SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment

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Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment
ML20149M985
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 12/31/1987
From:
LONG ISLAND LIGHTING CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SNRC-1429, NUDOCS 8802290346
Download: ML20149M985 (170)


Text

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r -IANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3rd and 4th Quarters of 1987 1987 Meteorological Sumary and Offsite Dose Assessment Facility: Shoreham Nuclear Pcwor Station, Unit 1 Licensee: Iong Island Lighting Company, Inc.

TABLE OF CONTENTS Section Page Introduction 1 A. Supplemental Information 1 j B. Gaseous Effluents 4 C. Liquid Effluents 8 D. Solid Waste 11 E. Radiological Impact on Man 13 F. Meteorological Data 55 G. PCP and ODCM Re' isions, RDiP Non Compliances 112 and Major Changes to Radioactive Waste Treatment Systems H. Miscellaneous Special Reports 114 8802290346 081231 PDR ADOCK 05000322 R PDR l l

INTRODUCTIM This Semiannual Effluent Release Report, submitted in accordance with Technical Specification 6.9.1.7, covers the periods from July 1, 1987 through September 30, 1987, and October 1, 1987 through December 31, 1987 Meteorological data summaries for the whole of 1987 are included as is an assessment of offsite doses due to liquid and gaseous effluents for the whole year. During 1987, the Shoreham Nuclear Power Station conducted tests below 5% power between May 26 and June 8, and was shutdown for the retainder of the year.

r A. SUPPLEMENTAL INFORMATION

1. Regulatory Limits shoreham's effluent regulatory limits are defined in Facility Operating License NPF-36, Shoreham Nuclear Power Station, Appendix A, Technical Specifications.

a) Limits for gaseous effluents and noble gases are covered by Technical Specifications 3.11.2.1 and 3.11.2.2.

b&c) Iodines and particulates with half-lives greater than 8 days in gaseous effluents are addressed in Technical Specifiustion 3.11.2.3.

d) Liquid effluent limits are described in Technical Specifications 3.11.1.1 and 3.11.1.2 e) The following radionuclides in liquid effluents had typical minimum detectable activities of:

Ce-141 3.04E-8 uCi/ml '

Co-58 4.03E-8 uCi/ml i Cs-137 2.54E-8 uCi/ml l Mn-54 3.05E-8 uCi/ml Mo-99 2.24E-8 uCi/ml Zn-65 6.04E-8 uCi/ml The following radiennelides in gaseous effluents had typical minimum detectable a;tivities of:

Cs-137 3.34E-14 uCi/cc I-131 5.83E-14 uCi/cc Kr-87 1.65E-8 uCi/cc Hn-54 3.13E-14 uCi/cc Xc-133 8.12E-9 uCi/cc Zn-65 8.35E-14 uCi/cc 1

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2. Maximum Permissible Concentrations a-d) Maximum permissible concentrations (MPC's) are those specified in 10 CFR 20, Appendix B, Table II, Column 2. If an isotope is listed with values for SOLUBLE and INSOLUBLE statea, the more conservative value is utilized. For gaseous effluents MPCs were not used. Direct calculations of dose were utilized to satisfy the dose rate limitations of Technical Specification 3.11.2.1,
3. Average Energy No isotopes above minimum detectable activities were measured in gaseous effluents. Therefore, there is no reportabic average energy for this time period.
4. Measuretients and Approximations of Total Radioactivity a-d) Samples were collected in the manner and with the frequency prescribed in Technical Specifications Surveillance Requirements 4.11.1.1.1 and 4.11.2.1.2. Samples were analyzed in accordance with Technical Specifications Tables 4.11.1.1.1-1 and 4.11.2.1.2-1 regarding both type of analysis and level of sensitivity. Most samples were analyzed by gamma spectroscopy with a Ge(Li) or intrinsic germanium detector. A liquid scintillation counter was used to analyze for H3 and Fe-55 while Sr-89,90 analyses were done by proportional counter. Samples analyzed for iron and strontium underwent a chemical separation prior to counting. Approv ed '

sample collection and analysis procedures were followed.

Analytical results are examined to ensure that the minimum sensitivity levels required by Technical Specifications lower limits of detection have been met. Any identifiable peaks above background are quantified.

The methods above were used for batch releases. These methods combined with gross activity measurements on process streams and ,

total flow for these streams were used for continuous discharges.

No estimate of percent total error is provided in Table 1A because all values for gaseous effluents were determined to be less than required lower limits of detection (LLDs) . Counting LLDs reflect a two-sigma lesel of confidence. For liquid measurements, the overall error is estimated from the tank sampling error and from counting error at values close to minimum detectable activities to be approximately 50%.

