Text

Semiannual Effluent Rept,Jul-Dec 1985. W/860220 Ltr
	ML17278A824
Person / Time
Site:	Columbia
Issue date:	12/31/1985
From:	Powers C; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Martin J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
	GO2-86-150, NUDOCS 8605130374
	Download: ML17278A824 (199)
	v • d • e

RECuVQRV INRDRN*TIQN DISTRIDVN S .Qi Ak ER FlLF, ACCESSION.~NBR 8605130374 DOC. DATE: 85/12/3f NOTARIZED: ~F KET FAC I L'0-397 WPPSS Nuclear Pro Jecti Unit 2> Washington Public Poue 050003'P7 AUTH. NAME AUTHOR AFF I LIATI QN POWERS> C. il. Washing ton Pub l ic Pokier Supply Siistem REC IP. NAME RECIPIFNT AFFILIATION MARTIN> J. B. Reg i on 5i OP t'1 c e o8 Director SUB JECT: "Semiannual. Ef f3, uent Rep t Jul-Dec 1'785. " W/860220 I tr.

Z~ En.~

DISTRIDUTIQN CODE: IEESL CQRIES RECEIVED: LTR t ENCL g SIZE: I TITLE: Pori ad ic Environ Monitoring Rep (50 DKT) -Annual/Semi annua'li"- fluent/

NOTES:

REC IP IENT CQP IES RECIPIENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR PD3 PD 04 5 5 BWR PSB 3 3 INTERNAL: ACRS 11 1 AEOD IE FILE 01 NRR BWR ADTS 1 NRR PWR-A ADTS 1 NRR PWR-B ADTS 1 NRR/DSRO/RRAB RQN2/DRSS/EPRPB 1 RM/DDAMI/MIB 1 1

~

EXTERNAL: 4X 1 1 LPDR NRC PDR TOTAL NUMBER OF COP IES REQUIRED: LTTR 20 ENCL 20

HHP-2 SEMI-AHHUAL EFFLUEHT REPORT

'ULY TO OECE)ABER 1985

'r/ASHIHGTOH PUBI.IC POWER SUPPLY SYSTEil L ICEfiSE HO. HPF-21 8605130374 851231 PDR ADOCN 050003'V7 R PDR

TABLE QF CONTENTS SECTION PAGE

1.0 INTRODUCTION

. 1 2.0 LIQUID EFFLUENTS 1 3.0 GASEOUS EFFLUEHTS 5 4.0 SOLID WASTE 15 5.0 METEOROLOGICAL DATA 20 6.0 DOSE ASSESStlEHT - IMPACT ON tlAN 27 7.0 REVISIONS TO THE ODCN 32

LIST OF TABLES TITLE PAGE WNP-2 LIQUID EFFLUENTS - SUhlhNTION OF ALL RELEASES-JULY - DECEMBER 1985 .

2-2 WNP-2 LIQUID EFFLUENTS - SOURCE TERhlS - JULY - DECEtlBER 1985 3-1 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS - MIXED MODE RELEASES - hlAIN PLANT VENT - JULY - DECEtlBER 1985 7 3-2 WttP-2 GASEOUS EFFLUENTS - SOURCE TERhlS GROUND LEVEL RELEASES - TURBINE BUILDING JULY - DECEtlBER 1985 .

3-3 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS GROUND LEVEL RELEASES - RADWASTE BUILDING JULY - DECEtlBER 1985 .

WNP-2 GASEOUS EFFLUENTS - SUhlMATION OF Al.L RELEASES - JULY - DECEMBER 1985 13 WNP-2 GASEOUS EFFLUENTS - BATCH RELEASES JULY - DECEMBER 1985 . 14 SCALING FACTORS FOR TRU, Sr-90, AND HI-63 JULY - DECEMBER 1985 . 17 WNP-2 SOLID WASTE SHIPMENTS JULY - DECEhlBER 1985 . 18 5-1 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROMi TAPE - 3RD QUARTER 1985 21 5-2 JOiNT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE - 3RD QUARTER 1985 22 5-3 JOINT FREQUENCY DiSTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROhl HOURLY AVERAGES FROM TAPE - 4TH QUARTER 1985 23 JOINT FPEQUENCY DISTRIBUTiON fOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM 'TAPE - 4TH QUARTER 1985 24 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FRCtl TAPE - 1985 YEARLY 25 11

LIST OF TABLES (Continued)

TABLE TITLE PAGE 5-6 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROtl TAPE - 1985 YEARLY . 26 6-1 ttAXIMUM INDIVIDUAL DOSES FROM MNP-2 LIQUID EFFLUENTS - 3RD AND 4TH QUARTERS 1985 28 6-2 AVERAGE INDIVIDUAL DOSES FROM MNP-2 LIQUID EFFLUENTS - 3RD AND 4TH QUARTERS 1985 29 6-3 50-MILE POPULATION DOSES FROM MNP-2 LIQUID EFFLUENTS - 3RO AND 4TH QUARTERS 1985 . 30 6-4

SUMMARY

Of DOSES FROM MNP-2 GASEOUS EFFLUENTS-3RD ANO 4TH QUARTERS 1985 31 111

1 .0 IN TRODUCT ION This report is submitted in compliance with Technical Specification 6.9.1.11. It includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from WNP-2 during the previous six months of operation with data summarized on a quarterly basis.

2.0 LIQUID EFFLUENTS The radwaste liquid effluents were released in a batch mode only during the reporting period. Two batch releases occurred during the third calendar quarter and one batch release during the fourth calendar quarter.

The total time period for the batch releases was 5.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , wi th the maximum time period being 3. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for a release, the minimum time period being 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for a release and the average time period was 1.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The volume of dilution water used, is the total volume of recirculating cooling tower blowdown flow for the period. The average flow rate of the Columbia River during July through December 1985 was 9.1E+04 cubic feet per second.

Periodic LADTAP II computer runs were performed to verify compliance with Technical Specification limi ts using the assumptions in the Offsi te Dose Calculation t1anual (ODCi~i).

The liquid batch releases were recirculated prior to sampling. A repre-sentative sample was obtained and analyzed for each batch release. The method for measurement of total radioactivity was by gamma spectroscopy, liquid scintillation and proportional counters.

The percen of MPC limit is based on the total MPC fractions using those nuclides in Tab'ie 2-2 and concentrations listed in 10CFR20, Appendix 8, Table 2, Column 2.

The percent of estimated total errors are listed in Table 2-1. These estimated error s are based on counting statistics, tank volume, and in obtaining a representative sample prior to discharge.

The estimated total errors were calculated by obtaining the square root of the sum of the squares of the errors of the individual contributors and multiplying by 1.96 for a 95< confidence level.

~,

Table 2-1 MNP-2 LIQUID EFFLUEHTS - SUMMATION OF ALL RELEASES July - December 1985 3rd 4th Est.

Uni t Quarter Quarter Total lError* Xl A. Fission and ac.ivation products I

1. Total release (not including I I tri tium, ases, al ha) Ci 4.1E-03 3.0E-03 l2.2 E+01 I

2. Average diluted concentration uCi/ml 5.6E-09 I 3.9E-09

3. Percent of MPC limit 1.6E-02 I 6.6E-03 B. Tri tium

1. Total release Ci 4.1E-01 1.9E-02 12. 2 E+01 I

2. Average diluted concentration dur in eriod uCi/ml 5.6E-07 2.5E-08

3. Percent of MPC limit 1. 9E-02 8. 3E-04 C. Gross alpna radioactivity I l

1. Total . el ease I Ci I 2.6E-07 l 5.1E-08 12.3 E+01I D. Volume of waste (prior to I I di1 uti on) 1 iters 1.8E+05 2.4E+04 ll.5 E+01 I I

E. Volume of dilution water I I I used durin eriod liters 7.3E+08 I 7.6E+08 ll.5 E+Oll

At 95 confidence level

'1 Table 2-2 MNP-2 LIQUID EFFLUE>lTS - SOURCE TERMS July - December 1985 BATCH MODE 3rd 4th Nuclides Released Unit Quarter Quarter Strontium-89 Ci -9.3 E-06 3.6 E-07 Strontium-90 Ci 7.4 E-06 2.9 E-07 Cesium-134 Ci 1.7 E-05 2.9 E-06 Cesium-137 Ci 1.8 E-05 2.8 E-06 Iodine-131 Ci 1.5 E-05 3.1 E-06 Cobalt-58 Ci 6.0 E-06 2.5 E-04 Cobalt-60 Ci 2.1 E-05 1.1 E-04 Iron-59 Ci 3.0 E-05 1.8 E-05 Zinc-65 Ci 3.7 E-05 2.4 E-04 Man anese-54 Ci 1.5 E-05 2.1 E-05 Chromium-51 Ci 1.4 E-04 8.6 E-04 Hiobium-95 Ci 1.6 E-05 1.6 E-05 Molybdenum-99 Ci 1.4 E-05 1.3 E-05 Technetium-99m Ci 1.9 E-05 2.0 E-05 Barium-1 an thanum-140 Ci 4.8 E-05 9.8 E-06 Cerium-141 Ci 2.5 E-05 3.8 E-06

TABLE 2-2 (Continued)

Cerium-144 Ci 1.1 E-04 2.2 E-05 Tritium Ci 4.1 E-01 1.9 E-02 Iron-55 Ci 3.1 E-05 1.2 E-06 Sodium-24 Ci 1.1 E-05 8.6 E-07 Cop er-64 Ci 3.4 E-03 9.3 E-04 Arsenic-76 Ci 2.9 E-'05 4.1 E-04 Tunasten-187 Ci ;" 1.4 E-05 5.0 E-05 Antimony-122 Ci 4.3 E-06 1.0 E-05 Antimony-124 ='.4 E-08 3.0 E-06 Silver-110m Ci 1.6 E-05 3.9 E-06 Zirconium-95 Ci 2.2 E-05 9.3 E-06 Total for Period ( Above )I Ci 4.1 E-01 2.2 E-02

3.0 GASEOUS EFFLUENTS

'he gaseous radwaste effluents from HNP-2 were released in a continuous mode. There are three (3) release points at HNP-2:

1. Main Plant Vent - mixed mode release

2. Turbine Building - ground level release

3. Radwaste Building - ground level release The gaseous source terms from each release point are listed in Tables 3-1 to 3-3. Table 3-4 provides a summation of the total activi ty released, the average release rate, the percent of Technical Specification limit, gross alpha radioactivity and the estimated total error associated with the measurements of radioactivity in the gaseous effluents.

Radioactivity measurements for gaseous effl uent releases are performed for fission and activation gases by collecting the samples on charcoal traps and analyzing them using gas+a spectroscopy. Tritium is sampled by freeze trapping and analyzed by liquid scintillation counting. Particu-lates and iodines are sampled using charcoal cartridges and particulate filters and analyzed using gamma spectroscopy.

The "Percent of Technical Specification Limit" calculations were based on exposure at specified locations. Air dose due to noble gases was deter-mined at the site boundary with the quarterly limit of 5 mrads for gamma being the more restrictive for each time period. The gamma air dose from noble gases for the thir d quarter was 1.6E-02 mrads and 2.1E-01 mrad for the fourth quarter. Iodines, particulates and tritium calculations were determined at Taylor Flats, located 4.2 miles southeast. A limit of 7.5 mrems per quarter to any organ was used in these calculations. The maxi-mum organ dose to a "Member of the Public" was 1.2E-02 mrem for the third quarter and 7.9E-03 mrem for the fourth quarter..

To verify compliance with Technical Specification limits, calculations were performed for each month's releases using the GASPAR computer program and parameters as outlined in the 00CM. Ooses were determined at two special locations.

1. The Site Boundary at 1.2 miles from the plant and for the sector with the maximum X/g value.

2. Taylor Flats - at 4.2 miles SE.

There were no abnormal releases of gaseous effluent during the third and fourth quarter s of 1985. Sampling and monitoring of the gaseous effluents were performed in accordance wi th Technical Specifications and Plant Procedures.

Total error estimates are based on grab samples, gamma spectrometry, analyzer detectors, and beta scintillation readings. The overriding uncertainty in all cases is the measurement of the effluent and sample volumes. The estimated error was determined to be 36% at the 95" confidence level.

In addition to the reactor site, MNP-2 has a permanent laundry facility located approximately 0.75 miles from the site. Its ventilation system contains HEPA filters on the discharge and is continuously monitored for particulates and radioiodines. A total of 5.4E-01 microcuries were released, from the laundry facility during this reporting period. Gamma spectrometry indicated no isotoPes present o'ther than those attributable to natural background.

Table 3-1.

MNP-2 GASEOUS EFFLUENTS SOURCE TERMS - MIXED MODE RELEASES tQIN PLANT VENT July - December 1985 CONTINUOUS t<ODE I r I I Nuclides Released I Unit I Quarter I- Quarter

1. Fission gases Kry ton-85 Ci 1.3 E-03 i 1.6 E-01 Kr ton-85m Ci 8.8 E-01 3.0 E+00 Kry ton-87 Ci 5.5 E-01 8.1 E-01 Kry ton-88 Ci 9.8 E-01 4.1 E+00 Xenon-133 Ci 6.9 E-01 2.7 E+00 Xenon-135 2.1 E-01 8.5 E-02 Xenon-135m Ci 1,1 E-02 1.1 E-03 Xenon-138 Ci 3,3 E+00 2.7 E+00 Xenon-131m Ci 1.3 E+00 1.9 E-01 Xenon-133m Ci 9.8 E-01 1.2 E+00 Ar on-41 Ci 9.9 E-03 2.1 E-07 Total for eriod Ci 8.9 E+00 1.5 E+01

2. Iodines Iodine-131 Ci 3.1 E-04 2.4 E-04 Iodine-133 Ci 2.2 E-03 2.3 E-03 Iodine-135 C i I 4 2. 4 E-03 I

~ 2. 5 E-03 I

Total for eriod Ci I 4,9 E-03 I 5.0 E-03

Table 3-1 (Continued)

3. Particulates Strontium-89 Ci 1.2 E-06 5.9 E-06 Strontium-90 Ci 3.1 E-07 1.8 E-06 Cesium-134 Ci 6.6 E-04 3.6 E-04 Cesium-137 Ci 5.8 E-04 3.3 E-04 Barium-lanthanum-140 Ci 2.2 E-03 1.2 E-03 Molybdenum-99 Ci 3.2 E-03 1.1 E-02 Cerium-141 Ci 6.2 E-04 3.3 E-04 Cerium-144 Ci 2.7 E-03 1.4 E-03 Cobalt-58 Ci 3.0 E-03 2.5 E-03 Cobalt-60 Ci 9.7 E-04 6.7 E-04 Chromium-51 Ci 5.9 E-03 3.8 E-03 Zinc-65 Ci 6.0 E-03 5.3 E-03 Zirconium-95 Ci 9.5 E-04 5.4 E-04 Iron-59 Ci 1.1 E-03 6.4 E-04 Manganese-54 Ci 1.8 E-02 3.8 E-04 Total for eriod Ci 4.6 E-02 2.8 E-02 I I I

) 4. Tr.i tium Ci ) 2.9 E-Ol ( 1.4 E+00 )

I I Total building release I Ci I 9.2 E+00 I 1.6 E+01

Table 3-2

,WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING July - December 1985 CONTINUOUS NODE I r th I I Nuclides Released Unit I Quarter I Quarter

1. Fission gases Kryoton-85 Ci I 3.4 E~OO 3.1 E+00 Krypton-85m. Ci 6.7 E-01 1.3 E-01 Kry ton-87 Ci ?.3 E+00 2.3 E+00 Kr ton-88 Ci 2.5 E+00 2.3 E+00 Xenon-133 Ci 3.1 E+00 2.3 E+00 Xenon-135 Ci 6.2 E+00 1.4 E+00 Xenon-130 Ci 6.8 E+00 2.0 E+01 Xenon-133m Ci 6.5 E+00 5.6 E+00 Xenon-135m Ci 2.7 E+00 2.2 E+00 Total for eriod Ci 3.4 E+01 3.9 E+01

2. Iodines Iodine-131 1.9 E-04 1.3 E-04 iodine-133 F 1 E-03 8.9 E-04 Iodine-135 Ci I~ 9.2 E-03 [ - 9.1 E-03 Total for period Ci ! 1.0 E-02 I 1.0 E-02

Table 3-2 (Continued)

3. Particulates Strontium-89 Ci 1.6 E-05 4,1 E-06 Strontium-90 Ci 1.7 E-06 3.7 E-05 Cesium-134 Ci 1.1 E-03 4.2 E-04 Cesium-137 Ci '.2 E-03 4.4 E-04 Barium-lanthanum-140 Ci 3.6 E-03 1.8 E-03 Cerium-141 Ci 1.3 E-03 4.9 E-04 Cerium-144 Ci 5.1 E-03 2.1 E-03 Cobalt-58 Ci 1.1 E-03 4.7 E-04 Molybdenum-99 Ci 4.7 E-03 4.6 E-03 Cobalt-60 Ci 1.4 E-03 5.4 E-04 Chromium-51 Ci 9.1 E-03 3.7 E-03 Zinc-65 Ci 2.7 E-03 1.1 E-03 Zirconium-95 Ci 1.9 E-03 7.6 E-04 iron-59 Ci ?.4 E-03 1.2 E-03 Man anese-54 Ci 1.3 E-'03 4.4 E-04 Total for period Ci 3. 7 E-02 1. 8 E-02 I

l4. Tritium I Ci I 1.5 E+00 I 3.3 E+00 I I Total building release I Ci I 3.6 E+01 I 4.2 E+01 I Table 3-3 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADWASTE BUILDING July - December 1985 CONTINUOUS MODE I 3l d 4th I I Nuclides Released I Unit Quarter Quarter I

1. Fission gases Yr oton-85 Ci 2.2 E-01 1.7 E-01 I I

Krypton-85m Ci 2.2 E-01 5.2 E-02 Kr ton-87 Ci 4.8 E-01 i 1 E-01 Kr ton-88 Ci 6.5 E-01 6.2 E-01 Xenon-133 Ci 1.6 E+00 1.1 E+00 Xenon-135 Ci 3.1 E+00 9.7 E-Ol Xenon-135m Ci 1.7 E+00 2.0 E+00 Xenon-138 Ci 3.4 E+00 4.5 E+00 Xenon-133m Ci 1.7 E+00 1.6 E+00 Xenon-137 Ci 1.5 E+01 1.7 E+GO Total for eriod Ci 2.8 E+01 1.3 E+01

2. Iodines iodine-131 4.1 E-05 2.1 E-05 Iodine-133 Ci 1.6 E-04 1.2 E-04 Iodine-135 Ci I- 3.1 E-03 3.1 E-03 Total for eriod Ci I 3.3 E-03 3.2 E-03

Table 3-3 (Continued)

3. Particulates Strontium-89 Ci 1.0 E-06 9.8 E-07 Strontium-90 Ci 2.4 E-06 2.6 E-06 Cesium-134 Ci 1.4 E-04 5.9 E-05 Cesium-137 Ci 1.2 E-04 5.3 E-05 Barium-Lanthanum-140 Ci 3.9 E-04 1.9 E-04 Hol bdenum-99 Ci 3.5 E-04 5.6 E-04 Cerium-141 Ci 1.4 E-04 6.2 E-05 Cerium-144 Ci 5.5 E-04 2.5 E-04 Cobalt-58 Ci 1.2 E-04 '.6 E-05 Cobalt-60 Ci 3.'4 E-04 1.5 E-04 Chronium-51 Ci 8.9 E-04 4.3 E-04 Zinc-65 Ci 2.8 E-04 '.3 E-04 Zirconium-95 Ci 1. 9 E-04 9. 0 E-05 Iron-59 Ci 3.1 E-04 2.4 E-04 Han anese-54 Ci 1.9 E-04 5.8 E-05 Total or eriod Ci 4.0 E-03 2.3 E-03 I I l4. Tritium Ci I 6.0 E-02 I 1.8 E-01 I Total building release I Ci I 2.8 E+01 I 1.3 E+01 0

Table 3-4 IIHP-2 GASEOUS EFFLUENTS SVhlh1ATION OF ALL RELEASES July - December 1985 I

3rd 4th lEst. Total I Unit Quarter Quarter t Error ~* I A. Fission 8 activation gases

1. Total release Ci 7.1 E+01 I 6.7 E+01 3.6 E+01[

verage re ease rate for eriod uCi/sec 8.9 E+00 8.4 E+00

3. Percent of Tech.

S ec. limit 3.2 E-01 4.2 E+00 B. Iodines ota io one (131, 133) Ci 1.8 E-02 1.8 E-02 3.6 E+Ol(

2. Average re1ease rate for eriod uCi/sec 2.3 E-03 2.3 E-03 Percent o ec .

S ec. limit 1.6 E-01 1.1 E-01 C. Particulates Particu ates w~t half-lives 8 daysl Ci 8.7 E-02 4.8 E-02 3.6 E+01I

2. Average release rate for eriod uCi/sec 1.1 E-02 6.0 E-03

3. Percent of Tech.

Spec. limit 1.6 E-Ol 1.1 E-01 ross a p a radioactivit Ci 6.1 E-04 9.5 E-04 D. Tritium I

1. Total releases Ci 1.9 E+00 4.9 E+00 3.6 E+01I Average re ease rate for period uCi/sec 2.4 E-Ol 6.2 E-01

3. Percent of Tech.

Spec. limit 1.6 E-01 1.1 E-01

At 95~ confidence level

Table 3-5 MHP-2 GASEOUS EFFLUEHTS 8ATCH RELEASES July - Oecember 1985 Total tlaxlmum Nl nl PlUm Mean Type Number Time (hrs) Time (hrs) Time (hrs) Time (hrs)

Purge 17 8.5 Vent 123 217.5 5.5 0.3 1.8

4.0 SOLID WASTE A total volume of 6432 ft3 (182 m ) of solid waste was transported in 21 shipments during the July 1 through December 31, 1985 reporting period.

