ML20205G900

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Annual Radioactive Effluent Radioactive Effluent Release Rept
ML20205G900
Person / Time
Site: Humboldt Bay
Issue date: 12/31/1998
From:
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20205G895 List:
References
NUDOCS 9904070414
Download: ML20205G900 (21)
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Text

Enclosure 1 PG&E HBL-99-006 I

IIUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l January I through December 31,1998 1

i 9904070414 990331 PDR ADOCK 05000133 R PDR

PACIFIC GAS AND ELECTRIC COMPANY HUMBOLDT BAY POWER PLANT DOCKET NO. 50-133, LICENSE NO. DPR-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,1998 TilROUGil DECEMBER 31,1998 TABLE OF CONTENTS INTRODUCTION . .. . . . . . . . . . .. ... .. . . . .. .... .. 2

1. SUPPLEMENTAL INFORMATION .. . . .. . . . . . . . . . . . . . . . . . . . . . . 4
11. GASEOUS AND LIQUID EFFLUENTS . . . . . . . . . . ... 8 Table 1 - Gaseous Efiluents - Summation of All Releases. . . ... . 9 Table 2 - Gaseous Efiluents - Nuclides Released . . .. . . .. . ., . 10 Table 3 - Liquid Efiluents - Summation of All Releases..... . ... . . . .. . . .. I 1 Table 4 - Liquid Effluents - Nuclides Released . . . . . . . . . . . . 12 l

111. SOLID RADIOACTIVE WASTE. .. . . . . . . . .. . . . . . . . . . . . . . . . . . 13 Table 5 - Solid Waste and Irradiated Fuel Shipments.. . . . .. .14 IV. RADIOLOGICAL IMPACT ON MAN . . . . . . . .. . 15 Table 6 - Radiation Dose for Maximally Exposed Individuals. .. . . . . . 16 V. CHANGES TO THE O SITE DOSE CALCULATION MANUAL (ODChi). . 17 VI. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP). . .. . . 20 Vll. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS. .. 20 l

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p HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 INTRODUCTION l.

l This report summarizes gaseous and liquid radioactive emuent releases from Humboldt Bay Power Plant Unit 3 for the four quarters of 1998. The report includes calculated potential radiation doses from these radioactive emuents and a comparien with the l numerical guidelines of 10 CFR 50, Appendix I, as well as a summary of shipments of l solid radioactive waste. The concentrations of plant emuent releases during the reporting period were well below Technical Specification limits.

The information is reposted as required by Section VII.J.3 of the Technical Specifications, and it is presented in the general format of Regulatory Guide 1.21, Appendix B (except for the topics identified below).

Meteorolouv The meteorological data logging system was removed from service in 1967 so the information specified by Regulatory Guide 1.21, Appendix B, Section F, is not available.

Previous Humboldt Bay W ver Plant Annual Radioactive Emuent Release Reports summarized the cumulative joint frequency distribution of wind speed, direction, and atmospheric stability for tire period April 1962 through June 1967, when the meteorological data logging system was in service.

Short-lived Nuclides The Unit was last operated on July 2,1976. Due to the long decay time since operation, short-lived radionuclides are neither expected nor reported. This includes iodines and noble gases other than Krypton-85.

Air Particulate Filter Composites - Sr-90 ,

Air pani:date sample filters are combined for approximately monthly intervals and analyzed off-site for Sr-90.

Air Paniculate Filter Composites - Gross Alpha Each weekly sample filter is individually counted for gross alpha activity, rather than analyzing a monthly composite of the filters, as described in Regulatory Guide 1.21.

Gaseous Emuents - Tritium Tritium releases during plant operation were less than detection levels. Sii.ce the plant  !

i was permanendy shutdown in 1976, current tritium release levels are less (nan the release levels that occurred during plant operations. Therefore, no tritium samples were collected during this reporting period.

