ML17286B030

WNP-2 Semiannual Radioactive Effluent Release Rept for Jan-June 1991. W/910828 Ltr

ML17286B030
Person / Time
Site:	Columbia
Issue date:	06/30/1991
From:	John Baker WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-91-158, NUDOCS 9109050190
Download: ML17286B030 (56)

Text

ACG7LERATED DEMONSTION SYSTEM DILUTION REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9109050190 DOC.DATE: 91/06/30 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BAKER,J.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"WNP-2 Semiannual Radioactive Effluent Release Rept for WPPS Unit 2 for Jan-Jun 1991." W/910828 ltr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR TITLE: 50. 36a(a) (2) Semiannual Ef fluent Release i ENCL Reports J SIZE: 3 ) D NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 3 3 PD5 PD 1 1 ENG,P.L. 1 1 D INTERNAL: ACRS '1 1 AEOD J)S>. 1 1 D NRR/DREP/PRPB11 2 2 1 1 RGN5 DRSS/RPB 2 2 RG 5 FILE 02 1 1 EXTERNAL: BNL TICHLER, J03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 R

D D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bar 968 ~ 3000 George Wasbtngton Way ~ Rtcbland, Wasbtngton 99352968 ~ (509) 372-5000 August 28, 1991 G02-91-158 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 SEMI-ANNUAL EFFLUENT REPORT JANUARY 1, 1991 JUNE 30, 1991 In accordance with Title 10 of the Code of Federal Regulations, Part 50.36a(a)(2), and section 6.9. 1. 11 of the WNP-2 Technical Specifications 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, J. W Baker WNP Plant Manager TEC/bk Attachments CC: JB Hartin - NRC RV NS Reynolds - Winston & Strawn PL Eng - NRC DL Williams - BPA/399 NRC Site Inspector - 901A D Sherman - American Nuclear Insurers TS Strong - DSHS RG Waldo - EFSEC 9i09050i90 9i0630 PDR ADOCK 05000397 PDR I

,C>

~I 1

REFERENCE:

10CFR50.36m(a)(2)

WNP-2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY THROUGH JUNE 1991 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LICENSE NO. NPF-21

TABLE OF CONTENTS

1.0 INTRODUCTION

. ~

1 2,0 LIQUID EFFLUENTS ~

1 3.0 GASEOUS EFFLUENTS ~

5 4.0 SOLID RADIOACTIVE WASTE 19 5.0 METEOROLOGY 24 6.0 DOSE ASSESSMENT IMPACT ON MAN 25 7.0 REVISIONS TO THE ODCM 26 8.0 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP) 27 9.0 NEW OR DELETED LOCATIONS FOR DOSE ASSESSMENTS AND/OR ENVIRONMENTAL MONITORING LOCATIONS.

28 10.0 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS. ~

29

LIST OF TABLES ILIU; 2-1 WNP-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES JANUARY JUNE 1991 2 2-2 WNP-2 LIQUID EFFLUENTS SOURCE TERMS JANUARY JUNE 1991 . 3 3-1 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS MIXED MODE RELEASES MAIN PLANT VENT JANUARY JUNE 1991 ~ 9 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING JANUARY JUNE 1991 12 3-3 HNP-2 GASEOUS EFFLUENTS, SOURCE TERMS GROUND LEVEL RELEASES RADWASTE BUILDING JANUARY JUNE 1991 ~

15 3-4 WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES JANUARY JUNE 1991 17 3-5 WNP-2 GASEOUS EFFLUENTS BATCH RELEASES JANUARY JUNE 1991 ~

18 4-1 SCALING FACTORS FOR REQUIRED NUCLIDES. 21 4-2 SCALING FACTORS FOR CONDITIONAL NUCLIDES 21 4-3 HNP-2 SOLID HASTE SHIPMENTS JANUARY JUNE 1991 ~

22 11

This report is submitted in compliance with 10CFR50.36a(a)(2) and 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 The radwaste liquid effluents were released in "batch mode" during the reporting period. No liquid releases occurred during the first calendar quarter and 26 batch releases occurred during the second calendar quarter. The total time period for the batch releases was 49.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, with the maximum, minimum and average time periods for a release being 2.8, 0.3 and 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, respectively. The volume of dilution water considered is assumed to be the total volume of recirculating cooling tower blowdown flow for the period. The average flow rate of the Columbia River during January through June 1991 was 1.59E+05 cubic feet per second.

Computer runs, using LADTAP II, were performed to verify compliance with Technical Specification limits. There were no liquid releases during the first quarter. The second quarter calculated dose for the maximum individual (adult age group) was 1.3E-03 mrem whole body and 2.2E-03 mrem for the maximum organ. No abnormal liquid releases occurred during this reporting period.