The total activity of the solid waste shipped was 100.4 Ci; 99.95 Ci

. contained in dewatered spent resins, 0.3529 Ci in Dry Active Waste (DAW) and 0.1380 Ci in absorbed oil.

A. Dewatered S ent Resin Dewatered resins accounted for 3184 ft3 (90.2 m ) of the 'radio-active wastes shipped during the reporting period. The burial containers were CNS 14-195 steel liners provided by Chem-Nuclear Systems, Inc. The total activity of the resins shipped during the reporting period was 99.95 Ci. The principle nuclides and their percent contribution to the total activity are listed in Table 4-2.

The solid wastes were shipped to the U.S. Ecology, Hanford burial site using flat bed trailers, CNS 14-195H, CNS 14-215H or NUPAC 14-210H casks as appropriate.

The counting error associated with the total activity of the ten principle nucl ides (about 99.4% of the total activi ty shipped) is 0.63% at one standard deviation. Since the remaining nuclides represent such a small portion of the total activity shipped, their erro~ contribution was neglected.

Other parameters considered in estimating the total error of the activity shipped included the error in measuring the absolute volume, the wei ght of the waste in the liners, the representative-ness of the sample taken, the homogeneity of the nuclide distribu-tion within a batch or liner and the geometry error in the garana spectroscopy analysis. The gamma spectroscopy calibration error was approximately 5%. The best estimate of the total error in the activity of spent resin shipped was assumed to be less than or equal to 20%.

B. Dry Active Waste (DAW)

A total of 2520 ft3 (71.4 m ) of DAW was shipped in 28 container Products Corporation, 8-25 steel boxes. The total activity of the DAW shipped was 0.3529 Ci. The values for the activities shipped were determined by using dose rate-to-curie conversion factors. The conversion factors were based on a nuclide distribution taken from reactor coolant sample analyses which are representative for the time period in which the waste was generated. Short lived nucl ides were eliminated based on decay of the DAW prior to shipment. A meaningful counting error cannot be generated for the DAM, however, the toul error may be assumed to be less than or equal to 20% since DAW woul d be subjected to similar error contributions as the spent resins.

Absorbed Li uids A total of 727.9 ft3 (20.6 m ) of absorbed oil (or oily material )

was shipped during the reporting period. About 6 gallons of oil was absorbed with diatmaceous earth in each of 99, 55 gallon Type 7A drums in order to meet burial ground requirements. The drums were of either a 17C, 17H or 17E/H designation but were shipped only as strong tight containers (STCs) per DOT requirements.

The values for the activities shipped were determined by using dose rate-to-curie conversion factors for the reported nucli des as described in paragraph B for DAW. As with the DAW, the total error is assumed to be less than or equal to 20 due to the likelihood of simular contributing errors to those associated with the resins.

Scalin Factor Methodolo H-3 In accordance with the procedure outlined in the AIF report "Method-ologies for Classification of Low Level Radioactive Waste from Nuclear Power Plants", the amount of H-3 insolid radwaste shipments was determined by estimating or measuring the amount of water pre-sent and multiplying by the average H-3 concentration in the coolant for the time period associated with the waste generation. Dewatered resin samples were wei ghed and dryed in an oven. It was found that the dewatered resin contained about 50 water by ~eight.

C-14 The generic scaling factor (C-14 to Co-60, 6.0 E-4) from the AIF report was used unless the results was less than 1.0E-6 uCi/g (typical MDA), in which case the MDA was used.

I-129 The I-129 concentration was determined by scaling to Cs-137. The Cs-137 MDA was used since Cs-137 was not detected, and the resulting value, if less than a typical I-129 MDA of 5.0E-7 uCi/g was reported The scaling factor taken from the AIF as less than the MDA value.

report is 7.0E-5.

Tc-99 The Tc-99 concentration was determined by scaling to Cs-137. The Cs-137 MDA was used since Cs-137 was not detected, and the resulting value, if less than a typical Tc-99 MDA of 6.0E-S uCi/g was reported The scaling factor taken from the final as less than the MDA value.

AIF report is 9.0E-5.

TRU, Sr-90, Ni-63 TRU nuclides were scaled to Ce-144. As recommended in the AIF

. report, these nuclides are noi considered to be present

'nCi/g for if -the scaled or 200 values are less than: 1 nCi/g for TRU, 35 Pu-241 nCi/g for Cm-242. During the reporting period the Ce-144 MDA was used to estimate the concentrations. Based on the scaling factors the calculated concentrations of TRUs, Pu-241 and Cm-242 were below the threshold values to report and were assumed not to be present.

Sr-90 is scaled to Cs-137 and Ni-63 is scaled to Co-60. The following table contains the scaling factors as reporting limits.

TABLE 4-1 Scalin Factors for TRU, Sr-90 and Ni-63 Scaling Nuclide Scalin Factor Re ortin Limit Pu-238 Ce-144 7.5 E-3 1.33 E-1 uCi/g Pu-239 Ce-144 5.0 E-3 2.00 E-1 uCi/g Pu-241 Ce-144 5.5 E-1 6.36 E-2 uCi/g Am-241 Ce-144 3.5 E-3 2.86 E-1 uCi/g C01-242 Ce-144 1.5 E-2 1.33 E+1 uCi/g Cm-244 Ce-144 3.0 E-3 3.33 E-1 uCi/g Ni -63 Co-60 2.0 E-2 Co-60 HDA uCi/g Sr-90 Cs-137 1.0 E-2 4.0 E-2 uCi/g S. 2 process Cootro~lpro rem No substantial changes were initiated in Chem Nuclear's process Control Program during the last semi-annual reporting period.

m Table 4-2 MHP-2 SOLID WASTE SHIPblEHTS July - December 1985 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Waste I

Waste Stream Unit 6-month lEst. Total I Period'rror

a. Spent resins, filter sludges, m3 90. 2 eva orator bottoms, etc. Ci 99. 95 20

b. Dry active waste, contaminated m3 71.4 e ui ., etc. Ci 0.3529 20

c. I r radiated components, control m3 Ho Ship-

'ods, etc. Ci ment

d. Other, absorbed liquids (oil) m3 20.6 20 Ci 0.1380

2. Estimate of major nuclide composition (by type of waste):

a. Cewatered Spent Resins Nuclide Ci Zn-6 5.92 4 .90 Co-Co- 4.28 14.2 5 Nn-54 3.66 3.66 6 Zr-95 0.98 0.9 7 Fe-59 0.93 0.93 tJB-9 .8 9

0. 8 0. 8 10 Sb- 24 .0 0. 03

b. Dry Active Wastes (DAM) uc>e n-0-

. 9 0. 53 4 Cr-5 5 Co-60 7.12 0.0251

0. .46E-04

c. Irradiated Components - None

d. Other -'bsorbed Liquids (oil)

Nuclide Ci

.0 7 2 Co-58 8. 5 9 5 Co- 0 6.38 0.0088 Nb>> .0071 7 Mn-54 3.46 0.0048

3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 21 Flat bed trailer (4) US Ecology 14-195H Cask (13) Richland, MA 14-215H Cask (1) 14-210H Cask (3)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

None

5.0 NETEORCLOGY The meteorological data contained in Tables 5-1 through 5-4 were obtained from the WNP-2 meteorological tower located 2500 ft. west of MHP-2. Data was recovered from 33 ft. and 245.ft. =levels. The meteorological data is a composite file from both manual and automated data recovery systems.

The second half of 1985 started cooler and became cold and much'drier than normal with a greater percentage of neutral and stable conditions affecting dispersion in the vicinity of WNP-2. The automated data recovery system continued to function at greater than 90% joint data recovery for the joint frequency parameters.

Tables 5-1 through 5-4 list the joint frequency distribution at the 33 ft.

and 245 ft. levels for the third 'and fourth quarters. Additionally, this report includes Tables 5-5 through 5-6 which list the joint frequency distribution for all of 1985. The tabulated stability classes, A-G, are denoted by numerals 1-7'espectively. Numerals 1-7 were used for the wind subfields as is noted at the top of each sensor level reported. The 16 compass sectors in Tables 5-1 through 5-4 pertain to the direction the wind is coming from.

Calibrations performed in August-September 1985 produced no values exceeding WNP-2 FSAR meteorological equipment tolerances. Therefore, no correction has beep made to the raw data. The NRC Delta Temperature Stability Classification scheme was utilized in the production of all joint frequency tabTes.

As mentioned in the previous report, some of the meteorological equipment

'as aged and must be replaced. An updated Climet Instruments, Inc.

Delta-T system was replaced at the August-September calibration of the N'P-2 keteorological Tower.

TABLE 5-1 THIRD QUARTER 1985 JOIHT FREQUEttCY DISTRIBUTIOH FOR THE 33 FT LEVEL CALCULATED FROtt HOURLY AVERAGES FROtl TAPE ttAXIttUtl MIHD SPEEDS FOR EACH CATEGORY IHiHPH ARE:

I - 0.6 2 - 3.0 3 - 7.0 4 - 12.D 5 - 18.0 - 24.0 HUttSERS GIVEH ARE HOURS STAB MIHD NHE HE EHE ESE SE SSE SSM SM MSM HM CLASS CAT I I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0, 0. 0.

I 2 1. 0. 0. 0. 0. 0. 0. 0. 20 1. 0. 2~ 0.

3 10. 70 2~ 0. 0. 0. $~ 9. 13. 11. 3. 5i 3. 0. 3.

I I, 3. i. f. 0. 0. 0. 9. 7. 3. 24 3. 1. 1. 3, 5 50 I. 0, 0. D. 0. 0. D. i. 3. 0. 7. 1. 0. 0.

I 6 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. I.

7 0. 0. 0. 0. 0. 0. 0. 0. 0 0. 0. 0, 0. 0. 0. 0.

2 I 0. 0. 0. Do 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 2 I. 0. 0. 0~ 0. 0. 0. 0. 0, 1. 1. 0. 0~ 0. 0. 0.

2 3 1. I. 0. 0. 0. 2~ 5. 8. 2~ 2~ 1. 0. 0. 1.

2 1. 0. i. 0. 0. 1. 0. 0. 2~ 0. 1. 0. 0. 2~

2 5 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. l. 0. 0.

2 6 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.

2 7 0. 0, 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.

3 2 1. 0. 0. 0. 1. 0. 0. 1. l. 0. 3. 1. 0. 0. 0. 0.

3 3 5~ 21 0. 0. '1. 2~ 9. 5~ 1. 2~ 1. 0. 0. 20 3 0. 0. l. 0. 2~ 2~ 3. 0. 2. 2~ 1. 2. 1. 3~ 3~

3 5 0. 0. 0. 0. 0. 0. 0. 0. 20 0. 1. I, 1. 0.

6 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0~ 0.

7 0. 0. 0. 0, 0. 0. '0, 0. 0. 0. 0. 0. 0. 0. 0. 0, I 0. -0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 8. 2I 6. 0. 0. I. 5~ 6. I. 6. 20 5. 8.

3 36. 25. 4. 1. 1. 6. 26. 36. 24. 9. 13. 9. 16. 12. 25.

5 5

5 6

7 I

2 19.

0.

12.

8.

0.

6.

3.

0.

6~

0.

1.

~

0.

1.

0.

2~

0.

0, 13.

0.

15.

11.

2~

0.

0~

11 12.

1.

0.

fk, 8.

0.

10

1. 5.

0.

0, 0.

6.

3.

0.

8.

fl, 1.

0.

1$ ,

5.

2~

0~

0.

12.

20 0.

0.

16.

5 3 23. 13. 16. 6. 8. 12. 33. 59. k3.

~

29 17. 15. 10. 23. 28. '8.

5 C'

2~ 3~ 0. 0. 0. 0, i. 10. 19. 'k.

7. 3~ 6. lb. 13. 7.

5 0. 0. 0, 0. 0~ 0. 0. 0. 0. 6~ 2~ 2I 12. 9. 0.

5 ~

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 1. l. 0. 0.

5 ? 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.

6 I 1. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. l. 0. 0.

6 2 5. $~ 6; 1. 3. 6. 10. 6. 3. 5~ 10. 3. 9. 8.

6 3 7. 12, 8. 1. 0. 13. 32. 30. 13. 7. 7. 11. 18. 18.

6 0. 0. I. 0. 0. 0. 0. 7~ 8. 0. f. 19. I1 ~

6 5 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 2. 0. 0'.

6 6 0. 0, 0. 0. 0. 0. 0, 0. 0, 0. 0. 0, 0. 0. 0. 0.

6 7 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 I 1. 0, 0. 1. 0. 0. 0. 0. 1. 0. 0. 3. 0. 1.

25. 32. 17. '7, 0. 5. 12. 18. 12. 7. 10. 8. 15. 12. 3I.

7 7

2 3 12. 1'2. 2~ 0. 10. 51. 32. 12. 2~ 8. 3, 16. Ik.

7 5

0.

0, '.

0. 0.

0.

l.

0.

2~

0.

1.

0.

1.

0.

6 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0.

TOTAL NUttSER OF HOURS USED = 2111 ttlSSIHG = CALtt = VARIABLE =

TABLE 5-2 THIRD QUARTER 1985 JOIHT FREQUEHCY DISTRIBUTIOH FOR THE 245 FT LEVEL CALCULATED FROH HOURLY AVERAGES FROII TAPE HAXIBUH MIHD SPEEDS FOR EACH CATEGORY IH HPH ARE:

0.6 2 - 3.0 3 - 7.0 4 - 12.0 5 - 18.0 6 - 24.0 HURBERS GIVEH ARE HOURS STAB MIHD H HHE HE EHE ESE SE SSE SSM SM MSM CLAS S 'AT

0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.

I 2 1. 0. 0. 0, 0. 0. 0. 0. 0. i. 1. I. 4, 2~ J~ 0.

3 13. 1. 0. 0. 0. 20 10. 11 6. 3. 0. 1. 2~ 5.

I 2~ 1. 0. 0. 0. 20 7. '0.

7. 3. 3. 2~

5 1. 0, 0. 0. 0. 0, 0. 2~ 3~ 2~ 9~ 1. 1. 0. 3.

5~

6 i. 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0. 0. 0. 0.

7 0~ 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 1 0. 0. D. 0. 0. 0. 0. 0 0. D. 0. D. 0. 0. 0. 0.

2 0. 0. 0. 0. 0. ~

0. 1. 0. 0. 1. I, 0, D. 0. 0.

2 3 0, D. 0. 0. I. 2 ~ 6. 3. 2~ 1. 1. 0. 1. 0. 3.

2 0. 2~ 0. 0~ 0. 0. 0. 1. 5. 3. 0~ 1. 0. 0. 1.

2 5 1. 0. 0. 0. 0. 0. I. 0. 0. 0. 0. 0. 0. l. '0. 1.

2 6 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0.

2 7 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0.

3 2 0. 0. 0. 0. l. 0. 1. 0. 1. 0. 0, 0. 0. 0.

3 3 2. 3. 2~ 0. 0. 0. 3. 8. 2~ 2~ 1. l. 0, D. i. 20 3 1. 0. 0. 2~ 3. 2~ 3. 2. 2~ I. I. 0. 0. 4~

3 5 0. 0. 0. 0. 0. 0~ 0. 0. 0. 2. 1. 2. 1. 2I I, 6 0. 0. 0. 0. 0. 0. 0. 0, 1. ~

D. 0, 0. 0. 1. 0~ 0.

7 0. 0. 0. 0. 0. 0, 0. 0, 0. 0. 0. 0. 0. 0. 0. 0.

I 0. 0. 0. 0. 0. D. 0. 0. D. 0. 0. 0, 0, 0. 0. D.

2 15. 0. 0. 0. 1. 0. I. 1. 1. 2. 2~ 3.

4 3 47. 34. 5~ 0. l. 2~ 15. 14, 24. 5, 7. 7 ~ 9. 21, 4 15. 22. 9. 0. 0. 2. 3. 5. 15 11. 8. 4. 3~ 8. 2~ 6.

5 3. 4. i. 0. 0. 0. 0. 3.

3~ 6. 1. 19. 8.

6 0. 'De" 0. 0. 0. 0. 0. 0. 2~ I ~ 0. 2~ 0. 2~ 0. 0.

7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.'. 0. 2~ 0. 0.

5 I 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0.

5 2 19. 1. l. l. 0. 4~ 8. 8. 14. 12. 7. 9. 7~ 7.

.5. 3 34. 27. 9. 3~ 5~ 14. 16. 27. 30. 31. 9. 8~ 9. 15. 15. 22.

5 9. 17. 16. 11. 20 3. 9, 16, 31, 15. 11, ,6., 8. 9. 7. 14.

5 5 1. 0. 20 1. 0. 0. D. 19. 5~ 3~

5 6 0. 0. 0. 0. 0. 0. 0. 0. Da 0. 3~ 0. 17. 0. 0.

5 7 D. D. D. 0. D. 0~ 0, 0. 0. 0. 1. 0. I. 1. D. 0, 6 0. 0. 0. 0. 0. 0. 0. D. 0. 0. D. 00 0. 0. 0. 0.

6 2 4 ~ 5. 2. 2e 0. I, 6. 6. 50 3. 2. 5. 4. 3~

6 3 16, 12. 5~ 3. 2~ 3. 11. 17. 10. 3. 3~ 11. 10, 8.

6 20 3. 6. i. I. 5. 9. 11. 10. 5. 6. 19 12. 6.

6 5 0. 0. 0. 4. 0. 0. 0. 0. 1. 7g 1. 0. 8. '6.

2~ 0.

6 6 D. 0. 0. 0. 0, 0. 0. 0, 0. D. a. 0. 2~ 0. D.

6 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 2 18. 9. 11. 8. 2~ 1. 24 6. 8, 13. '7.'2. 10. 8. 12. 8. 13.

7 3 28, 29. 9. 3~ 5~ 12. 19. 24.' 15. 8. 20. 27.

1. 2. 4. 3~ 0. l. 4, '15. 21 ~ 1. 1. l. 11. 16. 2.

5 D. 0. 0. 0. 0. 0. 0. 2i D. 1. 0. 0. 0. 2~ 1. D.

6 0. 0. 0. D. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 D~ 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0~ 0. 0. 0. 0.

OTAL HUGGER OF HOURS USED = 2150 RISSIHG = % l.h VARIABLE = 19

TABLE 5-3 FOURTH QUARTER 1985 JOIHT FREQUEHCY DISTRIBUTIOH FOR THE 33 FT LEVEL.

CAI.CULATED FROlI HOURLY AVFPAGES FROII TAPE iIAniHUll MIHD SPEEDS FOR EACH CATEGORY IH llPH ARE' 0.6 3~0 3 7 0 4 1210 5 - 18 ~ 0 6 - 24,0 HUllBERS GIVEH ARE HOURS STA MIHD H HHE HE EHE ESE SE SSE SSM SM MSM MNM HM HHM CLASS CAT 1 0. 0. Q. D. 0. 0, 0. 0. 0. 0. 0. 0, 0. 0. 0. 0.

1 2 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. Q. 0. 0. 0. 0. 0.

3 0. 0. Q. 0. 0. 0. 0. 0. 0, 0. 0, 0. 0. 0. De 0.

1 0. 0. 0. 0, 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

1 5 0. D, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0.

6' 0. 0. 0. 0. 0. 0. 0. 0. 0. ~

Q, 0. 0. 0. 0. Q. 0.

1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0. 0. 0. 0.

2 1 0. 0. Q. 0. 0. Q. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 2 0. 0. 0. 0. 0. Q. 0. 0. 0, D. 0. 0. 0, 0. 0. 0.

2 3 0. 0. 0. Q. 0, 0. 0. 0. 0. 0. 0, 0. 0. 0, 0. 0.

2 0. 0. i. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 5 Q. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0, Q. 0. 0. 0. .0.

2 6 0. 0. 0. 0 ~ 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0.

2 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0.

3 0. 0. 0. 0~ 0, 0. 0. 0. 0. 0. 0. Q. 0~ 0. 0. 0.

3 2 0. 0.'. Q. 0. 0. 0. 1. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 3 0. 0. D. 0. 0. 0. 2~ 0. 0: 0~ 0~ 0. 0. 0.

3 0. 2~ 2~ 0, 0. 0. 0. 2~ 9. 0. 0. 0. 0. 0. 0. Q.

C'

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.

7 0. 0. 0. 0. 0. 0. 0. D. 0, 0~ 0. 0; D. 0. 0. 0.

5. 4. 2. 0. 0." 2. 3~ 0. l. l. 3~ 2~ 1.

2 22. 7. 7~ 8. 22. 2I. 17. 21, 22. 15. 27. 26. 25. 26. 15.

3 13. i. 0. 2~ 6. 13. 18. 13. 7, 5~ 20 8. &~ 18.

Do 5. 0. 0. I, 2~ 8. 18. 2~ 2~ /j, 20. 8.

lj 5' i. l. 0. 0. Q. 0. 1. 9. 3, 0. 0~ 3~ 0. 5.

0. 0. 0. 0. 0. 0. 0. 0. 1. 2~ 0, 0, 0. 0. 0. 24 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

5 1 0. 0. 2. 0. 0. 3~ 1. 2~ 1. D. 1. 0. 0. 1. 2.

2 12. 10. 5. l. l. 12. 12. 12.. 11. 22. 21. 36. l4. 31. 17. 9.

5 3 10. 5~ 5l 0. 2~ 13. 22. 28. 17. 7. 10 25. 23. k4, 23. 26.