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r Errata A review of the 1996 Radioactive Efiluent Report found a typographical error in Table 2, Part 1, for the total fission gas release for the fourth calendar quaner. The total value should have been "<5.58El" rather than "<5.52El" Since the difference is much smaller than the detectable amount and calculated public exposure was not affected, no specific correction will be made to the 1996 Radioactive Efiluent Report.

l A revie'v of the 1997 Radioactive Efiluent Report found that the Sr-90 value had been neglected in the calculation of total particulate release shown in Table 2, Part 2, for the third calendar quarter. The total value should have been "6.84E-6" rather than l "6.70E-6" This error also affected the third calendar quaner values for particulate releases in Table 1, Part B, where the total release should have been "6.84E-6" rather l than "6.70E-6", the average rcl ease rate should have been "8.60E-7" rather than "8.43E-7", and the percent of applicable limit should have been "4.00E-7" rather than I l

"3.92E-7" The error was in a computer spreadsheet cell formula, which was subsequently corrected. This error did not affect the reported public exposure which l is calculated from individual radionuclide detected activities rather than from total activity. Since the difTerence is well within the uncertainty of the applicable analyses, and calculated public exposure was not affected, no specific correction will be made to the 1997 Radioactive Efiluent Report.

l A review of previous Radioactive Efiluent Reports identified that the section for i

Gaseous Abnormal Release Statistics (Part E.2. of Section I," Supplemental Information") was not included, because there were non- to be reported In the future,  ;

this section will be explicitly incorporated into the report. I

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j 1. FUPPLEMENTAL INFORMATION A. Regulatory Limits' l 1. Gaseous EfIluents l

a. Noble Gas Release Rate Limit The radioactive noble gas release rate limit is based on concentration l limits from 10 CFR 20, divided by an annual average dispersion i factor for the sector with the least favorable atmospheric dispersion.

l The applicable concentration limits changed from the "old" 10CFR20 MPCs (Maximum Permissible Concentrations) to the "new" 10CFR20 ECLs (Efiluent Concentration Limits), effective 5/7/98.

l As of 10/9/98, the gaseous effluent release height was reduced from 250 feet to 50 feet, when a modified ventilation system was placed in service. This changed the applicable annual aserage dispersion factor from 1.4E-6 seconds per cubic meter to 1.0E-5 seconds per cubic meter.

l l b. Iodine Release Rate Limit

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does not define an iodine release rate limit. 1

c. Particulate Release Rate Limit ,

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The radioactive particulate release rate limit is based on concentration l

limits from 10 CFR 20, divided by an annual average dispersion l factor for the sector with the least favorable atmospheric dispersion.

l The applicable concentration limits changed from the "old" 10CFR20 MPCs (Mr.ximum Permissible Concentrations) to the "new" 10CFR20 ECLs (EfIluent Concentration Limits), effective 5/7/98.

As of 10/9/98, the gaseous effluent release height was reduced from 250 feet to 50 feet, when a modified ventilation system was placed in service. This changed the applicable annual average dispersion factor l

from 1.4E-6 seconds per cubic meter to 1.0E-5 seconds per cubic meter.

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' Regulatory limits in this report that refer to "old" 10 CFR 20 are based on the version of 10 CFR 20 in effect prior to January 1, 1994 (20.1-20.602), as referenced in the Technical Specifications prior to License Amendment 32. Regulatory limits in this report that refer to "new" 10 CFR 20 are based on the version of 10 CFR 20 in efTect on January 1,1994 (20.1001-20.2402), as referenced in the Offsite Dose Calculation Manual described by License Amendment 32, effective 5/7/98.

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( 2. Liquid Emuents

a. Concentration Limit Concentration limits for liquid emuent radioactivity released to Humboldt Bay are taken from 10 CFR 20. The applicable limit changed to "new" 10CFR20 ECLs (Emuent Concentration Limits),

from "old" 10CFR20 MPCs (Maximum Permissible Concentrations),

efTective 5/7/98.

B. Maximum Permissible Concentrations

1. Gaseous Emuents Maximum Permissible Concentrations for gaseous emuents are taken from "old" 10 CFR 20, Appendix B, Table II, Column 1 (for releases prior to 5/7/98), or from "new" 10 CFR 20, Appendix B, Table 2, Column 1 (for releases beginning 5/7/98).
2. Liquid Emuents j 1

Maximum Permissible Concentrations for liquid emuents taken from "old" 10 CFR 20, Appendix B, Table 11, Column II (for releases prior to 5/7/98),

or from "new" 10 CFR 20, Appendix B, Table 2, Column 2 (for releases beginning 5/7/98).