The liquid batch releases were recirculated prior to sampling. A representative sample was obtained and analyzed for each batch release.

A composite of the batch samples for each quarter was analyzed for strontium and iron. The methods used for measuring the total radioactivity were gamma spectroscopy, liquid scintillation and proportional counting. Table 2-1 provides a summation of all liquid releases during this reporting period.

The percent of MPC limit in Table 2-1 is based on the total of the MPC fractions using the nuclides in Table 2-2 and the concentrations listed in 10CFR20, Appendix B, Table 2, Column 2.

Estimated total errors are listed in Table 2-1, and are propagated from individual error estimates of sample activity, sample volume, tank volume, and tank homogeneity. The estimated total errors were calculated by obtaining the square root of the sum of the squares of the individual error contributions and multiplying by 1.96 for a 95% confidence level.

1 Table 2-1 WNP-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Report Period: January June 1991 I

Unit 1st'2nd'Est Quarter ,'uarter 'Total I

I I

I I

Error* ~O 0

A. Fission and activation products

1. Total release (not including I I I tritium, gases, alpha)

I Ci I

~

I NA I

~

I 2 'E 02 2 'E+01 I

I I I I

2. Average diluted concentration', I I

I I

during period 'uCi/ml', NA ( 4 ~ 9E 08 I I I I I Percent of MPC limit I I I I I 3 ~

I g+ I NA (

7 ~ 6E 02 B. Tritium

1. Total release Ci ~

NA ~

8 5E 01 2 ~ 2E+01 I I I I I I I I I I

2. Average diluted concentration', I I

during period 'uCi/ml'.

NA 1. 7E-06 I

Percent of MPC limit NA (

5 ~ 7E 02 I

C. Dissolved and entrained gases

1. Total release I Cx I

NA )

I

<1 1E 04

~

(

I 2 ~ 2E+Ol I I I I

2. Average diluted concentration',

during, period 'uCi/ml,' NA,'A I I

I I

3 ~ l Percent o f MPC imit I

I I

~+

4 I

I I

I NA,'A I I

I I

D. Gross alpha radioactivity

1. Total release Ci i NA i 3 ~ 2E 09 i 2 ~ 3E+01 E.

Volume of waste (prior to I I

I I

I I

I I

I I

dilution) ',liters~ NA ~

1 'E+06 ~

1 'E+01 F.

Volume of dilution water I l

,'liters,'NA I I I I I I used during period ~

5 OE+08 1 'E+01

• At 95% confidence level

Table 2-2 NNP-2 LIQUID EFFLUENTS SOURCE TERMS Report Period: January June 1991 BATCH MODE I

I I I

I I

I 1st 2nd I

Nuclides Released I

Unit Quarter Quarter I I Strontium-89 Ci

• NA 8.8E-06 I

Strontium-90 I

ci NA 5.6E-06 Cesium-134 Ci NA 2.5E-04 Cesium-137 Ci NA 4.2E-04 Iodine-131 Ci NA <7.7E-05 Cobalt-58 Ci NA 6. OE-04 I

I I Cobalt-60 Ci NA 6.7E-03 I

Iron-59 Ci NA 2.9E-04 I

Zinc-65 Ci NA 5.4E-03 II Manganese-54 Ci NA 5.8E-04 Chromium-51 Ci NA 9.5E-03 Zirconium-Niobium-95 Ci NA 2.0E-04 Molybdenum-99 Ci NA <8.4E-04 I

Technetium-99m Ci NA <3.1E-05 I I I I I

I Barium-Lanthanum-140 Ci NA <2.8E-04 I I I I I

Cerium-141 Ci NA 1.2E-04 Cerium-144 Ci NA <3.3E-04 I

I Iron-55 Ci NA 2- 7E-04

Table 2-2 (continued)

I I I I I I I

I 1st .2nd Nuclides Released Unit Quarter Quarter I I I I Others 1 I I Silver-110M NA 2.1E-04

,'Ci I I I I I I Total for period (above)

I I 2 ~ 5E 02 Xenon-133 l Ci I NA <5.4E-05 I I I I I I Xenon-135 Ci NA <5.9E-05 Tritium ci NA 8 ~ 5E Ol

• There were no liquid releases during the first quarter of 1991.

Note: Less than (<) values are not included in the Total For Period Values.

3.0 The gaseous radwaste effluents from HNP-2 were released from three (3) release points:

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, 3-2, and 3-3. Table 3-4 provides a summation of the total activity released, the average release rate, the percent of Technical Specifica-tion 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 iodi nes are sampled using particulate filters and charcoal cartridges both are analyzed using gamma spectroscopy.