5 1. 0. 0. i. 0. 0. 8. 18, 29, 8.

9. 24. 28. Il.

5 5 1. i. 0. 0. 0. 0. 0. 1. 29. 15, 1. 0. 6, 3. 3, 5 6 D. 0. 0. Q. 0. 0. 0. 0. 0. 24 0. Q. 0. 0. 0. 0.

5 7 0. Qs D. 0. 0. 0. 0. 0. 0. 0. 0. D. D. 0. 0. 0.

6 1 0. 0. 0. 0. 0. 0. 0. 0. 0. 1. 0. 2. 2~ 0.

6 1 13. 6~ 2. 3. l. 2~ 9. 11. 10. ik. 22. 20. 15. 9.

6 3 11, 6. 1. 0. 0. 23. 33. 7 ~ 5. 7. 13. 21. <0. 16.

6 0. 0. 0. 0. 0. 0. 8, 9. 1. 0. 2~ 1. 1. 6, 0.

6 5 0. 0. 0. 0, 0. 0. 3. 0. 0. 0. 0 ~ 0, 0. 0. 0.

6 6 0. 0~ 0. 0. D. 0. 0. 0. 0. 0. 0. 0. 0. 0. D.

6 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 1 0. 0. 0. 0. 0. 0; 0. 0. 0. 0, 0. 0, D. D. 0.

7 2 11 10. 2. 1. 1. 4. 7~ 10; 8. 6. Ih. I lj ~ 25. 24. 16 7 3 8. 5. 0. 0. 0. 2~ 9. 13. 1. 3 ~ 2. 5, 13. 8. '2.

Q. 0. 0. 0. Q. D. 0. 2'. 1. 0. 0. 0. 0. Q. 0. Q.

5 0. 0. 0. 0. 0. D. 0. 0. 0. 0. 0. 0. 0, 0. 0.

6 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0, TOTAL HUIIBER OF HOURS USED = 1989 lIISSIHG = CALH = VARIABLE = 28 Cl 0

TABLE 5-4 FOURTH QUARTER 1985 JOIHT FREQUEHCY DISTRIBUTIOH FOR THE 245 FT LEVEL CALCULATED FROh HOURLY AVERAGES FROh TAPE HAXIHUH MIHD SPEEDS FOR EACH CATEGORY IH HPH ARE:

0.6 2 " 3,0 3 - 7.0 4 - 12,0 5 - 18.0 6- 24.0 NUHBERS GIVEH ARE HOURS STAB MIHO H HHE HE EXE ESE SE SSE SSM SM MSM CLASS CAT

0. 0. 0. 0>> 0. 0. 0. 0. 0. 0. 0, 0. 0, 0. 0. 0.

1 Q. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0, 0. 0.

1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, Q, a. 0. 0. 0.

1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0.

1 a. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0. 0. 0. 0. 0.

1 2

2 0.

0.

D.

0.

0, 0.

0.

'. 0.

0.

0, 0.

0.

D.

0.

2 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0.

2 0. 0. 1. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0.

2 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0.

2 0. 0. a. 0. 0. 0. 0. 0. 0. a. 0. 0. D. 0, Q. 0.

2 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. Q. 0. 0. 0. 0. a.

3 3

0.

0. 0.

I 0.

0.

0, 0.

0.

5.

2~

6.

0.

a.

0.

0. '.0.

0. 0. 0. 0. 0. 0. 0. 0. 0. 1. 0, 0. 0. 0. a, D.

0. 0. 0. 0. 0. 0. 0. '0. 0. 0~ 0. 0. 0. 0. 0. 0,

0. 0. 0. 0. 0. 0. 0. 0. 0. O. 0. 0. 0, 0. 0. 0.

1. 1, 0. 0. I 0 ~ 1. 2~ 0. ~ l. 3. l. 2~ 0.

26. 10. 5>> 7~ 2~ 5>> 5>> 9. 16. 18. 26. 12. 19. 17. 18. 26.

28. 18. 3. 2. 0. 1. 3. 20. 17. 9. 9. 3. 0. 8. 11.

3~ 11. 15. 8~ 0. 0. 1. 5~ 12. 2. 3. '.

11. 13.

3~ 0. 0. 2. 8. 6. 0. 0. 0. 2. 3 ~ 1. a. 2~

0. 0. 0. 0. 0. Q. ,9. 3~ 2>> 4 ~ 0. 0. 0. D. 0,

0. 0. 0. 0. 0. 0. 0. 0. 2~ 1. 0. 0. 0. 0. 0. 0.

5 5>> 1. 0. 0. 2>> 0, 2>> 0. 0. 2~ 2~ D.

5 42. 8, 5~ 3. S. 8. 3~ 7~ 9. 12. 14. 17. 19. . 10.

5 47. 44, 12. 5>> 0. 1. 10. 25. 19. 9. l. 5. 8. 18. 31.

5 7. 6, 21.'. 16. 2~ a. 0, 6. 8. 9, 5. 1. l. 12, 25. 31.

5 1. 0. 8. 25. 11. 1. 2>> 6. 15. 10. 1. 10, 8, 3.

5 a. 0. 0. 0. 0. 1. ia. 17. a. 11. 0. 0. 0. 6. 0.

L'

0. 0. 0. 0. 0, 0. 0. 0. 3. a. a. 0. D. a. a.

6 a. 0. 0. 0. 1. O. 1. 2~ 0. 0. 0~ 1. a. 0. 0. l.

6 23. 6. 2. 2>> 0. 7~ 5. 6. 0>> 9. 0. />> h. h.

6 48. la. 5. 0, 0~ 10. 12. 9. 3. 5, 2. 12, 13.

6 20 7. 17. 11. 0. a. 1. 9. 17. 8~ 1. Q. 0. 9. ia.

6 0. 0. 7. 4. 0. a. 0. 3. 3. 2~ 0. 0. 4, 2~ 0.

6 0. 0. a. 0. 0. 0. a. a. D. 1. 0. 0; 0. 0. 0. a.

6 0. 0. 0. 0. a. a. 0. 0. a. 0~ 0. 0. 0. 0. 0. 0.

7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. )0 ~ 0. 0. 0, 7 27. 5. 5, 3, 2>> 2~ 7. 7~ 3. 5~ 3. 2>> 0. l. 2~

7, 26. 18. 13. 3. 3. 0. 2. 12. 15. 11 ~ 2. 3 ~ 0. 2>> 10. 25.

7 9. 2~ 3. 0.'. 0. 0. 10. 8. 1. 0. 0, 0., 0. 6, 3.

0. 0. 0~ 1. 0. 0. 0. D. 1. 0. 0. 0~ 0. D. 0, O. 0. 0. 0. a. a. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0,

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. a. 0~ 0. 0. 0. 0.

TOTAL HUhBER OF HOURS USED = 1939 hISSIHG = CALh = 68 VARIABLE =

-2<-

TABLE 5-5 198S YEARLY JOIHT FREQUEHCY DISTRIBUTIOH FOR THE 33 FT LEVEL CALCULATED FROh HOURLY AVERAGES FROh TAPE HAXIRUh MIHD SPEEDS FOR EACH CATEGORY IH HPH ARE:

D.6 2 - 3.0 3 - 7.0 4 - 12.0 '5 - 18.0 - 24 '

HUhBERS GIVEH ARE HOURS STAB MIHD H HHE HE EHE SE SSE SSM 'M MSM M MHM HM HHM CLASS CAT 1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0, 0. D. 0.

1. 0. 0. 0. 0. 0. 0. 0. l. 2I 2I 2~ 3. 1.'. 5~

1 10. 7~ 2~ 0. 0. 0. 9. 13. 11. 4. 5. 3. 3.

1. 3. 1. 1. 0. 0. 0. 9. .7. 5. 3~ 2~ 3. l. 3~

1 5~ 0. 0. 0. 0. 0. 0. 1. 1, 7~ 1. 0. D.

0. 0. 0. 0. 0.' 0. 0. 0. 0. 0. 0. D. 0. 0. 0. l.

1 0. 0. 0 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0.

2 0. 0. 0. 0. 0. l. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

2 1. 0, 0. 0. 0. 0. 0. 0. 3. 3. 0. 0. 0. 0. 1.

2 2~ 1. i. 0. 0. 0. 2. 6. 8. 2~ 2~ 1. 0. 0. l. 5.

2 1. 0. 21 0. 0. i. 0. 3~ 3. 6, D. 1. 0. 0. 2~

2 0. 0. 0. 0. 0. 0. 0. 1. 1. 0. 0. 0. l. 0, 0.

2 0. 0. 0. 0. 0. 0. 0. 0. 0. 3. 0. D. 0. 0, 0. D.

2 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. D. 0. 0, 0. 0. 0, 3 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

3 1. 0. 0. 1. 0. 1. 1. 3. l. 3. 2~ 0. 2. 5.

3 8. 3. 0, 0. 1, 2~ 16. 7~ 8. 2~ 2~ 0. 0. 10.

3 6. 2i 2~ 0. 2~ 2~ 5. 11. 7. 5. l. 4 ~ 6.

3 0. 0. 0. 0. 0~ 0. 0~ 0. 1. 3. 4, 1. 3. 20 0.

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0.

0. 0. 0. 0. 0. 0. 0. D. 0. 0, 0. 0~ 0. 0. 0. 0.

5~ 4. 2~ 3~ 0. 2~ i. l. 3. 2I 5. 4 ~ 3.

59. 20. 19. 11. 25. 34. 28. 32. 44 34. 55. 52, 65. 45.

89. 51. 12. 20 3~ 11. 25. 52. 80. '6.

24. 24. 33. 46. 56. 95.

37e lb. 7~ 0, 0. 26. 50. 37. 16. 16. 11. 41. 25. 17.

2~ 0. 0. 0. 0. 1. 21. 8. 9. 6. 2~ 8. 13. 9.

D. 0. D. 0. 0. 0. 0. 0, 1. 2. 1. 2~ 0, 0. 3.

0. 0, 0. D. 0. 0. 0. 0. 0. 0. 2~ 2~ 1, 1. 2. 0.

5 0. 0. 3. 1, 0. '.

3. 1. 3~ 2. 0. 1. 1. 5~ 2. 7.

5 45. 32. 21. 21. 32. 46. 50. 54. 47. 63. 77. 91. 78. 60.

5 72. 60. 40. 10. 16. 38. 83. 159. 138. 100. 71. 94. 80, 120. 146. 122.

5 29 14. 6. 4~ 0. 0. 18. 55. 87. 87. 41. 34. 59. 76. 79. 50.

C

1. 0. 0. 0~ 0~ 1. 48. 38. 18. 12. 19. 39. 46. 3.

5 0. 0. 0. 0. D. 0. 0. 0. 1, 5.. 0. 3~ 4. 3. 0.

5 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0. 0. 4. 0. 0. 0. D.

l. 1. 0. 0. D. 0. 0. 0. 0. 1. l. 0. 3. 3. 1. 0.

6 29. 20, 18. 7. 11. 11. 17. 31. 24. 30. 24. 33. 49. 40. 65. 39 ~

35 ~ 33. 25. 7. 1. 10. 50, 101. 80. 38. 29. 39, 40. 68. 114. 82.

6 D. l. 0. 0. 10, 50. 25. 16 ~ 8. 8. 16. 65. 48. 13.

6 0. 0. 0. 0. 0. 0. 5~ 3~ 9. 6. 1. 1. l. 11. 0.

6 0. 0. 0. D. 0. 0. 0. 0. 0. 0. 0, 0. D. 0.

6 0. 0. 0. 0. 0. 0. 0. 0. 0. l. 0. 0. 0. 0, 0. 0.

7 0. 0. 1. 0. 1. 0. 0. l. 1. 1. 0. 0. 3~ 0. l.

7 71. 64. 33. 16. &. 7. 24. 44 35. 29. 37. 34. 60. 58. 76.

7 43. 43. 42. 14. 1. 9. 43. '42.

98. 38. 20. 25. 18. 39. 53. 57.

7 a

0. 1, Se i. 0. 0. 0. 23. 15. 7~ 2~ 2. 3. 8. ? ~ 0.

0. 0. 0. 0. 0. 0. 0. 1. 0. 2i 0. 0. 0. 0. 0. 0.

0. 0. 0, 0. 0. 0~ 0. 0. 4. 2. 0. 0, 0. 0. 0. 0,

0. D. 0. D. 0, 0. 0. 0. 0. 0. 0. D. 0. 0. 0.

TOTAL HUhBER OF HOURS USED = 8027 hISSIHG = 249 10 VARIABLE =

Cl

TABLE 5-6 198S YEARLY JOIHT FREGUEHCY DISTRIBUTIOH FOR THE 245 FT LEVEL CALCULATED FROH HOURLY AVERA6ES FRON TAPE HAXDIUh MIHD SPEEDS FOR EACH CATEGORY IH ttPH ARE:

D.6 2 - 3.0 3 - 7.0 4 - 12.0 5 - 18.0 " 24.0 HUNBERS GIVEtl ARE HOURS STAB MIHD H HttE HE ESE SE SSE SSQ Stt USU CLASS CAT I I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0.

2 2~ 0. 1. 0. 0. 0, 0. 0. 0. 1. 2. 3. 2~ 3. 0.

3 13. I. 0. 0. 0. 2~ 10. 11. 6. 1. 0. 1. 2. 5.

I 24 1. l. 0. 0. 0. 2~ 7. 10, 8. 3~ 3. I ~ 2I I 5 5. 1. 0. 0. 0. 0. 0. 0. 21 3. 9. 1. l. 0. 3.

6 l. 0. 0. 0. 0. 0. 0. 0. Q. 0. 0. 0. 0. 0. 0. 0.

I I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. D.

2 1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0'.

0.

2 2 1. '.

0. 0. 0. 0~ 0. 2~ 0. i. 2~ 3. 0. 0. 2~

2 3 5. 0. 0. 0. 1. 2~ 6. 6. 2~ 1. 1. 0. I ~ 0. 4.

2 0. 21 1. 0. D. 0. 0. 2~ 6~ 2. 0. 1. 0. 0. 1.

2 5 4. 0. 0. 0. 0. 0. I. 0. 0. 1. 0. 0, 0. I, 0. 2~

2 6 0. 0. 0. 0. 0. 0. 0. 0. 1. l. 0. 0. 0. 0. 0. 0.

2 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 2. 0. 0. 0. 0. 0. 0.

3 0. 0~ 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0.

3 2 2~ 0. 0. 0. 0. i. 0. 1. 24 2~ 0. 2~ 5.

3 3 6. 2l 0. 0. 0. 3~ 13. 3. 10. 5. 1. 1. 2~ 2. 9.

3 2~ 4. I, 0. 2~ 3, 24 10. 10. 2~ 4~ 3. 2~ 0. 6.

5 I, 0. D. 0. 0. 0. 0. 0. 0. 7~ 5~ 2I 1. b. 2~ 3.

6 0, 0, 0. 0. 0. 0. 0. 0. 1. 0. 3. 0. 0. 1. 0. 0.

7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0.

2. 1. 0. 1. I, 2~ 0. 3~ de 2~ 0. 20 3. 2. 2~ 0.

2 60. 16 11, 9. 3. 8. 18. 21. 38. 34. 41. 31. 41. 40. 49. 54, 3 117. '8.

25, 7~ 0. 8. 50. 50. 48. 24. 20. 25. 29. 58. 77.

4 38. 38. 24. 8, Sl 37. 42. 19. 18. B. 16. 25. 38.

5 6. 4e l. 2~ '8. 8. I, 5. 20. 21. 11. 9. 3. 29. 7~

5 6

7 '. 0, 5.

0.

1.

0.

0~

1.

0.

1.

0~

0.

2~

0.

0. 0.

3~

0.

2~

8.

3~

5~

1.

3.

7.

3.

2.

5.

1.

~ 1.

0.

7.

2~

2I l.

20 5.

0, 0.

.5 2 77. 21. 12. 7~ 6. 17. 25. 32. 42. 39. 41. 39. 38. 49, 52. 50.

5 3 127. 95. 33. 17. 13. 26. 50. 98. 121. 101. 48. 40. 46. 69. 128. 111, I 31. 59. 74. 78.

5 42. 43. 41, 33. 6, 7. 23. 50. 102. 78. 58. 31.

5 5 7~ I, 10. 26. 12. 1. 3. 27. 71. 30. 19 29, 71. 40. 26.

5 6 0. 0. 0. 0. 0. I, 10. 17. 1.

'9.

19. 'l.

8. 0.

5 7 0. 0. 0. 0. 0. 0. 0. 0. 9. 5~ Il. 6. 3. 13. 0. 0.

6 0. 0. 0. 0. I. l. 2. 1. 2~ l. 1. 0~ 0, 0.

6 34. 25. 12. 10. ID. 10. 14. 23. 17. 19. 17. 24. 13. 22. 17. 18.

6 3 75. 39, 28. 21. 7~ 6. 16. 38. 61. 34. 16. 25. 32. 42. 56. 48.

6 24. 15. 23. 20. 2~ 1. 19. 45. 57. 33. 13. 8. 24, 68. 54. 29.

6 5 3. 0. 0. 14, 4. 0. 3. 5~ 12, 15. 8. 5. 17. 91. 16. 24 6 6 0. 0. 0. 0. 0. 0. 0. 2. 5~ 7~ 5~ 9. 25. 0.

6 7 0. 0. 0. 0. 0. 0. 0. 0. 3. 3~ 2~ I. 10. 0. 0, 7 I. 0. 0. 0. 0. 0. 0. 0, 2~ 0. 1. 0. 0. 1. 0. 0.

7 2 53. 19. 22. 14, 7. 6; 15. 12. 26. 33. 26. 20. 20. lb. 20. 23.

3 76 66. 35. 13, 13. 12. 25. 65. 81. 65. 39. 32. 13. 23. 54. 79.

7

'2.

15. 13. 10, 2~ 8. 47. 62. 19, 9. 5. 15. 29. 20.

5 0. 2~ 0. 0. 3~ 3~ 5. 3. 6. 23. 13.

6 0. 0. 0. 0. 0. 0. 0. I. 2~ 0. 0. 2~ 7~ 6. 0.

7 - 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 2~ 0. 0.

TOTAL HUtlBER OF HOURS lJSED = 8053 ttISSING = 249 CALtl = VARIABLE = 69

'I 6.0 DOSE ASSESSMENT - If<PACT ON tiAN Liquid Effluents - The doses to the maximum individual from MNP-2 liquid effluents were calculated using the LADTAP II computer code and the site specific input parameters applicable to the reporting period (e.g., food production, agricultural productivity, etc.) The maximum exposed indi-vidual considered in the analysis was assumed to be an adult residing in Richland, who fishes at the MNP-2 slough area and eats food locally grown at the Riverview area district southwest of Pasco, Mashington.

Table 6-1 lists the doses to the maximum individual during the third and the fourth quarters respectively. The liquid source terms used in the analyses are listed in Table 2-2 of this report.

The doses to the average exposed individual are listed in Table 6-2. The 50-mile population doses are listed in Table 6-3. All data was obtained from calculations using the LADTAP II computer code.

Gaseous Effluents - The GASPAR computer code was used to calculate doses a ne . mi e site boundary and Taylor Flats, located at 4.2 miles southeast. The sector wi th the highest X/Q values at the 1.2 mile loca-'ion wag used to verify compliance with Technical Specifications. The quarterly GASPAR runs utilized the quarterly averaged X/Q and D/Q values, and si .e specific input parameters pertaining to food productions (e.g.,

goat and cow grazing periods, etc.) The air doses at the site boundary were used to verify compliance with Technical Speicifcation 3.11.2.2. To verify compliance with Technical Specification 3.11.2.3, the maximum organ dose to the maximum exposed individual located at Taylor Flats was evalua+ed. Table 6-4 lists the doses at these special locations.

6.1 Ex osure to "A Hember of the Public" Two specific locations were evaluated for assessment of radiation doses to "t>embers of the Public", due to their activities within the site boundary. The two locations being the DOE Train and MNP-2 Visitor Center with the latter having the higher potential for exposure. The ODCtl assumes an eight (8) hour per year occupancy by "A Vember of the Public" a+ the Visitor Center. The dose assessment resulted in an annual calculated air dose due to noble gases of 1.5E-02 mrad for gamma and 9.5E-03 mrad for beta. The maximum annual organ dose was 1.1E-02 mrem and the annual thyroid dose was 5.9E-03 mrem.

The direct radiation contribution to a "i')ember of the Public" located at the MNP-2 Visitor Center was calculated to be 3.1E-01 mrem. This result was obtained by using the quarterly mean of TLD stations 90, 91, and 92, which are located at the Protected Area fenceline. The quarterly mean was based on the average mp/day (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), therefore the value is for a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months stay time without credit for shielding.

Table 6-1 MAXIMUt1 INDIVIDUAL DOSES FROtl WNP-2 LIQUID EFFLUENTS(l) 3RD At]0 4TH QUARTERS 1985 Third Quarter 1985 Cumulative I Cumulative Whole Body Whole Body Max. Organ. Max. Organ.

Pathway (mrem/qtr) (mrem/yr) (mrem/qtr) (mrem/yr)

Drinking 4.2E-07 2. 7E-06 5.9E-07 5.8E-06 Shoreline 6.3E-08 4'.4E-07 7.2E-08 4.5E-07 Fishing 6.7E-04 3.5E-03 1.0E-03 5.9E-03 Swimming 6.5E-10 2.1E-09 6.5E-10 2.1E-09 Boating 7.9E-10 2.6E-09 7.9E-10 2.6E-09 Leafy Veg. 8.3E-08 4.6E-07 22E07 1.3E-06 Vegetables 5.6E-07 2.8E-06 1. OE-06 6.6E-06 Milk 9.8E-06 4.3E-05 1.2E-05 5.7E-05 Heat 3.7E-08 1.5E-07 1.0E-07 3.8E-07 Total 5.8E-04 3.6E-03 1.0E-03 6.0E-03 Fourth Quarter 1985 Cumulative I Cumulative Whole Body Whole Body t1ax. Organ. Max. Organ.