C. Measurements and Approximations of Total Radioactivity

1. Gaseous Emuents
a. Fission and Activation Gases All ventilation and system vents are routed to the Unit 3 stack. The gaseous activity released from the stack is monitored by a continuous monitor equipped with a beta scintillator, with its response calibrated for Kr-85.

The "less than" value reported for Kr-85 is based on the estimated sensitivity of the stack Kr-85 monitor.

The estimated sensitivity of the stack. Kr-85 monitor permits detection of Kr-85 at approximately 0.5% of applicable Lower Limit of Detection (LLD) presented in the ODCM.

j b. lodines l

l Due to the long decay time since operation (shutdown July 2,1976),

no detectable releases of radioactive iodines can be expected.

Therefore, the Technical Specifications do not require that these radionuclides be monitored.

c. Particulates Radioactive paniculates released from the plant stack are monitored by continuous sample collection on particulate filters. Filter papers are removed from the stack sampling system weekly, and are analyzed for the concentration of gamma-emitting nuclides (intrinsic germanium detector). All statistically significant gamma peaks are identified.

After decaying 7 days, the filters are analyzed for gross alpha radioactivity (internal proportional counter).

Filters are composited monthly and arialyzed monthly for strontium-90 (the only strontium present). The monthly composite results are averaged together to produce the quarterly composite.

The estimated error of the reported particulate release values is based on uncertainty in sample flow rate, stack flow rate, detector calibration, and typical sample counting statistics.

The Minimum Detectable Activity (MDA) for all particulate filter samples was less than the applicable Lower Limit of Detection (LLD) presented in the ODCM.

2. Liquid Efiluents
a. Batch Releases All water from contaminated plant systems was collected, filtered,  !

and analyzed before discharge (on a batch basis) through the liquid j radwaste process monitor. Analysis ofweekly composite samples i from the plant efIluent canal did not detect any significant additional release of radioactive liquids during the report period. I Samples ofliquid waste batches were analyzed for the concentration of gamma-emitting nuclides (intrinsic germanium detector). All statistically important peaks were identified. Quarterly composites of all batches were analyzed for radioactive strontium (Sr-90), and monthly composites of all batches were analyzed for gross alpha and tritium.

The error of the reported release values is estimated based on uncertainty in sample volume, batch volume, detector calibration, and typical sample counting statistics.

l The Minimum Detectable Activity (MDA) for all batch samples was less than the applicable Lower Limit of Detection (LLD) presented in the ODCM.

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b. Continuous Releases l

There were no continuous liquid effluent releases during this report I period.

l D. Batch Release Statistics 1

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1. Liquid
a. Number of batch releases. .. . . 13
b. Total time period for batch releases . 2.29E3 minutes
c. Maximum time period for a batch release. 4.90E2 minutes
d. Average time period for a batch release.. 1.76E2 minutes
e. Minimum time period for a batch release.. 1.71E2 minutes
2. Gaseous
a. Number of batch releases. . . . . . .. . . O
b. Total time period for batch releases . . . . N/A
c. Maximum time period for a batch release. . .. . N/A
d. Average time period for a batch release.. . . . N/A
e. Minimum time period for a batch release.. . . . N/A E. Abnormal Release Statistics
1. Liquid
a. Number of abnormal releases. . O
b. Total activity released. . N/A
2. Gaseous
a. Number of abnormal releases. O
b. Total activity released. . N/A s

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11. QASEOUS AND LIOUlD EFFLUENTS A. Gaseous Emuents Table 1 summarizes the total quantities of radioactive gaseous emuents.

Table 2 presents the quantities of each of the nuclides determine to be released.

B. Liquid Emuents Table 3 summarizes the total quantities of radioactive liquid emuents. Table 4 presents the quantities of each of the nuclides determined to be released.