The percent of Technical Specification limit for fission and activation gases (air dose) was determined for locations 1 through 7 and were based on quarterly limits of ten (10) mi llirads for beta and five (5) mi llirads for gamma. Locations 3 through 7 were used to determine the most restrictive value to be used in Table 3-4, Section A.3.

The percent of Technical Specification limit calculations for iodines, particulates with half-lives greater than eight (8) days and tritium are based on the quarterly limit of 7.5 mrem to any organ. Locations 3 through 7 listed below were used to determine the most restrictive value to be used in Table 3-4 for each quarter.

Total error estimates are propagated from individual error estimates of sample volume, sample activity 'and effluent flow rate measurements. The overriding uncertainty in all cases is in the measurement of the effluent and sample volumes. The estimated error was determined to be 36% at the 95/ confidence level.

Calculations were performed for releases using the GASPAR II computer program and parameters as outlined in the ODCM. Quarterly doses were determined at the following locations:

l~aijizLJ.: Site Boundary; 1.2 miles 1st Qtr. 2.0E-02 0.20 1.1E-02 0.22 2nd Qtr. 3.7E-03 0.04 5.1E-03 0.10 1st Qtr. 5.9E-02 0.79 2nd Qtr. 1.3E-02 0.17 Beyond Site Boundary; 4.0 miles ESE and 3.2 miles ESE, respectively (ground and inhalation pathways) at locations having the highest X/Q values for mixed mode release.

'hh 1st Qtr. 1.3E-03 0.01 8.0E-04 0,02 2nd Qtr. 3.0E-04 0.00 3.0E-03 0.06 1st Qtr. 4,3E-03 0.06 2nd Qtr. 2.6E-03 0.03

~L  : 4.8 miles SE (ground, vegetables and inhalation pathways) al Jb" ~~

1st Qtr. 1.8E-03 0.02 1. 2E-03 0.02 2nd Qtr. 2.0E-04 0.00 1.6E-04 0.00 h.

1st Qtr. 1 . 2E-02 0.16 2nd Qtr. 7.0E-03 0,09 3,~~~:

pathways) 6.4 miles SE (ground, meat, cow milk, and inhalation 1st Qtr. 9.1E-04 0.01 5.9E-04 0.01 2nd Qtr. 1.2E-04 0.00 1.0E-04 0.00 r D 1st Qtr. 3.4E-03 0.05 2nd Qtr. 1.1E-02 0.15 4.2 miles ESE (ground, vegetables and inhalation pathways) r D 1st Qtr. 1.4E-03 0.01 1.1E-03 0.02 2nd Qtr. 2.2E-04 0.00 2.9E-04 0.01 Hih r nD e . T ch. e 2nd Qtr.'.8E-03 1st Qtr.

7.6E-03 0.12 0.10

4.3 miles NE (ground and inhalation pathways)

A r 0 1st Qtr. 4.6E-04 0.00 3.5E-04 0.01 2nd Qtr. 6.5E-04 0.00 5.3E-05 0.00 r D 1st Qtr. 1. 3E-03 0.02 2nd Qtr. 4. 8E-04 0.01 4.1 miles ENE (ground, vegetables and inhalation pathways) 1st Qtr. 9.6E-04 0.01 7.0E-04 0.01 2nd Qtr. 6.8E-05 0.00 5.9E-05 0,00 UKQJll 1st Qtr. 5.4E-03 0.07 2nd Qtr. 4.0E-03 0.05 In addition to the reactor site, HNP-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. Also, near this location is a backup chemistry laboratory within the Emergency Operations Facility (EOF). The radiochemical hood within the chemi stry lab contains HEPA filters and is moni tored for radioactive releases when in operation. Gamma spectrometry indicated no radioactive material present other than that attributable to natural background.

There were no abnormal releases of gaseous effluent during the first and second quarters of 1991.

There were two reportable occurrences for inclusion into this Semiannual Radioactive Effluent Release Report.

1 ~ A PER, 291-432, was issued to correct a non-sampling condition; a temporary air flow cart was set up with improper valve settings which resulted in no noble gas, iodine or particulate collection for a 6-1/2 hour period. The reactor had been shut down for 39 days, no dose consequence to station personnel, equipment or general public was incurred.

2. A NRC inspection report 91-09 closed an Iron-55 analysis problem. A report, IR 89-15-03, opened an issue when the analytical cross check disagreed for Fe-55 results on liquid sampling. Evaluation of the

test found a standard lower in activity than was labeled. The liquid release calculations were overly conservative for the third quarter of 1990. The semi-annual reported value was a factor of 1.48 too high; the amended value for Fe-55 results should be 1.01 f-OS Ci. There was no dose consequence to the public.