Pathway (mrem/qtr) (mrem/yr) (mrem/qtr) {mrem/yr)

Drinking 4.2E-08 2.7E-06 1. 6E-07 6.0E-06 Shoreline 1.9E-07 6.3E-07 2.2E-07 6.7E-07 Fishing 4.0E-04 3.9E-03 1.4E-03 7.3E-03 Swimming'oating 8.6E-10 3.0E-09 8.6E-10 3.0E-09 1.1E-09 3 7E On 1.1E-09 3;7E-09 Leafy Veg. 2.'2E-08 4.6E-07 9.3E-08 1.3E-06 Vegetables 1.2E-08 2.8E-05 4.2E-07 5.6E-06 Milk 8.2E-06 5.1E-05 1,7E-OS 7.4E-05 Meat 3.0E-08 1.8E-07 1.2E-07 5.0E-07 Total 4.1E-04 4.0E-03 1.4E-03 7.4E-03 (1) Age Group - Adult: Maximum individual resides at Richland and fishes at the WNP-2 slough area.

0 Tabl e'-2 AVERAGE INDIVIDUAL DOSES FROM MNP-2 LIQUID EFFLUENTS 3RD AND 4TH QUARTERS 1985 Total er 3rd Quarter Total er 4th Quarter (modem)

IYiax. Organ. Mhole BodylMax. Organ. Mhcle Bodyl Pathwa (mrem) (mrem) (mrem)

Fish 2.5E-06 1.7E-06 3.5E-06 1.0E-06 Drinking Mater 3.4E-07 2.5E-07 9.1E-08 2.5E-08 Shoreline 2.5E-09 2.1E-09 7.4E-09 6.3E-09 Swimming 8.5E-11 8.5E-11 9.3E-11 9.3E-ll Boating 5.0E-11 5.0E-11 5.4E-11 5.4E-ll Vegetables 3.5E-06 1.6E-06 9.6E-07 3.8E-07 Leafy vegetables 3.4E-06 1.1E-06 9.9E-07 3.3E-07 Milk 7.4E-08 5.8E-08 1.1E-07 5.4E-08 Peat 4.9E-08 2.0E-08 5.4E-08 1.8E-08 Total 9.9E-06 4.7E-06 5.7E-06 1.9E-06 Table 6-3 50-MILE POPULATION DOSES FROM WHP-2 LIQUID EFFLUENTS 3RD AND 4TH QUARTERS 1985 Total er 3rd Quarter Total er 4th Quarter (Max. Organ. Whole Body/Max. Organ. hhole Body(

Pathwa l(man-rem) (man-rem) (man-rem) (man-rem)

Fish 1.5E-06 9.3E-07 1.8E-C6 6.4E-07 Drinking water 1.9E-05 1.5E-05 4.6E-O6 1.6E-06 Shoreline 8.2E-07 7.0E-07 2.4E-06 2.1E-06 Swimming 2.8E-08 2.8E-08 3.0E-08 3.0E-08 Boating 7.0E-09 7.0E-09 7.5E-09 7.5E-09 Vegetables 3.8E-05 1.8E-05 1.1E-05 4.2E-06 Leafy vegetables 3.7E-05 1.3E-05 1.1E-05 3.6E-06 Milk 1.1E-06 8.4E-07 1.6E-06 7.8E-07 Meat 5.0E-07 2.0E-07 5.5E-07 1.8E-07 Total 9.8E-05 4.9E-05 3.3E-05 1.3E-05 0

Table 6-4 SN1MARY OF DOSES FROtl WNP-2 GASEOUS EFFLUEiiTS 3RD AND 4TH QUARTERS 1985 Location: 1.2 miles site boundary

~Ri i: Thi d h0 <<1 1C 1 i,198*

Third Fourth Annual Quarter Quarter Cumulative Beta air dose (mrad)* 1.7E-02 1.4E-01 2.1E-01 Gamma air dose (mrad)* 1.6E-02 2.1E-01 2.9E-OI Location:

hi <<h Taylor Flats, 4.2 miles SE ~

Third Fourth Annual

~uarter Quarter Cumulative maximum organ dose 1.2E-02 7.9E-03 4.2E-02

,(mrem)**

Technical Specification 3.11.2.2.

Technical Specification 3.11.2.3.

7. 0 REY IS IONS TO THE GDCH During the semi-annual reporting period, revisions were made to the Offsite Dose Calculation manual (ODCN), which are included under this section.

I AMENDMENT NO. 3 February 1986 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Section Ti tl e ~Pa e

1.0 INTRODUCTION

2.0 LIOUID EFFLUENT DOSE CALCULATION................ 2 2.1 Introduction . ~ ~ e e....... e... ~ . e e a 2 2.2 Radwaste Liquid Effluent Radiation Monitoring System .

2.3 10 CFR 20 Release Rate Limits 3 2.3.1 Pre-Release Calculation 3 2.3.2 Post-Release Calculation . 4

~

2.3.3 Continuous Release . . 5 2.4 10 CFR 50, Appendix I, Release Rate Limits . . . . . . . . . . . 6 2.4.1 Projection of Doses . . . . . . . . . . . . . . . . . . . . . . 9 2.5 Radwaste Liquid Effluent Dilution Ratio and Alarm Setpoints Calculations . 9 2.5.1 Intr oduction . 9 2.5.2 Methodoloay for Determining the Maximum Permissible Concentra-tion (MPC) Fraction.. 10 2.5.3 Methodology for the Determination of Liquid Effluent Monitor Setpoint e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .11 !

2.6 Verification of Compliance with 10 CFR 50, Appendix I, and 10 CFR 20, Appendix B. . . . . . . . . . . . . . . . . . . . 12b I 2.7 Methods for Calculating Dose to Man from Liquid Effluent thva P a th vays 12b I 2.7.1 Radia6on Doses . 13 2.7.2 Plant Parameters . . 17 2e8 Compliance with Technical Specification 3.11.1.4 .

2.8.1 Maximum Allowable Liquid Radwaste Activity in Temporary Radwast Hold-Up Tanks . .19 I 2.8.2 Maximum Allowable Liquid Radwaste in Tanks That Are Not Surrounded by Liners, Dikes, or Walls . 22 2.9 Liquid Process Monitors and Alarm Setpoints Calculations 22 2.9.1 Standby Service Water (SW) Monitor . 23 2.9.2 Turbine Building Service Water (TSl() Monitor . . 24 2.9.3 Turbine Building Sumps Water (FD) Monitor 24

NEHDtlENT NO. 3 February 1986 Section Title Page 3.0 GASEOUS EFFLUEHTS DOSE CALCULATIOH . 33 3.1 Introduction.............., .. 33 3.2 Gaseous Fffluent Radiation Monitoring System . 34

3. 2.1 Main Plant Release Point . . . . . . . . . . . 34 3.2.2 Radwaste Building Ventilation Exhaust Honitor 35 3.2.3 Turbine Building Ventilation Exhaust Monitor . 36 3.3 10 CFR 20 Release Rate Limits ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 36

3. 3.1 Noble Gases ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 37 3.3.2 Radioiodines and Particulates 37 3.3.2.1 Dose Parameter for Radionuclide i (P; ) . 40 3.4 10 CFR 50 Release Rate Limits 41 3.4.1 Noble Gases (Technical Specification 3.11.2.2) ~ ~ 42 3.4.2 Radioiodines and Particulates (Technical Specification 3.11.2.3) . . . . . . 44 3.4.2.1 Dose Parameter for Radionuclide i (R; ) 47 3.4. 3 Annual Dose at Special Locations . 54 3.5 Compliance with Standard Technical Specifications 3.11.2.4 . 54 3.6 Calculation of Gaseous Effluent tlonitor Alarm Setpoints 54a 3.6.1 Introduction . . 54a 3.6.2 Setpoint Determination for All Gaseous Release Paths . 55 3.6.2.1 Setpoints Calculations Based on Mhole Body Dose Limits . ~ ~ 55 3.6.2.2 Setpoints Calculations Based on Skin Dose Limits . ~ ~ 58 4.0 CCt1PLIAHCE MITH 40 CFR 190 .

4.1 Technical Specification Requirement. 91 4.2 ODCM Methodology for Determining Dose and Dose Commi from Uranium Fuel Cycle Sources. ~ ~ 91 4.2.1 Total Dose from Liquid Effluents . ~ ~ 9la 4.2.2 Total Dose, rom Gaseous Effluents. ~ ~ 91a 4.2.3 Direct Radia .ion Cont.ibution. ~ ~ 91a 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 92 5.1 Radiological Environmental Monitoring Program (REMP) . 93 5.2 Land Use Census 5.3 Laboratory Intercomparison Program . 95 5.4 Reporting Requirements . 96 6.0 SEMI-ANNUAL RADIOACTIVE EFFLUEHT RELEASE REPORT .110 11

AMEHOMEHT Wo.

February 1986 iabl e Title Pace 3-9 Input Parameters Needed for Calculating Dose to the Maximum individual from WHP-2 Gaseous Effluent...... 71 3-10 Reactor Building Stack X/Q and D/Q Values .......... 73 3-11 Turbine Building X/Q and D/Q Values . . . . . . . . . . . . . 77 3-12 Radwaste Building X/Q and D/Q Values . . . , . . . . . . . . . 81 3-13 Characteristics of WHP-2 Gaseous Effluen Release Points . . . 85 3-14 References for Values Listed in Table 3-9 ~ ~ ~ ~ ~ ~ ~ ~ 86 3>>15 Desi gn Base Percent Noble Gas (30-Minute Decay ) e ~ ~ ~ ~ ~ ~ 87 3-16 Annual Doses at Special Locations Within WHP-2 Site Boundary.

Source: WNP-2 Gaseous Effluent . . . . . . . . . . . . . . . 88 3-17 Annual Air Dose at Special Locations Within WNP-2 Site Boundary ~ ~ ~ ~ ~ ~ ~ ~ 89 Section 5.0 5-1 Radiological Environmental Moni toring Program Pl an, ~ ~ ~ ~ ~ 98 5-2 WNP-2 REMP Locations . 102 5-3 Environmental Radiological Monitoring Program Annual Summary . 108 5-4 Reporting Levels for Honroutine Operating Reports . . . . . . 109 L IST OF FIGURES

~Pi ure Title ~Pa e Site Boundary for Radioacti ve Gaseous and Liquid Effluents ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ \ ~ ~ ~ 90 Radiological Environmental Monitoring Sample Locations Inside of 10-Mile Radius . . . . . . . . . . . . . . . . . , . 106 5-2 Radiological Environmental Monitoring Sample Locations Outside of 10-Mile Radius . . . . . . . . . . . . . . . . . . 107

AblEHDIIEHT HO. 3 February 1986 2.0 LIQUID EFFlUENT DOSE CALCULATIOH 2.1 Introduction Liquid radwaste released from WHP-2 will meet 10 CFR 20 limits at the point of discharge to the Columbia River. This design objective will be kept at all times. Based on the radionuclides mixture obtained from. the WHP-2 GALE liquid computer run and Columbia River dilution flow, a theoretical, continuous con-cent-, ation of radionuclides at 10 CFR 20 limits at the point of discharge to the Columbia River will result in compliance with 10 CFR 50 Appendix I limits in ihe unrestricted areas. Actual discharges of liquid radwaste effluents will only occur on a Batch Bases, and the average concentration at the point of discharge will be only a small percentage of the allowed limits.

The cumulative quarterly dose contributions due to radioactive liquid efflu-ents released to the unrestricted areas will be determined once every 31 days using the LADTAP II computer code. The maximum exposed individual is assumed

.o be an adult whose exposure pathways include potable water and fish consump-e tion. The choice of an adult as the maximum exposed individual is based on the highest fish and water consumption rates shown by that age group and the fact that most o the dose from the liquid effluent comes from these -wo pathways.

The dose contributions will be calculated for all radionuclides identified in the released effluent. The calculations are based on guidelines provided by the HRC Hureg-0133 and the LADTAP II computer code.

The methods for calculating the doses are discussed in Section 2.4 of this manual.

2.2 Radwaste Liquid Effluent Radiation Honitorin System This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.

AMENDMENT HQ. 3 February 1986 All radwaste effluent passes through a four-inch line which has an off-line sodium iodide radiation monitor. The radwaste effluent flow, variable from 0 to 190 gpm, combines with the 36-inch cooling water blowdown line, variable from 0 to 7500 gpm, (average of 2690 gpm) and is discharged to the Columbia River with a total flow based on ttPC; total, and cooling water flushing needs.

The radiation monitor has a minimum sensitivity of 10 pCi/cc of Cs-137, and the radiation indicator has a range of seven decades. The radiation .

monitor is located on the 437'evel of the Radwaste Building.

2.3 10 CFR 20 Release Rate Limits The requirements pertaining to discharge of radwaste liquid effluents to the unrestricted area are specified in Technical Specification 3.11.1.1:

"The concentration of radioactive material released from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases, and 2 x 10-< ~Ci/m total activity concentratra-tion 'or all dissolved or entrained noble gases."

In order to comply with the requirements stated above, limits will be set to assure that blowdown line concentrations do not exceed 10 CFR 20, Appendix B, Table II, Column 2 at any time.

2.3.1 Pre-Release Calculation The activity of the radionuclide mixture will be determined in accordance with Supply System procedure PPM 12.5.3, Liquid Ef luent Discharge Determination.

Liquid effluent discharge is determined and calculated according to PPH 12.11.1, Radiological Effluent Monitoring Gaseous and Liquid. The effluent concentration is determined by the following equation:

Ci xfw Ci ~1

l Pl 0

At<Et/DHEHT HO. 3 February 1986 where:

ConCi Concentration of radionuclide i in the effluent at point of discharge - qCi/ml.

Ci = Concentration of radionuclide i in the batch to be released - qCi/ml.

Discharge flow rate from sample tank to the blowdown I line - variable from 0 to 190 gpm.

fb = Blowdown flow rate - variable from 0 to 7500 gpm.

Total discharge flow rate - (f = fb + fw)

Tne calculated concentration in the blowdown line must be less than the con-centrations listed in 10 CFR 20, Appendix B. Before releasing the batch to the environment, the following equation must hold:

m g (ConC,./HPC,.

i=1 1 (2)

. where:

"'nC. The concentration of radionuclide i in the effluent at the point of dis'charge into the river.

Mr C. 'laximum permissible concen.ration of nuclide i as listed in 10 CFR 20, Appendix B, Table li.

Total number of radionuclides in the batch.

2.3.2 Post-Release Cal cul ation The concentration of each radionuclide in he restricted area, following the batch release, will be calculated as follows:

F

AtlEllDNENT HO. 3 February 1986 The average activity of radionuclide i during the time period of .he release is divided by the Plant Discharge Flow/Tank Discharge Flow ratio yielding the concentration at the point of discharge:

Cik x fw (3)

Cik rt where:

ConCik The concentration of radionuclide i in the effluent at the point of discharge during the release period k

- (~Ci/ml).

Cik = The concentration of radionuclide i in the batch during the release period k - (uCi/ml).

fw = Discharge flow rate from sample .ank to the blowdown line - variable from 0 to 190 gpm.

fb = Blowdown flow rate - variable from 0 to 7500 gpm.

ft = Total discharge (ft = fb + fw) flow ra e - variable from 0 to 7690 gpm.

To assure compliance with 10 CFR 20, the following relationships mus hold:

m g (Con,.k/NPC; C)k < 1 (4) where the terms are as defined in Equation (2).

2.3.3 Continuous Release Continuous release of liquid radwaste effluent is not planned for MNP-2.

However, should it occur, the concentrations of various radionuclides in the

Cl 0

NENDMENT HO. 3 February 1906 unrestricted area would be calculated according to Equation (3) and Equa-tion {4). To show compliance with 10 CFR 20, the two equations must again hold.

2.4 10 CFR 50, A endix l, Release Rate Limits Technical Specification 4.11.1.2 requires tha" the cumulative dose contribu-tions be det rmined in accordance with the ODCM at least once per 31 days.

Technical Spe'cification 3.11.1.2 specifies. that the dose to a member of the public from radioactive material in liquid effluents released to the unre-stricted area shall be limited to:

< 1.5 mrem/Calendar quarter - Total Body and

< 5.0 mrem/Calendar quarter - Any Organ.

The cumulative dose for the calendar year shall be limited to:

< 3 mrem - Total Body and

< 10 mrem - Any Organ.

The dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted area, using the following equation:

(5) where:

D ~ The cumulative calendar quarter or yearly dose to any organ j from liquid effluent for the total release period - (in mrem).

AMENDMENT NO. 3 February 1986 The length of the 1th release period over which C;1 and Fl are averaged for liquid releases - (in hours).

The number of releases for the time period under consideration.

Average concentration of nuclide i in the liquid effluent at point of discharge during the release period Tl from any liquid release - (vCi/ml).

The site-related ingestion dose factor to the total body or critical organ j for each identified nuclide listed in Table 2-2 (in mrem/hr per qCi/ml).

The near field average dilution factor for C;1 during any liquid waste release. Defined as the ratio of the average radwaste discharge flow during the release to the product of the average flow from the site structure to unrestricted receiving waters times 100. This is a conservative value since the average river flow is 120,000 cfs and blowdown rate is only 6 cfs.

Li uid Radwaste Flow fw s scnarge true:ure ex> t x rrtx r0 (6)

NEHDMEHT NO. 3

.February 1986 The term A, lj the ingestion dose factors for the total body and critical organs, are tabulated in Table 2-2. It embodies the dose factor, fish bioac-cumulation factor, pathway usage factor, and the dilution factor for the plant diffuser pipe to the nearest potable water intake. The following equation was used to calculate the ingestion dose factors:

"w

' (7) i 5 F Fi Fi where:

The composite dose parameter for total body or criti-cal organ of an adult for nuclide i (in mrem/hr per yCi/ml).

K A conversion factor:

1.14E+05 = (10 6 ..

pCijpCi) x (10 3

ml/liter) : 8760 hr/yr.

730 liter/yr - which is the annual water consumption by the maximum adult (Table E-4 of Regulatory Guide 1.109, Revision 1).

Bioaccumulation factor for radionuclide i in fish Fi

- (pCi/Kg per pci/liter) (Table A-1 of Regulatory Guide 1.109, Revision 1).

Adult ingestion dose conversion facto for nuclide i

- Total body or critical organ - (mrem/pCi) (Table E-11 of Regulatory Guide 1.109, Revision 1).

w Dilution factor from near field area to the nearest potable water intake - 200.

Adult fish consumption, 21 kg/yr .(Table E-5 of Regulatory Guide 1.109, Revision 1).

Ab)ENDt1EiQT i%0. 3 February 1986 The trip/alarm setpoint for the liquid radwaste effluent monitor is calculated from the results of the radiochemical analysis of the waste solution. The setpoint will be set into the radwaste monitor just prior to the release of each batch of radioactive liquid.

2.5.2 Wethodolo y for Determining the tlaximum Permissible Concentration (t~iPC)

Fracti on Radwaste liquid effluents can only be discharged to the environment through the four-inch radwaste line. The maximum radwaste discharge flow rate is 190 gpm. Prior to discharge, the tank is isolated and recirculated for at least thirty minutes, and a representative sample is taken from the tank. An isotopic analysis of the batch will be made to determine the sum of the HPC fraction (tiPCf) based on 10 CFR 20 limits. From the sample analysis and the HPC values in 10 CFR 20, the tPCf is determined using the following equation.

(8) 'lI where:

i~lPC f Total fraction of the Maximum Permissible Concentra-tions (lPCs) in the liquid effluent waste sample.

C- The concentration of each measured radionuclide (i) observed by the radiochemical analysis of the liquid waste sample ( Ci/ml).

S AMENDMENT NO; 3 February 1986 MPC 1

The limiting concentrations of the appropriate radionuclide (i) from 10 CFR 20, Appendix 8, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04

~Ci/ml total activity.

The total number of measured radionuclides in the liquid batch to be released.

If the MCPf is less than or equal to 0.8, the liquid batch may be released at any radwaste discharge or blowdown rate." If the MPCf exceeds 0.8, then a dilution factor (Fd) must be determined. The liquid effluent radiation monitor responds proportionally to radioactivity concentrations in the undiluted waste stream. Its setpoint must be determined for diluted releases.

2.5.3 Methodolo for the Determination of Liquid Effluent Monitor Set oint The measured radionuclide concentrations are used to calculate the dilution factor (Fd), which is the ratio of the total discharge flow rates (fw + fb) to the radwaste tank effluent flow rate (fw) that is required to assure that the limiting concentrations of Technical Specification 3. 11.1.1 are met at the point of discharge.

The dilution facto~ (Fd) is determined according to:

I9)

Nhere:

The dilution factor required for compliance with 10 CFR 20, Appendix B, Table II, Column 2.

11

AMENDttENT NO. 3 February 1986 C ~ The concentration of each radionuclide (i ) observed by radiochemical analysis of the liquid waste sample (gCi/ml).

MPC The limiting concentration of the appropriate radionuclide (i) from 10 CFR 20, Appendix 8, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 gCi/ml total activity.

The safety factor; a conservative factor used to compensate for statistical fluctuations and errors in measurements. For example, a safety factor (Fs) of 1.5 corresponds to a fifty (50) percent ( ) variation.