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 ,

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l TABLE 1 l

l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l Units First Second Third Fourth Est. Total Quarter Quarter Quarter Quarter Error, %

A. Fission & Activation Gases

1. Total release Ci <5.46El <5.52El <5.58El <5.23 El 3.20El l
2. Average release rate pCi/sec <7.02E0 <7.02E0 <7.02E0 <6.58E0
3. Percent of applicable limit  % <3.28 E-3 <3.28E-3 < l .40 E-3 <9.40E-3 '

B. Particulates

1. Total release Ci 1.92E-6 1.83 E-6 6.35 E-6 <2.96E-6 2.80El l
2. Average release rate pCi/sec 2.47E-7 2.33E-7 7.99E-7 <3.72 E-7
3. Percent of applicable limit  % 1.37E-7 4.01 E-7 1.37E-6 <4.75 E-6

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4. Applicable limit (mixture MPC Ci/cc 2.52E 10 8.14E.11 8.14 E-11 7.83E-11 i or ECL, see note) I
5. Gross alpha radioactivity Ci 1.02E-7 1.24E-7 1.09E-7 <9.90E-8 l

1 Note: The < symbol used in this table means that a majority of the measurements contributing to the )

result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected.

The < symbol is applied ifless than 50% of the combined value is made up of detected results. When combining detected and non-detected results for different nuclides (e.g. activity totals of multiple nuclides), values with the < symbol are ignored (i.e. treated as zero). When combining non-detected results for different nuclides (e.g. activity totals of multiple nuclides, when none were detected), all values with the < symbol are used.

The applicable limit changed from "old" 10CFR20 MPCs to "new" 10CFR20 ECLs, effective .5/7/98. The " percent of applicable limit" for fission gas releases is calculated with MPCs for the first quarter and second quarters, and with ECLs for the third and fourth quarters. The " percent of applicable limit" for the second quarter particulate releases would be <l.40E-3, ifit were based on ECLs. The " percent of applicab!c limit" for particulate releases is calculated with MPCs for the first quarter, and with ECLs for the second, third and fourth quarters. The " percent of applicable limit" for the second quarter particulate releases would be 1.15E-7, ifit were based on MPCs. The calculation for " percent of l

applicable limit" includes the atmospheric dispersion factor, which changed from 1.4E-6 l seconds / meter' to 1.0E-5 seconds / meter', effective 10/9/98. The fourth quarter percent of limit is conservatively assumed for the entire quarter.

l Since the fourth quarter particulate releases were "less than" values, the fourth quarter limit is based on the typical historical mixture (50% Cs-137,48% Co-60,2% Sr-90).

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m HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 TABLE 2 GASEOUS EFFLUENTS - NUCLIDES RELEASED l.

Continuous Mode Nuclides Released Unit First l Second Third Fourth Quarter l Quarter Quarter Quarter 1.- Fission Gasses Krypton-85 Ci <5.46El <5.52El <5.58El <5.23 El Total for period Ci <5.46El <5.52El <5.58El <5.23 El

2. Particulates ,

Cobalt-60 Ci 9.22E-7 7.85E-7 2.72E-6 <7.83 E-7 Strontium-90 Ci 8.14E-8 5.58 E-8 1.90E-7 <3.92 E-8 Cesium-137 Ci 9.16E-7 9.94E-7 3.43 E-6 <7.47E-7 Am-241 Ci <l .02 E-6 < l .42E-6 <9.21 E-7 < l .39E-6 Total for period Ci 1.92E-6 1.83E-6 8.35E-6 <2.96E-6 Note: '

The < symbol used in this table means that a majority of the measurements

- contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied ifless than 50% of the combined value is made up of detected results. When combining detected and non-detected results for different nuclides (e.g activity totals of multiple nuclides), values with the < symbol are ignored (i.e. treated as zero).