The above mentioned occurrences had no adverse effect on plant emissions or the health and safety of the public or plant personnel.

I I

y r,v0}z

~ t I '( '*~ ~ $ 8'%i t

Table 3-1 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS MIXED MODE RELEASES MAIN PLANT VENT Report Period January June 1991 CONTINUOUS MODE I

I I I I 1st 2nd I

I Nuc lides Re leased I I

Unit Quarter Quarter I I

1. Fission gases Krypton-85 I

I Ci 4 2E+00 I3 I

I I

~ 6E+01 I

I Krypton-85m Ci 2 ~ 3E 01 I 2 1E 02 I I I I Krypton-87 Ci <5.6E-01 <4. 4E-01 I I I I Krypton-88 Ci <8.9E-01 <5.2E-01 I I Xenon-133 I

Ci 2.7E+00 '<6.7E-01 I

I I I Xenon-133m Ci <2 ~ OE+00 I < 1 ~ 1E+00 I I I I I I Xenon-135 Ci 4 ~ 0 E+ 0 0 I "1 ~ 9 E+ 0 0 I I I I Xenon-135m Ci 3.6E+00 7.2E-01 I I I

Xenon-138 Ci 1.2E+01 1.6E+00 I

OTHERS I I I Xenon-137 Ci 1. 6E+01 <2.2E+00 I I I I Argon-41 Ci 4.8E+00 4.8E-01 I I I I I I Total for period (above) Ci 4 3E+0 1 I 4 ~ 7E+00

0 f"

Table 3-1 (continued)

2. Iodines 1st 2nd Nuclides Released Unit Quarter Quarter I

I Iodine-131 Ci 1.1E-03 1.0E-03 Iodine-133 Ci 4.9E-03 3.5E-03 Iodine-135 Ci 1 ~ 6E 04 I <7 OE 05

~

I Total for period (above) Ci 6.2E-03 '.5E-03 I

3. Particulates 1st 2nd Nuclides Released Unit Quarter Quarter Strontium-89 Ci 5.5E-04 7.1E-04 Strontium-90 Ci 3.8E-06 1.1E-05 Cesium-134 Ci <2 9E 05

~

I 1 ~ 4E 05 I

I Cesium-137 Ci <3 1E 05

~

I 7 1E 05 I

I I Barium-Lanthanum-140 Ci 1 ~ OE 02 I 1 ~ 4E 04 I I I

Molybdenum-99 Ci <1. 9E-04 <1.6E-04 I

Cerium-141 Ci <2.0E-05 '1.7E-05 I

Cerium-144 Ci <9.3E-05 <8.1E-05 Cobalt-58 Ci <2.4E-05 1 ~ 9E 05 I

Cobalt-60 Ci 3.3E-04 1.5E-03 I

Iron-59 Ci <8.7E-05 <7.6E-05 I

I Manganese-54 Ci <2.3E-05 <2-OE-05 I

Zinc-65 Ci 5.9E-04 '7.2E-04 I

10-

t lg eu

'I ~

Table 3-1 (continued)

3. Particulates (continued)

I I I I I I

I I

I I

I 1st 2nd Nuclides Released I

Unit I Quarter Quarter I

I I I OTHERS, I I I I I

Chromium-51 Ci 7 ~ 7E 04 I 9 ~ 4E 05 I I I I I

Total for period (above) I Ci I

I 1 'E 02 I

I 3 'E 03 I

OTHERS with T 1/2 <8 days I I I I I I I I I Sodium-24 Ci i 3 ~ OE 05 I <3 . 4E-05 I I I I I I I Strontium-91 I Ci I 6.2E-05 5 ~ 3E 06 ii I I I Technetium-99m I

I Ci '7.4E-05 I

I 1.4E-06 I

I I I Tellurium-132 Ci OE 04 i 4 ~ 2E-04 Barium-139 Ci 2.6E-02 2.6E-03 I

I Neptunium-239 Ci' 4 ~ 9E 05 I <9 OE 05

~

I Total with T 1/2 < 8 days 'Ci I

2.7E-02 I

'2.6E-03 I

4. Tritium Tritium Ci I 9 'E Ol I 7 'E 01 Total building release C3. i 4 'E+01 i 5 'E+00 Note: Less than (<) values are not included in the Total For Period Values.