The total number of measured radionuclides (i) in the liquid batch to be released'.

The dilution which is required to ensure compliance with Technical Specification 3,11.1.1 concentration limits will be set such that discharge rates are:

fw + fb (10) and follows that:

fb (loa)

I fb ~ fw(Fd-1) (1 ob )

~Ahere:

The dilution factor from equation 9.

12

N)ENDMEHT i(0. 3 February 1986 fw The discharge flow rate from the liquid radwaste tank to the blowdown line - variable from 0 to 190 gpm.

The cooling tower blowdown flow rate - variable from 0 to 7500 gpm, The liquid effluent radiation monitor response is based on the results of the radiochemical analysis of the waste solution. Therefore the calculation for the radia. on monitor's alarm/trip setpoint is; SP = C + BKg + K [C + Bkg]

Mhere:

SP Radiation monitor setpoint (count rate) i=1 (C; x Ef; ) represents the count rate from the radionuclides in the liquid radwaste.

Ci The concentration of each measured radionuclide (i) observed by radiochemical analysis of the liquid waste sample ( qCi/ml).

Same as for equation 9.

Ec ~

The radwaste effluent monitor's response to radionuclide (i) (count rate per ~Ci/ml).

12a

NIENDf1ENT NO. 3 February 1986 BKg Background count rate of the radwaste effluent monitor.

A constant to compensate for normal expected statistical variations in the liquid effluent radiation monitor count rate to reduce the chance of false alarms/trips; K=3.

2.6 Yerification of Com liance with 10 CFR 50, Ap endix I, and 10 CFR 20, A oendix B Yerification of compliance with 10 CFR 50, Appendix I, and 10 CFR 20, Appen-dix 8, limits will be achieved by following MNP-2 Plant Procedures for liquid discharge and the periodic application of the LADTAP II computer code.

2.7 liethods for Calculatin Doses to Man From Li uid Effluent Pathwa s Dose models presented in NRC Regulatory Guide 1.109, Revision 1, as incorporated in the LADTAP II computer code, will be used for offsite dose calculation. The details of the computer code, including the program listing and user instruction, are included in the Radiological Programs Procedure R.P. I. 2.3, Offsite Dose Calculation Reference manual LADTAP.

12b

NE>lDtlEPT HO. 3 February 1986 The deposition rate of nuclide i, in pCi/m per hour.

The flow rate of the liquid effluent, in ft3/sec.

The fraction of the year crops are irrigated, dimensionless.

FiA The stable element .rans er coefficient that relates the daily intake rate by an animal to .he concen-tration in an edible portion of'nimal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal pro-duct) oer pCi/day.

The mixing ratio (reciprocal of the dilution factor) at the point of exposure (or. the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless.

The effective "surface density" for soil, in kg (dry soil)/m~ (Table E-l, Regulatory Guide 1.109, Revision 1).

OAw The consumption rate of contamina.ed water by an animal, in liters/day.

The consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight).

The release rate of nuclide i, in Ci/yr.

The fraction of deposited activity retained on croos, dimensionless (Table E-15, Regulatory Guide 1.109, Revision 1).

15

e

\

AMENDMENT NO. 3 February 1986 P

apg The total annual dose to organ j of individuals of age group a from all of the nuclides i in pathway p, in mrem/yr.

The period of tive'for which sediment or soil is exposed to the contaminated water, in hours (Table E-15, Regulatory Guide 1.109, Revision 1).

The time period that crops are exposed to contamina-tion during the growing season, in hours (Table E-15, Regulatory Guide 1.109, Revision 1).

A holdup tie that represents the time interval between harvest and consumption of the food, in hours

{Table E-15, Regulatory Guide '1.109, Revision 1).

The radioactive half life of nuclide i, in days.

The average transit time required for nuclides to

.reach the point of exposure. For internal dose, t is the total time elapsed between release of the nuclides and ingestion of food or water, in hours (Table E-15, Regulatory Guide 1.109, Revision').

A usage factor that specifies the exposure time or intake rate for an individual of age group a associ-ated with pathway p, in hr/yr, g/yr, or kg/yr (Table E-5, Regulatory Guide 1.109, Revision 1).

NENDHENT HO. 3 February 1986 The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109, Revision 1). I Y The agricultural productivity (yield), in kg (wet weight) /m (Table E-15, Regulatory Cuide 1.109, Revision 1).

Ei The effective i from crops, in

". is the radioactive removal hr,

-1 where ~E Ei

~ + X 1

rate constant for radionuclide decay constan , and X is the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Revision 1, Table B-15).

The radioactive decay constant of nuclide i, in hr-'100 The factor to convert from (Ci/yr)/(ft3 /sec) to pCi/1 i ter.

110,000 The factor to convert from (Ci/yr)/(ft3 /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equations yield the dose rates to various organs of individuals from the exposure pathways menti oned above.

'2.7.2 Plant Parameters WNP-2 is a river shoreline site with a variable effluent discharge flow rate 0 to 7500 gpm (2690 gpm average). The population center nearest MHP-2 is the city o, Richland, where drinking water withdrawal takes place. The applicable dilution factor is 20,000, using full river flow. The time required for re-17

0 NENDMENT NO. 3 February 1986 leased liquids to reach Richland, approximately 12 miles downstream, is esti-mated at 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Richland is the "realistic case" location, and doses cal-cula .ed for the Richland location are typically applicable to the population as a whole. Individual and population doses based on Richland parameters are calculated for all exposure pathways.

Only the 75,000 population downstream of the WNP-2 site is affected by the liquid effluents released. There is no significant commercial fish harvest in the 50-mile radius region around WNP-2. Sportfish harvest is estimated at-14,000 kg/year.

For irrigated foods exposure pathways, it can be assumed that, production with-in the 50-mile radius region around MNP-2 is sufficient to satisfy consumption requirements.

Other relevant parameters relating to the irrigated foods pathways are defined as follows:

II P ii ~B

~Food T e (1 iter/m /mo) (kg/m2) (Days)

Vegetation 150 5.0 70 Leafy Vegetation 200 1.5 70 Feed for Milk Cows 200 1.3 30 Feed for Beef Cattle 160 2.0 130 Source terms are measured based on sampled effluent.

I Table 2-3 summarizes the LAOTAP II input parameters. Documentation and/or calculations of these parameters are discussed in detail in R.P. I. 2.3, and Rad. Prog. calculation Log 83-1.

18

NENDh1ENT NO. 3 February 1486 2.8 Compliance with Technical Specification 3.11.1.4 2.8.1 htaximum Allowable Li uid Radwaste Activity in Tem ovary Radwaste Hold-Up Tanks The use of temporary liquid radwaste hold-up tanks is planned for WNP-2.

Technical Specification 3.11.1.4 states the quantity of radioactive material contained in any outside temporary tanks shall be limited to the limits calculated in the ODCN such that a complete release of the tank contents would not result in a concentration at the nearest offsite potable water supply that, would exceed the limits specified in 10 CFR Part 20 Appendix 8, Table Il.

Equation 18 will be used to calculate the curie limit for a temporary radwaste hold-up tank. The total tank concentration will be limited to less than or equal to ten (<10) curies, excluding tritium and dissolved or entrained gases.

Surveillance requirement 4.11.1.4, states that the quantity of radioactive material in the hold-up tanks shall be determined to be within the limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Kd (18) '-

T 1

where:

Total allowed activity in .ank (curies ).

A. Activity of radioisotope i (curies).

AMENDMENT NO. 3 February 1986 MPC. ttaximum permissible concentration of radionuclide i (10 CFR 20, Appendix B, Table. II, Column 2).

Decay constant (years ) radioisotope i.

Transit. time of ground water from HNP-2 to MNP-1 well (MNP-2 FSAR Section 2.4) = 67 years.

Fraction of radioisotope fi = .

A ~

Ai'ndex for all radioisotopes in tank except tritium and noble gases.

Kd Dispersion constant based on hydrological parameters, (2.4E+05 Ci per qCi/cc.)

19a

NEHDMEHT HO. 3 February 1986 The total allowed activity (A ) is based on limiting WHP-1 well water to than 1 MPCi of the entire liquid content of the tank spilled to ground

'ess and then migrated via ground water to the MHP-1 well. The WHP-1 well is the location of maximum concentration since it is the nearest source of ground water and conditions are such that no spill of liquid should reach surface water. The 70-85 foot depth of the water table and the low ambient moisture of the soil requires a rather large volume of spillage for the liquid to even reach the water table in less than several hundred years. However, allowed tank activity (A ) is conservatively based on all liquid radwaste in the tank instantaneously reaching the water table.

The hydrological analysis performed for the MHP-2 FSAR (Section 2.4) deter-mined that the transit time through the ground water from MHP-2 to the WHP-1 well is 67 years for Strontium and 660 years for Cesium. These two radio-nuclides are representa ave of the radionuclides found in liquid radwaste.

Strontium is a moderate sorber and Cesium strongly sorbs to soil particles.

This calculation conservatively treats all radionuclides as moderate sorbers with a transit time of 67 years.

The concentration of each radionuclide in the well (CM.)1 is simply the con-centration in the tank (CTi) adjusted for radioactive decay during transit (e ) and divided by the minimum concentration reduction factor (CRF min ).

Limiting well concentration to 1 HPC yields:

CM.

1

=Z~ (F, CT,. e min i

'.t 2.<< ll - .) (19),

1/2 CRF . = (4 L) Y (20) ml n 20

NEiRDMEiNT NO. 3 February 1986

<vhere:

L = Migration distance = 1 mile.'

= Volume of tank.

a x > a, v

a z

= Dispersion constants.

Combining Equations 19 and 20 yields:

CT 1

~ 2V e i 1 (21)

(4 -.

L) (a a a ) HPC.

Substituting Ai or CTi V and reorganizing terms yields:

3/2 1/2

) A; (22)

HPC. e 1

i tweaking the follo<ving substitutions i = fi AT K

d (4" L) 3/2

( x av a 1/2 x 10

-6 ..

Ci/qCi = 2.4 x 10 5 Ci per pCi CC (23) 21

NEHOHEHT HO. 3 February 1986 yields:

thPC,.e or T ~

HPC ~

2.8.2 tlaximum Allowable Liquid Radwaste in Tanks That Are Not Surrounded by Liners, Dikes, or Walls Although permanent outside liquid radwaste tanks which are not surrounded by

'liners, dikes, or walls are not planned for WHP-2, Equation 18 will be used should such tanks become necessarv in the future.

2,9g Liquid Process tionitors and Alarm Setpoints Calculations As mentioned in Section 2.2 of this manual, all liquid radwaste effluent is discharged through a four-inch line that is monitored by an off-line sodium iodide radiation monitor. This monitor is located on the of the Radwaste Building. All MNP-2 radwaste 1'.iquid effluent is 437'evel discharged to the Columbia River through the 36-inch Cooling Mater Blowdown line. in addition to the liquid effluent discharge monitor there are three liquid streams that are normally non-radioactive but have a finite possibility o, having radioactive material injected into them.

These liquid str ams are:

o Standby Service Mater (SM) o Turbine Building Service Mater (TSM) f n Turbine Building Sump Mater (FD) 22

NEiNONEr<T f!0 3 February 1986 To prevent any discharges of radioactive liquid from these streams, radiation monitoring systems have been installed to detect any increase above the normal background concentration of radioactive material.

Alarm/setpoints are established to prevent any release of radioactive material in concentrations greater than 10CFR20 limits. The maximum radiation detector setpoint calculation for the three systems is based on i concentration of Cs-137 which is 2.05-05 nCi/ml. The follow-ing equation is used to calculate the maximum setpoint:

Setpoint max. = (2.0E-05 pCi/ml ) (CF) (.w5)

(in cpm or cps) where:

k 2.0E-Q5 pCi/ml = f1PC limit for Cs-137 CF = Yonitor calibration factor - in cpm/ pCi/ml or cps/ pCi/ml 2.9.1 Standby Service Water (SM) t1onitor - The Standby Service Mater t<onitors (SM) are located on the 522'evel of the Reactor Building.

The meter is located in the main control room on panel P-604.

The flow rate through the monitor is variable, from zero (0) to two (2) gpm with a normal flow of 1.0-1.5 gpm.

To ersure 1QCFR20 limits are never exceeded, the alarm setpoint shall be established at 80 or less of the maximum setpoint plus background.

If the setpoint is exceeded, an alarm will activate in the main control room. The control room. operator can then terminate the di scharge and miti gate any uncontrolled release of radioactive material.

23

NENDtlENT $ 0. 3 February 1986 Table 2-1 FISH BIOACCUMULATION FACTORS (BF )

AtJD ADULT INGESTION DOSE CONVERSION FACTORS (DFi)

Dose Conversion Factor (DF,.)

Fish Bioaccumulation Total GI Nuclide Factor (BF, ) Body Bone Thyroid Liver Tract p i g per Tmmem p'eerp i 1eg'eesee pCi/liter)

H-3 9.0E-01 1.1E-07 (3) 1.1E-07 1.1E-07 1.1E-07 Na-24 1. OE+02 1.7E-06 1.7E-06 1.7E-OR 1.7E-OR 1.7F.-O6 P-32 1.OE+05 7.5E-06 1.9E-04 (3) 1. 2E-05 2 2E"05 I Cr-51 2. OE+02 2.7E-09 (3) 1.6E-09 (3) 6.7E-07 Mn-54 4.0E+02 8.7E-07 (3) (3) 4.6E-06 1.4E-05 t~n-56 4.0E+02 2.0E-08 (3) (3) 1.2E-07 3,7E-06 Fe-55 1.0E+02 4.4E-07 2.8E-06 (3) 1.9E-06 1.1E-06 Fe-59 1.0E+02 3. 9E-06 4. 3E-06 (3) 1. OE-05 3. 4E-05 Co-58 5.0E+Ol 1.7E-OR (3) (3) 7.5E-07 1.5E-05 Co-60 5. OE+01 4. 7E-06 (3) (3) 2.1E-06 4.0E-05 Ni-65 1.0E.02 3.1E-08 5.3E-07 (3) 6.9E-OB 1.7E-06 Cu-64 5.OE+01 3. 9E-08 (3) (3) Be3E-08 7.1E-06 Zn-65 2.0E+03 7.0E-06 4.8E-06 (3) 1.5E-05 9.7E-06 Zn-69 2.0E+03 1.4E-09 1. OE-08 (3). 2.0E-08 3.0E-09 Br-83 4.2E+02 4.0E-08 (3) (3) (3) 5.8E-08 Br-8< 4. 2E+02 5. 2E-08 (3) (3) (3) 4.1E-13 Rb-89 2. OE+03 2. 8E-08 (3) (3) 4.0E-08 2.3E-21 Sr-89 3. OE+01 8.8E-06 3.1E-04 (3) (3) 4 9E-0 Sr-90 3. OE+01 1.9E-03 7.6E-03 (3) (3) 2.2E-O<

NEHDMEHT HO. 3 February 1986 Table 2-1 (contd. )

Dose Conversion Factor (DF 1 )

Fish Bioaccumulation Total GI Nuclide Factor (BF;) Body Hone Thyroid Liver Tr act pCi/kg per ~mgem per pci Ingeeteee pCi/liter)

Sr-91 3.Of+01 2.3E-07 5.7E-06 (3) (3) 2.7E-OS Sr-92 3.OE+01 9.3E-08 2.2E-06 (3) .(3) 4.3E-OS Y-90 2.SE+Ol 2.6E-10 9.7E-09 (3) (3) 1.0E-04 Y-91m 2.Sf+01 3.5E-12 9.1E-11 (3) (3) 2.7E-10 Y-91 2.5E+01 3.8E-09 1. 4E-07 (3) (3) 7.8E-OS ~

Y-92 2.Sf+01 2. SE-11 8.5E-10 (3) (3) 1.SE-OS Y-93 2,SE+01 7. 4E-11 2.7F.-09 (3) (3) 8.5E-OS t<o-99 1.0E+01 8. 2E-07 (3) '3) 4.3E-OG 1.0F.-05 Tc-99m 1.5E+01 8.9E-09 2.SE-10 (3) 7.0E-10 4.1E-07 Tc-101 1.Sf+01 3. 6E-09 2. 5E-10 (3) 3.7E-10 1.1F.-21 Ru-103 1.Of+01 8.0E-08 1,9E-07 (3) (3) 2. 2E-05 Ru-105 1.0E+01 6 e 1 E-09 1. Sf -08 (3) (3) 9.4E-OG Rh-105 1.Of+01 8.9E-08 1.2E-07 (3) 8 9F08 9.1E-07 Te-129m 4.Of~02 1.8E-06 1.2E-05 4.0E-06 4.3E-06 5.8E-OS Te-129 4.Of+02 7.7E-09 3.1E-08 2.4E<<08 1.2E-08 2.4E-08 Te-131m 4.Of+02 7;1E-07 1.7E-06 1.3E-OG 8.5E-07 8.4E-OS Te-131 4.OE+02 6.2E-09 2.0E-08 1.6E-08 8.2E-09 2.8E-09 Te-132 4.Of+02 1. 5E-06=- 2. 5E-06 1.8E-06 1.6E-06 7.7E-OS T-131 1.5E+01 3. 4E-06 4. 2E,-OG 2.0E-03 G.OE-06 1.6E-06 I-132 1. Sf1 1.9E-OS 2.0E-07 2.0E-05 5.4E-07 1.0E-07 I-133 1.SE+Ol 7.5E-07 1.4E-06 3.6E-O< 2.5E-OG 2.2f-OG i-134 1.SF+01 1.0E-07 1.0E-07 S.OE-OG 2.9f-07 2.SE-10 I-135 1.5E+01 4. 3E-07 4. 4E-07 7.7E-05 1.2E-OG 1.3E-06 Cs-134 2.Of+03 1. 2E-04 6. 2E-05 (3) 1.5E-04 2.5F-OG Cs-136 2. Of&3 1.9E-05 6.5E-OG (3) 2.6E-05 Z. 9E-OG Cs-137 2. Of+03 7.1E-05 8.0E-OS (3) 1.1E-04 2.1E-OG Cs-138 2.0E+03 5.4F.-08 5.5E-08 (3) 1.1E-07 4.7E-13 Ba-139 4.Of+00 2.8E-09 9.7E-08 l3) 6.9f-ll 1. 7E-07 27

0 AMEHDMEHT NO. 3 February 1986 Table 2-1 (contd.)

Dose Conversion Factor (DF,.)

Fish Bioaccumulation Total GI Nucl i de Factor (BF.) Body Bone Thyroid Liver Tr act pC> g per mRem per pC~ .IngestedT pCi/liter)

Ba-140 4.0E+00 1.3E-06 2.0E-OS (3) 2.6E-08 4.2E-05 La-140 2.5E+01 3.3E-10 2.5E-09 (3) 1.3E-09 9.3E-05 La-141 2.5E+01 1.6E-11 3.2E-10 (3) 9.9E-11 >.zz-os [

La-142 2.5E+Ol 1.5E-11 1.3E-10 (3) 5.8E-ll 4. 3E-07 Ce-141 1.0E+00 7.2E-10 9.4E-09 (3) 6.3E-09 2. 4E-05 Ce-143 1.0E+00 1.4E-10 1.7E-09 (3) 1.2E-06 4.6E-05 Pr-143 2.5E+01 4.6E>>10 9.2E-09 (3) 3.7E-09 4.0E-05 M-187 1. 2E+03 3.0E-08 1.0E-07 (3) 8.6E-OS 2.8E-05 Hp-239 1.0E+Ol 6.5E-11 1.2E<<09 (3) 1.2E-10 2.4E-Q5 (1) HRC Regulatory Guide 1.109, Revision 1, Table A-1.

(2) NRC Regulatory Guide 1.109, Revision E-ll.

1, Table (3) No data listed in Regulatory Guide 1.109, Revision E-ll.

1, Table (Use whole body dose conversion factor as an approximation.)

28

NEHDMEHT HO. 3 February 1986 Table 2-2 IHGESTIOH DOSE FACTORS (A-.) FOR TOTAL BODY AHD CRITICAL ORGAN 1n mrem r per q i m Liquid Ei'fluent*

Total Gi Huc1i de Body Bone ihyre i d Liver Tract H-3 2.8E-01 2. 8E-01 2.8E-01 2.8E-01 Ha-24 4.1E+02 4.1E+02 4.1E+02 4.1E+02 4.1E+02 P-32 1.8E+06 4;6E+07 2.9E+07 5. 3E+06 Cr-51 1.3E+00 7.7E-01 3.2E+02 tIn-54 8.3E+02 4. 4E+03 1.3E+04 t~n-56 1.9E+01 1.2E+02 3.6E+03 Fe-55 1.1E+02 6.7E+02 4.6E+02 2.6E+02 Fe-59 9.4E+02 1,DE+03 2.4F+03 8.2E+03 Co-58 2.0E+02 9.0E+01 1.BE+03 Co-60 5.7E+02 2.5E+02 4eQE+03 Hi-65, 7.4E+00 1.3E+02 1.7E+01 4.1 E+02 Cu-64 4.7E+00 1.DE+01 8.5E+02 Zn-65 3.4E+04 2. 3E+05 7.2E+04 4.7E+04 Zn-69 6.7E+00 4.8E+01 9.65+01 1. 4E+01 Br-83 4.0E+01 5.8E+01 Br -84 5.2E+01 4.1E-04 Rb-89 1.3E+02 1.9E+02 1.1E-10 Sr-89 6.4E+02 2. 3E+04 3.5E+03 Sr-90 1.4E+05 5. 5E+05 1. 6E+04 Sr-91 1.7E+01 4.1E+02 2. DE+03 Sr-92 6.7E+00 1.6E+02 3.1 E+03 29

Table 2-2 (contd.)