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HUMBOLDT BAY POWER PLANT l

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 TABLE 3 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second Third Fourth Est. Total Units Quarter Quarter Quarter Quarter Error, %

A. Fission & Activation Products

1. Total release (not including tritium, gases, alpha) Ci 6.42E-4 9.22E-5 2.25 E-4 1.92E-4 1.30El
2. Average diluted concentration Ci/ml 2.58 E-11 4.67E-12 1.01 E-11 8.03E-12
3. Percent of applicable limit  % 9.19E-4 1.25 E-4 9.59E-4 9.01 E-4
4. Applicable limit (Mixture MPC pCi/ml 2.80E-6 3.72E-6 1,05 E-6 8.91 E-7 I or Mixture ECL, see note) l l

B. Tritium

1. Total release Ci 3.60E-4 3.98E-5 1.58E-4 5.84E-4 1.50El l
2. Average diluted concentration pCi/ml 1.45E-I l 2.02E-12 7.08E-12 2.45 E-I l
3. Percent of applicable limit  % 4.82 E-7 6.72E-8 7.08 E-8 2.45 E-6 ,

l C. Gross Alpha Radioactivity l 1. Total release l Ci l 2.10E-6 l 5.17E-7 l 1.72 E-6 l 7.42E-7 l 1.00El l D. Volume of waste released Liters 1.95E5 2.11 E4 2.59E4 7.13E4 3.00E0 (prior to dilution) l E. Volume of dilution water l Liters l 2.49E10 l 1.98E10 l 2.23E10 l 2.39E10 l 1.50El l 4

Note: The < symbol used in this table means that a majority of the measurements contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied ifless than 50% of the combined value is.made up of detected results. When combining detected and non-detected results for difTerent nuclides (e.g. activity totals of multiple nuclides), values with the < symbol are ignored (i.e treated as zero).

The applicable limit changed to "new" 10CFR20 ECLs (Emuent Concentration Limits), from "old" 10CFR20 MPCs (Maximum Permissible Concentrations),

effective 5/7/98. The " percent of applicable limit" is calculated with MPCs for the first and second quarters, and with ECLs for the third and fourth quarte. . There were no liquid releases between 5/7/98 and 7/1/98.

HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 TABLE 4 LIQUID EFFLUENTS - NUCLIDES RELEASED l

I Batch Mode Nuclides Released Unit First Quader l Second Quarter l Third Quarter l Fourth Quarter Strontium-90 Ci 6.02E-5 6.15E-6 1.62E-5 3.44E-5 Cesium-137 Ci 5.48E-4 8.40E-5 1.67E-4 1.41E-4 Cesium-134 Ci <2.71 E-6 <3.31 E-7 <8.03 E-7 <l .06E-6 Cobalt-60 Ci 3.36E-5 2.02E-6 4.10E-5 1.66E-5 Am-241 Ci <5.17E-6 <6.22E-7 <3.56E-6 <l .79E-6 Total for period Ci 6.42E 4 9.22E-5 2.25E-4 1.92E-4 Continuous Mode Nuclides Released . Unit First Quaner l Second Quarter l Third Quarter l Fourth Quarter

Strontium-90 Ci N/A N/A N/A N/A l Cesium-137 Ci N/A N/A N/A N/A Cesium-134 Ci N/A N/A N/A N/A Cobalt-60 Ci N/A N/A N/A N/A f Am-241 Ci N/A N/A N/A N/A i Total for period - Ci N/A N/A N/A N/A _

Notes: The < symbol used in this table means that a majority of the measurements contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied ifless than 50% of the combined value is made up of detected results. When combining detected and non-detected results for different nuclides (e.g. activity totals of '  ;

multiple nuclides), values with the < symbol are ignored (i.e. treated as zero).

N/A - There were no continuous mode liquid ellluents during the report period.

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1 111. SOLID RADIOACTIVE WASTE Table 5 summarizes the shipments of solid radioactive waste made during the report f period. The volume reported is the 'as-buried' quantity.

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 TABLE 5 j

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite For Burial Or Disposal

1. Type of Waste Unit 12 Month Period Estimated Total Error, %
a. Spent resins, filter sludges, Cubic Meter None N/A evaporator bottoms, etc. Ci N/A N/A
b. Dry compressible waste, Cubic Meter 2.01El 1.00E0 contaminated equipment, etc. Ci 4.38E-2 5.60El
c. Irradiated components, Cubic Meter None N/A control rods, etc. Ci N/A N/A
d. Other (dewatered sludge) Cubic Meter None N/A Ci N/A N/A
2. Estimate ofmajor nuclide Unit Nuclide 12 Month Period composition (by type of waste)
b. Dry compressible waste,  % H-3 6.36E0 contaminated equipment, etc.  % C-14 1.31 El