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o 5. Batch Releases a) Liquid 3rd quarter 4th Quarter

1. Number of batches 4.40E+1 5.40E+1
2. Total Time (minutes) 6.33E+3 7.86E+3
3. Maximum Time (minutes) 2.26E+2 1.85E+2
4. Average Time (minutes) 1.44E+2 1.46E+2
5. Minimum Time (minutes) 8.00E+0 1.00E+0
6. Average Flow (gpm) 2.82E+5 7.13E+4 (Dilution) b) Gaseous - None
6. Abnormal Releases a) Liquid - None b) Gaseous - None

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Uv Jr I L SEMIANNUAL RADIOACTIVE EFFLUDIT RELEASE REPORT B - GASEOUS EFFLUDTTS 3rd and 4th Quarters of 1987 All samples of gaseous effluents were analyzed and determined to be at or below minimum detectable activities for all radionuclides listed in Shoreham's Technical Specifications. These MDAs were below the lower limits of detection required in Technical Specification Table 4.11.2.1.2-1. In addition, no other radionuclides were identified. Therefore, no entries were made in Tables 1A, 1B or IC.

Composite sample results for the fourth quarter of this reporting period are not available at this time. As has been done in the past, we are reporting previous corposite results for portions of this reportirig period. When the actual results are available, any significant differences will be noted in supplements to this report, however, as stated previously, all results are at or below MDA's.

A Station Ventilation Exhaust System outage occurred from October 19 to November

6. During portions of this time period the Reactor Building Standby Ventilation System (ABSVS) war. operating and gaseous ef fluent samples were obtained from this release point. When the RBSVS was not operating, grab samples were taken in the Peactor Building, Turbine Building and Radwaste Building.

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TAB LE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1987 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ,

Unit Ownst Qwner Est. Tout 3 4 Enw,%

A. Fision & act;vation seus

1. Total releau Ci . E .

E_ . E

2. Average release rate for penod pCi/see . E . E
3. Percent of Technical specification bmit  % . E , E- _

B. lodines

1. Total iodine 131 Ci . E . E . E
2. Average release rate for period pCi/see . E . E
3. Percent of techrucal specification hrnit  % . E . I C. Paeticulates
1. Particulates with half bves >6 days Ci . E . E . E
2. Average release rate for period pCilue . E . E
3. Percent of technical specification brrut  % . E . E
4. Gross alpha radioactivity C . E . E D. Tritium __

l 1. Total release Ci . E . E . E

' 2. Average release rate for penod pCi/se e . E . E_

j 3. Percent of technical specification lunit 9 . E . E, 5

i TABLE 18 l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1987 GASEOUS EFFLUENTS-ELEVATED RELEASF CONTINDOWS MODE SATCH MODE Nelms Rennesed Unit Oenw 3 Owner 4 Qwner 3 Odneg

1. Fission pass krypton 45 Ci . E . E . E , E i krypton 45m C . E , ~E . E . E krypton.87 Ci . E . E . E . E krypton 48 Ci . E . E . E . E menon 133 Ci . E . E . E . E menon.135 Ci . E . E . E . E xenon.135m Ci . E . E . E . E xenon.138 Ci . E . E . E . El Others (specify) Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E . E unidentified C . E . E . E . E Total for period Ci . E' . E . E . E l 2. lodines  !

! iodine.131 Ci . E . E . E , E iodine 133 Ci . E . E . E . E j 6odine.135 Ci . E . E . E , E Tott! for period Ci . E . E . E . E ,

! 3. Particulates .

strontium 49 Ci . E . E . E . E strontium.90 Ci . E . E . E . E

. casium 134 C . E . E . E . E cesium 137 Ci . E . E . E . E banum. lanthanum f40 Ci . E . E . E . .E Others (specify) Ci . E . E . E . E d

C . E . E . E . E Ci . E . E . E . E unidentified Ci . E ,

. E . E . E i

)

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TABLE 1C ,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1987 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUQUS MDDE BATCH MDDE Nwdien Roleseed Unit Owner, Owner Qwnv4 4 Owner 3

1. Fission gues krypton.85 Ci . E . E . E , E krypton.55m Ci . E . E . E . E krypton.S7 Ci . E . E . E . E k rypton.55 Ci . E . E . E . E xenon.133 Ci . E . E . E . E

~

xenon.135 C . E . E . E , E xenon.135m Ci . E . E . E . E xenon.138 - Ci . E . E . E . E Others (specify) Ci . E . E .

E_ . E Ci . E . E . E . E Ci . E . E . E . E unidentified Ci . E . E . E . E Total for period Ci . E . E . E . E

2. lo&nes i iodine.131 Ci E E

. . . E . E iodane.133 Ci . E . E . E . E iodme135 Ci . E . E . E . E Total for period Ci . E . E , E . E

3. Particulates 1

st rontium.89 Ci . E . E . E , E st rontium.90 Ci . E . E . E . E I

cesium.134 Ci . E . E . E .

E__

eeuum.137 Ci . E . E . E . E l banum lanthanum.140 Ci . E . E . E . E" '

Others (specify) Ci . E . E . E ,

E]

l Cs . E .