'E 1

~ 4'

Table 3-2 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES TURBINE BUILDING Report Period January June 1991 CONTINUOUS MODE I I I

I 1st 2nd Nuclides Released Unit Quarter Quarter I

I

1. Fission gases Krypton-85 Ci '<1.0E+02

, <2.5E+02 I I Krypton-85m Ci <3.7E-01 <2.3E+00 I

I Krypton-87 Ci <2.3E+00 <1.7E+00 Krypton-88 Ci I <3.2E+00 <2.8E+00 I

Xenon-133 Ci 3.1E+00 <2.4E+00 I I I I Xenon-133m Ci <6.0E+00 <5.7E+00 I I I Xenon-135 I

I Ci '3.6E+00 I

I 1.5E-01 I

I Xenon-135m I

I Ci '8.4E+00 I

I

<3.9E+00 I

Xenon-138 Ci 1.5E+01 4.1E-01 I I Total for period (above)

I Ci ,'.0E+01 5.6E-01

2. Iodines I

I I

I 1st 2 lid Nuclides Released Unit Quarter Quarter I

I Iodine-131 I

Ci I

l. 4E-'03 1 'E-03 I

I I Iodine-132 Ci 3. 3E-03 1.1E-03 I

I Iodine-133 Ci 8.8E-03 2.3E-03 I

I Iodine-135 I Ci I 1.5E-02 2 ~ 2E-03 I I I I I I Total for period (above) I I Ci I I

2.9E-02 6. 9E-03 12-

0 "H

C" I I

Table 3-2 (continued)

3. Particulates 1st 2nd Nuclides Released Unit Quarter Quarter I

I I

I Strontium-89 Ci 2 ~ /E 03 i 7 ~ 9E 04 I

1 I

I Strontium-90 Ci 7.1E-06 2.3E-05 I

I I I

I Cesium-134 Ci <9 5E 04

~

)

<6 ~ 8E 04 I

I I

I Cesium-137 Ci <1.1E-03 <6.9E-04 I

I I I

I Barium-Lanthanum-140 Ci 4 ~ 6E 03 ) 1 ~ OE 03 I I I I I

Molybdenum-99 Ci <1.7E-02 <6.6E-03 I

I Cerium-141 Ci <1.3E-03 <6.0E-04 I

Cerium-144 Ci <4.2E-03 '1.6E-03 I I Cobalt-58 Ci <1.4E-03 <7.3E-04 Cobalt-60 Ci <1. 4E-03 2.3E-05 I

I Iron-59 Ci <2.7E-03 <2.2E-03 I

I Manganese-54 Ci <9 OE 04

~

(

<6 6E 04

~

I I

Zinc-65 Ci <2.4E-03 <1.7E-03 I

Total for period (above) Ci 7.3E-03 '1.9E-03 13-

e f s

Table 3-2 (continued)

I I

I 1st 2nd Nuclides Released I

Unit Quarter Quarter I

with I

OTHERS Strontium-91 T 1/2 < 8 days Ci I

1 'E-03 '1 I

I I

'E-04 I I

I I

Tellurium-132 Ci 1 1E 05 (

<7 ~ 3E 04 I I I I I I I I Barium-139 Ci 8 ~ 9E 01 I 1 ~ 2E 01 I I I I I I Rubidium-89 Ci 8 ~ 3E 04 I <1 2E 03

~

I I I I Strontium-92 Ci 4.2E-02 <8.6E-05 I I I I I Cesium-138 Ci 9E+00 i 2 ~ 4E 01 I I I I Total with T 1/2 < 8 days Ci 2 ~ 8E+00 I 3 ~ 6E 0 1

4. Tritium Tritium Ci ) 3 'E+00 )

2 'E+00 Total building release Ci '3.4E+01 '3.2E+00 Note: Less than (<) values are not included in the Total For Period Values.

Table 3-3 WNP-2 GASEOUS EFFLUENTS SOURCE TERMS GROUND LEVEL RELEASES RADNASTE BUILDING Report Period January June 1991 CONTINUOUS MODE I

I I 1st 2nd I

Nuclides Released I

Unit Quarter Quarter I I

1. Fission gases Krypton-85 Ci < 1 8E+0 1 (

< 1 ~ 3 E+02 I

I Krypton-85m Ci <2.5E-01 ', <5.5E-01 I

I I Krypton-87 Ci <4.3E-01 <4.8E-01 I

Krypton-88 I

I Ci <1.4E+00 '7.5E-01 I

I I Xenon-133 Ci 6.9E+00 2.3E-01 I I I

Xenon-133m Ci <4.0E+00 <2.4E+00 I

I Xenon-135 Ci 1.7E+00 3.1E+00 I

I Xenon-135m Ci 5.7E+00 1.6E+00 I I I I Xenon-138 Ci <7 9E 0 1

~

)