% Fe-55 8.03E0

% Ni-59 1.84E-2

% Co-60 3.66E0

%- Ni-63 2. I6E0

% Sr-90 1.60El

% Tc-99 5.7 I E-3

% I-129 7.00E-6

% Ce-144 1.84E-7 )

% Cs-137 2.98El I

% Cs-134 1.31E 2

% Pu-238 4.61 E-l

% Pu-239/40 6.82E-1

% Pu-241 1.95El

% Am-241 4.25 E-2

% Cm-242 4.18E-3

% Cm 243/244 1.09E-1

3. Solid Waste Disposition Number of Mode of Transportation Destination Shipments 1 Truck Barnwell. SC 1 Truck Clive, UT B. Irradiated Fuel Shipments
1. Irradiated Fuel Disposition Nuniber of Mode of Transportation Destination Shipments None N/A N/A IV RADIOLOGICAL IMPACT ON MAN A comparison of calculated doses from various paths has shown that the offsite doses are primarily due to direct radiation and to the consumption of aquatic foods.

Maximum doses to individuals (for the maximally exposed organs and age groups) are summarized in Table 6. These doses comply with 40 CFR 190 as there are no other uranium fuel cycle facilities within 8 km of the Humboldt Bay Power Plant.

A. Doses to the average individual in the population from all receiving-water-related pathways were calculated for detected releases, based on the guidance of Regulatory Guide 1.109. The highest results were less than 0.001 mrem /yr (total body) for the Adult age group, and 0.001 mrem /yr for the bone of the Adult age group.

These doses are well below the 10 CFR 50, Appendix 1 numerical guidelines for limiting efiluents as low as is reasonably achievable (ALARA) (3 mrem /yr to the total body and 10 mrem /yr to any organ).

B. Total body doses to the average individual in the population from gaseous effluents to a distance of 50 miles from the site are not calculated, but this dose is less than the total body dose to an average individual present at the maximally exposed location. For an average individual at the maximally exposed location, the total body dose (calculated with the same dispersion and deposition parameters as were used to calculate , maximum exposure) was less than 0.001 mrem /yr.

This maximum calculated dose is well below the 10 CFR 50, Appendix I numerical ALARA guidelines (10 mrem /yr for gamma radiation and 20 mrad /yr for beta radiation from noble gases and <l5 mrem /yr to any organ froin tritium and radionuclides in particulate form).

C. Total body doses (to the average individual in unrestricted areas from direct )

radiation from the facility) are based on TLD results of stations at the site l boundary, using the shoreline occupancy factors given in Regulatory Guide  !

1.109 for the highest average potential individual (Teen age group). For this group, direct radiation would result in an exposure ofless than 0.001 mrem /yr.

This maximum potential dose is well below the 10 CFR 20.1302(b)(2)(ii) limit of 50 mrem /yr from external sources necessary to demonstrate compliance with the 10 CFR 20.1301 dose limit for individual members of the public.

HUMBOLDT BAY POWER PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 TABLE 6  ;

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RADIATION DOSE FOR MAXIMALLY EXPOSED INDIVIDUALS Dose, milli-rem First Second Third Fourth Annual {

Dose Source Quarter Quarter Quarter Quarter Total Liquid Effluents Water-related Pathways (1) <0.01(5) <0.01(5) <0.01(5) <0.01(3) l 0.04(5)

<0.01(6) <0.01(7) <0.01(7) <0.01(6) 0.04(6) {

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Airborne Effluents Particulates (2) <0.01(8) <0.01(8) <0.01(8) <0.01(8) <0.04(8)

<0.01(7) <0.01(7) <0.01(7) <0.01(7) <0.04(7)

Noble Gases (3) - - - - -

Direct Radiation (4) <0.01 <0.01 <0.01 <0.01 <0.04

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1. Maximum total body and organ doses to individuals in unrestricted areas from receiving-water-related exposure pathways were calculated from the average concentrations ofliquid releases detected during the repon period, following the applicable portious of Regulatory Guide 1.109.

- 2. Maximum total body and organ doses to individuals in unrestricted areas from airborne-particulate-related exposure pathways were calculated from the average concentrations of airborne particulate releases detected during the report period, following the applicable portions of Regulatory Guide 1.109.