_E . E . E Ci . E . E . E '

. E I unidentified Ci . E . E , E . E  :

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT C - LIQUID EFFLUENT 3rd and 4th Quarters of 1987 Tables 2A and 2B contain information on the liquid batch releases for the third and fourth quarters of 1987 During cortions of the reporting period there was no circulating water flow and dilution was by service water only. There were no radionuclides above MDA in continuous liquid relaares, therefore, liquid discharge data for the continuous releases are not included in the table.

Radionuclides that were at or below the MDA's, which were below the LLD's required in Technical Specification Table 4.11.1.1.1-1, are not included in the Tables. Percent of applicable limit was calculated as a sum of the fractions of individual isotopic limits instead of using the average diluted concentration.

Composite sample results for the fourth quarter of this reporting period are not available at this tine. An has been done in the past, we are reporting previous composite results for portions of this reporting period for Fe-55, Sr-89 and Sr-90. When the actual results are available any significant differences will be noted in supplements to this report. Due to the low concentrations and resulting doses, no significant differences qtween the reported composite results and the actual results have occurred.

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7ABL E 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1987 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 E rror, to A. Fision and actintion products

1. Total release (not includmg tritium, gases, alpha) Ci 5.os Ed 2.68 ps ,s.oo E+t _
2. Average diluted concentration during period #Ci/ml 7. 48 E-11 1. 3 E_m
3. Percent of appucable limit G 2. 9 8 E-s 1.40 E -5 B. Tritium
1. Total release Cl . E- . E . E l
2. Average dduted concentration during period uCi/ml . E .

E_

3. Percent of appbcable limit 9 . E i . E C. Dissolved and entrained pses
1. Total release Ci . E . E . E l
2. Average dduted concentration during period uCi/ml . E . E
3. Percent of appbcable lirrut 9 . E . E D. Gross alpha radioacthity l 1. Iotal release l Cl l . E l .

E l . E l E. Volume of nste released (prior to dilution) liters 2.78 E6 9.02 Es 4 1.00 E +1 F. Volume of duution water used during period liters 6.75 E 9 < 2.12 E+ 9l 2. 00 N1 9

. TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1987 LloVID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuctices Released Unit Quanet Cuaner/ Quaner3 l Qwaner 4 strentium49 strontium 90 Ci Ci

\.\.

E E

E[

lif E

E E

E cesium 134 Ci \. E . E . E . E cesium.137 Ci \ E .E 1.2 6 E-S . E iodine 131 C .\1 E .

I

/E , E . E cobalt.58 Ci .\E ./E 8.70 E 5. 2. 6 8 E 5, l

cobalt.60 -

Ci . \E ./ E . E E iron.59 Ci . \E / E . E i . E zine 65 Ci . E I. E . E . E manganese.54 - Ci . R /. E o .7 s E_ s E.

chronuum 51 _C .

E\ /. E 2.36 E-4 E. ]

\ I zirconium. niobium.95 Ci . E \l . E . E . E molybdenum.99 Ci . EA . E . E . E i technetium.99m Ci . E/ \. E . E , E barium. lanthanum 140 Ci . E/ \. E . E . E cerium 141 Ci . V \. E . E . E I 1 Other (specify) l Ci .

/E \ E . E . E ,

IRON 55 Ci ./E .\ E 1 en E_4 . E Ci ./E .\E . E . E Ci ./ E .\E . E . E Ci ./ E .

\E . E . E unidentified Ci / E .

Vi . E . E  ;

I \

Total for period (above) Ci I

/. E .

E\

\

5.05 E-4 2.os E-5 xenen.133 -

Ci / . E . E\ . E , E -

xenon.135 Ci / . E ,

E\. E , E  :

l 5

l i 10

,E9 f

l 4 SEMIANNUAL PADI0 ACTIVE EFTLUENT' '

. RELEASE REPORT

~

SOLID WASTE D .

3rd and 4th Quarters of 1987 I

-A,

. Table 3 provides information on shipments of solid wasto-for the third and -

fourth quarters of 1987. - All shipments consisted of dowatered Class A Resins, Filters and Evaporator Bottoms. There were no irradiated fuel shipments. . Waste r

.. was shipped in 158.1 ft8 DOT Spec 7A High Integrity Containers (HIC's), approved l by the South Carolina Department of Health and Environmental Conservation.

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TABLE 3

  • *
  • REGULATORY GUIDE 1.21 REPORT *'*

SOLID WASTE SHIPPED OFFGITE FOR DISPOSAL

    • DURING PERIOD FROM 7/1/87 to 12/31/87**

WASTE STREAM: Resins, Filters, & Evaporator Bottoms WASTE CLASS CUBIC METERS CURIES  % ERROR (CI)