< 1 ~ 6E+00 I I I I I Total for period (above) Ci 1 ~ 4E+0 1 (

5 ~ OE+00

2. Iodines I

I I

I 1st 2nd Nuclides Released Unit Quarter Quarter I

I Iodine-131 Ci 3.1E-04 ' .7E-04 I I I I I I Iodine-132 3.5E-04 4.7E-05 I

I Iodine-133 Ci 1 ~ 2E 03 I 2 ~ 5E 04 I I I I I I Iodine-135 Ci 3 ~ 3E 04 I 4 1E 05 I I I

Total for period (above) Ci 2 'E-03 I

', 4 'E-04 I

r f)

~

'l Af I

Table 3-3 (continued)

3. Particulates I

I I

I 1st 2nd Nuclides Released Unit Quarter Quarter I I I I Strontium-89 Ci 2.1E-07 7.5E-06 Strontium-90 Ci <1.2E-05 '4.9E-07 I

Cesium-13 4 Ci <2.5E-05 <2.3E-05 I

I Cesium-137 Ci <2.0E-05 <2.3E-05 I

Barium-Lanthanum-140 Ci <6.4E-05 '<6.3E-05 I

I I

I Molybdenum-99 Ci <2.5E-05 <2.7E-04 I I I I Cerium-141 Ci <2 2E 05

~

I <1 9E 05

~

I I I I Cerium-144 Ci <8.2E-05 <7.3E-05 I

Cobalt-58 Ci <1.8E-05 <2.0E-05 I

I Cobalt-60 Ci <4.0E-05 <4.5E-05 I

I I Iron-59 Ci <5 ~ 5E 05 I <6 8E 05

~

I Manganese-54 Ci <1 'E-05 <2.1E-05 I

Zinc-65 Ci <4.6E-05 <6.0E-05 I

Total for period (above) Ci 2 ~ 1E 07 I 7 5E 06

4. Tritium Tritium Ci 2 'E 01 I 7 'E 02 i~

Total building release Ci 1 ~ 5E+01 I 5 ~ 1E+00 Note: Less than (<) values are not included in the Total For Period Values.

~ f

~t

~t

Table 3-4 WNP-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Report Period January June 1991 I

I 1st 2nd I Est Unit Quarter Quarter Total I

I Error 4*,'.

Fission and activation gases

1. Total release Ci 8.8E+01 1 ~ OE+0 1 ( 3 ~ 6E+0 1 I

I I

2. Average release I I

rate for period ,uCi/sec 1.1E+01 1 ~ 3 E+ 0 0 I

I

3. Percent of Tech. I Spec. limit 2.4E-02 5.8E-03 I

B. Iodines I

1. Total iodine release Ci 3.7E-02 1 'E 02 I 3 'E+Ol I

2. Average release I rate for period ',uCi/sec I

4.7E-03 1.5E-03 I

3. Percent of Tech. I I

Spec. limit I o

1.6E-01 1.5E-01 C. Particulates

1. Particulates Ci 2.0E-02 ~ 2E-03 ' 'E+01 I

2. Average release I I

rate for period ',uCi/sec I

2.5E-03 6.6E-04

3. Percent of Tech.

Spec. limit ~O 0 1.6E-01 1. 5E-01 I

4. Gross alpha radioactivity Ci 1.7E-04 5.8E-04 D. Tritium

1. Total release Ci 5.0E+00 3 ~ 4E+00 ( 3 ~ 6E+01 I I I

2 ~ l Average re ease rate for period I

I I

,'uCi/sec 6.5E-01 4.4E-01 I I I I I I

3. Percent of Tech. I I I

Spec. limit I

~O 0 1.6E-01 1.5E-01

• At 954 confidence level 17-

e f I

4 Table 3-5 WNP-2 GASEOUS EFFLUENTS BATCH RELEASE Report Period January June 1991 Total Maximum 'Minimum 'Mean Type 'Number 'Time (hrs) Time (hrs) 'Time (hrs) 'Time (hrs)

',Purge 15.4 7.5 0.6 2.6 I I I I

'Vent 8 8.2 1.8 0.5 1.0

~ C 4.0 A total volume of 1,482.8 ft (42.0 m ) of solid waste was transported in 7 shipments during the January through June 1991 reporting period. The total activity of the waste shipped was 1049,4 Ci; 1045.4 Ci contained in dewatered spent resins and 4.6 Ci contained in DAW.

A.

Dewatered resins accounted for 1,312.6 ft (37.2 m ) of the radioactive wastes shipped during the reporting period. The burial containers were ES-190, and EA-142 liners provided by NUPAC Services, Inc. The total activity of the resins shipped during the reporting period was 1,045.4 Ci. The principle nuclides and their percent contribution to the total activity are listed in Table 4-3.

