Text

Wppss Nuclear Plant 2 Semiannual Effluent Rept,Jul-Dec 1986. W/870224 Ltr
	ML17278B198
Person / Time
Site:	Columbia
Issue date:	12/31/1986
From:	Powers C; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GO2-87-063, GO2-87-63, NUDOCS 8703030153
	Download: ML17278B198 (71)
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REGULA Y INFORNATI ON D I BTR I BUT I CYST RTS TEP Fg PP'Pr 48 ACCESSION,NBR: 8703030153 DOC. DATE: 86/12/31 NOTARIZED: N T FACIL: 50-397 WPPSS Nuc leal Pv o Jecti Unit 2i Washington Public Porc 05000397 AUTH. NAf'fE AUTHOR AFFILIATION POWERS, C. t'f. Washington Public Power Supply System REC IP. NAl'fE RECIPIENT AFFILIATION BUf3 JECT: "WPPBS Nuc leav Plant 2 S'emiannual Ef Fluent Rept> Jul-Dec I986. " W/870224 I tv.

DISTRIBUTION CODE: IE25D COPIES RECEIVED; LTR ~ ENCL / SIZE:

TITLE: 'nviv'onmental Nonitoring Rept (per Tech Specs)

RECIPIENT COP IEB RECIPIENT CO< IES ID CODE/NANE LTTR ENCL ID CODE/NAME LTTR ENCL gWR PD3 LA 0 84JR PD3 PD 05 5 5 BWR PBB 3 3 INTERNAL: 'CRB 1 AEOD AEOD/PTB IE FILE 02 NRR BWR ADTS 1 NRR PWR-A ADTS NRR PWR-9 ADTS 1 1 NRR/DSRO/RRAB RGN5 01 1 RGN2/DRSS/EPRPB Rl'f/DDAN I/NI8 1 1 EXTERNAL: LPDR 04 NRC PDR 03 TOTAL NUf'fBER OF COPI EB REQUIRED: LTTR 22 ENCL 21

Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 993524968 (509)372-5000 February 24, 1987 G02-87-063 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JULY 1, 1986 TO,DECEMBER 31, 1986 (ATTACHED)

In accordance with Title 10 of the Code of Federal Regulations, Part 50.36a (a) (2}, the subject report is herewith being submitted.

Should you have any questions, please contact Mr. R. G. Graybeal, Manager, WNP-2 Health Physics/Chemistry.

Very truly yours, C. M. Powers WNP-2 Plant Manager tmh Attachment cc: JO Bradfute - NRC C Eschels - EFSEC D Jaquish - DOE JB Martin - NRC RV (2)

D Sherman - Amer. Nuclear Insurers TR Strong - DSHS JM Taylor - NRC NRC Site Inspector

0 4

r Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 August 20, 1986 G02-86-810 Docket No. 50-397 Q Hr. J. B. Hartin V.

Regional Admini strator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596

Dear Mr. Martin:

Subject:

'UCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1986 TO JUNE 30, 1986 (ATTACHED)

In accorda/ce wi,th Title 10 of the Code of Federal Regulations, Part 50.36a (a) (2), the subject report is herewith being submitted.

Should you have any questions, please contact Hr. R. G. Graybeal, Manager, WNP-2 Health Physics/Chemistry.

Very truly yours, C H. Powers WNP-2 Plant Manager tmh Attachment cc: JO Bradfute - NRC C Eschels - EFSEC D Jaquish - DOE D Sherman - Amer. Nuclear Insurers TR Strong - DSHS JM Taylor - NRC NRC Site Inspector Document Control Desk - NRC

- 2.M

4 e C

~

'i

WNP-2 SEMI-ANNUAL EFFLUENT REPORT JULY TO DECEMBER 1986 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LICENSE NO. NPF-21 8703030153 861231 PDR ADOCK 05000377 PDH R

TABLE OF CONTENTS SECTION PAGE

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS ~ ~ 1 3.0 GASEOUS EFFLUENTS 5 4.0 SOLID WASTE 15 5.0 METEOROLOGICAL DATA 20 6.0 DOSE ASSESSMENT - IMPACT ON MAN ~ ~ ~ ~ ~ ~

7. 0 REVISIONS TO THE ODCM 37

LIST OF TABLES TABLE TITLE PAGE WNP-2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES-JULY - DECEMBER 1986 ~ ~ ~

2 2-2 WNP-2 LIQUID EFFLUENTS - SOURCE TERMS - JULY - DECEMBER 1986 3-1 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS - MIXED MODE RELEASES - MAIN PLANT VENT - JULY - DECEMBER 1986 .

3-2 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS GROUND LEVEL RELEASES - TURBINE BUILDING JULY - DECEMBER 1986 3-3 WNP-2 GASEOUS EFFLUENTS - SOURCE TERMS GROUND LEVEL RELEASES - RADWASTE BUILDING JULY - DECEMBER 1986 .

WNP-2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - JULY - DECEMBER 1986 . 13 3-5 WNP-2 GASEOUS EFFLUENTS - BATCH RELEASES JULY - DECEMBER 1986 . . . . . . . . . . . ~ . ~ 14 4-1 SCALING FACTORS FOR TRU, Sr-90, AND NI-63 JULY - DECEMBER 1986 .

4-2 WNP-2 SOLID WASTE SHIPMENTS JULY - DECEMBER 1986 . 18 5-1 JOiNT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-1ST QUARTER 1986 . ~ ~ ~ ~ ~ ~ ~ ~ 21 5-2 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-1ST QUARTER 1986 . 2?

5-3 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-2ND QUARTER 1986 . 23 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-2ND QUARTER 1986 24 5-5 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOUPLY AVERAGES FROM TAPE-3RD QUARTER 1986 . 25 5-6 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-3RD QUARTER 1986 . 26

LIST OF TABLES (Continued)

TABLE TITLE PAGE 5-7 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-27 4TH QUARTER 1986 .

5-8 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED FROM HOURLY AVERAGES FROM TAPE-28 4TH QUARTER 1986 .

5-9 JOINT FREQUENCY DISTRIBUTION FOR THE 33 FT. LEVEL 29 CALCULATED FROM HOURLY AVERAGES FROM TAPE - 1986 YEARLY 5-10 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT. LEVEL CALCULATED AVERAGES FROM HOURLY AVERAGES FROM TAPE- 30 1986 YEARLY . . . . . . . . . . . . . . . . . . . . ~

6-1 NIXIMUM INDIVIDUAL DOSES FROM WNP-2 LIQUID 32 EFFLUENTS - 1986 .

6-2 AVERAGE INDIVIDUAL DOSES FROM WNP-2 LIQUID 34 EFFLUENTS - 1986 .

6-3 50-MILE POPULATION DOSES FROM WNP-2 LIQUID EFFLUENTS - 1986 .

35 6-4 SUMtQRY OF DOSES FROtl WNP-2 GASEOUS EFFLUENTS - 1986 . 36

1.0 INTRODUCTION

This report is'ubmitted 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 MNP-2 during the previous six months of operation with data summarized on a quarterly basi s.

2.0 LIQUID EFFLUENTS The radwaste liquid effluents were released in a batch mode only during the reporting period. Three batch releases occurred during the third calendar quarter and 5 batch releases during the calendar fourth quarter.

The total time period for the batch releases was 12.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , with the maximum time period being 1.76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months for a release, the mi nimum time period being 1.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months for a release and the average time period was 1.51 hours5.902778e-4 days 0.0142 hours 8.43254e-5 weeks 1.94055e-5 months . The volume of dilution water used, is the total volume of recirculating cooling tower blowdown flow for the peiDecember iod. The average flow rate of the Columbia River during July through 1986 was 97,620 cubic feet per second.

A'iquid release Licensee Event Report, LER, was filed for an unmonitored discharge to the plant discharge line. Report number 86-044 contained the evaluation of the problem and its resolution. A .sample of the tank to be discharged was taken in accordance to technical specification 7.4. 11. l. l. l. The analytical results yielded the MPC fraction of 0.3, which met the 10CFR20 guidelines, the pre- and post- release analysis agreed. There was no threat to the safety of the plant, the public or the environment as a result. Further i nformation is contained in the f'iled LER.

Periodic LADTAP II computer runs were performed to verify compliance with Technical Specification limits. The calculated dose to the adult individual due to liquid releases for the third quarter was 8.6E-04 mrem whole body and 1.4E-03 mrem for the maximum organ. The fourth quarter sentativee calculated dose was 1.3E-03 mrem whole body and 2.1E-03 mrem for the maximum organ.

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

The percent of MPC limit is based on the total MPC fractions using those nuclides in Table 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 errors 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 95K confidence level.

Table 2-1 WNP-2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July - December 1986 3rd 4th Est.

Unit Quarter Quarter Total IError* XI A. Fission and activation products

1. Total re 1 ease ( not i nc 1udi ng I I tritium, ases, alpha) Ci 5. 9E-04 4.1E-03 l2.2 E+Oll

2. Average diluted concentration I during period uCi/ml 7.8E-10 I 1.0E-08

3. Percent of MPC limit 1.5E-03 I 1.6E-02 B. Tritium

l. Total release Ci 2.8E-01 4.6E"01 l2.2 E+Oll

2. Average diluted concentration during period uCi/ml 3.7E-07 1.2E-06

3. Percent of MPC limit 1.2E-02 3.8E-02 C. Dissolved and entrained gases I

l. Total release i Ci Q6.9E-05 '9.3E-05 l2.2 E+01I

2. Average diluted concentration durin eriod uCi/ml ~9.1E-11 &2.3E-10

3. Percent of MPC limit 4.6E-05 I 1.2E"04 D. Gross alpha radioactivity I I I 1. Total release Ci I '2.7E-07 I 2-lE-07 l2.3 E+01 I I

E. Volume of waste (prior to I dilution) liters 1.8E+05 3.2E+05 l1.5 E+Oll F. Volume of dilution water I I I used durin eriod liters I 7.6E+08 4.DE+08 ll.5 E+Ol I

At 95% confidence level

Table 2-2 WNP-2 LIQUID EFFLUENTS - SOURCE TERMS July - December 1986 BATCH MODE 3rd 4th Nuclides Released Unit Quarter Quarter Strontium-89 Ci 6.1E-06 2.8E-05 Strontium-90 Ci 1.1E-06 1.1E-07 Cesium-134 Ci I ~ 1.5 E-05 I