A 62.6 9.57E-2 125%

    • ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STRFAM **

WASTE STREAM: Resins, Filters & Evaporator Bottoms with .0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES A Fe-55 25.563% 2.45E-02 Co-60 24.222% 2.32E-02 Co-58 12.294% 1.18E-02 i Cr-51 8.984% 8.60E-03 Mn-54 8.280% 7.93E-03 Pu-241 7.026% 6.73E-03 En-65 4.050% 3.88E-03 Ag-110m 3.052% 2.92E-03 Ce-144 2.162% 2.08E-03 Fe-59 1.667% 1.60E-03 Ni-63 1.016% 9.75E-04 Cs-137 800% 7.66E-04 H-3 e274% 2.62E-04 Co-57 .165% 1.58E-04 Nb-95 .146% 1.40E-04 Sb-124 129% 1.23E-04 Er-95 .080% 7.71E-05 Ce-141 .053% 5.08E-05 Sr-90 .016% 1.55E-05 Ni-59 016% 1.55E-05 C-14 .002% 1.70E-06 Nb-94 .000% 3.21E-07 Tc-99 .000% 0.00E+00 1-129 000% 0.00E+00 Cm-242 000% 0.00E+00

    • SOLID WASTE DISPOSITION

SUMMARY

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 3 Truck Barnwell 0 Truck Richland 1 0 Truck Peatty l 0 Truck other l

1

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SEMIANNUAL RADIOACTIVE EFTLUENT RELEASE REPORT E - RADIOLOGICAL IMPACT ON MAN 1987 Radiation doses due to the liquid releases reported for 1987 were calculated in accordance with the methodology and parameters in the ODCH, using the LADTAP II computer program. There was no release of radioactivity via the gaseous effluent pathway in 1987. Table 4 summarizes population doses, doses to the maximum exposed individual and doses to members of the public due to their activities insido the site boundary. Members of the public are assumed to be inside the site boundary for recreational activities on the Wading River.

Detailed individual and population doses are given in the following pages, along with usage and other parameters used in the calculations. These detailed doses were calculated on a quarterly basic using the total liquid release for the quarter although the results are given in terms of annual dose.

Direct radiation (as measured on quarterly TLD's) made no contribution to offsite doses based on a comparison of 1987 dose rates with 1984 (preoperational) dose rates. Tue highest dose measured was 5.0 mPem/ standard month (30.4 days) at indicator location 6Al compared to the 1984 dose at the same maximum location of 5.1 mPem/ standard month. Sinilarly, the average for all indicator locations was 3.7 mrem / standard month compared t > a 1984 value of 3.9 mrem / standard month.

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TABLE 4

SUMMARY

',r DOSES DUE TO LIQUID ret. EASES

  • TOR 1987 Estinated Population Dose Applicable 2nn Man-rem Total tody 6.78 '-3 one 3.53 E-2 Estimated Dose ta Most Likely Exposed Member of the Public x

Applicable Organ prem '

Adult Total Body 8.24 E-6 '

Bone 4.68 E-5 Teenager Total Body 9.12 E-6 Bone 4.93 E-5 Child Total Body 1.15 E-5 Bone 6.%7 E-5 Estimated Dose to Members of the Public Due To Their Activities Inside the Site Boundary [

Applicable Organ erem j Adult Total Body 8.25 E-8 i Skin 0.92 E-8 I

Teenager Total Body 4.30 E-7 Skin 4.97 E-7 i

Child Total Body 9.22 E-8 Skin 1.04 E-7 l

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at QUllrtCI' I

_ . _ _ _ _ . _ . . --- - ~ , - e e AS LON AS REASONABa.Y ACHIEVASLE O e e s

AOULT DOSES DOSE _tHREN PER YEAR INTAKE D PATHNAY SKIN BOE LIVER TOTAL BODY THYROIO KIDEY LLMG GI-LLI FI"J 1.69E-06 1.28E-06 5.36E-07 0.0 0.0 6.51E-07 3.06E-06 '

INVERTEBRATE ^ -- ~~ -" 2.68E-06 2.13E-06 1.06E-06 0.0 0.0 1.03E-06 6.75E-06 .#

~~ .

^

SHORELINE 2.61E-06 2.23E-06 2.23E-06 2.23E-08 2.23E-08 2.23E-06 2.23E-08 2.23E-08 SMIT 911NG 0.0 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 90ATING 0.0 3.56E - 3.56E-09 ~~ 3.56E-09 3.56E-09 3.56E-09 3.56E-09 TOTAL- 2.61E'08 ~~ 3.56E-09 4.40E-06 3.45E-06 '1.63E-06 3.30E-06 3.30E-08 1.72E-06 ' 9.84E-06

~ ~~

sK w IKG/YR,HR/YR3 OILUTION TIMIHR I SHOREMIOTH FACTOR =0.5 FISH 21.0 8.9 24.00

~ ~

INVERTEBRATE 5.0 8.9 te. fro SHORELINE 12.0 8.9 0.0

, SMItttING 52.0 8.9 0.6 BOATING 52.0 8.9 i TEENAGER 00SES i

DOSE tNREN PER YEAR INTAKEl P'.THN4Y SKIN BONE LIVER TOTAL 900Y THYROIO KIDEY LUNG GI-LLI FISH 1.77E-06 1.37E-06 5.62E-07 0.0 0.0 7.95E-07 2.16E-06 INVERTEBRATE 2.80E-06 2.26E-06 1.10E-06 0.0 0.0 1.26E-06 4.69E-06 H SHORELINE 7.46E ~ 1.24E-07 ~ ' 1.24E-07 '~ 1.24E-07 1.24E-07' 1.24E-07 1.24E-07 1.24E-07