Total Gi Nucl ide Body Bone Thyroid Liver Tract Ce-143 3.9E-04 4.8E-03 3. 4E+00 1, 3E+02 Pr-143 2.8E-02 5,5E-Ol 2. 2E-01 2.4E+03

!A-187 8. 6E+01 2.9E+02 2.SE~02 8.0E+04 Np-239 1. 6E-03 2.9E-02 2.9E-03 5.8E+02

Based on conservative radionuclide mix obtained from GALE Liquid Code.

Equation (7) was used to calculate the ingest" on dose factor s (Ai i )

No Ingestion Dose ."-actor (DFi

) is listed in Table E-ll of Regulatory Guide 1.109, Revision l. (!Ahole body dose factor value will be used as an approximation. )

31

NENDt1EHT HO. 3 February 1986 All other locations listed in Figure 3-1 support WHP-2 activities and are controlled by the Supply System.

'I Air doses and doses to individuals at these locations were calculated based on the HRC GALE code design base mixture, location specific estimated occupancy, and X/Qs from XOQDOQ. (Note: Desert Sigmas. were used in calculating X/Q and D/Q values, and are listed in Table 3-10 to 3-12). These doses are listed in Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.

The maximum exposed individual is considered to be residing in Taylor Flats (4.2 miles SE of WNP-2). This is the closest residential area with the high-est X/Q and D/Q values.

3.2 Gaseous Effluent Radiation Monitorin S stem 3.2.1 Hain Plant Release Point The thain Plant Release is instrument monitored for gaseous radioactivity prior to discharge to the environment via the main plant vent release point.

Particulates and iodine activity are accumulated in filters which will be changed and analyzed as per Technical Specification 4.11.2.1.2 and Table 4.11.2. The effluent is supplied from: the gland seal exhauster, mechanical vacuum pumps, treated off gas, standby gas treatment, and exhaust air from the entire reactor building's ventilation.

Two 100-percent capacity vanaxial fans supply 98,000 CFM ventilation air. One is normally operating, the other is in standby. The radiation monitors are located on the ventilation exhaust plenum.

Effluent monitoring consists of beta scintillators and two ion chamber LOCA monitors. The beta scinti.llator has a four inch thick lead shielded chamber and has an approximate response of 80'cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc I

to Xe-133. I The read out meter and recorder are located in the main control room panel 6

BD-RAD-24. The analogue count rate meter has a range of 10-10 cpm. Power

NENDi4lENT NO. 3 February 1986 is provided .from 125 VOC divisional buses. This monitor has no control function but annunciates in the main control room. The alarm will initiate proper action as defined in the WNP-2 Plant Procedures.

3.2. 2 Radwaste Buildin Ventilation Exhaust t<onitor The radwaste building ventilation exhaust monitoring system monitors the radio-activity in the exhaust air prior to discharge. Radioactivity can originate fram: radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.

The radwaste building exhaust system has three 50 percent capacity exhaust filter units of 42,000 cfm capacity. Each exhaust unit has a medium-efficiency prefilter, a high efficiency particulate air filter (HEPA) and two centrifugal fans. Total exhaust flow will vary as the combined exhaust unit maintains a r adwaste building dif erential pressure of -0.25 inches H20 to the I environment.

Particulate and iodine air sample filters are changed weekly for laboratory analysis. After the particulate and iodine filters, the air sample streams are combined in a manifold prior to being monitored by a beta scintillator.

The beta scintillator, on radwaste 487'evel southwest corner is mounted in a three inch lead shielded chamber and has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133. The readout meter and recorder are l,ocated in the main control room panel BO-RAD-24. The analog 6

count ra.e meter has a range of 10 to 10 cpm. Power is provided from 125 VDC divisional buses. This monitor has no control func ions but annunciates in the main control room. The alarm will initiate proper action as defined in the MNP-2 plant procedures.

4 AMENDMENT NO. 3 February 1986 3.2.3 Turbine Building Ventilation Exhaust Monitor This monitoring system detects fission and the activation products from the turbine building air which may be present due to leaks from the turbine and other primary components in the building.

The turbine building main exhaust system consists of four roof-mounted centri-fugal fans which draw air from a central exhaust plenum. Three fans operate continuously, wi th one in standby to provide a flow of 260,000 cfm.

A representative sample is extracted from the exhaust vent and passed through a particulate and charcoal filter. The air sample then passes to a beta scintillator.

The beta scintillator is mounted in a three inch lead shielded chamber and has an approxima .e response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133. Thc monitor is on the 525'evel of the radwaste building and the readout meter and the recorder are located in the main control room panel BD-RAD-24. one analog count rate meter has a range of 10 to 10 6 cpm. Power is provided from the 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room. The alarm will initiate proper action as de,ined in the MNP-2 plant procedures.

3.3 10 CFR 20 Release Rate Limits Limits for release of airborne effluents to the unrestricted area are sta .ed in Technical Specification 3.11.2.1. The dose rate in unrestricted areas due to radioactive mat rials released in gaseous effluents from the site shall be limited to the following values:

{a) "The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin.

{b) "The dose rate limit for all radioiodines and for all radio-active materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days shall be <1500 mrem/yr to any organ."

36

NEHDMEHT NO. 3 February 1986 3.3.1

~ ~ Noble Gases In order to comply with Technical Specification 3.11.2.1, the following equa-tions must hold:

Hhole body:

m Ki (77/) Q. + (77Q) Q. ) ( 500 mrem/yr (1) 1 Skin (L. + 1.1Ni)((770) Qi + (V0) Q. ) ( 3000mrem/yr (2) 1 3.3.2 Radioiodines and Particulates Part "b" of Technical Specification 3.11.2.1 requires that the release rate limit for all radioiodines and radioactive materials in particulate form and radionuclides other than noble gases must meet the following relationship:

Any organ:

m g P. MM Q. + M Q. ( 1500 mrem/yr (3)

The terms used in equations 1 through 3 are defined as follows:

K-1

= The total body factor due to gama emissions for each iden-tified noble gas radionuclide i (mrem/yr per pCi/m ).

L.

1

= The skin dose factor due to beta emissions for each iden-tified noble gas radionuclide i (mrem/yr per yCi/m ).

37

NENDMEN1'O. 3 February 1986 The air dose fac.or due to gamma emissions for each identified noble gas radionuclide in mrad/yr per >Ci/m (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

The dose parameter for all radionuclides other than noble gases for the inhalation pathway, (mrem/yr per pCi/m 3 )

and for food and ground plane pathways, m 2 (mrem/yr per uCi/sec). The dose factors are based on the critical individual organ and the most restrictive age group.

Qim The release rate of radionuclide i in gaseous ef luent from mixed mode release. The main plant: release point is a partially elevated mixed mode release (pCi/sec).

Q;g The release rate of radionuclide i in gaseous effluent from all ground level releases (>Ci/sec).

3 (Txc}) (sec/m ). For partially elevated'ixed mode releases from the main plant vent release point. The highest calculated partially elevated annual average relative concentration for any area at or beyond the site boundary.

3

( jxq) (sec/m ). For all Turbine Building and Radwaste releases. The highest calculated ground level annual average relative concentration for any area at or beyond the site boundary.

38

Ai4lENDMEHT HQ. 3 February 1986 M = The highest calculated annual average dispersion parameter g

for estimating the dose to an individual at the controlling location due to all ground level releases.

(sec/m ). For the inhalation pathway. The location is the site boundary in the sector of maximum concentration. .

M = m . For ground plane pathways. The location is the site boundary in the sector of maximum concentration.

The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to partially elevated releases:

sec/m, For inhalation pathway. The location is the site boundary in the sector of maximum concentration.

m . For ground plane pathways. The location is the site boundary in the sector of maximum concentration.

The fac.ors, L; and H;, relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are listed in Table B-1 of Regulatory Guide 1.109, Revision 1, and in Table 3-1 of this manual.

Tne ~j values used in the equations for the implementation of Technical Specification 3.11.2.1 are based upon the maximum long-term annual average at the site boundary. The distances between the nearest unrestricted area and the !ANP-2 site are listed in Table 3-2. The dis .ances between WWP-2 and the nearest vegetable garden, milk cow, and beef animal are tabulated in Table 3-3, along with representative X/Q and D/Q values.

39

AMENDMEHT NO. 3 February 1986 The X/Q and D/0 values listed in Tables 3-10 through 3-12 reflect correct meteorological data up to 1983 and were utilized in the initial GASPAR ac-'uired Computer runs. Subsequent reports will use updated X/Q and D/Q averages Char-acteristics of NNP-2 gaseous effluent release points are listed in Table 3-13.

3.3.2.1 Dose Parameter for Radionuclide i (P.)

The dose parameters used in Equation 3 are based on:

l. Inhalation and ground plane. (Note: Food pathway is not applicable to MNP-2 since no food is grown at or near the restricted area boundary. )

2. The annual average continuous release meteorology at the site boundary.

3. The critical organ for each radionuclide (thyroid for radioiodine).

4. The most restrictive age group.

Calculation of P.

1

( Inhalation): The following equation will be used to calcu-late I (Inhalation).

P,.

P.I = K A (BR) DFA. 3 (Inhalation) (mrem/yr perpCi/m )

40

4 NfNDHEHT NO. 3 February 1986 where:

K = A constant of conversion, 10 pCi/pCi.

BR = The breathing rate of the child age group, 3700 m 3,/yr.

DFA. The critical organ inhalation dose factor for the child age group for the ith radionuclide in mrem/pCi. The total body is considered as an organ in the selection of DFA,.

The inhalation dose factor for DFA. for the child age group is listed in 1

Table E-9 of Regulatory Guide 1.109, Revision 1, and Table 3-4 of this manual. Resolving the units yields:

9 3 P- = (Inhalation) = (3.7 x 10 )(DFA.) (mrem/yr per pCi/m ) (6)

The P. ( Inhalation) values for the child age group are tabulated in Table 3-4 1

of this manual.

3.4 10 CFR 50 Release Rate Limits The requirements pertaining to 10 CFR 50 release rate limits are specified in Technical Specifications 3.11. 2. 2 and 3.11. 2. 3.

Technical Specification 3.11.2.2 deals with the air dose from noble gases and requires that the air dose at or beyond the site boundary due to noble gases released in gaseous effluents shall be limited to the following:

(a) "During any calendar quarter, .o <5 mrad for gamma radiation and to <10 mrad for beta radiation."

(b) "During any calendar year, to,<10 mrad for gamma radiation and <20 mrad for beta radiation."

NENDHENT NO. 3 February 1986 Technical Specification 3.11.2.3 deals with radioiodines and radioactive mate-rials in particulate form, and requires that the dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas shall be limited to the following:

(a) "During any calendar quarter, to < 7.5 mrem."

(b) "During any calendar year, to <15 mrem."

3.4.1 Noble Gases (Technical S ecification 3.11.2.2)

The air dose at or beyond the site boundary due to noble gases released in the gaseous effluent will be determined by using the following equations.

a. During any calendar quarter, for gamma radiation:

3.17 x '10 g1 II. [{770) 0 +(X/.q) q. + {~) 0. + (X/q) q. ]m5 mrad (8)

During any calendar quarter, for beta radiation:

3.17 x 10 Z1 N I(XII) 0 e

+ (X/q) q + (X7{}) {}. + (X/q) q.

]

< 10 mrad (9)

b. During any calendar year, for gamma radiation:

3.'l7 x 10 g II. (X7I}') 0. + (X/q) q. + (}7{() 0. + (,",/q) q.

]

< 10 mrad,(10)

NENOMENT NO. 3 February 1986 During any calendar year, for beta radiation:

3.17 x 10 Z 1 N (770) (} + (X/q) q + (XT0) (}. + (X/q) q. < 20 mead (11) where:

The air dose factor due to gamma emmissions for each identified noble gas radionuclide., in mrad/yr per pCi/m (M. values are listed in Table 3-1).

1 H = The air dose factor due to beta emissions for each iden-tified noble gas radionuclide, in mrad/yr per pCi/m (H. values are listed in Table 3-1).

1 For ground level release points. The highes calculated annual average rela .ive concentration for area at or beyond the site area boundary for long-term releases 3

(greater than 500 hr/yr). (Sec/m )

(X/q) For ground level release points. The rela ive concentration for areas at or beyond the site area boundary for short-term releases (equal to or less than 500 hr/yr). (Sec/m )

(~A)m For partially elevated release points. The highest calculated annual average relative concentration for areas at or beyond the site boundary for long-term 3

releases (greater than 500 hr/yr). (Sec/m )

(X/q) = 'or partially elevated release points. The relative concentration for areas at or beyond the site boundary for short-term releases (equal to or less than 3

500 hr/yr). (Sec/m )

43

1 NEHDHEHT HO. 3 February 1986 qim The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from the main plant r'elease point, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

q ~ The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal" to or less than 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

Qim The average release of noble gas radionuclides in gaseous releases, i, for long-tenn releases (greater than 500 hr/yr) from the main plant release point, in pCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

Q;g The average release of noble gas radionuclides in gaseous effluents, i, for long-term releases (greater than 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropr iate.

-8 3.17 x 10 = The inverse of the number of seconds in a year.

3.4.2 Radioiodines and Particulates (Technical Specifica ion 3.11.2.3)

The following equation calculates the dose to an individual from radioiodines, radioac.ive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to the unrestricted areas:

0 NENOHENT HO. 3 February 1986

~

a.~ During any calendar quarter:

3.17 x 10 Z R M0. + w q. + M 0. + w q. < 7.5 mrem I

b. During any calenda'r year:

r (13) 1 where:

The releases of radionuc1ides, radioactive materiais in particulate form, and radionuclides other than noble gases in gaseous effluents, i, for long- erm releases greater than 500 hr/yr, in pCi. Releases shall be cumu-lative over the calendar quarter or year,. as appropriate (m is for mixed mode releases, g is for ground level releases).

lm'g The releases of radionuclides, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents, i,. for short,-term releases equal to or less than 500 hr/yr, in I Cie Releases shall be cumulative over the calendar quarter or year as appropriate (m is for mixed mode releases, g is for ground level releases).

NEHDMEHT HO. 3 February 1986 The dispersion parameter for estimating the dose to an individual at the controlling location for long-term

( ) 500 hr . ) releases (m is for mixed mode releases, g is for ground level releases).

3 M = (Xg) for the inhalation pathway, in sec/m .

M = (Vjg) for the food and ground plane pathways in meters The dispersion parameter for estimating the dose to an individual at the controlling location for short-term

(( 500 kr.) releases (m is for mixed mode releases, g is for ground level releases).

3 w, = (77q) for the inhalation pathway, in sec/m .

w = (U7q) for the food and ground plane pathways in meters 3.17 x 10 = The inverse of the number of seconds in a year.

R.

1

= The dose factor for each identified radionuclide, i, in 3

m (mrem/yr per pCi/sec) or mrem/yr per pCi/m .

46

AMENDMENT NO. 3 1986 'ebruary 3.4.2.1

~ ~ ~ Dose Parameter for Radionuclide i (R,.)

The R. values used in equations 12 and 13 of this section are calculated 1

separately, or each of the following potential exposure pathways:

o Inhalation Ground plane contamination Grass-cow/goat-milk pathway Grass-cow-meat pathway Vegetation pathway Monthly dose assessmen.s for NHP-2 gaseous effluent will be done for all age groups.

Calculation of R.

1 (Inhalation Pathway Factor)

R.

I (Inhalation) = K1 (BR) (DFA.) (mrem/yr per qCi/m 3

) (14) 1 where:

R ~ The inhalation pathway factor (mrem/yr per pCi/m 3 ).

Y1 A constant of unit conversion, 10 pCi/pCi.

The breathing rate of the receptor of age group (a) in meter 3 /yr. (Infant = 1400, child = 3,700, teen = 8,000, adult = 8,000. From P.32 NUREG-0133).

47

NENDtlEilT HO. 3 February 1986 (DFA,. ) The maximum organ inhalation dose factor for receptor of age group (a) for the ith radionuclide (mrem/pCi). The ia'a total body is considered as an organ in the selection of (DFAi )

. (DFA.) values are listed in Tables E-7 through E-10 of Regulatory Guide 1.109 manual, Revision

1. Values of R. are listed in Table 3-5.

1 G

Calculation of R. (Ground Plane Pathway Factor)

R,. (Ground Plane) = K K (SF)(DFG,.) (1-e )/A,. (m x mrem/yr per pCi/sec) (15) where:

2 R. = Ground plane pathway factor (m x mrem/yr per pCi/sec).

1 A 6 K = A conversion constant of (10 pCi/pCi).

K A conversion constant - (8760 hr/yr).

1 The decay constant for the ith radionuclide (sec ).

Exposure time, 4.73 x 10 sec (15 years).

DFGi The ground plane dose conversion factor for the ith radio-nuclide, as listed in Table E-6 of Regulatory Guide 1.109, 2

Revision 1 {mrem/hr per pCi/m ).

SF = Shielding Factor (dimensionless) 0.7 i, building is present, as suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.

NENDMEHT NO. 3 February 1986 (DFL,.), The maximum organ inges ion dose factor for the ith radio-nuclide for the receptor in age group (a), in mrem/pCi (Tables E-ll to E-14 of Regulatory Guide 1.109, Revision 1).

The decay constant for the ith radionuclide, in sec The decay constant for removal of activity on leaf and

-7 -1 plant surfaces by weathering, 5.73 x 10 sec (cor-respon'ding to a 14-day half-life).

The transport time from pasture to animal, to milk, to recepto~, in sec.

The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec.

fp Fraction of the year that the cow/goat is on pasture (dimensionless).

Fraction of the cow/goat feed that is pasture grass while the cow is on pasture (dimensionless).

The input parameters used for calculating R. are 1

listed in Table 3-6 and the R.

1 values are tabulated in Table 3-7.

or Tritium

In calculating R, pertaining to tritium in mil', the airborne concentration rather than the deposition will be used:

R (Grass-Cow/Goat-llilk Factor ) =

T AC 0.75(0.5/H) (mrem/yr per uCi%n )

3 (17)

K K F gFU (DFLi) 50

NENDHEt)T i90. 3 February 1986 tf = The transport time from pasture to receptor, in sec.

th = The transport time from crop field to recepto'r, in sec.

The input parameters needed for solving equation 18 are listed in Table 3-7.

For Tritium:

In calculating the RT for tritium in meat, the airborne concentration is used rather than the deposition rate. The following equation is used to calculate the R values for tritium:

R'Grass-Cow-Heat Pathway) =

T K~K FfgFUa (DFL,-)a 0.75(0.5/H) (mrem/yr per p.Ci/m ) (19)

Mhere the terms are as defined in equations 16-18, R. values for tritium pertaining to the infant age group is zero since there is no meat consumption by this age group.

V Calculation of R.

1 (Vegetation Pathway Factor )

Y Pathway Factor) =

i (Vegetation R.

K I

v 1 w (DFL )

aL 'g (20) 2 (m x mrem/yr per >Ci/sec)

AMENDMENT NO. 3 February 1986 RT (Vege ation Pathway Fac.or) =

K K U fL + U f (DFL.) 0;75(0.5/H) (mrem/yr per uCi/m ) (21)

Where all terms have been defined above and in equations 15-18, the R.V value 1 for tritium is zero for the infant age group due to zero vegetation consump-tion rate by that age group. The input parameters needed for solving equations 20 and 21 are listed in Table 3-8.

3.4.3 Annual Doses At S ecial Locations The Radioactive Effluent Release Report submitted within 60 days after January 1 of each year shall include an assessment of the radiation doses from radio-active gaseous effluents to, "Members of the Public", due to their activities inside the site boundary during the report period.

Annual doses wi thin the site boundary have been determined for several loca-tions using the NRC GASPAR computer code and source term data from Table 11.3-7 of the FSAR. These values are listed in Tables 3-16 and 3-17. Of the locations listed within the site boundary, only two, the DOE Train and WNP-2 Visitor Center are considered as being occupied by a "Member of the Public".

Annual doses to the maximum exposed "Member of the Public" shall be determined for an individual at the ANP-2 Visitor Center based on occupancy of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per year due to it being the higher of the two locations.

3.5 Cpm liance with Standard Technical Specification 3.11.2.4 Standard Technical Specification 3.11.2.4 states:

"The GASEOUS RADWASTE REA7ilENT SYSTEM shall be in opera-tion in either the normal or charcoal bypass mode. The charcoal bypass mode shall not be used unless the offgas post-trea nent radiation monitor is OPERABLE as specified in Table 3.3.7.11-1."

"APPLICABILITY: Whenever the main condenser steam jet air P

NEHDNENT NO. 3 February 1986 Prior to placing the Gaseous Radwaste Treatment System in the charcoal byoass mode, the alarm setpoints on the main plant vent release monitor shall be set to account ,or the increased percentages of short-lived noble gases. Noble gas percentages shall be based either on actual measured values or on primary coolant design base noble gas concentration percentages adjusted for 30-minute decay. Table 3-15 lists the percentage values for 30-minute decay.

3.6 Calculation of Gaseous Effluent Monitor Alarm Setpoints 3.6.1 Introduction The following procedure used to ensure that the dose rate in the unrestricted areas due to noble gases in the NNP-2 gaseous effluent do not exceed 500 54a

NENDNENT HO. 3 February 1986 mrem/yr to the whole body or 3000 mrem/yr to the skin. The initial setpoints determination is calculated using a conservative radionuclide mix obtained from the WNP-2 GALE code. Once the plant is operating and sufficient measur-able 'process fission gases are in the effluent, then the actual radionuclide mix will be used to calculate the alarm setpoint.