~ 2.9 E-05 Cesium-137 Ci Jc 1.5 E 05 [~ 2.2 E 05 Iodine-131 Ci I ~1.6 E-05 l>> 2.2 E-05 Iodine-133 Ci I 3.0 E-07 I 1.6 E-05 Cobalt-58 5.0 E-05 5.2 E-05 Cobalt-60 Ci 5.1 E-05 2.1 E-04 Iron-59 Ci ~1.7 E-05 I~4.6 E-05 Zinc-65 Ci 2.4 E-04 3.3 E-04 Mang ane se-54 Ci 2.2 E-05 7.3 E-05 Chromium-51 Ci 1.3 E-04 2.0 E-04 Zirconium-Niobium-95 Ci ~ 2.2 E-05 c 3.6 E-05 Molybdenum-99 Ci c 1.2 E-05 7.5 E-05 Technetium-99m Ci 1.5 E-05 2.7 E-05 Barium-Lanthanum-'.40 Ci I

~ 4.4 E"05 '.8 E-05 Cerium-141 Ci 1~2.2 E-05 3.0 E-05

Others Cerium-144 Iron-55 Sodium-24 Cop Arsenic-76

'i er-64 Sil ver-110m Total for TABLE Period (Above)I 2-2 (Continued)

Ci Ci Ci Ci Ci Ci I>> 9.7 E-05 I~

I 1.7 E-05 5.7 E-05 1 ~ 1 E-03 3.1 E-05 1.7 E-05 5.9 E-04 I 1.3 E-04 7.2 E-05 4.5 E-04 2.6 E-03

~ 4.3 E-05 2.1 E-05 4.1 E-03 Xenon-133 Ci I

~ 5.6 E-05 I 7.3 E-05 Xenon-135 Ci f 1.3 E-05 I 2.0 E-05 I Tri tium I Ci I 2.8 E-Ol l 4.6 E-01 NOTE: Less than (~) values are not included in the Total For'Period values.

1

3.0 GASEOUS EFFLUENTS

@ The gaseous radwaste effluents from WNP-2 were released mode. There are three (3) release points at WNP-2:

in a continuous

1. Main Plant Yent - 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 activity 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 effluent releases are performed for fission and activation gases by collecting the samples on charcoal:

traps and analyzing them using gamma 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 gatma 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 third quarter was 6.6E-02 mrads and 1.2E-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 2.6E-02 mrem for the third quarter and 7.8E-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 ODCM. Doses 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/(} value.

2. Taylor Flats - at 4.2 miles SE.

There were no abnormal releases of gaseous effluent during the third and fourth quarters of 1986. A gaseous sampling LER was issued due to a missed sampling period of the containment air while it was being purged, exhausting through the reactor building HYAC system. The reactor building elevated release monitor indicated no unusual activity. The sampling is required by Technical Specification 7.4.11.2.8.3. LER number 86-040 contains the details and corrective action taken. There was no threat to the safety of the plant, the public or the environment as a result.

Evaluation of Nitrogen-13, a positron emitter with a half life of 9.97 minutes and the result of the 0-16(p,~) N-13 reaction, was ma'de with respect to its release to the environment. Two pathways of possible release were considered, release through the turbine building exhaust as the result of steam leaks and release through the reactor building ele-vated release duct. Calculations based upon data collected to date indi-cate that the total annual release of Nitrogen-13 was less than 44 curies based on the lower limit of detection (LLD) values from the turbine building and less than 2.8 curies from the reactor building. The annual site boundary doses corresponding to these maximum releases would be 0.43 mrem and 0.00093 mrem respectively. Further analytical work is in pro-gress to refine "the results.

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 addi tion to the re'actor site, WNP-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. Also at this location is a backup chemistry lab within the EOF. The radiochemical hood containing HEPA filters is monitored for radioactive releases when in operation. Gamma spectrometry indicated no isotopes present other than those attributable to natural background.

The average energy for fission and activation product gases in airborne effluents was 0.4485 Mev.

Table 3-1 WNP-2 GASEOUS EFFLUENTS SOURCE TERt1S - MIXED NODE RELEASES tlAIN PLANT VENT July - December 1986 CONTINUOUS tdODE I l I I Nuclides Released Unit I Quarter I Quarter

1. Fission gases K ryp ton-85 Ci l4 3.7 E-06 I< 7.4 E-07 Krypton-85m Ci 1.5 E-01 1.3 E-01 K ryp ton-87 Ci 5.4 E-01 4.1 E-01 Kry ton-88 Ci 1.9 E+00 2.3 E+00 I Xenon-133 Ci 3,1 E+00 6.7 E-01 Xenon-135 Ci 8.5 E+00 3.6 E-01 Xenon-135m Ci 3.9 E+00 1.1 E-03 Xenon-138 Ci 1.7 E+00 1.7 E+00 I Xenon-133m Ci 4.6 E+00 6.7 E-01 Total for eriod Ci 2.4 E+01 6.2 E+00 I

2. I odi nes Iodine-131 Ci 5.9 E-04 1.9 E-04 Iodine-133 Ci 3.5 E-03 1.2 E-03 Iodine-135 Ci I~ 5.0 E-03 I

~ 5.0 E-03 Total for eriod Ci I 4.1 E-03 I 1.4 E-03 NOTE: Kr-85 value is a fission product ratio from other fission gas isotopes.

Tabl e 3-1 (Continued)

3. Particulates Strontium-89 Ci 1.8 E-05 1.9 E-06 Strontium-90 Ci l~ 8.4 E-06 4.8 E-07 Cesium-134 Ci I~ 3.8 E-04 I~1.4 E-04 Cesium-137 Ci 4.3 E-05 I ~ 1.3 E-04 Barium-Lanthanum-140 Ci 1.1 E-03 + 4' E-04 Molybdenum-99 Ci 1.6 E-02 6.3 E-03 Cerium-141 Ci [~3.3 E-04 l~ 8.9 E-05 Cerium-144 Ci 1.7 E-03 I~4.8 E-04 Cobalt-58 Ci 7.0 E-04 4.2 E-04 Cobalt-60 Ci 1.3 E-03 4.4 E-04 Iron-59 Ci l~ 9.9 E-04 I

= 2.5 E-04 Manganese-54 Ci l~ 3.8 E-04 8.7 E-05 Zinc-65 4.1 E-03 2.3 E-03 Others Chromium-51 Ci I>> 2.6 E-03 2.8 E-04 Zirconium-95 Ci l~ 5.8 E-04 I>> 2.1 E-04 Total for period Ci. I 2.2 E-02 I 9.8 E-03 I I I 4. Tri ti um Ci I 2.2 E-01 I 6.6 E-02 I I Total buildin release I Ci I 2.4 E+01 I 6.3 E+00 I NOTE: Less than (~ ) values are not included in the Total For Period values.

Table 3-2 WNP-2 GASEOUS EFFLUEHTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING July - December 1986 CONTINUOUS MODE I

th I I Nuclides Released I Unit I Quarter I Quarter

1. Fission gases Kry ton-85 Ci I~ 1.4 E-05 l~ 1.2 E-05 Krypton-85m Ci Ii 7.9 E-Ol < 6.1 E-01 K ryp ton-87 Ci 2.0 E+00 1.7 E+00 Kry ton-88 Ci 2.8 E+00 2.6 E+00 I I

Xenon-133 Ci 3.6 E+00 3.2 E+00 I Xenon-1 35 Ci 9.0 E-01 8.0 E-01 Xe non-135m Ci I

< 2.3 E+00 I ~ 1.3 E+00 Xenon-138 Ci 1.1 E+01 7.6 E+00 I Xenon-133m Ci 7.2 E+00 1.7 E+01 Total for eri od 2.8 E+01 3.3 E+Ol

2. I odi nes I

Iodine-131 Ci 2.2 E-03 6.7 E-05 I Iodine-133 Ci 2.4 E-02 3.4 E-04 Iodine-135 Ci c 3.0 E-0 3 ~ 2.1 E-03 Total for eriod Ci I 2.6 E-02 4.1 E-04 NOTE: Kr-85 value is a fission product ratio from other fission gas isotopes.

Table 3-2 (Continued)

3. Particulates Strontium-89 Ci 3.1 E-06 1.7 E-05 Strontium-90 Ci 1.7 E-05 1.8 E-06 Cesium-134 Ci I~ 4.1 E-04 I~ 1.2 E"04 Cesium-137 Ci l~ 4.9 E-04 I ~ 1.4 E-04 Barium-Lanthanum-140 Ci 1.2 E-03 c 5.2 E-04 Molybdenum-99 Ci 2.4 E-04 l~ 3,8 E-04 Cerium-141 Ci ~ 4.9 E-04 Ic 1,2 E 04 Cerium-144 Ci ~ 2.0 E-03 < 4.7 E-04 Cobalt-58 Ci 3.5 E-04 l~ 1.3 E-04 Cobalt-60 Ci 5.2 E-04 l~ 1.8 E-04 Iron-59 Cl I

~ 9.8 E-04 ~ 3.0 E-04 Manganese-54 Ci I

+ 6. 9 E" 04 I ~ 1. 2 E-04 Zinc-65 Ci 1.3 E-03 5.0 E-04 Others Chromium-51 Ci 2.6 E-03 3.1 E-04 Zirconium-95 Ci I~ 6.0 E-04 1.9 E-04 Total for period Ci 5.0 E-03 8.3 E-04 I I I 4. Tri tium Ci 2.2 E+00 1.0 E+00 I Total buildin release I Ci I 3.0 E+01 I 3.4 E+Ol NOTE: Less than (') values are not included in the Total For Period values.

Table 3-3 MNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADWASTE BUILDING July - December 1986 CONTINUOUS MODE r t I I Nuclides Released I Unit I Quarter I Quarter I

1. Fission gases K ryp ton-85 Ci I~ 4.2 E-06 )~ 8.3 E-06 Krypton-85m Ci l~ 1.8 E-01 1

~1.6 E-01 K ryp ton-87 Ci 6.1 E-01 1.2 E+00 Kry ton-88 Ci 8.3 E-01 1.8 E+00 Xenon-133 Ci 9.4 E-01 1.3 E+00 Xenon-135 Ci 7.8 E-01 4.7 E-01 Xenon-135m Ci 6.0 E-01 1.5 E+00 Xenon-138 Ci 2.2 E+00 2.2 E+01 Xenon-133m Ci 1.6 E+00 2.7 E+00 Total for period Ci 7.6 E+00 9.0 E+00

2. Iodi nes Iodine-131 Ci 7.8 E-05 9.2 E-05 Iodine-133 Ci 2.4 E-04 5.6 E-04 Iodine-135 Ci I~5.9 E-04 I ~9.1 E-04 Total for period Ci I 3.2 E-04 I 6.5 E-04 NOTE: Kr-85 value is a fission product ratio from other fission gas isotopes.