~ ~-

SMItttING 0.0 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 7.12E-09 BOATING 0.0 3.56E-09 3.56E-09 3.56E-09 3.56E-09 3.56E-09 3.56E-09 3.54E-09 TOTAL 1.46E-07 4.70E-06 3.77E-06 1.80E-06 1.35E-07 1.35E-07 2.19E-06 6.99E-06 8 MM IKG/YR,HR/YR) 3ILUTION TIMtHR) SHORENIDTF FACTUR=0.5 FISH 16.0 8.9 24.00 INVERTEBRATE 3.8 8.9 24.00 SHORELINE - - - ~ 67. 0 ~ ~ ~ ~ - -- " 8. 9 - ~ ~ ~ ~ 0.0

- ' - - ~ ~ ~ ~ ~ ' ~ ~ ' "-

SMItttING 52.0 8.9 0.0 BOATING 52.0 8.9 0.0 D0SES

- ~ " ~

.. _ _ _ _ _ . - HILD DOSE _INtEN PER YEAR INTAKEl

- ~

P*. TIS 4AY ~ ' SKIN' ~ ~ BOE ~~~ LIVER ' TOTAL 800Y THYROID KIDEY

^

LLNG 'GI-LLI

~~ ~~

FISH 2.32E-06 1.32E-06 6.67E-07 0.0 0.0 6.96E-07 7.73E-07 INVERTEBRATE 3.81E-06 2.25E-06 1.33E-06 0.0 . 0.0 1.14E-06 1.72E-06 SHORELINE ~--

3.05E-08 ~ 2.60E-08 ^ 2.60E-08 2.60E-08 2.60E-06 2.60E-08 2.60E-08 2.60E-08

=SHItttING ~ 0.3' 3.97E-09 3.97E-09 - 3.97E-09 3. 97E-09 3.97E-09 ' 3.97E-09 3.97E-09

~ ~

BOATING 0.0 1. 98E-09 1.90E-09 1.98E-09 1.98E-09 1.90E-09 1.90E-09 1.98E-09 T3TAL 3.05E-08 6.16E-06 3.61E-06 2.03E-06 3.20E-06 3.20E-08 1.87E-06 2.52E-06 eMacE (KG/YR,HR/YR) DILUTION TIMt HR) SHORENIDTH FACTOR =0.5 FISH 6.9 8.9 24.00 ItWERTEBRATE 1.7 8.9 24.00 SHORELINE ~ '"

14.0 8.9 0.0

" ~ ~ '

-SHItttING 29.0' 8.9 0.0

'  % TING 29.0 8.9 0.0 e O

.. . . . . , . . ~ . .

n~o~n "S2LECTEI LOCATI(Ni 'n' ~ e h O

~

' ~ ' ~ ~ '~-~ ~~ ~~ Guarter 1" ' '

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LOCATION IS SHORELIE a

).,-.

DOSE _ttetEN PER YEAR INTAKEl

~ ~

Pl.THNAY SKIN BONE LIVER TOTAL 800Y THYROID FISH 1.69E-06 1.28E-06 KIDEY LUNG GI-LLI INVERTEBRATE 5.36E-07 0.0 0.0 6.51E-07 2.68E-06 2.13E-06 1.06E-06 0.0 3.06E-06 SHORELINE 2.61E-06 2.23E-08 0.0 1.03E-06 6.75E-06 SMIretING ' 2.23E-08 2.23E-08 2.23E-08 2.23E-08 0'. 0 '7.12E 3 9 ~ ~ ~ 2.23E-08 7.12E-09 ~ 7.12E-09 7.12E-09 2.23E-08 ~ ~ ~~

1 80ATING 0.0 3.56E-09 7.12E-09 7.12E-09 7.12E-09 3.56E-09 3.56E-09 3.56E-09 3.56E-09 TOTAL 2.61E-08 4.40E-06 3.45E-06 1.63E-06 3.56E-09 3.56E-09 3.30E-06 3.30E-OC 1.72E-06 9.G4E-06

" ~ Ut m (KG/YR.HR/YR3 DILUTION TIEt HR )

FISH 21.0 SHOREMIDTM FACTOR =0.5 8.9 24.00 l INVERTEBRATE 5.0 8.9 24.00

SHORELINE.~ 12.0 8.9 0.0 j BOATING 52.0 - ~ ~ ~ ~ ~ 8. 9 ~ ^~

0.0 ~ ' ~ ~

52.0 8.9 0.0 LOCATION IS SHOREL,IE _,

T it ENAGER DOSES

-- - DOSE _t79tEY. PER YEAR INTAKE D

>-. PATHNAY SKIN SCE _

O FISH LIVER TOTAL 800Y THYROID 1.77E-06 1.37E-06 KIDEY LUNG GI-LLI INVERTEBRATE 5.62E-07 0.0 0.0 7-95E-07 2.80E-06 2.26E-06 1.10E-06 0.0 2.16E-06 SHORELIE - ~ 1.46E-07 ~ ~~ 1.24E-07 '