The solid wastes were shipped to the U.S. Ecology, Hanford burial site using NUPAC 10-142, U.S. Ecology 14D-2.0 casks, on flatbed trucks.

The counting error associated with the total activity has consistently been found to be less than 3.01. at one standard deviation for previous reporting periods. The statistical counting error is assumed to be 31. 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 distribu-tion within a batch or liner and the geometry error in the gamma spectroscopy analysis. The gamma spectroscopy calibration error is approximately 5%. The best estimate of the total error in the activity of spent resin shipped is assumed to be less than or equal to 251..

B. D v A total of 170.2 ft (4.8'm ) of DAW was shipped in 1 NUPAC Services ES-190 encapsulai,"ion liner. The total activity of the DAW shipped was 4.6 Ci. The value of the activity shipped was determined by using computerized dose rate-to-curie conversion factors. The conversion factors were based on a nuclide distribution taken from analysis of contamination found in the major DAW production areas. This distribution is updated annually in conjunction with offsite analyses of hard-to-measure nuclides. A meaningful counting error cannot be generated for DAW; however, the total error may be assumed to be less than or equal to 251. since DAW would be subjected to similar error contributions as spent resin.

19 "

I t

(I 7i

4.1 Scaling factors are based on outside laboratory (SAIC) analysis of hard-to-measure nuclides. Scaling factors are updated on an annual basis or when triggered by an order of magnitude change in corrosion to fission product ratios (Co-60/Cs-137) in the resin waste streams as compared to the previous offsite anlaysis.

The ratio of each of these nuclides to Co-60 is determined by outside laboratory analysis of each waste stream, The resulting scaling factors are applied to the measured Co-60 concentration for a particular batch or container of radwaste to arrive at the C-14, Ni-63 and Fe-55 concentrations.

T -1 r-The ratio of each of these nuclides to Cs-137 is determined by outside laboratory analysis of each waste'stream. The resulting scaling factors are applied to the measured Cs-137 concentration for a particular batch or container of radwaste to arrive at the H-3, Tc-99, I-129 and Sr-90 concentrations.

The ratio of hard to measure TRU nuclides to Ce-144 is determined by outside laboratory analyis of each waste stream as recommended by the AIF report, "Methodologies for Classification of Low Level Radioactive Waste for Nuclear Power Plants." These nucli des will be reported if Ce-144 is detected and the TRU nuclides have been detected by outside laboratory analyses. TRU nuclides include Pu-239, Pu-238, Pu-241, Am-241, Cm-242 and Cm-244.

Outside laboratory LLD's must be at least 1 nCi/g for TRU, 35 nCi/g for PU-241 or 200 nCi/g for Cf-242.

SCALING FACTORS B

RWCU CFD EDR/FDR EDR/FDR POWDER POWDER POWDERED BEAD D E H-3/CS-137 1. 97EO" 1. 88E-6* 6.34E-2" 1.07E-4* 1.27E-2*

C-14/Co-60 2.25E-3* 8.63E-6 1.32EO 2.61E-4 3.20E-3 Tc-99/Cs-137 3,11E-1* 1.37E-6* 8.76E-3" 9.82E-6" 2.97E-3*

I-129/Cs-137 4.02E-l* 1.44E-5* 1.24E-2" 8.04E-6* 2.41E-3*

• Scaling factor based on LLD value".'i-63/Co-60 NOTE 1 5.12E-3 3.32E-2 1. 84E-1., NOTE 1 Fe-55/Co-60 2.36E-l 9.83E-2 "2.23E-l 2.46E-l NOTE Sr-90/Cs-137 NOTE 1 1.30E-2 1.92E-1 2.81E-3 1'.84E-2 Pu-239,240/Ce-144 NOTE 1 9.65E-2 NOTE 1 2.60E-3 NOTE 1 Pu-238/Ce-144 NOTE 1 4.70E-2 NOTE 1 7,03E-3 NOTE 1 Pu-241/Ce-144 NOTE 1 5.50EO NOTE 1 2.14E-l NOTE 1 Am-241/Ce-144 NOTE 1 8.29E-3 2.56E-4 NOTE 1 NOTE 1 Cm-242/Ce-144 NOTE 1 9.25E-3 7.80E-3 2.75E-2 NOTE 1 Cm-243,244/Ce-144 NOTE 1 1.13E-2 4.08E-4 NOTE 1 NOTE 1 NOTE 1: Isotope not identified by offsite laboratory analyses.