3. Total body and skin doses to potentially exposed individuals located at the point of maximum offsite ground-level concentrations of radioactive gaseous eflluents were not calculated because there were no detected releases of radioactive noble gases, and because the total body doses would be less than 0.005 milli-rem /yr at the level at which the releases could be detected.
4. Total body doses (to the maximum individual in the population) are based on TLD results of stations at the site boundary, using the shoreline occupancy factors of Regulatory Guide 1.109 for the maximum potentialindividual(Teen age group).
5. Total body (Adult age group).
6. Bone (Adult age group).
7. Bone (Child age group).
8. Total body (Child age group).

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V. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

The initial (Revision 0) ODCM was submitted with License Amendment Request (LAR) 96-02, on 12/9/96 in PG&E Letter 11BL-96-027. The ODCM was revised three times during the report period. The changes maintained the level of radioactive emuent control and dose commitment required by regulation. The changes did not adversely afTect the accuracy or reliability of emuent, dose or setpoint calculations.

Revision I was issued to implement the license amendment. This revision involved the following changes:

. Corrected references in introduction and in Part I, Section 4.1, to renumbered Technical Specification sections.

. Added column and entries for " Extension Period" to Part 1, Table 1-1 (test frequency definitions).

. Deicted Caisson Sump Monitor (and corresponding inoperable actions) from Part I, Table 2-1. The Caisson Sump Monitor is not currently installed equipment.

. Deleted Caisson Sump Monitor from Part I, Table 2-2.

. Corrected Process Water Monitor information in Part I, Table 2-2, for type and location ofinstrument failure indication.

. Changed Process Water Monitor source check frequency in Part I, Table 2-2 from "P" (prior to release) to "Q" (quarterly).

. Corrected instrumentation information in Part I, Table 2-3, identifying minimum channels to be operable, adding inoperable action requirements, and adding supplemental notes.

. Added channel checks and calibrations for Emuent Flowrate Monitor, added channel check for Sampler Flowrate Monitor, and added supplemental notes to Part I, Table 2-4.

  • Deleted references to Sr-89 from Part I, Tab le 2-5 and Table 2-6.

. Added Tritium and Gross Alpha sampling for continuous releases in Part I, Table 2-5.

. Changed Sampling Frequency from continuous sampling to grab sampling for continuous releases in Part I, Table 2-5.  !

. Deleted note "c" from Part I, Table 2-5. l

. Added asterisk to note "a" for Part 1, Tables 2-5 and 2-6. l

. Clarified treatment of"nn* > .ected" nuclides in las'. footnote to Part I, Table 2-5 and Table 2-6.

. Corrected first column heading in Part 1, Table 2-6 to agree with table title.

. Removed or reduced various elective (non-NRC) samples from Part I, Table 2-7 for influent canal, emuent canal and milk samples.

  • Deleted groundwater gross alpha and gross beta analyses from Part 1, Table 2-7.
  • Added explanation (based on N'UREG-1166) why Tritium sampling is not i necessary to Part I, Section 3.6.

j . Revised titles of annual reports in Part I, Section 4.1 l

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i l t o Corrected Part I, Section 4.4.a to include Plant hianager approval for changes I to the radwaste treatment systems.

Clarified California State Water Quality Control Board considerations for liquid waste treatment, in Pan 11, Section 3.1.2.

  • Clarified system flowrate for radwaste demineralizer in Part II, Section 3.2.2.c.

. Inserted inadvertently omitted words into Part II, Section 4.1.2.b.

e Inserted inadvertently omitted words into release rate term ("Q") defmition in '

Part II, Section 4.2.3.

  • Deleted unnecessary reference to average population from shielding factor term

("SF") defmition in ODCM Pan 11, Section 4.3.5.

  • Corrected values for" baseline releases"in Tables A-1 and A-2 of Appendix A.
  • Minor changes to the PCP were made as described below.

Revision 1 to the ODCM was reviewed by the PSRC on 5/6/98 and approved by the Plant Mar.ager on 5/7/98. It was effective on 5/7/98.