3.6.2 Set oint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on an instantaneous noble gas dose rates. A monthly analysis of radioiodines and radionuclides in particu-late form will be performed to ensure compliance with 10 CFR 20 and 10 CFR 50 Appendix I limits. The three release points will be partitioned such that their sum does not exceed 100 percent of the limi . Originally, the setpoints will be set at 40 percent for the reactor building, 40 percent for the turbine building and 20 percent for the radwaste building. These percentages could vary at the plant discretion, should the operational conditions warrant such change. However, the combined rel eases due to variations in the setpoints will not result in doses which exceed the limit stated in technical specifica-ion. 8oth skin dose and whole body setpoints will be calculated and the lower limit will be used.

3.6.2.1 Set pints Calculations 8ased on Whole 8ody Dose Limits The fraction ( i) of the total gaseous radioactivity in each gaseous effluent release path (j ) for each noble gas radionuclide i will be determined by using he following equation:

C..

(dimensionless) (22)

J wher e:

C..

1J

= The measured individual concentration of radionuclide i in the gaseous effluent release path j (pCi/cc).

NEHDHENT HO. 3 February 1986 C

The measured total concentration of all noble gases identified in the gaseous effluent release path j (qCi/cc).

Based on Technical Specification 3.11.2.1, the maximum acceptable release rate o all noble gases in the gaseous effluent release path j is calculated by using the following equation:

Fj 500 m (qCi/sec) (23)

X/Qj Zi =1 (K,)( ~,j) where:

QT>

= The maximum acceptable release rate (I Ci/sec) of all noble gases in the gaseous effluent release path j (I Ci/cc).

Fj = Fraction of total dose allocated to release path j.

500 = Whole body dose rate limit of 500 mrem/yr as specified in Tech-nical Specification 3.11.2.la.

X/Q. Maximum normalized diffusion coefficient of effluent release path j at the site boundary (sec/m ). Turbine Building and Radwaste Building values are based on average annual ground level values. Main plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release.

K.

1

= The total whole body dose factor due to gamma emission from 3

noble gas nuclide i (mrem/yr per IiCi/m ) (as listed in Table B-l of Regulatory Guide 1.109, Revision 1).

56

OiEHDMENT 'l0.

February 1986 defined in equation 22.

ij As m = Total number of radionuclides in the gaseous effluent.

Oifferent release pathways.

The total maximum acceptable concentration (CT.) Tj of noble gas radionuclides j

in. the gaseous effluent release path (pCi/cc) will be calculated by using the following equation:

CT.

Tj

=

~

QTj

(~Ci/cc) (24) where:

CT.

Tg

= The total allowed concentration of all noble gas r adionuclides in the gaseous effluent release, path j (I Ci/cc).

QT.

Tj

. The maximum acceptable release rate (pCi/sec) of all noble gases in the gaseous effluent release path j. !

R- = Tne effluent release rate (cc/sec) at the point of release.

J iA of noble gas To determine the maximum acceptable concentration (C.A) radio-nuclide i in the gaseous effluent for each individual noble gas in the gaseous effluent (pCi/cc), the following equation will be used:

C,

= ..CT. (pCi/cc) (25) 57

ANEHDHEHT HO. 3 February 1986 where:

gT>

= The maximum acceptable release rate of all noble gases in the gaseous effluent release path j in >Ci/sec.

X/gj = The maximum annual normalized diffusion coefficient for release 3

path j at the site boundary (sec/m ).

F. = Fraction of total allowed dose.

J L. The skin dose factor due to be a emission for each identified 3

noble gas radionuclide i in modem/yr per pCi/m (L.1 values are listed in Table 3-1).

The air dose factor due to gas+a emmissions for each identified noble gas radionuclide, in mrad/yr per I Ci/m (M. values are listed in Table 3-1).

1.1 = A conversion factor to convert dose in mrad to dose equivalent in mrem.

3000 = Skin dose rate limit of 3000 mrem/yr as specified in Technical Specification 3.11.2.1.

le 3-1 DOSE FACTORS FOR NOBLE GASES ANO DAUGIITERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K~ L- /.1. Ni Radionuclide (mrem/yr per ~,Ci/m ) (mrem/yr per uCi/m ) (mrad/yr per nCi/m ) (mrad/yr per pCi/m )

Kr-85m 1.17E+03"* 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E~01 1.34Et03 1.72E+01 1.95E<03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E~04 2.37Et03 1.52E404 2.93Ew03 Kr-89 1.66E+04 1.01E+04 1.73&04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E<04 7.83E+03 Xe-131m 9.15E401 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E<02 9.94E+02 3.27E<02 1.48E+03 XQ-133 2.94E+02 3. 06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39Ew02 Xe-.135 1.81E+03 1.86E+03 1.92E<03 2.46E+03 Xe-137 1.42E403 1.22E+04 1.51E<03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E<03 2.69E<03 9.30E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

fD Z cr m 7.56 x 10 2.

s

+7.56E-02 = C Ql D

The values listed above were taken from Table B-l of NRC Regulatory Guide 1.109, Revision 1. The values 6 -1 were multi plied by 10 to convert picocuries to microcuries

PJ1EHDMEHT NO. 3 February 1986 Table 3-4 DOSE RATE PARNETERS IMPLEMENTATION OF 10 CFR 20, AIRBORNE RELEASES Child Dose Factor* PI 1

A 0 G.

~

Inhalation mrem/hr mrem/yr Nuclide sec ~mrem/ Ci pCi/m SCi/m H-3 1.8E-09 3.0E-07 0.0 1.1E+03 I-131 1.0E-06 4.4E-03 3.4E-09 1.6E+07 I-133 9.2E-06 1. OE-03 4.5E-09 3.7E+06.

Cr-51 2.9E-07 4. 6E-06 2.6E-10 1.7E+04 iMn-54 2.6E-08 4. 3E-04 6.8E-09 1.6E+06 Fe-55 8.5E-09 3.0E-05 0.0 1.1E+05 Fe-59 1.8E-07 3.4E-04 9.4E-09 1.3E+06 Co-58 1.1E-07 3.0E-04 8 2c 09 1.1E+06 Co-60 4.2E-09 1.9E-03 2.0E-08 7.0E+06 Zn-65 3.3E-08 2.7E-04 4.6E-09 1.0E+06 Sr-89 1.5E-07 5.8E-04 6.5E-13 2.2E+06 Sr-90 7.9E-10 2.7E-02 2 6E-12** 1.0E+08 Zr-95 1.2E-07 6.3E-O4 5.8E-09 2.3E+06 Ho-99 2. 9E-06 3.7E-05 2.2E-09 1.4'E+05 Cs-134 1.1E-08 2.7E-O4 1.4E-08 1.0E+06 Cs-137 7.3E-010 2.5E-04 4.9E-09 9.3E+05 Ba-140 6.3E-07 4.7E-04 2.4E-09 1.7E+06 Ce-141 2.4E-07 1.5E-04 6.2E-10 5.4E+05 Ce-144 2.8E-08 3.2E-03 2.5E-09 1.2E+07

Maximum Organ

~Ho data is listed for Sr-90 in Table E-6 of Regulatory Guide 1.109, Revi-sion 1. Y-90 valves were used for dose conversion fac.or Sr-90.

63

Table 3-5a DOSE RATE PhRAtlfTERS--1HPLEHBITATIOW OF 10 CFR 50 A)RDORtif RELEASES hge Group: infant Dose Parameters (Haximum Qr an)

Ii~aat on Cr~cun H)T ow 01% goaK)

'i ql R' R' RC i

A-1 2 2 HIclide sec mrem/ r m x mrem/ r (IaCi/m ) (IIC(/sec) (I>C(/sec ) (I,C i/sec )

H-3 1.8E-9 6.5E42 0.0 3.4E43 7.DE+3 1-131 1.0E-6 1.5E 47 1.0E47 2.4E411 4.3E411 1-133 9.2f -6 3.6E46 1.5E46 2.2E49 4.0E49 Cr-51 2.9E-7 1:3E44 5.5E46, 2.0E46 3.5E45 Fe-55 8.5E-9 8.7E44 0.0 7.0E4-7 7.1E46 Fe-59 1.8F.-7 1.0E46 3.2E48 1.7E48 3.2E47 2.0E47 . 2.9E46 Hn-54 2.6E-O 9.9E45 1.6E49 Co-58 1.1E-7 7.8f45 4.4E40 2.8E47 4.5546 Co-60 4.2E-9 4.5E46 2.5E410 1.1E48 1.4E47 Sr-89 1.5E-7 2.OEI6 2.5E44 5.6EI9 1.6E410 Sr-90 7.9E-10 4.1E47 8.9E46* 7.lf410 1.7E411 Ho-99 2.9E-6 1.3f 45 4.7E46 1.6E48 2.4E48 Cs-134 1.1E-D 7.0E45 D.OE49 3.6E410 1.3E411 Cs-136 5.9E-7 5.6EI4 1.7E48 2.6E49 1.2E410 Cs-137 7.3E-10 6.1E45 1.2E410 3. 4E 410 1.2E411 Da-140 6. 3f-7 1.6E46 2.3E47 f 1.1 48 1.9Eil IO 2.4f-l 5.2E45 1.5E47 3.6E47 6.2E46 cr m Ce-141 1.1E48 6.0f 47 D Ce-144 2.8E-D 9.8E46 O.OE47 4 m

'iio data is listed for Sr-90 in Table E-6 of Regulatory'uide 1.109, Revision l.

Y-90 values were used for the dose conversion factor for Sr-90. IC) ~r CO ch O

Tahle 3-5h DOSE RAlf PARAIIETERS--IHPLBIfIITATIOIIOF 10 CFR 50 AlROORHE RfLEASES Age Group: Child Dose Parameters (IIax(aem Ori an)

Tnlia I a tTnn C~rouni H(l):TCoM) l61F7 oat ccctal~as I@~a R RC R R" I/sec RH I

R'ucl 2 2 2 2 2 I de sec nrem/vr ai x mrem/ r (iCI/si ) (i,C I/sec ) (nCI/sec) (wCI/sec) (qCI/sec) (i,C )

It-3 1.GE-9 1.lfi3 0.0 2.3ft3 4.6E<3 5.6E+3 3.4E~2 I-13l 1.0E-6 1.6E>7 1.0E47 9.9E+10 1.8E 411 1.1ftl0 1.3fig I-133 9.2E-6 3.8E i6 1.5fi6 9.2fiG 1.7Ei9 la7E~O 3.Offal Cr-51 2.9E-7 1.7Ei4 5.5ft6 2.3Ei6 4.1E~5 5.3fi6 2.DE~5 Fe-55 8.5E-9 l.lft5 0.0 5.Of<7 9.1fi6 3.9fiO 2.4fiG FQ-59 1.GE-7 1.3fi6 3.2E~O 9.0fi7 la6E~7 6.0EiG 2.8fiG Iln-54 2.6E-G 1a6E46 la6fi9 l.1 fi7 1.6fi6 6,3EiO 4.lfi6 Co-58 1. IE-7 1.1E i6 4.4ENG 3.2fi7 5.2fi6 3.4E>G 4.4E+7 Co-60 4.2E-9 7.1E~6 2. 5E i10 1.3EiG 1.8fi7 2.0E49 2.1EiG Sr-89 1.5E-7 2.2Ei6 2.5E>4 3.0fig 8.6Ei9 3.3Ei10 2.2E~G Sr-90 7.9E-10 I.OE>8 8.9fi6" 6.5fi10 1.6f~ll 1.3E i12 6.1fig Ilo-99 2.9E-6 1.4E45 4.7Ei6 G.GE i7 1.3EiO 7.0fi6 1.3E45 Cs-134 1.1E-G 1.0Ei6 G.DE~9 2.Of>10 7.Of<10 2.5fil0 7.9EiG Cs-136 5.9E-7 1.7Ei5 1.7EWG 1.2E~9 5.6fig 1.5EWG 2.0fi7 Cs-137 7.3E-10 9.If<5 1.2ftl0 1.8ftl0 6.4fil0 2.4E~IO 7.5E<8 in Ga-140 6.3E-7 1 7fi6 2.3E~7 5,2fi7 9.4E<6 1.8E>G 2.DE<7 CT Pl

~ s 1.6fi7 6.2fi6 O Ce-141 2.4E-7 5.4Ei5 3.6E i7 3.6E~G 6.0E46 ni ivl Ce-144 2.8E-G 1.2E47 O.Oft7 4.0EEG 5.9E+7 9,5E i9 9.5Ei7 "Ilo data Is listed for Sr-90 In Tahle E-6 of Regulatory Guide 1.109, Revlslon l. 00 Ch O

Y-90 values iiere used for the dose conversion factor for Sr-90. a

~ ~

Table 3-Sc DOSE RATE PARAIIETFRS>>-IHPLIflfHTATIONOF 10 CFR 50 AIRGORIIE RELEASES Age Group: Teen I tuel I de st R'res/yr 2 roood RG I

2 R'C Dose Parameters ltitk 1~oar (Max(mua Organ) 1llTETCoat) 2 :

Vesta a i1~s 2

R 2

ket I

tata/o,t (PCI/sec) (qCI/sec) (nCI/sec) (PCI/sec) (ktCI/sec)

II-3 1.8E-9 1.3E~3 0.0 1.4E03 2.9E~3 3.5fi3 2.8E+2 1-131 I.OE-6 I.SE47 I,DE<7 S.lfilO 9.1ftIO 7.0fa9 8.4fi8 I-133 9.2E-6 2.9E~6 1.Sf~6 3.9E~G 7.0Ei8 9.4ftl I.lfol Cr-51 2.9E-7 2.)E~4 S.Sf<6 3.6&6 6.4E<5 G.SE i6 4.IE45 Fe-5S 8.5E-9 Ie2fi5 0,0 1.6fwl 3.6fi6 3.0fiG 8.8ft7 Fe-59 1.8E-7 1.5ft6 3.2E<8 1.3fiG 2.3fi7 8.7E~G 5.2E~G Hn-54 2.6E-G 2.0E>6 1.6fig 1.5Eil 2. 2E<6 3.7E<G 7.4E46 Co-58 I.IE-7 1.3fk6 4.4fiG S.OE47 G.lfi6 5.4fiG G.gfil Co-60 4.2E-9 8.7E<6 2.5filO 2.0ft8 2.8E>7 3.If<9 4.If~8 Sr-89 1.5E-7 2.4fi6 2.5fi4 1.2fi9 3.5fi9 1. 3E410 1.1E+8 Sr-90 7.9E-IO I.IEiG G,gfi6+ 3.8E>10 9.4ft)0 7.9ftll 4.7ft9 Ho-99 2.9E-6 2.7f<5 4.7fi6 5.2Et7 7.8fi7 5.5ft6 1.DE+5 Cs-134 l.lf-8 5.5E iS G.DE<9 I.2E410 4.4fil0 1.SERIO 6.5E48 Cs-136 5.9f-7 1.9E+5 1.7E48 7,9ftG 3.5fig I.DE<10 1.6E~7 Cs-137 7.3E-10 G.Sf<5 I ~ 2E410 1.0E>10 3.5fil0 1.3E4}0 5.4E~G Ga-140 6.3E-7 2.0fk6 2.3fi7 3.3E+7 6.0ft6 1.2f<8 1.6E~7 Ce-141 2.4f-l 6.If~5 1.6fi7 4.4E+7 7.7E<6 4.6E~G 9.8E i6 Ce-144 2.GE-G 1.3E~7 8. DE~7 5.0fiG 7.4E+7 1.2E<10 1.6E+8

'IIo data Is 1Isted for Sr-90 In Table E-6 of Regulatory Guide 1.109, Rev. l.

Y-90 values were used for the dose conversion factor for Sr-90.

Table 3-5d DOSE RATE PARAMETERS IIIPI.BIFIITATIO)IOF 10 CFR 50 AIRDGRIIE RELEASES Age Group: Adult Dose Parameters (Maxlraaa Or an) roooil ost~ov HllrT a ege aQes I' C I

R" RH A 1 a' 2 csrea/ r Mucl lde sec R',"I/n (4$ I/sec) iacf/see)

R'nCI/sec)

) (>@I/sec) (uCI/sec)

II-3 1.8E-9 1.3f 43 0.0 1.1E43 2.2E43 3.0E43 4.7E42 I-'131 1.0E-6 1.2E47 1.0E47 3.2E410 5.7E410 8.2E49 1.2E49 1-133 9.2E-6 2.2f46 1.5E46 2.3E48 4.1E48 1.1 f48 2.2E41 Cr-51 2.9E-7 1 ~ 4F44 5.5E46 3.1E46 5.5E45 8.7E46 7.7f45 Fe-55 8.5E-9 .7.2E44 0.0 1.3E47 2.0E46 1.8E48 1,5E48 Fe-59 1.8E-7 1.0E46 3.2E48 1.0E48 1.9547 O.OE48 9. 2E40 Mn-54 2.6E-O 1.4E46 1.6E49 1.3E47 1.9E46 8.5E40 1.4E+7 Co-58 1 .lf-7 9.3E45 4.4E48 4.4547 7.1E46 5.3E48 1.7E48 Co-60 4.2E-9 6.DE<6 2.5E410 1.7E48 2.4E47 2.9f49 7.6E48 Sr-89 1.5E-7 1.4E46 2.5E44 6.5E48 1.9E49 8.2E49 1.3E48 Sr-90 7.9E-10 9.9E47 8.9E46>> 2.7E410 6.7E410 6.2E411 7.2f 49 Mo-99 2.9E-6 2.5E45 4.7E46 2.9E47 4.4f47 6.QE46 1. 2E45 Cs-134 1.1E-O 8.5E45 O.OE49 7.0E49 2.5E410 9.9E49 8. 2E48 Cs-136 5.9E-7 1.5fc5 1.7f48 4.6E48 2.1E49 9.0E47 2.1E+7 Cs-137 7.3E-10 6.2f 45 1 ~ 2E410 5.6E49 1.5E410 8.3E49 6.7E40 cn Da-140 6.3E-7 1. 3E46 2.3E47 2.5E47 4.4E46 1.4E48 2.6E47 cr m s

Ce-141 2.4F.-7 3.6fc5 1.5E47 3.3E47 5.7E46 4.0f 48 I.6E+7 c Cu D

Ce-144 2.8E-O 8.6E47 O.OE47 3.7E48 5.4E47 1. OE410 2.5E48 s m

'Ho data Is listed for Sr-90 In lable E-6 of Regulatory Guide 1.109, Revlslon 1: OO O Y-90 values were used for tbe dose conversion factor for Sr-90. ch

AMENDMENT NO. 3 February 1986 Table 3-6 INPUT PARNETERS FOR CALCULATING R.

Parameter Value Tabl e*

r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 F (days/liter) Each stable element E-1 U

ap (liters/yr) Infant 330

-Child 330 E-5

--Teen 400

--Adult 310 (DFL,. ) (mrem/pCi ) Each radionucl ide E-11 to E-14 Yp (kg/m ) 0.7 E-15 Y (kg/m ) 2.0 E-1 5 tf (seconds) 1.73 x 10,. (2 days) E-15 5'.78 6

th (seconds) x 10 (90 days) E-15 gF (kg/day) 50 for cow 6 for goat E 3 fs (dimensionless) 1.0 NUREG-0133 fp (dimensionless) 0.5 for cow Site speci fic 0.75 for goat Site specific

Of Regulatory Guide 1.109, Revision 1 unless stated otherwise.

68

AMENDMENT NO. 3 February 1986 Table 3-7 INPUT PARNETERS FOR CALCULATING R ~

Parameter Value Table*

r (dimensionless ) 1,0 for radioiodine E-1 5 0.2 for particulates E-15 Ff (days/kg) Each stable element E-1 U

ap (kg/yr) Infant 0 E-5 Chil d 41 E-5 Teen 65 E-5 Adul t 110 E-5 (DFL,.) (mrem/pCi) Each radionuclide E-11 to E-14 Y (kg/m ) 0.7 E-15 P

Y (kg/m ) 2.0 E-15 6

tf (seconds) 1.73 x 10 (20 days) E-15 th (seconds) 7.78 x 10 6 (90 days) E-15

()F (kg/day) 50 E-3

Of Regulatory Guide 1.109, Revision 1.

69

4 i

NENDHENT NO. 3 February 1986 Table 3-8 INPUT PARAMETERS FOR CALCULATING Ri Parameter Yalue Table~

r (dimensionless ) 1.0 for radioiodine E-1 0.2 for particulates E-1 (DFL,.)a (mrem/pCi) Each radionuclide E-11 to E-14 U

L a

(kg/yr ) Infant 0 E-5

->>Child 26 E-5 Teen 42 Adul t 64 E-5 U

a (kg/yr) Infant 0 Chil d 520 Teen 630 E-5

--Adul t 520 E-5

( di mens ionl ess ) Site speci fic (de faul t = 1.0) E-5 fg (dimensionless) Site specific (default =*

0.76) RG 1.109, p 28 tL seconds 8.6 x 10 4" (1 day) E-15 th (seconds) 5.18 x 10 6 (60 days)

Y(kg/m ) . 2.0 E-15

Of Regulatory Guide 1.109, Revision 1.

70

AMENDMENT NO. 3

~.