1.24E-07 0.0 1.26E-06 4.69E-06 SMIff1ING 1.24E-07 1.24F-07

1. 24E-07 1.24E-07 ' ~ ~ '

0.0 7.12E-09 7.12E-09 7.12E-09 7.12E-09 1.24E-07 BOATING 0.0 3.56E-09 3.56E-09 7.12E-09 7.12E-09 7.12E-09 TOTAL 3.56E-09 3.56E-09 3.56E-09 3.56E-09 1.46E 4.70E-06 3.77E-06 1.80E-06 1.35E-07 3.56E-09

- 1.35E-07 -

2.19E-06 6.99E-06 mW (KG/YR,HR/YRD OILUTION FISH TIMEtHk) SHOREMIDTH FACTOR =0.5 16.0 8.9 24.00 INVERTEBRATE 3.8 EN - - ~-

~ ~' ~

8.9 24.00 67.0 ' 8.9 0.0 '~ ~

SHIP 9fING 52.0 ~~

8.9 0.0 BOATING 52.0 8.9 0.0 LOCATION IS ~ SHORELIE ~' " - ~ ~ ~ ' - - ^~ ~

~ ~ ' ~ ' - -

CNILD DOSES DOSE _(PWtEN PER YEAR INTAKE)

PATHHAY SKIN BCE FISH LIVER TOTAL 800Y THYROID 2.32E-06 1.32E-06 KIDE Y LtMG GI-LLI INVERTEBRATE-- - 6. 67E-07 0.0 0.0

'- ~ 3.81E-06 2.25E-06 1.35E-06 6.96E-07 7.73E-07 SHORELIE 3.05E-08 0.0 0.0 1.14E-06 2.60E-08 2.60E-06 2.60E-06 2.60E-06 1.72E-06 ~

$NIPf11NG 0.0 3.97E-09 3. 97E-09 2.60E-08 2.60E-06 2.60E-08 BOATING 5. 97E-09 3.97E-09 3.97E-09 I

O.0 1.98E-09 1.98E-09 3. 97E-09 3. 97E-09

==T"JTAL ' ^ - ~ ' 3.05E-08~ 1.98E-09 1.98E-09 1.98E-09 1.98E-09

~~ 6.16E-06 ^ 3.61E-06 ~

2.03E-06 3.20E-08 1.98E-09 3.20E-08 1.87E-06 2.52E-06 USAGE IKG/YR,HR/YR) DILUTI(Ni FISH 6.9 TIEt hR) SHOREMIDTH FACTOR =0.5 8.9 24.00

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.I DOSE IMAN-ItEMI PATHNAY ACE G8t0UP USAGE BONE LIVER TOTAL 800Y THYROID KIDE Y LtAIG I FISH ~ ~ ADULT CI-LLI

) FISH TEENAGER

' I.37E *07 1.08E-03 8.14E-04 3.32E-04 0.0 0.0 4.15E-04 1.86E-03 FISH CHILD 1.60E+06 1.73E-04 1.33E-04 5.33E-OS 0.0 0.0 7.77E-05 2.01E-04 1.11E+06 5.64E-04 2.07E-04 1.02E-04 0.0 0.0 1.09E-04 1.16E-04 FI.S_11_ __ _ . TOTAL 1.64E+07.._1_ .61E 03. .1.15E-05 . 4.87E,04 . 0.0 0.0

. 6.02E-04 2. 17E-03 LOCATION DILUTION CATCH .

SPORT FISHING TIE (HRI-18CLLSES FOOD PHOCESSIPE TIE OF 1.68E+02 HR POPULATI(West.80E+06 8.85E+00 1.64E+07 1.92E+02 AVERAGE 19eIVIDUAL'CONSEA9 TION (KC/YRI' ' ADULT =6.90E+00 ~~ TEEN =S.20E*00 CHILD =2.20E+00 ~~ ~~ '-

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~~ AOULT LIVER TOTAL 900Y THYROIO KIDEY Lt2C GI-LLI i

INVER '~1.99E+06 1.04E-03~ 8.24E-04 3.90E-04 0.0 0.0 4.02E-04 2.49E-05 INVER TEENAGER 2.31E+05 1.67E-04 1.34E-04 6.34E-05 0.0 INVER CHILD 0.0 7.5GE-05 2.66E-04 1.67E*05 3.65F-04 2.15E-04 1.24E-04 0.0 0.0 1.10E-04 1.57E-04 INVEK TOTAL 2.39E+06 1.58E-03 1.17E-03 5.85E-04 0.0 -0.0 5.87E-04 2.92E-03 LOCATION DILUTION CATCH SPORT INVERT.