Table 3-3 (Continued)

3. Particulates Strontium-89 Ci 2.7 E-05 3.2 E-06 Strontium-90 Ci 1.1 E-05 7.5 E-06 Cesium-134 Ci I 3.4 E-05 - 4.7 f-05 Cesium-137 Ci 1~3.0 E-05 - 3.6 E-05 Barium-Lanthanum-140 Ci I 1.0 E-04 .

1.6 E-04 Molybdenum-99 Ci 1 ~ 1 E-04 I ~ 4.1 E-04 Cerium-141 Ci 3.6 E-05 I-' " f-05 Cerium-144 Ci 1.4 E-04 '.9 E-04 Cobalt-58 Ci lc 2.9 f-05 I~ 4.8 E-05 Cobalt-60 Ci I 4.9 E-05 I 7.6 E-05 Iron-59 Ci 1.0 E-04 I '.6 E-05 Manganese-54 Ci l~ 3.4 E-05 I 5.2 E-05 Zinc-65 Ci l~ 8.0 E-05 )~1.3 E-04 Others Chronium-51 Ci - 2.3 E-04 '.2 E-04 Zirconium-95 Ci 5.2 E-05 I ~4.1 E-04 Total for eriod Ci 3.8 E-05 1.1 E-05 f4. Tritium Ci I 1.0 E-Ol I 6.1 E-02 I I Total building release I Ci I 7.7 E+00 I 9.1 E+00 I NOTE: Less than ( ) values are not included in the Total For Period values.

Table 3-4 WNP-2 GASEOUS EFFLUENTS SUMNTION OF ALL RELEASES July - December 1986 3rd 4th lEst. Total Unit (}uarter quarter I Error %*

A. Fission 8 activation gases

1. Total release Ci 6.0 E+01 4.9 E+01 3.6 E+01 I verage re ease rate for period uCi/sec 7.5 E+00 6.2 E+00 ercent o ec .

Spec. limit 1 .3 E+00 2. 4 E+00 B. Iodi nes

1. Tota > od> ne (131 133) Ci 3.0 E-03 2.5 E-03 3.6 E+011 verage re ease rate for period uCi/sec 3.8 E-04 3.1 E-04 ercent o ec .

S ec. limit 3.5 E-01 1.0 E-01 C. Particulates artscu ates wit hal f-lives>8 days Ci 2.7 E-02 1 ~ 1 E-02 3.6 E+01 I verage re ease rate for period uCi/sec 3.4 E-03 1.4 E-03 ercent o ec .

Spec. limit 3.5 E-01 1.0 E-01 ross ap a radioactivity Ci I 8.1 E-04 1.5 E-03 D. Tritium

1. Total releases Ci 2.3 E+00 1.1 E+00 3. 6 E+011 verage re ease rate for period uCi/sec 2.9 E-01 1.4 E-01 ercent o ec .

Spec. limit 3.5 E-01 1.1 E-01

At 95K confidence level

-1 3-

Table 3-5 WN)'-2 GASEOUS EFFLUENTS BATCH RELEASES July - December 1986 ota ax 1 mum 1nlmum i ean Type Number Time (hrs) Time (hrs) Time (hrs) Time (hrs)

Purge 82. 6 54. 6 28 41. 3 Vent 82 144.3 4.0 0.75 1. 76

A total volume of 5615 ft3 (159.0 m3) of solid waste was transported in 22 shipments during the July through December 31, 1986 reporting 1

period. The total activity of the waste shipped was 408.51 Ci; 408.24 Ci contained in dewatered spent resins, 0.1892 Ci in Dry Active Waste (DAW) and 7.85E-2 Ci in absorbed liquid.

A. Dewatered S ent Resin Dewatered resins accounted for 4175 ft3 (118.2 m3) of the radio-active wastes shipped during the reporting period. The burial containers were LSA-190 liners provided by NUPAC, Inc. The total activity of the resins shipped during the reporting period was 408.24 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, or NUPAC 14-21 OH casks as appropriate.

The counting error associated with the total activity has been found to be less than l.R at one standard deviation in previous effluent reports and to decrease with increasing activity. The statistical counting error is assumed to be 1% for the purpose of this error evaluation.

Other parameters considered in estimating the total error of the activity shipped included the error in measuring the absolute volume, the weight of the waste in the liners, the representative-ness of the sample taken, the homogeneity of the nuclide di stribu-tion within a batch or liner and the geometry error in the gamma spectroscopy analysis. The gambia spectroscopy calibration error was approximately 5L. 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. Dr Active Waste (DAW)

A total of 1260 ft3 (35.68 m3) of DAW was shipped in 30 Container Products Corporation, B-25 steel boxes. The total activity of the DAM shipped was 0.1892 Ci. The values for the activities shipped were determined by usi ng 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 nuclides were eliminated based on decay of the DAM prior to shipment. A meaningful counting error cannot be generated for the DAM, however, the total error may be assumed to be less than or equal to 20'X since DAM would be subjected to similar error contributions as the spent resins.

0 Absorbed Liquids A total of 176.4 ft3 (4.995 m3) of absorbed aqueous liquid containing a total of 7.85E-2 Ci was shipped during the reporting period. The drums were of either a 17C, 17H or 17E/H designation to meet burial ground requirements but were shipped only as strong tight containers (STCs) per DOT LSA requirements.

The values for the activities shipped were based on using dose rate-to-curie conversion factors and sample analysis. As with the DAW, the total error is assumed to be less than or equal to 20% due to the likelihood of similar 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" and the final EPRI report, "Radionuclide Correlations in Low-Level Radwaste", EPRI NP-4037 June 1985, the amount of H-3 insolid radwaste shipments was determined by estimating or measuring the amount of water present and multiplying by the average H-3 concentration in the coolant for the time period associated with the waste generation. In accordance with the final EPRI report a water percentage of 55% was'used for powdered resin, 50K for bead resin and 25K (very conservative) was used for DAW.

C-14 The generic scaling factor (C-14 to Co-60, 1.0 E-4) from the EPRI report was used unless the result was less than 5.0E-8 uCi/g (typical MDA), in which case the MDA was used.

1-1 29 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 3.0E-8 uCi/cc was reported The scaling factor taken from the EPRI as less than the MDA value.

report is 2.0E-S.

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 2.0E-8 uCi/cc was reported as less than the MDA value. The scaling factor taken from the final EPRI report is 3.0E-5.

TRU, Sr-90, Ni-63 TRU nuclides would be scaled to Ce-144. As recommended in the AIF report, these nuclides are not considered to be present if the scaled values are less than: 1 nCi/g for TRU, 35 nCi/g for Pu-241 or 200 nCi/g for Cm-242. TRU nuclides will be reported if the scaling nuclide (Ce-144) is reliably detected and Cs-137 is also present.

Sr-90 is scaled to Cs-137 and Ni-63 is scaled to Co-60. The following table contains the scaling factors, required LLD's and reporting thresholds.

TABLE 4-1 Scalin Factors for TRU, Sr-90 and Ni-63 Scaled Seal i ng Seal i ng Required Reporting,.

Nuclide Nuclide Factor LLD (uCi/cc) h h( ( i(g(

Pu-238 Ce-144 8.0 E-3 1.0 E-5 Ce-144 detected PU-239 Ce-144 5.0 E-3 1.0 E-5 Ce-144 detected Pu-241 Ce-144 5.5 E-1 3.5 E-4 Ce-144 detected Am-241 Ce-144 3.0 E-3 1.0 E-5 Ce-144 detected Cm-242 Ce-144 1.5 E-2 2.0 E-3 Ce-144 detected Cm-244 Ce-144 '.3.5 E-3 1.0 E-5 Ce-144 detected Ni-63 Co-60 2.0 E-2 3.5 E-2 Co-60 detected Sr-90 Cs-137 6.3 E-3 4.0 E-4 Cs-137 detected 4.2 Process Control Pro ram The Process Control Program (PCP) used to control solidification at Wl<P-2 will be provided by the vendor waste processor, Pacific Nuclear Inc. in accordance with Contract C-20452, and will be subjected to POC review prior to any solidification of radwaste.'wo Pacific Nuclear generic solidification PCP's, TP-04, "Portable

'Solidification System and TP-05, "Radwaste Solidification System" are currently under NRC review. As an alternative, approved High Integrity Containers (HIC's) could be used for the transport of wastes requiring stabilization. Other portions of the radwaste program are controlled by the WNP-2 procedures PPM 1.12.1, "Radwaste Management Program", PPM 1.12.2, "Radwaste Process Control Program",

and 1.12.3, "Contract (Vendor) Waste Processing". No significant changes have occurred in these procedures during this reporting period.

-1 7-

Table 4-2 WNP-2 SOLID WASTE SHIPMENTS July - December 1986 A. SOLID WASTE SHIPPED OFFSITE FOR HURIAL OR DISPOSAL

l. Type of Waste Waste Stream Unit 6-month lEst. Total Period Error, X

a. Spent resins, filter sludges, m3 118. 2 eva orator bottoms, etc. Ci 408. 24 20

b. Dry active waste, contaminated m3 35.68 equi ., etc., Ci 0.1892 20

c. Irradiated components, control m3 No Ship-rods, etc. Ci ment

d. Other, (absorbed aqueous liquid) m3 4'. 995 Ci 0. 0785 20

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

a. Dewatered Spent Resins uc 1 e n- 2 9.4 0-0-

Cr- 1 n-d-1 9 n-13 Ni-63* 0.240 0. 980

Indicates scaled nuclide

b. Dry Active Wastes (DAW) uc 1 e

0. 8 4 Co-58 12. 9 0-H-3+ 3.30E-3 Ns-

c. Irradiated Components - None

d. Other - Absorbed Liquids (oil) uc 1 e 58.20 0.0457 0-4 Nn-54 .8 .9 0- E-Zr-9 1. 1E-Fe- 9

3. Sol i d Waste D i s posi ti on Number of Shi ments Mode of Trans ortation Destination 22 Flat bed trailer (4) US Ecology 14-2'10H Cask (18) Richland, WA B. IRRADIATED FUEL SHIPt1ENTS (Di sposition)

None

Indicates scaled nuclide

5.0 METEOROLOGY The 'meteorological data contained in Tables 5-1 through 5-8 were obtained from the WNP-2 meteorological tower located 2500 ft. west of WNP-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 1986 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 except during the fourth quarter of 1986. The data recovery for the fourth quarter was 74%.