Table 4-3 WNP-2 SOLID HASTE SHIPMENTS January June 1991 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Haste Haste Stream Unit 6-month Est. Total Er

a. Spent resins, filter sludges, m 37.2 V

b. Dry active waste, contaminated m 4.8

c. Irradiated components, control m No r i m

d. Other, (absorbed aqueous liquid) m No

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

a. Dewatered Spent Resins 4,

2. 2

b. Dry Active Waste (DAW)

.2 4 -12 .1 7 5 4 "Indicates scaled nuclide J

t I

c. Irradiated Components None

d. Other Absorbed Liquids None

3. Solid Haste Disposition 10-142 Cask (1) US Ecology 14D-2.0 Cask (2) Richland, HA Flatbed (4)

S. IRRADIATED FUEL SHIPMENTS (Disposition)

None

• Indicates scaled nuclide

- 23

The meteorological data for the first half of calendar year 1991 will be included in the Semiannual Effluent Report due 60 days after January 1, 1992, and will include data covering the full calendar year 1991. An extended outage of the main meteorological tower occurred during the 2nd Quarter 1991, as a result of in-plant electrical/computer work scheduled during refueling.

"24-

6.0 D The dose impact on man for the Calendar Year 1991 will be included in the Semiannual Effluent Report due 60 days after January 1, 1992.

~s I

~

. 0 IKKUQE5~

During this reporting period, no admendments to the Offsite Dose Calculation Manual (ODCM) have been approved and implemented. During this period, the Plant Operations Committee (POC) reviewed and recommended approval of an amendment to the ODCM for the relocation of the Radiological Effluent Technical Specifications (RETS) per NRC Generic Letter 89-01, dated January 31, 1989. As discussed below, this ODCM amendment cannot be implemented until the HNP-2 response to Generic Letter 89-01 is approved by the NRC.

7.1 The amendment requests that those Technical Specifications addressing radiological effluent and radiological environmental monitoring be relocated to'he ODCM. The guidelines provided in the Generic Letter have been followed without exception.

7.1.1 Specific procedural details contained in the relocated Technical Specifications, including the limiting conditions for operation, their applicability, remedial actions, surveillance requirements, and bases are included in the ODCM.

7.1.2 The revisions for annual radiological environmental reporting and semiannual radioactive effluent release reporting are being simplified, deleting specified details of the reports'ontent. These changes are consistent with the staff's guidance in Generic Letter 89-01.

7.1.3 In accordance with Technical Specification Section 6.14.2.b, POC approved the ODCM, incorporating the applicable Technical Specification changes. POC further concurred that the changes to the ODCM will become effective and implemented following NRC approval.

7.2 These changes do not affect safe Plant operation or the release of radioactive material to the environment, 7.2.1 These changes will not reduce the accuracy or reliability of dose calculations or setpoint determinations.

7.3 The relocation of RETS to the ODCM in accordance with Generic Letter 89-01 was reviewed and approved during POC Meeting 91-04 held on January 23, 1991.

7.4 The complete package pertaining to this revision of the ODCM was sent to the NRC staff for review under written correspondence G02-91-124, dated June 28, 1991, Docket No. 50-397.

7. 4.1 A comple'te, legible copy of the entire ODCM will be provided as per Generic Letter 89-01 after NRC approval.

8.0 E E No changes were made'o the Process Control Program (PPH 1.12.2) during this reporting period other than the enhancements to the scaling methodology described in Section 4.1.

9.0 I L 9.1 Locations where GASPAR II dose calucations were performed for the first and/or second quarters of 1991:

9.1.1 4.8 miles southeast (SE) for the highest organ dose using ground, inhalation and vegetation pathways.

9,1.2 6,4 miles southeast (SE) for the highest organ dose using ground, cow milk, inhalation and meat pathways.

9.1. 3 4.2 miles east southeast (ESE) for the highest organ dose using ground, inhalation and vegetable pathways.

9.1.4 4.3 miles northeast (NE) for the highest organ dose using ground and inhalation pathways.

9.1.5 4.1 miles east northeast (ENE) for the highest organ dose using ground, inhalation and vegetable pathways.

9.1.6 Dose assessments at the 7.2 miles east southeast were not performed during this reporting period as they were completed at 6.4 miles southeast which is in reasonable proximity for the cow milk pathway.

9.2 During Janaury 1991, a milk cow was moved from Station 63 to Station

40. Both sampling stations are located 6.4 miles SE; therefore, the cow milk calculations were not affected.

9.3 No environmental monitoring locations were deleted during this reporting period other than the cow milk being moved from Station 63 to Station 40.

," 28-

V' 10.0 D I Ho major changes were made to the radioactive waste systems (liquid, gaseous, or solid) during this reporting period.

29-

0 t e.,

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