 5 0 The procedure contains adequate equipment lists, precautions and limitations,-

yrerequisites, graphs, diagrams or data sheets as required..... ..... ~

Survei llaace and Maiatenance Procedure utiliscs PLANT IMPACT statement associated with ayprovai/yermiss ion for use.....,..... ~ 00010\ ~~1 00 OHO 010 100 101 0 OOOHOOOO

~ ~~ ~ ~ ~ ~ ~1~ 11 00

~ ~ ~ ~ ~0 ~

0 As appropriate. procedure addresses use of MARK - UPs...............................,........;................. 0

- . If appropriate, procedure requires use of fire yrotection measures.

isa hfe vo~ ~n$ nts'nose rnfec. as ~ 00 1 ~ 00th hto 0 1000H0 000000000000000000000000000000000tootoootoo ~

0

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~ 0 ~ 11010 ~ ~ OOHOHO ~ 0 ~ 0 1 ~ 01100 ~

0 lf leads are lifted, jumpers placed or blocks used in the procedure, the PLANT IMPACT statement ackaowledges such use........................................................,......................................

Aa appropriate. procedure notifies other affested departments such as O.C.. Operations, IAC. Maintenance, Rad Protection etc......H. H.....H......H....H.H..H. ~

~ 00 '0000 F0 ~ ~ 00 ~ 0 ~ 0 ~ 011H1 ~

if Teohnloal Speoiffoatlon Is exceeded. approprlme sation is Identified, ................... EY CI The yrocedure references valve numbers, motor control numbers. power supplies.

Instrumentation identification is clear and correct....., .........,.........,...:......,

t Ef 0 When encountered. EQ. related equipment is identified as such...........=................................... 0 prooedurs maps aro olear and m surete. They are not unnecessarily dlfffoult to Implement.... cl W

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IS'he proosdm s reflects the lateit aysttoa or smapenent oonfisuratfon.-................:............. 0 The prooedure ref lasts uorh'es It is to he done st the station.............-........,,....................:.-. fl Procedure removes aay jumpers or blocks aad restores lifted leads used to effect the ofkH00000000000HH\HHHOOOHHHOHHOOOHHOOOOOHH0000000000HOOHOO 1111t010to ~ OHHOttttHHOOOHtttttttttttt~ tHOOOHttttttttttttttt 0 RETURN TO SERVICE uses double verification and identifies specifics being verified.......... 0 For mainteaance procedures, RETURN TO SERVICE either pciforms a POST MAINTENANCE TEST Of'efefenoeS a fequlfed 0 teSt000ttttt000t000000000t0000t0000000000ttt000t0000t0000000tt00000ttttt0tt000000totottoootttooto 0, 9 MAQR'PH a~ cleared or surrendered................................................................................... 0 "ACCEPTANCE CRITERIA" Ideatifiea accomplishment of specific goals...............:.................... 0 "CV FORM PREPARED BY.... ... DATTr .Q2-..'g/65 FIG 2.0-2 SH 4 OF 4 AP-2.0 H32 Decefmber 1989

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