February 1986 Table 3-9 INPUT PARAMETERS NEEDED FOR CALCULATING DOSE TO THE MAXIMUil INDIVIDUAL FROM ANP 2 GASEOUS EFFLUENT In ut Parameter Value Reference*

,Distance to Maine (miles) 3000 Ref 1 Fraction of year lea y vegetables are grown 0. 42 Ref 2 Fraction of year cows are on pasture 0.5 Ref 2 Fraction of crop from garden 0.76 Pef 3 Fraction of daily intake of cows derived from pasture while on pasture 1.0 Ref 3 Annual average relative humidity ( ) 53.8 Ref 4 Annual average temperature (Fo) 53. 0 Ref 5 Fraction of year goa.s are on pasture 0. 75 Ref 2 Fraction of daily intake of goats

~

derived from pasture>>hile on pasture

~ ~

1.0 Ref 2 Fraction of year beef cat.le are on pasture 0.5 Pef 2 Fraction of da ily intake of beef cattle derived from pasture while on pasture 1.0 Ref 2 Population within 50 miles of plant and the year that the population is used 336,115 (year 2000) Ref 6 Annual 50-mile milk production (liters/yr ) 9.91E+06 Refs 7 & 9 Annual 50-mile meat production (kg/yr) 3.54E+06 Refs 6, 7, & 9 Annual 50-mile vegetable production (kg/yr) 2.0E+07 Refs 6, 7, & 9 Source terms Ref 8 71

NENDtlENT NO. 3 February 1986 Table 3-9 (contd.)

In ut Parameter Yalue Reference X/g values by sector for each dis-tance [recirculation, no decay) See Tables 3-11 (sec/m~) through 3-12 Ref 10 X/9 values by sector for each dis-tance (recirculation, 2.2$ days See Tables 3-11 decay, undepleted) (sec/m~) through 3-12 Ref 10 X/g values by sector for each dis-

, tance (recirculation, 8 0 days See Table 3-11 decay, depleted) (sec/m ) through 3-12 Ref 10 0/g values by sector for each dis- See Table 3-11 tance (1/m2) through .3-12 Ref 10

References are listed in Table 3-. 14.

72

NEHDHEHT NO. 3 February 1986 Table 3-14 REFERENCES FOR VALUES LISTED IH TABLE 3-9 Reference 1 U.S. Map Reference 2 Site Specific Reference 3 Regulatory Guide 1.109, Revision 1, Table E-15 Reference 4 Section 2.3, WNP-2 FSAR, Table 2.3-20 Reference 5 Section 2.3, MHP-2 FSAR, page 2.3-3 Reference 6 Keith E. Yandon, October 1980, "Projections and Distributions of Population Within a 50-Nile Radius of Washington Public Power Supply System Huclear Projects Hos. 1, 2, and 4 by Ccmpass Direction and Radii Intervals," 1970-2030 Ref rence 7 WHP-2 EP., Table 5.2-12 Reference 8 WNP-2 Effluent Analysis for Applicable Time Period Reference 9 Radiological Programs Calculation Log Ho. 83-1 Reference 10 MNP-2 XO(}000 Computer Run

NEHDNENT NO. 3 February 1986 TABLE 3-16 ANNUAL DOSES AT SPECIAL LOCATIONS WITHIN MNP-2 SITE BOUNDARY Source: WNP-2 Gaseous Effluent, (Miles) Whole Thyroi d Distance Occupancy Body Dose Dose Location (hrs/yr) (mrem/ r) (mrem/yr )

BPA Ashe Substation 0.5 N 2080 1.7E+00 DOE Train 0.5 SE* 78 '.1E+006.7E-02 1.0E-01 Mye Burial Site 0.5 MHM 4.1E-03 6,5E-03 MNP-1 1.2 ESE 2080 3.8E-02 1.3E-01 MNP-4 1.0 ENE 2080 7.0E-02 1.1E-01 MNP-2 Yisitor Center 0-.08 ESE 8.6E-02 1.3E-Ol Taylor Flats~ 4.2 SE 8760 3.1E-02 5.2E+00 Site Boundary~ 1.2 SE 8760 1.1E+00 1.7E+00

The sector with the highest X/g values (within 0-0.5 mile radius) was used.

~Hot within site boundary. Closest residental area representative of maximum individual dose from p1ume, ground, ingestion, and inhalation exposure pathways. Included for comparison.

~Assumed continuously occupied. Actual occupancy is very low. Doses from Inhalation and Ground Exposure pathways. No food crops.

NENDMENT NO. 3 February 1986 TABLE 3-17 ANNUAL OCCUPIED AIR DOSE AT SPECIAL LOCATIONS Hi (l - S BOUN AR Annual Annual Beta Air dose Gamma Air Dose Location (mrad) (mrad)

BPA Ashe Substation 8.9E-01 1.5E+00 DOE Train 5.3E-02 9.2E-02 Wye Burial Site 3.2E-03 5.7E-03

'fNP-1 3.3E-02 2.8E-02 WNP-4 5.3E-02 8.5E-02 WHP-2 Visitor Center 7.0E-02 1.2E-01 Taylor Flats~ 2.3E-02 1.4E-02 Site Boundary 8.7E-01 1.5E+00

Not within site boundary. Closest residential area. Included for comparison.

89

4 '

0

AMENOMEHT NO. 3 February 1986 4.0 COMPLIANCE MITH 40 CFR 190 4.1 Technical S ecification Re uirement Technical Specification 3.11.4 states, "The annual (calendar year) dose or dose commitment to any Member of the Public, due to release of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

4.2 ODCM Methodolo for Oeterminin Dose and Dose Commitment from Uranium Fuel Cycle Sources The annual dose or dose commitment to a Member of the Public for the uranium fuel cycle sources is determined as:

a) Dose to the total body due to the release of radioactive materials in liquid effluents.

b) Dose to any or gan due to the release of radioactive materials in liquid effluents.

c ) Air doses due to noble gases released in gaseous effluents.

d) Dose to any organ due to the release of radioiodines, tritium and radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents.

e) Dose due to direct radiation from the plant.

AMENDMEHT HO. 3 February 1986 The annual dose or dose commitment to a Member of the Public from the uranium fuel cycle sources is determined whenever the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceed twice the limits in Technical Specification 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b. Direct radiation measurements will also be made to determine if the limits of Specification 3.11.4 have been exceeded.

4.2.1 Total Dose from Liquid Effluents The annual dose to a Member of the Public from liquid effluents will be determined using NRC LADTAP computer code, and methodology presented by quation (5) in Sec ion 2.4. It is assumed that dose contribution pathways to a Member of the Public do not exist for areas wi thin the site boundary.

4.2.2 Total Dose from Gaseous Effluents The annual dose to a Member of the Public from gaseous effluents will be determined using HRC GASPAR compu .er code, and methodology presented by equations (10), (11) and (13) in Section 3.4. Appropriate atmospheric dispersion parameter s will be used.

4.2.3 Direct Radiation Contribution The dose to a Member of the Public due to direct radiation from the reactor plant will be determined using thermoluminescent dosimeters (TLDs). TLDs are placed at sample locations and analyzed as per Table 5-1.

TLD stations 1S-16S are special interest sta ions and will not be used for direct radiation dose determinations to a Member of the Public.

9la

AMEHDMEHT HO. 3 February 1986 Radiological environmental monitoring activities implemen.ed by PPM 1.11.1 "Radiological Environmental Monitoring Program (REMP) Implementation Proce-dure", as detailed in the following sections, meet or exceed the criteria of the REMP plan as speci ied by Plant Technical Specifications, 3/4.12.

5.1 Radiolo ical Environmental Monitoring Pro ram (REMP)

Environmental samples for the REMP are collected in accordance with Table S-l. This table provides a detailed outline of the environmental sampling plan including both Technical Specification and non Technical Specification items by sample type, sample location code, sampling and collection frequency, and type and frequency of analysis of samples collected within exposure path-way. Deviations from the sampling frequency detailed in Table 5-1 may occur due to circumstances such'as hazardous conditions, malfunction of automatic sampling equipment, seasonal unavailability, or other legitimate reasons.

'Ahen sample media is unobtainable due to equipment malfunction, special actions per program instruction shall be taken to ensure that corrective action is implemented prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing speci-men. All deviations from the sampling plan Technical Specification items detailed in Table 5-1 shall be documented and reported in the Annual Radio-logical Environmental Operating Report in accordance with PPM 1.10.2, "Routine or Periodic Reports Required by Regulatory Agencies", Regulatory Guide 4.8 and BTP.

in the event that it becomes impossible or impractical .o continue sampling a media of choice at currently established location(s) or time, an evaluation shall be made to determine a suitable alternative media'and/or location to provide appropriate exposure pathway evaluations. The evaluation and anv sub-stitution made shall be implemented in the sampling program within 30 days of identification of the problem. All changes implemented in the sampling pro-gram due to unavailability of samples shall be fully documented in the nex.

Semiannual Radioactive Effluent Release Report and ODCM per PPM 1.10.1, "Reportable Events and Occurrences Required by Regulatory Agencies". Revised sampling plan table(s ) and figure(s ) reflecting the new locations and/or media shall be included with the documentation.

93

NENDHENT NO. 3 February 1986 MNP-2 sampling stations are described in Table 5->. Each station is identi-fied by an assigned number or alphanumeric designation, meteorological sector (16 different, 22-1/2'ompass sections) in which the station is located, and radial distance from NNP-2 containment as estimated from map positions. Also included in Table 5-2 is information identifying the type(s) of samples col-lected at each station and whether or not the specific sample type satisfies a Technical Specification criteria. Figures 5-1 and 5-2 depict the geographical locations of each of the sample stations listed in Table 5-2.

5.2 Land Use Census A land use census shall be conducted in accordance with the requirements of Plant Technical Specifications. Field activities pertaining to the land use census (LUC) will be initiated during the growing season and completed no later than September 30 each year. The information obtained during the field survey is used along with other demographic data to assess population changes in the unrestricted area 'that might require modifications in the sampling plan to ensure adequate evaluation of dose commi tment. More specific data within each of the 16 meteorological sectors, such as distance to near est . esident, nearest milk animal, and nearest garden greater than 50m (500 ft ) in si e producing broad leaf vegetation shall be identified to support recalcula-tion of maximum I

individual dose estimates. Site-speci,ic considerations such as the Department of Energy's Hanford Reservation Site Boundary, within which MNP-2 is located, may require that specific information be collected beyond a 5-mile (8 km) radius in certain meteorological sectors to adequately identify pertinent data.

The results of the land use census will be submit". d no later than October 31 of each year for evaluation of individual and population doses. All changes, such as a location yielding a greater estimated dose or different location iIi th a 20 percent greater estimated dose than a currently sampled location,

t NENDMENT NO. 3 February 1986 will in the next Semiannual Radiological Effluent Report in accor-d ~

be reported dance with PPM 1.10.2 and Technical Specification. The RBIP plan, ODCH, will

~

~ ~

be changed to reflect new sampling locations.

The best available census informa .ion, whether obtained bv aerial survey, door-to-door survey, or consultation with local authori ties, shall be used to complete the Land Use Survey and the results reported in the Annual Radiologi-cal Environmental Operating Report in accordance wi th PPN 1.10.2 and Technical Specification requirements.

'5.3 Laboratory Intercomoarison Program Analysis of REHP samples is contracted to a provider of radiological analyti-cal services. By contract, this analytical service vendor is required to con-duct all activities in accordance with Regulatory Guides 4.1, 4.8, and 4.15 and to include in each monthly report; actions pertinent to their participa-tion in the Environmental Protection Agency's (EPA) Environmental Radioactiv-ity Laboratory Intercomparison Studies (Crosscheck) Program. A precontract award survey and annual audit at the contractor's facility ensure that the contractor is participating in .he Crosscheck Program, as reported.

The resul .s of the contractor's analysis of Crosscheck samples shall be included in the Annual Radiological Environmental Operating Report in accordance with PPH 1.10.2 and Technical Specification.

Besides the vendor's required participation in the EPA's Crosscheck Program, the Department of Social and Health Services (DSHS) of the State of Mashing. on oversees an analytical program for the Energy Facility Site Evaluation Council (EFSEC) to provide an independent test of WNP-2 RBlP sample analyses. The MNP-2/DSHS split samples are analyzed by Mashington State's Office of Public Health Laboratories and Epidemiology, Environmental Radiation Laboratory

( ERL). The State's ERL participates in the EPA Crosscheck Program, as well as

TABLE RADIOLOGICAL EHVIROOJEHTAL hJOHITORIHG PROGRAJl PLAN Sampling and Type and Frequency 1 d Collection Fre uency 1 of Analysis

1. A IRBORHE

a. Particulates and 1, 4-9, 21, 23, 40, Continuous sampling Part culate: Gross radioiodine 40 and 57 Weekly collection ieta , wee y; (6/12) gamma isotopic3, quarterly composite (by location)

Radioiodine: I-131 11

b. Soi 110 9, 1, 7, 21, and 23 Annually Gamma isotopic (0/5)

2. DIRECT RADIATION TLD4 1-9, 10-25, 40-47, (}uarterly, annually Gamma, quarterly data (34/56) 49-51, 53-56, 1S-16S review

3. WATERBORNE

a. Surface/ 26, 27, 28 and 29 Composite Gamma isotopic3, Drinking6 tritium aliquots5,'onthly Gross ,

(3/4) quarterly composite

b. Ground water 31, 32, and 52 quarterly Gamma isotopic3 (2/3) and tritium, quarterly

I 0

TABLE 5-1 contd. )

11 Saropling and Type and Frequency l San~le T e ~Sain le Location Code Collection Fre uency of Analysis l)ATERBORNE (contd. )

c. Sediment from 33 and 34 Semiannually Gamma isotopic shoreline (1/2)

4. INGEST ION

a. Milk 7 9, 35, 36, and 40 Semimonthly during Gamma isotopic (4/5) grazing season, Iodine-131 monthly at other times

b. FishB 30, 30, or 39 Seasonal or Gamma isotopic3 (2/2) Semiannually

c. Garden produceg 37 and 9 Honthly during grow- Gamma isotopic (2/2) ing season in the Riverview area of Pasco and a control near Grandview

Sample locations are graphically depicted in Figures 5-1 and 5-2.

Deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal avail-ability, malfunction of automatic sampling equipment, or other legitimate reasons; All deviations will be documented in the Annual Radiological Environmental Monitoring Report.

2Particulate sample filters will be analyzed for gross beta after at least 24-hour decay. If gross beta activity is greater than 10 times the mean of the control sample, gamma isotopic analysis should be performed on the individual sample.

Gamma isotopic means identification and quantification nf gamma-emitting radionuclides that may be attributable to the effluents of the facility.

n 0

fABLE 5-1 ontd.)

"TLD refers to thermoluminescent dosimeter. For purposes of WNP-2 REHP, a TLD is a phosphor card

( 32mm x 45mm x 0.5ma) with eight individual read-out areas (four main dosimeter areas and four back-up dosimeter areas) in each badge case. TLDs used in REh1P meet the requirements of Regulatory Guide 4.13 (ANSI H545-1975), except for specified energy-dependence response. Correction factors are available for energy ranges with response outside of the specified tolerances. TLO stations 1S-16S are special interest stations and are not included amongst the 34 routine TLD stations required by Plant Technical Specifi-cation, Table 3.12-1.

5Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are short relative to the compositing period.

Station 26, WNP-2 makeup water intake from the Columbia River, satisfies the Technical Specifica-tion criteria for upstream surface water and drinking water control samples. Station 28, 300 Area Drinking Water Intake satisfies the Technical Specification criteria for downstream surface water and drinking water sample. Drinking water samples are not routinely analyzed for I-131 from two week composite. I-131 analy-sis will be performed when the calculated dose for the consumption of water is greater than 1 mrem per year to the maximum organ.

tiilk samples will be obtained from farms or individual milk animals which are located in sectors c with high calculated annual average ground-level D/l}s and high dose potential. .There are no milk animals located within 5 km of WNP-2. If Cesium-134 or Cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then Strontium-90 analysis should be performed.

OThere are no commercially important species in the Hanford reach of the Columbia River. t1ost recreationally important species in the area are anadromous, primarily salminoids. Four fish specimen will normally be collected by electroshock technique in the vicinity of the plant discharge (Station 30). If electroshocking produces insufficient fish samples, anadromous species may be obtained from Ringold Fish I/atchery (Station 39). Control samples are normally collected in the vicinity of Ice Narbor Dam (salminoids may he obtained through the National Marine Fisheries Service at Lower Granite Dam).

9Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, a'nd a fruit should he collected each sample period if available. The variety of the produce sample will be dependent on seasonal availability.

10Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA),

WHP-2.

TABLE 5-I contd.)

The fraction in parenthesis under each sample type gives the ratio of the nun4er of Technical Specificaton sample locations to the total number of sample locations for the sample type that is currently included in the overall WNP-2 radiological environmental monitoring program.

TAB). -2 WHP-2 REttP LOCATIONS Station Sector Badi al tli1 es TLD AP/AI SW Dlt GW SE HI FI GP SOb 1 S 1.3 0 X 2 NHE 1.8 3 SE 2.0 4 SSE 9.3 0,'

5 ESE 7.7 0 X 6 S 7.7 0 X 7 . WNW 2.7 0 X 8 ESE 4.7 0 0 9A* WSW 30.0 0 0 98* WSW 35.0 0 9C* WS'W 33. 0 0 10 E 3.1 0 11 Et)E 3.1 X 12 ttHW 6.1 X 13 SW 1.4 0 14 WSW 1.4 0 15 W 1.4 0 lD 16 WtN 1.4 0 o m D

17 HtiW 1.2 0 QJ s m tD M G)

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T 5-2 (Continoedj Station Sector Gadial lliles TLO AP/Al SW Oll GM SE ill FI GP SO b

18 tt 0 19 ttf 1.8 0 20 EHE 1.9 0 21 Et>f 1.5 X X 22 E 2;I 0 23 ESf 3.0 X X 24 SE 1.9 0 25 SSE 1.6 0 26* E 3.2 0 0 27 E 3.2 X 28 SSE 7.4 0 0 29 SSE 11.0 0 30 f 3.5 31 E 0 32 E 1.2 X 33" ENE 3.3 34 ESE 3.3 35 Ettf 10. 5 36 fSE 7.2 37A SSE 17.0 370 SSE 16. 0 38k E 26.5 (95.0}

TABLE 5-2 (Continued)

Station Sector Radial !tiles TLO AP/Al Sli OM Gll SE hil FI GP SO>

39 HE 4.3 40 SE 6.4 0 0 0 41 SE 5.8 0 42 ESE 5.6 0 43 E 5.7 0 44 EtJE 5.7 45 EHE 4.2 0 46 NE 4.7 0 47 N 0.5 X 48 NE 4.3 49 tJW 1.2 50 SSW 1.2 0.

51 ESE 2.1 0 52 H 0.1 53 tJ 7.5 54 ~

HHE 6.5 5 SSE 7.0 56 SS'I< 7.0 III 57 tl 0.7 cr m S

I O m

00 Ch O

~

E 5-2 (Continued)

Station Sector Radial Miles TLD AP/AI SW DW GW SE tlI FI GP SOh 1S H 0.3 2S HHE 3S HE 0.5 4S EHE 0.4 5S E 0.4 6S ESE 0.4 7S SE 0.5 QS SSE 0.7 9S S 0.7 10S SSW 0.8 11S SW 0.7 12S WSW 0.5 13S W 0.5 14S WHW 0.5 15S HW 0.5 16S HHW 0.4 X-Sample collected at station (non-RETS) 0-Radiological Environmental Technical Speci fication (RETS) sample collected at station.

aEstimated from center of WHP-2 Containment from map positions.

Included in sampling program to satisfy requir'ements for Site Certification Agreement with the State of Washington.

AP/AI = Air Particulate and Iodine SW = Surface Water (River Water)

DW = Drinking Water GW = Ground Water SE = Shoreline Sediment tlI = thilk FI = Fish GP = Garden Produce SO = Soil

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AMENDMENT HO. 3, february 1986 I
6.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I
Routine Radioactive Effluent Release Reports covering the operation of WNP-2 I
during the previous 6 months of operation are submitted within 60 days after January 1 and July 1 of each year.
l These reports shall include a summary of the quantities of radioactive liquid and gaseous e fluents released from the unit ('ANP-2). Reports shall include each class of soild waste (as defined by 10 CFR 61) shipped offsite dur.'ng the reporting period with the following information; container volume, total curie quantity, principal radionuclides, source of waste and processing employed, container type, and solidification agent or absorbent.
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid made during the reporting period.
The Radioactive Effluent Release Reports include any changes made during the reporting period to the Process Control Program and to the ODCM pursuant to Technical Specification'6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment System, pursuant'to Technical Specification 6.15. It also includes a listing of new locations for dose calculations and or environmental monitoring identified by the Land Use Census pursuant to Technical Specification 3.12.2.
The Radioactive Effluent Release Reports also include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specifieh in Technical Specification 3.3.7. 11 or 3.3.7.12, respectively; and a description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 3. 11.l.il.
110
AMENDMENT HO. 3 February 1986 The Radioactive Effluent Report to be submitted within 60 days after January 1 of each year includes an annual summary of meteorological data collected over the previous year. This annual summary will be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report includes an assessment of the radiation doses due to the radio-active liquid and gaseous effluents released from the unit during the previous calendar year. This same report also includes, an assessment of the radiation doses from radioactive liquid and gaseous effluents to Members of the Public due to their activities inside the Site Boundary during the report period.
All assumptions used in making these assessments, i.e., specific activi .y, exposure time and location, are included in these reports.
The assessment of radiation doses is performed in accordance with the method-ology and parameters in the ODCh1.
The Radioactive Effluent Release Report to be submitted 60 days a ter January 1 of each year also includes, as required by Technical Specification 3.11.4, an assessment of radiation doses to the likely most exposed Member of the
'ublic frcm WNP-2 reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR 190, "Environ-mental Radiation Protection Standards for Nuclear Power Operation".
~r S'

ML17278A824

Contents

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1.0 INTRODUCTION

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ML17278A824

Text

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

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