An editorial correction to revision 1 (identified as revision l A) was made on 6/19/98, to change a reference in Specification Basis 3.10 from 10CFR20.405c (obsolete) to 10CFR20.2203a4 (new equivalent regulation).

Revision 2 was primarily issued so that the ODCM would be applicable for the lower elevation of airborne ef1luent releases that would result from replacing the Unit 3 stack. This revision involved the following changes:

  • Corrected 7* paragraph ofintroduction, deleting " approval" by Plant Stafr Review Committee.
  • Corrected instrument failure indication in Part 1, Table 2-2 to reflect equipment modification:

. Added inadvertently omitted chemical yield correction to Lower Limit of Detection equations for Part 1, Table 2-5, Table 2-6 and Table 2-9.

. Added an alternate formula and term definition to the notes for Part 1, Tables 2-5,2-6 and 2-9. The formula was taken from NUREG-4007 for calculating the lower limit of detection for low background counting.

  • Throughout the ODCM, editorial / format changes were made to more clearly distinguish between Specifications (Part I, Section 2), Specification Bases (Part I, Section 3) and Administrative Controls (Part I, Section 4) and to correct references to these sections.

. Changed " limit level" to " reporting level" in the formula in Part 1, Specification 2.11, to be consistent with the title of Part 1, Table 2-8.

  • Deleted the symbol for " air particulate station" from Station 45 in Part 1, Table 2-10 and Figure 2-5, as that sample is not part of the monitoring program.
  • Corrected a reference in Part I, Section 4.1.i to (non-existent) Attachment 6.6
  • Reformatted the example for the Radiological Environmental Monitoring

' Program reponing format (Part I, Table A 1).

. Added explanation for " conservatism fe; tor" in Part II, Section 1.1.1.

  • Added more restrictive " plant policy" alarm limits for the liquid monitor in Part 11, Section 1.1.6 and 1.1.7.

F I

o Corrected terminology for factors in equations 1-4 and 1-5 of Part II, Section

1.2.2, equations 4-1 and 4-2 of Part 11, Section 4.2.3, and equation 4-4c of Part

! II, Section 4.3.12. This does not afTect calcu'ated results.

  • Throughout Part 11 of the ODCM, new values for the " atmospheric dispersion .

l parameter" and the " atmospheric deposition factor" were provided to correctly calculate doses and alarm setpoints for releases from the replacement (shorter) l stack.

  • Changed the corresponding setpoints for the stack monitor given in Part II, Section 1.2.3.
  • Clarified the use of the caisson sump pumps described in Part 11, Section 3.2.c.

e corrected minor typos throughout the ODCM.

Revision 2 to the ODCM was reviewed by the PSRC on 9/10/98 and approved by the Plant Manager on 9/10/98. It was effective on 9/24/98.

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VI. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

The initial version of the PCP was part of the ODCM submitted with License Amendment Request (LAR) 96-02 on 12/9/96 in PG&E Letter HBL-96-027.

Revision 1 of the ODCM made the following changes to the PCP:

  • References to " disposal" were changed to " land burial disposal."

. Added option to use high integrity containers having a certificate of compliance.

. References to " temporary" procedures (e.g. for vendors) were removed.

Procedures will be incorporated into the Plant Manual.

a References to absorbed or solidified oil were removed, replaced by reference to l thermal treatment to remove freestanding liquid.

l The changes did not affect the overall conformance of any solidified waste product l

to applicable regulatory requirements.

Vll. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS l There were no major changes to the liquid or solid radwaste treatment systems I during the report period.

There was a major change to the gaseous radwaste treatment system during the ,

report period. The original Unit 3 exhaust stack was replaced with a shorter stack.

l As of 10/9/98, the height of the gaseous radioactive emuent release point was reduced from 250 to 50 feet. This change was reviewed by the PSRC and I

approved by the Plant Manager. The change did not involve an unreviewed safety question as defmed in 10 CFR 50.59, nor involve a change to the Technical

{

Specifications. l 1

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i Enclosure 2 PG&E HBL-99-006 l

IlUMBOLDT BAY POWER PLANT UNIT 3 A',

CIIANGES TO TIIE SAFSTOR OFFSITE DOSE CALCULATION MANUAL DURING 1998 i

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