Overall data recovery for all four quarters of 1986 remained above 90%.

Tables 5-1 through 5-8 list the joint frequency distribution at the 33 ft.

and 245 ft. levels for 1986 by quarters. Additionally, this report includes Tables 5-9 through 5-10 which list the joint frequency distribu-tion for all of 1986. The tabulated stability classes, A-G, are denoted by numerals 1-7 respectively. Numerals 1-7 were used for the wind sub-fields as is noted at the top of each sensor level reported. The 16 compass sectors in Tables 5-1 through 5-8 pertain to the direction the wind is coming from.

Calibrations performed in 1986 produced no values exceeding WNP-2 FSAR meteorological equipment tolerances. Therefore, no correction has been made to the raw data. The NRC Delta Temperature Stability Classification scheme was utilized in the production of all joint frequency. tables.

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4~ 2~ !!a a 1 ~
~ 0.
C
0. I C
~
10, 10, 13. 14 ' o 8~ 10 V~ I S. !Q. ~ ~ ~ a ~ V~ ~
a ~ 2. 1. 0. 1. 1. 'I ~ ~ 6. 9. 10. 1. 0~
A A 2~ 2. 0. I 0. 0. 0. 0. ~ ~ as V~ 2l 3 0. 0. 0, e. 0. 1
~ ~ I. 0. 0.
0. Q. 0. Q. 0. 0, 0~ 0. 0. 0. Q.
n~ 0. 0. 0. 0. n~
0. 0~ 0. 0. 0. 0. 0. 0. 0. 0.
' O
'1 ~ a~ Q. 0. 1 V~
C V~ 5~ II ~ 2~ o, Ce 1~ '1 I V f5. 3 ~
o al C. 8~ 18. 17. 17. 10. 15, 13. 13. 7~ }Q.
5. 13, ~ ~ ~ ~ I ~ 7 ~
13 4. 10, 14, 5. 5. o, OI ~
5 6. 0. 2~ 0. 0. aa 0. 12. 5. Je 9, ~ ~
6 0~ Cs 0, 0. 0. 0~ 0. 0. 0. 0. 0. 0. ~ ~ 8. e.
7 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0. G, 1 0, 0. 0. e. 0, 0. 0. 0. 0 ~ 0 n, 0. 0. 0. 0.
I 2 0. as 1
~ ~ 0. 2. 0. 3. 5. 3~ 5.
lo ~ 10 ~ 3 ~ 0. l. o aa 2O 5. 16. 17. 5. 9. f3. 16. o, 8.
4 8. 9. as O
1~ 0. t ~ 2. 5O 14, 13. }t, 11. 24. 24. V~
5 0. r.Ol V~ 1 ~ 0. 0. a ~
1
~ ~ 8. 15. 26. l ~
0. 0. o~ 0.
6 n, 0. 0, 0. 0. 0. 0. 0. 0. 0. 0.
7 0, 0. 0. 0~ 0, 0. 0. 0. 0, Q. Q. 0. 0~ 0.
6 1 0. 0. 0. Q. 0~ 0. 0~ 0. 0. 0. 0. 0. 0. 0. 0. 0.
C C 2 1". 1 3l al ~ V~ 7~ 5. Cs 7. 6~
1C C 11. 13, 6, 0. 2O 4. 11, 15. 11. 8. 6, 14 ~ ~
4 V~
r 0, 0~ 5. I! vs V~ e. ~ ~ 13 '.
~
f 6 C~ V~ ~
5 I ~ C~ 0. 0. 0. 0. 1 1
0. 0. 0.
0. 0, 0, 0. 0. 0~ 0. e. r V~ G. G. 0.
0. e. 0, 0.
O V~ 0. 0~ 0. 0. 0. 0. 0. G. 0,
0. n 0.
0. 0. 0. e. 0. 0. 0~ 0. 0. 0~ ~ ~ V~
5, ae as '1 ~ l. Cr 5,
~
O C~ 8. 5. l ~ ~ ~ I~
t I I II t OCO t ~ as ~ ~ ~ ~ V~
C V~ i0 ~ C~ ~ ~ ~
as 0. 0. 0. 0, 0. 0~
Ia a~ Ce V~ 2O ~ ~ l. ta O ~ }0.
O, OI ~ ~ ~
te 0. 0. ' ~
n ~ ~ 0. 0 ~ Ve ~ ~ ~ ~
A A
e. G. V~ Vs 0, 0, 0. O ~ G. e. 0 G. V~
a rs hV A A nV ~ A
0. nO ~
O ~ Q. Vs V~ t ~ ~ Va 0. V~ Vo M11 Inc A A At l ~ s '1'ARIADL: =
~ VV
TABLE 5-5 3RD QUARTER 1986 JOINT FREQUEHCY DISTRIBUTION FOR THE 33 FT LEVEL CALCULATED FRON HOURLY AVERASES FRON TAPE HAXIHUN MIND SPEEDS FOR EACH CATESORY IN HPH ARE:
0.6 2" 3.0 3- 7.0 4-12.0 5 - 1' 6 - ?4.0 NUHBERS GIVEN ARE HOURS STAB HIND NH:" NE EHE ESE SE SSE SSM SM MSM Vi MHii Hli NHM CLASS CAT
0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. O. 0. 0. O. .0, I~ 2>> 1. 2>> 0. 0. 2>> 7. 7. 6. 4. 5.- 2>> 9. 11.
24. 13. 7. 2>> 0, 5. 21. 53>> 50. 10. f6. ff, 6. 26.
IC. 3. 0s 0. 0>> l. 'I ~ 11. 20. 11. 15. 10 j>> Ie 13
0. 0~ 0. 0. 0. 0. 0. l. 0. 1. 1. 0. 9. 0.
0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ O. 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. 0. 0.
2 2 l. 0. 0. 0. 0. 1. 2>> 2>> 2. 5>> I. 3>> 0, 7>> 6. 4. 2>> 1. 4. b. 6, 7>> 8. b. 4. 10, 0.
2 4 6. 5>> 1, 0. 0~ l. 2. 2>> 2>> I ~ 2. l. 2~ 2~ 0s 2 5 2>> 0. O. 0. 0. 0. 0. 0. 0. 0 0. 0. 5. 2. 0.
2 6 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0, 0. 1. 0. 0.
2 7 O. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, a. 0. 0 0, 0.
I O. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. l.
3 2 1. 0. l. 0. 0. 0. 1. 1. l. 0. 0. 1. 2~ 1.
3 b. 11 ~ 2. 0. 2>> 10. 5. 8. 2. 6. 6. 13.
4 3. 1. 0. I. 1. 0. l. 4s 2>> 2>> 0. 0s 2>>
5 0, 0. 0, 0. 0, 0. 0>> 0, 0. 0~ 0. 0. I. 0. l.
6 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0.
3 7 0. 0. 0, 0. 0. 0. 0>> 0. 0. 0. 0. 0. 0. 0, 0. 0, 4 I 0. Os 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
2 2>> 5. 0. l. 0. 3. 0. 3. 7, I. 3. 5. 0. 3>> I ~
4 14. 8. 7. 2~ Il. 9. 14. 16. 9. 7~ l. 5. 8. 19, 19 0, 0. 0~ 1. 2, 0. 5. 4. 6. 2. 17. 20, 6~
4 5 0. 0. 0. 5. 0. 0. 1. 1. 0. 0. 0. 2, 20. 5, 2~
4 6 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 2~ 0, 0.
7 O. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 1. 0. 0, 5 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. O. 0. 0, 0.
5 2 12. 5, 20 ~ o 1. 2>> 2>> 6, 5 6. 5~ 8. 7. 9, 7.
5 3 8. 1. 7~ 8. b. 19. 10. 14. 18. 16. 31, 30.
1',
5 4 0. 0. 0. 0. l. l. 7. 3. 2>> 3. I. 1. 3, 29. 7.
5 5 0. 0. 0. 0. 0. 0. l. 2. 0. 0. 0. 0. 0s l. 0. 0.
5 6 0. 0. 0. 0. 0. 0. O. 0. 0. 0. 0. 0. 0. 0. 0. 0.
5 7 0. 0. 0. 0. 0. 0, 0~ 0. 0. 0~ 0. 0. 0>> 0. 0. 0.
6 I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0, 0.
C 6 2 5. 4s 0. 1. ds 6. 10. 8. 9. 9. 10. 0>> 7~ 17. 12.
6 20. 5>> 0. 3. 3. 19. 29. 34 13 7. 10. 6. 19. 24. 22>>
6 0. 0. 0. 0. 0. 0. 0. 3. '. 2>> 0. 0. 0, 1.
6 5 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 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.
0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0~ 0, O.
7 2 13. 10. 5. 3. 7>> 13. 11. 5. 8. 17. 19 ~
7 f7. 6. 14. 2>> l. Ib ~ 39. 27, 2>> f. 8. 15.
7 4 1. 1 ~ l. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. 1. 0.
7 5 O. 0. 0, 0. 0.. 0. 0. 0. 0. 0. 0. 0. 0. 0, O. 0.
7 6 0. 0. 0. 0. 0. 0, 0. 0. O. 0. 0. 0. 0. 0. 0. 0.
7 7 0. 0 0. 0. 0. 0. 0., 0. 0. 0. 0. 0, 0. 0. 0~ 0.
TOTAL HUHBER OF HOURS USED = 2084 'iISSINB = 16 CALH = VARIABLE = C?
3RD QUARTER 1986 JOINT FREQUENCY DISTRIBUTION FOR THE 245 FT LEVEL CALCULATED FRON HOURLY AVERABES FROil TAPE NAXINUN MIND SPEEDS FOR EACH CATEGORY IN NPH AREl 0.6 2 - 3.0 3 - 7.0 4 - 12.0 . 5 - 18.0 6 " 24.0 NUNBERS GIVEN ARE'HOURS STAR ENE ESE SE SSE S SSM SM M MNM NM CLASS 1 1 O. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0~ n. 0. 0. O.
2 0. O. 0. 0. 2>> 0>> 3>> 6. b. 9. 5. 8, 6, 9. 0, I 11. 7. 8. 5. 6. 14. 28. 27, 27. 15. 16. 17. 35. 24. 13.
t 'l, Ill s
1 17. 8. 5~ I ~ 2>> C~ ~ ~ 0>> sl ~ 'I ~ 10.
I 5 0s 0. 0. 0. 0. 1. 0. 0. 2, 0s 10. 3. 0, 1 6 0. 1, l. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 2>> 0.
1 7 0~ O. 0, 0. 0~ 0. 0. 0. 0~ 0. O. 0, 0. 0. O. 0 2 1 O. 0. 0. 0. 0. 0. I. 0. 0. O. 0. 0. 0, 0. 0, 0, 2 2 0. 0. 0. 0. 0. 0. 0. 2>> 0~ 4. 5. as 1.