TIE (HRI-IELUDES F000 PROCESSIle3 TIE OF 1.68E+02 HR POPULATI m =2.81E*06 8.85F+00 2.39E+06 1.92E+02 AVERi=GE IleIVIOUAL Com0N (KG/YR)- - AOULT=1.00E+00 TEEN =7.50E-01 CHILO=3.30E-01 '- ~ ~ ~- ~

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AOULT DOSES SKIN 90E LIVER TOTAL BODY TifYROIO KIDE Y

  • - PITIO4AY FISH LLM G GI-LLI 6.52E-05 4.52E-05 1.00E-05 3.21E-12 1.74E-08 2.51E-05 2.86E-05

. . _ . . _ . _ __ _ _ . 1.04E-04' 7.18E-05 ' 1.73E-05 3.82E-12 3.04E-09 3.99E-05 4.67E-05 SHORELIE 2.92E-07 2.48E-07 2.48E-07 2.40E-07 2.48E-07 2.48E-07 2.48E-07 2.48E-07 SMIf9 TING 0.0 6.99E-09 6.99E-09 6.99E-09 6.99E-09 6.99E-09 6.99E-09 6.99E-09 90ATIWG 0.0 3.49E-09 3.49E-09 - 3.49E-09 3.49E-09 3.%9E-09 - 3.49E-09 2.92E-07 1.69E-04 ~3.49E-09~

TITAL ~ 1.17E-04 2.84E-05 ~~ 2.58E-07 2.79E-07 6.53E-05 7.54E-05

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a snas gKG/YR HR/YR) DILUTItBE TIEllIR ) SHORENIDTM FACTOR =0.5 FISH 21.0 8.9 24.00

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INVERTEBRATE - ~ ~S.0 8.9 24.00

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SHORELIE 12.0 8.9 0.0 SMItetING 52.0 8.9 0.0 l BOATING. 52.0 _S. 9 0 . 0_ _ _ _ _ _ , _ _ , _ , , _

TEENAGER DOSES

. _ _ _ 00SE_tPetEN PER YEAR INTAKEI ,

d i PATIO 44Y SKIN BCE LIVER TUTAL 800Y THYROIO KIDOR.Y Ltse GI-LLI FISH 6.83E-05 4.86E-05 1.16E-05 3.08E-12 1.72E-08 3.07E-05 2.27E-05 INVERTEBRATE 1.08E-04 7. 70E -05 1.85E-05 3.66E-12 3.00E-09 4.86E-05 3.71E-05 SHORELINE - 1.63E-06 1.38E-06 1.38E-06 ' -- - 1.38E-06 ' ~ 1.38E-06 ~-' 1.38E-06 -" 1.38E-06 1.38E-06

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PJ SMIT 9fING 0.0 6.99E-09 6.99E-09 6.99E-09

  • 6.99E-09 6.99E-09 6.99E-09 6.99E-09 BOATING 0.0 3.49E-09 3.49E-09 3.49E-09 3.49E-09 3.49E-09 3

3.49E-09 3.49E-09 TOTAL...

1.63_E-06 .

1.78.E-04---.

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3.15E-05 1.39E-06 1.41E-06 - 8.07E-05 6.12E-05 --

USAGE IKG/YR,HR/YR) DILUTI(36 TIMEIIR) SHORENIDTM FACTOR =0.5

] FISH 16.0 8.9 24.00 INVERTE8AATE 3.8 8.9 24.00 SHORELIE- 67.0 8. 9 - --~ ' O 0. ~ ~ ' - - ' ~ ' - -

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SMIP911NG 52.0 8.9 0.0 80ATING 52.0 8.9 0.0

- _ . - ~ ~ ~ ~~

i C NTUD - D 0 $ E S -

DOSE _,fletEN PER YEAR INTAKE)

PAT)G44Y ' - - ' SKIN 80E' -~ LIVER '~ TOTAL BODY TNYROIO KIDE Y Ltas GI-LLI '

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FISH 8.96E-05 4.77E-05 1.50E-05 3.28E-12 1.27E-08 2.69E-05 9.40E-06

} INVERTEBRATE 1.4 7E-04 7.83E-05 2.49E-05 2.31E-09 4.04E-12 . 4.42E-05 1.58E-05

$HORELINE 3.40E-07 2.89E-07 2.89E-07 2.89E-07 2.89E-07 2.89E-07 2.89E-07 2.89E-07 gg,,7,g - . ---. 0. 0 ~ ~~~ ~ - - ' ~ 3. 90E - 3.90E-09 ' ~

3.90E-09 3.90E-09 3.90E-09 3.90E-09 3.90E-09 BOATING 0.0 1.95E-09 1.95E-09 1.95E-09 1.95E-09 1.95E-09 1.95E-09 1.95E-09 TOTAL 3.40E-07 2.37E-04 1.26E-04 4.02E-05 2.95E-07 3.10E-07 7.13E-05 2.55E-05

- smau gKC/YR,HR/YR) ~ DILUTIIDs - TIEtist) ~ SHORENIDTH FACTOR =0.5 ' -' ~

FISH 6.9 8.9 24.00 IM.ERTEBRATE 1.7 8.9 24.00 5890 RELINE 14.0 8.9 0.0

~ ~ -

-SHIf911NG 29.0 - - " - ~ -~~ ' 8. 9 ' ' - ' O.0 ' '

  • DOATING 29.0 8.9 0.0 e

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LOCATIENE IS SHORELIE s .