2 &. l. 8, l. 1. l. 6. 7~ 7. 8. 6. 7. 6.
2 10. 0. 0. 0. O. 2>> 2>> 0, I. 2, 2, 2. 6, 2 5 0. 0. 0. l. 0. 0~ 0. 0. 0. 0. 0. 0. O. 1. 0.
2 6 O. I ~ l. 0. 0, 1. 0. 0. 0~ 0, 0. O. l. 1. O.
2 7 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. O. 0, 0, 0, O.
I 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0.
2 0. 0. l. 1. 0. 0. 0. l. 2>> 0. l. 1. 0. 0. 0,
7. 6. l. i. 5>> 5>> 10, 6, 5. 6, 3. 7, 3. 8.
3>> 0. 2>> 2>> ~ ~ 1. 1. 2>> 1. 5. 1. 2. 2>>
5 O. 1 ~ 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 1. l. l. 2, 3 6 O. 0. 0, 0. O. 0, 0, 0. 0, 0. O. 0. 0. I. O. 0.
7 0~ 0. 0. 0. 0. 0. 0. 0, 0. 0. 0, 0. Oe O. O. 0.
0. 0 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0~ 0~ O. 0.
'1
>>1>> 0. 0, 0. 2i 3, 2. bs 1. 3>> 2~ I ~ 0. 2. s i 4 3 22>> 8. 4. 10. 4. 6.- 6. 12. 9. 7, 11. 12. 13.
24 2>> 2. 3. b. 6. 2>> 6. 10. 5. 8>>
4 5
'2.
13, 4, 1. 2>> l. 0. 0. 0. 0. 0. 0. 0. 7. 8. 1.
4 6 O. 0>> 6. 0. 0. 0. 2>> 2>> l. l. 0. 0. 1
~ ~ 'l ~ 5. 0.
4 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0~ 0. 0. 0, 5 I 0, 0. 0. 0, 0, 0. 0, 0. 0. 0. 0. 0~ 0. 0. 0. 0.
5 2 ~ ~ 1. 2~ 0. 0. 0. 5>> 0. 2>> 2. 4~
5 20. 7~ 5~ 6. 7, 5. 8>> 8. 4. 4~ 7>> 14. 22 i 15.
5 18, 7>> 5, 2>> 2>> 4. &, 8, 0. 1. 2~ 6. 21. lb. 12.
l.
5 5 3. 2>> 2~ O. 0. I. I. I ~ 0. I ~ 8. 0e-5 6 0. 0. 0.'. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. I. 1. 0.
5 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0.
6 1 0. 0. 0. 0. 0. 0. O. 0. 0. 0. 0. 0. 0. 0. 1. 0.
6 s 1. 2. 6~ 2>> 3. 4>> 7. 5. 8. 7>> 7>> 3. b.
6 20. lb. 0. 12. 6. 9. 5. .6. 6, 11. 6, 8. 20. lb. 15. 12.
6 Ds 7, 1. 3>> 2>> 5 ~ 3. 4~ 8. 12. 26. 8.
6 5 O. 0. 0. 0. 0. 0. O. 0. 2>> 0. 0. O. 0. 2>> 4. 0.
6 6 0. 0. 0. 0. 0~ 0~ 0. 0. 0~ 0. 0. O. 0. 0. O. 0.
6 7 0, 0. 0. 0. 0. 0. n. 0, 0. 0~ 0. 0~ 0. O. 0. 0.
7 l 1. O. O. 0 0. O. O. 0. 0. O. O. 0. 0. O. 0. 0.
7 2 6. ~ ~ 6. 4. 2. 6. 8. 6. 4. 6. 8. 7. 4, 7 12. 5~ 8. 8. ls 15. 13i 12 ~ 7~ 6. 13. 14, s
7 O. 2>> 4, 9. 6. 1. 2. 2>> 5>> 2, O. 0. 2>> 6. 14. lb.
7 5 0, 0. 0. O. 0. i. 0, 0. 0. 0, 0. O. I. 0.
7 6 0. 0, 0. 0~ 0. 0. 0. 0, 0. 0. 0, 0. 0 ~ 0. 0. Oe 7 0. 0. 0, O. 0. 0. 0. O. 0. O. O. O. 0. 0. 0, O.
TOTAL NUNBER OF HDURS USED = 2099 NISSIK6 = 18 CALM = VARIABLE - 36
TABLE 5"7 4TH QUARTER 1986 JOlt?T FREQL'ENCY DISTRIBUTION FOR THE33 FT LEVEL CALCULATED FROtl HOURLY AVERABES FRON TAPE NAXINUN MiND SPEEDS FOR EACH CATEBDRY IN NPH ARE:
0.6 2 - 3.0 3 - 7.0 4 - 12.0 5 - 18.0 6 - 24.0 NUNBERS 6IVEN ARE HOURS STAB MIND tit?E tiE ENE ESE SS= SSn 'SN NSN t'NP NN NNt, CLASS CAT I I 0. G. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0. Oe G. 0.
I 2 0. 1. 0. 0. G. 2. 0. 2>> 1. 0. 2>> 0. l. I, I 3 0, 0. 0. 0~ 0. 0. 0. 2>> l. 0. 1. 0. 0~ 0. I.
'T >>e
>>I ~ e. Q. 0. G. 0 ~ Q. I ~ 2~ e>> ~ e>> ~ 2>> 0 >>I ~ 0. 0 ~
I 5 0. 0. 0. 0~ 0. 0~ 0. 0. 0. 0~ l. 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~ 0, 0.
2 0. 0, 0. 0. 0. 0. O. 0. 0. 0>> 0; 0. 0, 0; 0. Q.
2 2 2~ 1 ~ 0. 0 ~ I, 0~ 2>> 0. Ge 0. I. 2~ f. 0e 1.
0. 0, 0, 0. 0. 0. 0. I. 0. 0. I. 0. I. 0. 0,
l. 0. 0. 0. 0. 0~ 0. 0. I ~ 1. 2>> 0, 0. 0. O.
2 5 0. 0. 0. 0. 0. 0. 0. 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.
2 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 3 G. 0. 0, 0, 0. 0, 0. 0. 0. 0. 0. 0. 0~ 0~ 0. 0~
3 2 2>> 1. 1. ~
1. l. 0>> 9>> 0. 0~ 2>> 0. 3. 4. 3~
0, 2. 2>> 0. 0, 0. 0. I, 0. 0~ I. 0. l. 0. 0. 0.
4 0. 0. 0. 0. 0. G. I. G. 1. 0. 0. 0. G. 2~
5 0. 0. 0 0. G. G, 0. l. 0. 0>> 1. 0. 0. O. 0~
6 0. 0. 0>> 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0~
3 7 0~ 0. 0. 0, 0. 0. 0. 0. 0~ 0. 0. 0~ 0~ 0. 0~ '.
0.
4 I l. 0. 0. 0. 0. 0. 0. G. 0. 0. 0. 0. 0. G. 0.
F 17, 9. 5. 11, 5>> 5, 10. 10. 6. 7 3>> 15. 19 ~ 19, 14, 7~ 10. l. 0. 5. 22. 1' 7~ 5>> l. l. 8. 25. 31.
5. 3~ 0. 0. 0. 0. 3. 8~ ~ 12. 5>> 3. 2>> 2>> 8. 11.
4 5 0. 0. 0. 0. 0. 0. 0. l. 2>> 0. 0. 0. 0. O. 0.
6 0. 0. 0. 0. 0. 0. 0. G. 0, l. 0. ~ 0. 0. 0. 0. 0.
I Q. 0. 0~ 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
5 I O. 0. 0. 0. 0~ 0. 0>> 0, I~ l. 0. l. 0~ 2>> 0.
5 14 ~ 14. B. 6. 10. 17. 25. 18. 16. B. 14. 24. 25. 20, 5 5. 9. 2. 0. 2. 48, 35. 0>> 7, B. 8. 18. 29. 22 ~
5 0. 0. 0. 0~ 0. 0~ 8; 16
25. 26. 10. 4. l. 1.
5 5 O. 0. 0. 0. 0~ 0. I. 14. 13. 5>> I 2~ l. 0. 0, 5 6 0. O. 0. 0. 0. 0. 0. 0~ O. 16. 0. 0. 0. 0. 0. 0.
5 7 0. 0. 0. 0. 0. 0. 0. 0. 0. l. 0. 0, 0, 0, 0. 0.
6 I O. 0. 0. 0. 0. 0~ 0. 0. l. 0. 0. I ~ 0. 0. 0, 0, 6 ? 15. 12. 0. 2. 5>> 8. 15. 6. 11. 9. 11. 25, 22.
6 6
6 5 11.
0.
0.
5>>
0, 0.
10.
0.
0.
0.
0.
0.
0, 0.
1.
0.
0.
7.
5>>
3..
25.
7>>
0.
18.
l.
'.B.
2>>
B.
1.
0.
4>>
0.
0.
2.
0.
12, 2.
Q.
14 ~
0.
0.
14.
0.
0.
6 6 0. 0. 0. 0~ 0. 0. 0. 0~ 0. l. 0. 0. 0. 0. 0. O.
6 7 0. 0, 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0, 7 0. 0. O. G. 0. 0. 0. 0. 1, 0, 0. 0. '0. 0. 0.
7 2 14. 12. 6. 6. 3. 2. 9. 6. 10. 4. 5. 5. 13. 16. 16.
I l. 6. 2~ 0. 0. 3. 18. 2. h.
I 4 0. 0. 1. 0. 0. 0, 0, 0. 5~ l. 0. 0. 0. 0. G. 0.
7 0. 0. 0, 0, 0. 0, 0, 0, 0. 0. 0. 0. 0. 0~ 0~ O.
I 6 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0. 0. 0. Q. 0~ 0~
2 7 G. 0. 0. 0. G, O. 0. 0. 0. 0. 0>> 0. 0, 0. 0.
TOTAL NUNBEP. OF HOURS USED
"-1640 NISSINS = )AI >>N
= VARIABLe TAELc 5-8 4TH QUARTER 1986 JOINT FREQUEHCY DISTRIBUTION FOR THE 245 FT LEVEL CALCULATED FROH HOURLY AVERAGES FROH TAPE IttUtt MIND SPEEDS FOR EACH CATEGORY IH HPH ARE:
F 6 2 - 3.0 3 - 7.0 4 - 12.0 5 - 16.0 24.0 HUHBERS GIVEN ARE HO'JRS STAB lilttD hKE tK EViE cS- Si SSE SS'>> SV KSH HH>> h">> Htl>>
CLASS CAT I 0~ 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0.
2 l. 1. 2i 0. l. 1, 0. 2>> 0. 0. 0. 20 l.
1 3 0. 0. 0. 0. 0. 0. 0. 1. 0~ 0. 0. l. 0. 0. 0. 1, I A
>> V~ 0~ G. 0. 0, 0. 7 ~ 3. 1. 0. 0. 0. 0.
1 5 0. 0. 0.'. 0. 0. 0. 0. l. 0. 1. 3. I ~ 0. 0. 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.
n C 1 0. 0, 0. 0. 0. 0. 0. 0, 0. 0. 0. 0, 0. 0. 0. 0, 2 21 I. 0. 0. 0. 0. 0. 0. 0. 2~ 1. 0. I, 2 0. 0. 0. 0. 1. 0. 0. 0. 1. 0. f. 0. 0. 0. 2. 0.
2 l. 0. 0. 0, 0. 0. 0. 0. l. 0. 20 3. 0. 0~ 0. 0.
5 0. 0. 0. 0 0. 0, 0. 0. 0. 0. 0, 0. 0. 0~ 0. 0, 2 6 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0, 0. 0.
C 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. 0. 0. 0. 0, 0.
2 1. aO 0. 1. be 20 0. 0. 0. 0. 1. 2l 1 ~ 3. 2~
3 0. t. 3, i. 0. 0. 0, l. 20 0, 0, 0, 0. 0.
4 2I 1. 0. Oe 0. 0. 0. 2>> 0. 0. 0. 0. 0., 0. l.
5 0. l. 0. 0. 0. 0. 0. 0. 0. 2~ 1. 1. 2~ 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. 0. 0.
1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 1. 0. 0. 0. 0, n
14. 8. 1. 20 6 S. 7~ 12, 6. 5~ 6, lb. 17 ~
4 15. 13. 8. 4. 5. 0. 11 16. 16. 5. 5. 20 8. 17, 12 ~
18 8~ 2. 0. 0. 0~ 0. 5. 11. 4 ~ 6. 2~ 20 7~ 14.
l.
4 5 20 0. 0. 0. 0. 20 3. 5. 7>> 1.
6 0. 0. 0. 0. 0. 0. 0. 0. 0. 2~ 0. 0. 0. 0. 0~
7 . 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 2I 0. 0. 0'. 0.
5 'I 0e 0. Oe 0, 0. 0. 0. 0. 0. 0. 0. 0. 20 l. 0. 0 ~
5 2 10. 8. 7. 4. 7. 6. 10. 12. 12. 7. 12. e. 6. 12.
5 25. 19, 11. 15. 12, 4, 12. 18. 23. 11, 5I 12. 13. 22. 21.
5 4 6. 2l 0. 0. l. 1. 1. 7. 11. 2$ , 20, 10. 2>> 3. 5. 16, c
5 0. 0, 0. 0, 0, 0, 0. 7. 6. 12 20. 17. 3. 1 ~
5 6 0. 0, 0, 0, 0. 0, 0, I, 2. 7. 10. 8. 4. 0. l. 0~
5 7 0. 0. 0, 0. 0. 0. 0. 0. 1. 14. 16. 0. 0~ 0. 0.
6 1 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
6 2 5, 7. SI 0, 7. 5. 4. 8. 6. 5~ 5. 6.
6 23 ~ 16. 13. 11. 3. 2. 9. 10. 8. 11. 7. 6. 70 14. 16.
6 5. 0. l. 0. 1. 0. 0. 10. 8. 10. 6. 5. 8. 17 6 5 0. 0, 0, 0. 0. 0. 0. 0. 3. 7. 8. 20 0. 0o 6 6 0. 0. 0. 0. 0. 0. 0. 0. 0. i. 3. 20 0, 0~ 0~ 0.
6 7 0. 0. 0. 0. 0. 0. 0. 0. 1, 20 0. 0. 0~ 0~ 0. 0.
7 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0, 0. t~
~ 0.
7 4~ 7. 20 8. 5. 6~ 2l 6. 7~ 5. 50 6. 1 ~
7 3 10.. 7. 9. 21 3. 2I 10, 14. 10. 8. 7, 2>> 2i 11.
7 20 0. 1 ~ 0. 0. 0. 0. 5. 9. 2~ 1. 0. 3~
7 5' 0, 0. 0. 0. 0. 0, 0, 0, 1. 0. >>~ 0. 0. 0.. 0.
7 0. 0. 0. 0. 0. 0. 0. 0, ~ 0. 0. 0. 0. 0. 0. 0.
7 7 0, 0. 0. 0. 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
TOTAL HUttBER OF HOURS USED = !686 HISSIHG = CALH = VARIABLE 66
)966 YEARLY JOINT FREOUcNCY DISTRIBUTION FOP THE 33 FT LEVEL CALCULATED FRON HOURLY AYERA6ES FRON TAPE NAKINUN HIND SPEEDS FOR EACH CATE6&RY IN NPH ARE:
0.6 ?- 3~ 0 3- 70 4 - I?.Q 5 - 18 ' 6 - 24.0 HUNBERS 6IVEH ARE HOURS STAB HI!6 Hff EKE CCC C SCc SSF SH HH>.'H NHN CLASS CAT I 0. 0. 0, 0. 0, 0, 0. e. 0. 0. 0~ 0. 0. 0. 0. 0.
1 2 lo 8. 20 2. I ~ 15. 15. 13. 50 18, 12. 11. 18. 20.
I 36 2&, -15. DI 1. 35. &O. 87. 31. 36. 29. 21. 29. 37. 45.
1 '0.
le. 4. O. 0, 2. 9. 21 55. 31, 24. 24, 10. 23. 3. 16, I 5 0. 0. 0. 0. 0. Q. 0. 0o 15. 8, O. 18. I ~ 0 6 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. I. 2. 0. 1. 0. 0~
7 0. 0. 0. 0. 0, 0. O. 0. 0. O. O. 0. 0~ 0. 0. 0.
2 '0. O. 0. 0. 0. 0. O. O. 0. 0. 0. 0. 0. 0. 0. 0, 2 ? 9. 4, 0. I. ?I 5, 9~ Ibad 5~ 5~ 10. 6, 9. 6~ 6,
12. 12. 10. 6~ 7. 10. 19. 16. 15. 14. 14. 10. 17. 11. 11.
1 6. 5. I. 0, 0. 17. 50 3. 11. 6. 3.
2 5 20 e. 0. 0, 0. 0. 0. 0, 0. 1. I. 2, 0. 5i 20 0.
2 6 0. 0. 0, 0~ Q. 0, 0. 0. 0. Q. 0. 0. 0. I. Q. 0.
2 7 0. 0. 0. 0. O. 0. 0. O. 0. 0. 0. 0. 0. 0. 0. 0.
3 j O. 0. 0. V~ O. Q. 0. 0. 0. 0, 0. 0. 0. I.
2 9. 4. 4, 2. 2. 2. 7. 1. 6. 7. 8. 10. 7.
14. b. I~ 5~ 6. 21 ~ 11, 13 17. 10. 16. 12. 18 ~
6. 0. 1. 0. 7. 12. 8. '9. 11. 20 4.
5 0. 0. 0. 0. 0. 0. . 0. 0. 1. 0. l. 20 ho 21 l.
6" 0. 0. 0. Q. Q. 0. 0. 0. 0. 0. 0. 1. 0. 1. 0. 0.
3 7 0. O. O. O. 0. O. 0. 0. 0. 0. 0. O. 0 0. 0. 0. '.
4 1 1. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. Q. 0. 0. 0.
2 33. 15. 50 8. 7, 22 I 17. I&. 26, 15, lb. 29, 22, 35, 30, 4 %I 50 21. 20. 8. 21 ~ 41. 65 45. 39. 18. 30. 36. 59. 80. 75.
23. 7I 0. 0. 1.'. 30 11. '3.
29, 36. 21. 12. 42. 23, 28, 4 5 0. 0. O. 5. 0. 4~ 4. 4, h. 11. 36. 6. 20 6 0. 0. 0, 0. 0. Q. 0. O. 0. 0, 0. Q. ?I O. 0.
4 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. Q. 0. 1. 0. 0.
5 0. 0. e. Q. 0. 0. 1. 0. I. 1. 0. 0. Ie l.
5 2 51 ~ 26. 17, 10. 21. 27. 40. 46. 60. 50.. 51. 39. &b. 91. 78. 61.
5 ?Oe 20. 17. 19. 50. 76. 107 73. 50. 31, 64. 110. 169. 109. 82.
.5 4 1. I. 0. Q. l. 28, '8.
44 43. 17. 18. 53 t 75. 31. 11.
C 5 5 0. 0. 0. 0. 0. 0. 5. 21
'4,
17. 5. 1. 12. al ~ 1. 0.
5 0. 0, 0, 0, 0. 0. 0, 16, 0, 0. 0. 0. 0. 0.
5 7 '0. 0. 0. 0. 0, 0. 0. 0. 0. l. 0. 0. 0. 0. Oo 0.
6 I O. 0. 0. 0. 0. 0. O. 0. 2i 0. 0. ?t 20 0. O. 0.
6 2 28 ~ 16. 8. 6. 24. 38. 51. 38. 35. 36. 43. 53. 83. 71.
6 43. 17. 82. 99. 87. 41. 28. 40. 34. 90. 96. 55.
6 O. 0, 0. 0. 0. 1. 10. 19. 12. ?0 ?l 7. 6~ l.
6 5 0. 0. 0. 0. 0. 0. 2I 5~ 9, 5. 0. O. 0. 0. 0. .0.
6 6 Q. 0. 0. 0. 0. 0. 0. 0. 0. Q. 0. O. 0. 0.
6 7 0. 0. 0, 0. 0, 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
7 0~ 0~ 0. 0. Q. O. 0. 0~ 1 ~ O. 1. 0. O. 1. 0.
7 2 43, 40. 13. 12. 10. 13. 24 31. 26. 30. 13. 20. 29. 46 ~ 60. 58.
7 3 26. 20. 5l "I, '7,
'2.
89. 48. 19. 12. 7. 18. 46. 33. 30.
7 I. 1. 2. 0, 0. 3~ 6. 8. 8. 0. 0. l. 0. l. e.
7 5 O. O. Q. 0. e. O. 0, ?0 Q. Q. 0, 0, 0. 0. 0, 0.
7 6 e. 0. 0. 0. 0. 0. 0. l. 1. 0. 0. 0. 0. 0. Q. 0.
7 7 O. 0. 0. 0. O. Q. Q. 0. 0. 0. 0. O. 0. 0. 0. O.
TOTAL HUNBER OF HOURS USED = 7746 NISSIHG = 56 CALN VARIABLE 258
TABLE 5-10 1'986 YEARLY JOINT FREQUENCY DfSTRIBUTIOM FOR THE 245 FT LEVEL CALCULATED FROM HOURLY AVERAGES FROtl TAPE HALIUHliIHD SPEEDS FOR EACH CATEGORY It( t!PH ARE; 0.6 2 - 3.0 3 - 7.0 4 - 12.0 S - }8,0 6- 24,0 NUHBERS GIVEN ARE HOURS STAB NINi'LASS Ntii NE EKE ESE SE SS. SSS S'h NSL'N'h Ntjl' CAT
0. 0. 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0. 0. 0.
2
9. ae 0. 3, l. 9. 18. 14. 18. 19. 10. 11. 15. 15.
1 20. 23. 19. 6. 11. 25. 51 ~ 43. 52. 43. 38. 36. 42. 38, 29, 37. t ?h 15
'e h
e) ~ 4~ C ee ~ 8. 12 ~ 37. 17. }2, 27. 12. 20. 20. 1 5 5e 2~ 0. P. 0. 0. 2e f. IP. 18. 6. 18. 12. ae 1 6 1. )~ 0. 0. 0. 0. 0. 0. 0. 7. 2. l.. 0, 6, 7 0, 0. 0. 0, 0, 0, 0. 0. 0 ~, 0, 0~ 0~ 0. 0. 2 I 0. 0. 0. 0. 0. l. 0. 0. 0. 0. 0. 0. 0. 0. 0~ 2 2 5. 0. l. 2~ 0, 5. 6. 5 7. 5. 10. 2~ 3. 2 3 16. 4. 15. 2. 4. 10. 10. 10.. 18. 22. 19. 14. 11. 6. 15. 2 4 16. Se 0. 0. 0. 0. 5e }j. 1}. 6, 6. 7. 5. e he 2 5 0. 0. 0. 2. 0. 0. 0. )
~~ 0~ I. 2e l. 2e 3. 0.
2 6 0. j. 0. 0. P. 0. 0. 0. 0. }I 1, l. 0. 2 7 0. 0, 0, P. 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.
2 5e 5. 4. 11. 4. l. 9. 3. 2. 11. 3 }7. lb. 15. 3~ 5~ }0. fe. 18, 12. 11. 11. 14. 11. 9. f2.
5. 5. 1. 2. 5e 6. 6. 9. lf. 6. 8. 4, 5 2. 0. P. 0. 0. f. 0. 3. 2e 6. 2e ae 6 0. 0. 0, 0, 0. 0, 0, 0. 0. 0, l. l. 2e 2e 1. 0.
7 0. 0, P. 0. 0~ 0. 0. 0. 0. 0. 0. 0~ 0. 1. 0. 0. 1 0, 0. 0~ 0. 0. 0. 0. 0. 0. 0. 0, 0. 0. 0. 0.
') 31. 7. 5.
16. 2. 11. 11. 14. 24. 24. 15. 10. 14. 12. 35. 32e t 62. 21. 15. }8. 14. 14. 37. 53 e 46. 20. 31. 24. 34. 48. 65.

52. 17, Se 6. 4~ 5. 5~ lb. 22e 26. 'g, 28. 15. 11 4} ~ 32e 4 5 18. 21. 4. 3. 2. 1. 3e 8, 25. 15.
'9.
37. 6.
6 0. b. b. 0. 0. 0. 2, 2e l. l. 2e 0. h. 5. f3. 0. 4 7 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 2e 1. 1. 2~ 0. S 1 1 ~ 0. 0. l. 0. 1. 2e 0. 2e 0. f. ~ 2~ 3. le 0. 5 1 33 22e 22. 12. }l. 14. 19. 31. 40. 39. 27. 28. 32e 21. 35. 47, 5 3 '00. 54 27. 22e 13. 13. 43. 7e. 65. 27e 31. 51. 63. 89 ~ }39, 5 4 69,
'7.
8. 6. 8. 7. 34. 45. 51. 48. 26. 23. 57. 89, 69.
5 5 '?. 4, 5, 0. 12. 15, 26, 38. 33. 16. 46. 53. 13 ~ 5 6 0. 0. 0. 0. 0. 0. 0. l. 2e 10. 23. 9. 4. 11. 0, 5 7 0. 0. 0. 0. 0~ 0. 0. 0. 2~ 14. 5e 16. 0. 2. 0. 0. 6 1 0. 0. 0. 0. 0, 1. 0. pe 0. 0. 0, 1 ~ 0. 1. 1 ~ 0. 6 2 28, 25. 14. 14. 10 17, 17. }6. 21. 24. a0e a2e 2je 2}, 14 23, 6 78, 55. 23. 28. '3. 17, 14 ~ 37. 47. 41. 53, 37. '5. 73. 6 19. 8. 13. 10. 10. 9, 19, 42, 39, 29, }6. 20, 36. 73. 73. 6 5 1. 2e 0. 0. 0. 0. 0. 0. 3e 14. }6. 7. 10. 11 ~ 5. 6 6 0. 0. 0, 0. 0. 0~ 0. 0. 0. 11. 4. 0. 0. 0. 0. 6 7 0. 0. 0. 0. 0. 0, 0. 0. 4e 2e 1, l. 0. 0. 7 I 2e 0~ P. 0. 0, 0. 0. 0. 0. 0. 1. 0. P. 0. 2e 0. 7 2 18. 23. 13. }9, 13. 11. 12. 12. 20. 28. 23. 15. 19, 19. lb. 7 58. 15, 30. 32e 13. 39. 53 e 39. 30. 25. 13, 21. 34. 7 4 5. 1}. 6. 1, 2. 11. 22. 19. 11. 3. 6. 13. 3}, 38 ' 7 0. l. 3. 0. P. 0 I ~ 0. 0. 8~ 7. 0. 3. a~ ~ 7 0 0. 0. 0. 0. 0. 0. 0~ 0. 0. 0. 2. 0. 0. 0. 0. 0~ 7 7 0. 0. 0. 0. 0. 0~ 0. 0. 1. 0. 0. P. 0. 0, 0 ~ TOTAL NUtlBER OF HOURS USED = 785? '}jcSINS CAIN = VARIABLE = 148
6.0 DOSE ASSESSMENT - IMPACT ON MAN Liquid Effluents - Pl >> The doses
'gto the maximum individual from WNP-2 specific input parameters applicable to the reporting period (e.g., food liquid 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 WNP-2 slough area and eats food locally grown at the Riverview area district southwest of Pasco, Washington.
Table 6-1 lists the doses to the maximum individual by calendar 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 doses were calculated using the LADTAP II computer code. Gaseous Effluents - The GASPAR computer code was used to calculate doses a e . m> e site boundary and Taylor Flats, located at 4.2 miles southeast. The sector with the highest X/Q values at the 1.2 mile loca-tion was used to verify compliance with Technical Specifications. The quarterly GASPAR runs utilized the quarterly averaged X/Q and D/Q values, and site 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 Specification 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 evaluated. Table 6-4 lists the doses at these special locations. 6.1 Exposure to "A Member of the Public" The WNP-2 Visitor Center was evaluated for assessment of radiation doses to "Members of the Public", due to thei r activities withi n the site boundary. The ODCM assumes an eight (8) hour per year occupancy by "A Member of the Public" at the Visitor Center. The dose assess-ment resulted in an annual calculated whole body dose of 1.1E-02 mrem. The annual thyroid dose was 6.9E-02 mrem and the maximum dose to any other organ was 1.3E-02 mrem. The annual assessment of radiation doses to the likely most exposed "Member of the Public" to show conformance with 40CFR Part 190 is assumed to be located in the Taylor Flats vicinity (4.2 miles SE). The Gaspar computer code with annual source terms and XOQDOQ meteorological data was used to obtain the dose assessment from gaseous effluents. It is assumed there is no dose contribution from
'liquid effluents at Taylor Flats. The assessment resulted in annual calculated whole body dose of 9.0E-03 mrem. The annual thyroid dose was 4.7E-02 mrem and the maximum dose to any other organ was 9.7E-03 mrem.
The direct radiation contribution showed no significant amount above normal background for that area which is approximately 80 mrem per year.
Table 6-1
.MAXIMUM IHDIV-IDUAL DOSES FROM WNP-2 LIQUID,EFFLUENTS 1ST AND 2ND QUARTERS 1986 First Quarter 1986 19 198 Cumulative Cumulative Whole Body Whole Body Max. Organ. Nax. Organ.
Pathway (mrem/ tr) (mrem/yr) (mrem/qtr) (mrem/yr ) Drinking 3.7E-07 3.7E-07 5.0E-07 5.0E-07 Shorel i ne 1.1E-07 1.1E-07 1.3E-07 1.3E-07 Swimming 6.5E-10 6.5E-10 6.5E-10 6.5E-10 Fishing 7.4E-04 7.4E-04 1.1E-03 1.1E-03 Boati ng 7.9E-10 7.9E-10 7.9E-10 7.9E-10 Leafy Veg. 8.3E-08 8.3E-08 2.1E-07 2.1E-07 Vegetables 5.3E-07 5.3E-07 1.0E-06 1.0E-06 Mi 1 k 1.3E-05 1.3E-05 1.9E-05 1.9E-05 Meat 4.6E-08 4.6E-08 1.1E-07 1.1E-07 Total 7.5E-04 7. 5E-04 1.1E-03 1.1E-03 Second Quarter 1986 9 Cumul ati ve Cumul ati ve Whole Body Whole Body Max. Organ. Max. Organ. Pathway (mrem/qtr) (mrem/y r ) (mrem/ tr) (mrem/y r) Drinking 3. 5E-06 3.9E-06 5. 1E-06 5. 6E-06 Shoreline 4.0E-06 4.1E-06 4.6E-06 4.8E-06 Swimmi ng 2.2E-08 2.2E-08 1.1E-06 1.1E-06 Fishing 2.2E-02 2.2E-02 4.2E-02 4.4E-02 Boating 2.5E-07 2.5E-07. 2.7E-07 2.7E-07 Leafy Veg. 1.5E-06 1.5E-06 3.0E-06 3.2E-06 Vegetables 8.3E-06 8.8E-06 1.5E-05 1.6E-05 Milk 4.3E-04 4.5E-04 8.9E-04 9.1E-04 Neat 1.5E-06 1.5E-06 2.9E-06 3.1E-06 Total 2.2E-02 2.2E-02 4.3E-02 4.5E-02 Table 6-1 MAXIMUM INDIVIDUAL DOSES FROM WNP-2 LIQUID EFFLUENTS(1) 3RD AND 4TH QUARTERS 1986 (Continued) Third Quarter 1986 Cumulative Cumulative Whole Body Whole Body Max. Organ. Max. Organ. Pathway (mrem/qtr) (mrem/yr) (mrem/ tr) (mrem/y r) Drinking 3.1E-07 4.'2E-07 4.3E-07 6.0E-07 Shoreline 1. 2E-07 4.2E-06 1.4E-07 4.9E-06 Swiomi ng 6.1E-10 2.3E-08 6.1E-10 1.1E-06 Fi shing 8. 4E-04 2.3E-02 1.4E-03 4.5E-02 Boating 8.3E-09 2.6E-07 8.3E-09 2.8E-07 Leafy Veg. 8.0E-08 1.6E-06 1.8E-07 3.4E-06 Vegetables 5.0E-07 9.3E-06 9.0E-07 1.7E-05 Milk 1.4E-05 4.6E-04 2.4E-05 9.3E-04 Meat 4.9E-08 1.5E-06 1.1E-07 3.2E-06 Total 8.6E-04 2. 3E-02 1.4E-03 4.6E-02 Fourth Quarter 1986 Cumulative I Cumulative Whole Body Whole Body Max. Organ. I h1ax. Organ. Pathway (mrem/qtr) 'mrem/yr) (mrem/ tr) (nrem/y r ) Drinking 4.5E-07 4.7E-06 7.0E-07 6.7E-06 Shorel i ne 3.9E-07 4.6E-06 4.5E-07 5.4E-06 Swimmi ng 2.2E-09 2.5E-OB 2.2E-09 1. 1E-06 Fi shing 1.3E-03 2.4E-02 2.1E-03 4.7E-02, Boating 3.3E-08 2.9E-07 3.3E-08 3.1E-07 Leafy Veg. 7.4E-08 1.7E-06 2.4E-07 3.6E-06 Vegetables 5.3E-07 9.8E-06 1.2E-06 1.8E-05 Milk 2.3E-07 4.6E-04 3.9E-07 9.3E-04 Meat 7.6E-08 1.6E-06 2.0E-07 3.4E-06 Total 1. 3E-03 2.4E-02 2.1E-03 4.8E-02 (1) Age Group - Adult: Maximum individual resides at Richland and fishes at the WNP-2 slough area.
-33
Table 6-2 AVERAGE INDIVIDUAL DOSES FROM WNP-2 LIQUID EFFLUENTS 1ST AND 2ND QUARTERS 1986 Total er 1st Quarter Total er 2nd Quarter IMax. Or an. Whole BodylMax. Organ. Whole Bodyl Pathway (mrem1 (mrem) (mrem) (mrem) Fish 2.8E-06 1.8E-06 1. OE-04 5.3E-05 Drinking Water 2.9E-07 2.2E-07 3.0E-06 8.5E-06 Shorel i ne 4.3E-09 3.6E-09 1. 6E-07 1. 3E-07 Swimming 7.6E-ll 7.6E-ll 1.6E-09 1.6E-09 Boating 4.5E-ll 4.5E-11 9.5E-10 9.5E-10 Vegetables 3.3E-06 1.6E-06 2.0E-05 1.3E-05 Leafy vegetables 3.2E-06 1.2E-06 2.3E-05 1.1E-05 Milk 1.2E-07 7.7E-08 3.9E-06 1.9E-06 Meat 5.2E-08 2.5E-08 1.2E-06 5.8E-07 Total 9.8E-06 4. 9E-06 1.5E-04 8. 8E-05 3RD AND 4TH QUARTERS 1986 I Total er 3rd Quarter I Total er 4th Quarter (Max. Organ. Whole BodylMax. Organ. Whole Bodyl Pathway (mrem) (mrem) (mrem) (mrem) Fish 3.4E-06 2.1E-06 4.8E-06 3.4E-06 Drinking Water 2.6E-07 1.8E-07 4.2E-07 2.7E-07 Shorel inc 4.7E-09 4.0E-09 1.5E-08 1.3E-08 Swimming 6.8E-11 6.8E-11 2.7E-10 2.7E-10 Boating 4.0E-11 4.0E-11 1.6E-10 1.6E-10 Vegetables 1.5E-06 8.1E-07 2.0E-06 8.4E-07 Leafy vegetables 1.4E-06 6.0E-07 1.8E-06 5.6E-07 Milk 1.0E-07 6.3E-08 1.6E-07 9.3E-08 Meat 4.6E-08 2.0E-08 8.0E-08 3.1E-08 Total 6.7E-06 3.8E-06 9.3E-06 5. 2E-06
Table 6-3 50-MILE POPULATION DOSES FROM WNP-2 LIQUID EFFLUENTS 1ST AND 2ND QUARTERS 1986 Total er 1st Quarter Total er .2nd Quarter IMax. Or g an. Whole Body lMax. Organ. Whole Bodyl Pathway I (man-rem) (man-rem) (man-rem) (man-rem) Fish 1.8E-06, 1.1E-06 6.5E-05 3. 4E-05 Drinking water 1.7E-05 1.3E-05 1.7E-04 1.3E-04 Shorel i ne 1.4E-06 1.2E-06 5.1E-05 4.4E-05 Swimmi ng 2.5E-OS . 2.5E-OS 5.2E-07 5.2E-07 Boating 6.2E-09 6.2E-09 1.3E-07 1.3E-07 Vegetables 3.6E-05 1.7E-05 5.1E-04 2.9E-04 Leafy vegetables 3.5E-OG 1.3E-05 2.8E-04 4.0E-04 Milk 1.8E-06 1.1E-06 8.3E-OG 4.2E-OG Meat 5.3E-07 2.5E-07 8.5E-06 1.6E-05 Total 9.4E-05 4. 7E-05 1.2E-03 9.6E-04 3RD, AND 4TH QUARTERS 1986 I Total er 3rd Quarter Total er 4th Quarter IMax. Organ. Whole BodylMax. Organ. Whole Body Pathwa l(man-rem) (man-rem) (man-rem) (man-rem) Fish 2.2E-06 1.2E-06 3.4E-06 2.0E-06 Drinking water 1.6E-05 1.1E-05 2.4E-OG 1.6E-05 Shorel i ne 1.5E-06 1.3E-06 5.0E-06 4.3E-06 Swimming 2.2E-08 2.2E-OS 8.7E-OS 8.7E-OS Boating 5.5E-09 5.5E-09 2.2E-OS 2. 2E-08 Veg etabl es 3.3E-05 1.6E-OG 3.3E-05 1.6E-05 Leafy vegetables 3.1E-05 1.2E-05 2.9E-05 1.1E-05 Mi 1 k 2.2E-06 1.3E-06 3.3E-06 1.9E-06 Meat 5.5E-07 2.7E-07 9.7E-07 4.2E-07 Total 8.6E-05 4.3E-05 9.9E-05 5.2E-05 Table 6-4
SUMMARY
OF DOSES FROM WNP-2 GASEOUS EFFLUENTS CALENDAR QUARTERS 1986 Location: 1.2 miles site boundary tl I I I , .88 First Second Third Fourth Annual Quarter Quarter Quarter Quarter Cumulative Beta air dose (mrad)* 3.4E-02 2.7E-01 4.0E-02 7.0E-02 1.5E-01 Gamma air dose (mrad)* 5.7E-02 3.7E-03 6.6E-02 1.2E-01 2.5E-01 Location: Taylor Flats, 4.2 miles Il <<Pt First Quarter Second SE Quarter
>> Third Qua rter I', ll Fourth Qua rier Annual Cumul ati ve Maximum organ dose 3.5E-03 3.9E-03 2.6E-02 7.8E-03 4. 1E-02 (mrem)~
Technical Specification 3.11.2.2.
** Technical Specification 3.11.2.3.
7.0 REVISIONS TO THE ODCM During this semi-annual reporting period, no revisions were made to the Offsite Dose Calculation Manual (ODCM).
Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 February 24, 1987 G02-87-063 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Gentlemen:
Subject:
NUCLEAR PLANT NO. 2 SEMI-ANNUAL EFFLUENT REPORT JULY 1, 1986 TO DECEMBER 31, 1986 (ATTACHED) In accordance with Title 10 of the Code of Federal Regulations, Part 50.36a (a) (2), the subject report is herewith being submitted. Should you have any questions, please contact Mr. R. G. Graybeal, Manager, WNP-2 Health Physics/Chemistry. Very truly yours, C. M. Powers WNP-2 Plant Manager tmh Attachment cc: JO Bradfute - NRC C 'schels - EFSEC D Jaquish - DOE JB - Hartin NRC RV (2) D Sherman - Amer. Nuclear Insurers TR Strong - DSHS JM Taylor - NRC NRC Site Inspector
l-
'C}}

ML17278B198

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