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90SE_,,,,4PetEN PER YEAR INTAKEI PATHNAY SKIN -- - BCE '

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LIVER TOTAL 800Y ' THYROID FISH 6.52E-05 KIDE Y LLBEB CI-LLI 4.52E-05 1.08E-05 3.21E-12 1. 74E-08 INVERTEBRATE 1.04E-04 7.18E-05 2.51E-05 2.84E-05 1.73E-05 3.82E-12 3.04E-09 3.99E-35 SHORELINE 2.92E-07 2.48E-07 2.48E-07 2.48E-07 4.67E-05 SMIttfING O.0 2.48E-07 2.48E-07 2.48E-07 2.48E-07 6.91E-09 6.99E-09 '6.99E-09 ~ ~6. 99E-09 '

BOATING 0.0 3.49E-09 3.49E-09 6.99E-09' ~ 6.99E-09 '~ 6.99E-09 - ~~ ~

3.49E-09 3.49E-09 3.49E-09 3.49E-09 TOTAL 2.92E-07 1.69E-04 1.17E-04 2.84E-05 3.49E-09 2.58E-07 2.79E-07 6.53E-05 7.54E-05 FISM

- ._ . USAGE ~IKG/YR.HR/YRI~'~ " ~ DILUTION ~ TIEt M S SNORENISTN FACTOR =0.5 ' '

~

21.0 8.9 24.00 9

INVERTE8AATE 5.0 8.9 24.00

! SHORELINE 12.0 8.9 0.0 l SNIP 9fING ~~ 52.0 BOATING

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LOCATION IS

.-- - - SHOREL.I E - - - - . . - - . . - . . ._

1 TEENAGER DOSES 4

_ .. _.. . _ . _. __ DOSE _t y ,M M AR M M l $ PATHN4Y SKIN BOE LIVER j FISH TOTAL 800Y THYROID KIDEY 6.83E-05 4.86E-05 LtStB GI-LLI INVERTEBRATE 1.16E-05 3.08E-12 1.72E-08 3.07E-05 1.08E-04 7.70E-05 1.85E-05 2.27E-05 l SHORELINE ~-- f.~63E-06 3.66E-12 3.00E-09 4.86E-05 3.71E-05 SNItttING 0.0 1.38E-06 ~~- ~ 1.38E-06 ~ ~" 1.38E-06 ~ 1.38E-06 1.38E-06 1.38E-06 1.38E-06 ^ '~

6.99E-09 6.99E-09 6.99E-09 6.99E-09 80ATING 0.0 3.49E-09 6.99E-09 6.99E-09 6.99E-09 3.49E-09 3.49E-09 3.49E-09 3.49E-09 TO.TAL 1.63E-06 1.78E-04 3.49E-09 3.49E-09

-.1.27E-04 .___._._3.15E-05 1.39E-06 8.07E-05 6.12E-05 1.41E-06..-

- ~ . _ . _ .

USAGE IKG/YR.HR/YR) DILtFTION TIEt NR I FISH 16.0 SHORENEDTM FACTOR =0.5 8.9 24.00 INVERTEBRATE 3.8 8.9 24.00 I EM- '

-~~6 7. 0 '~ ~ 8. 9 ~ ~ ~ ~ ~ 0. 0 ~ ~- ' ' ~ ~' ~~ ~ ' ' '

SMItttING 52.0 8.9

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0.0 80ATING 52.0 8.9 0.0 73 g.- y g - -.--. _ . _ . - . ~ . - -- .- -- ... .- -

i CMILD DOSES .

_ _ __ _. . . . _ . . . __ .~

~ ~ OOSE_,tletEM PER YEAR INTAKEl ~ ~~

( PAT *DIAY SKIN BOE LIVER TOTAL 900Y THYllOIO l FISH 8.96E-05 4.77E-05 KIDEY LtStG GI-LLI INVERTE8 MATE ~ ~""~ 1.50E-05 3.28E-12 1.27E-08 2.69E-05

~1.47E-04~ 7.83E 2.49E-05 ~ 9.40E-06 SHORELIE 3.40E-07 2.89E-07 4.04E-12 2.31E-09 4.42E-05 1.58E-05 ~

2.89E-07 2.89E-07 2.89E-07 2.89E-07 SNIP 9 TING 0.0 3.90E-09 3.90E-09 2.89E-07 2.89E-07 BOATING 3.90E-09 3.90E-09 3.90E-09 3.90E-09 0.0 1 95E-09 1.95E-09 1.95E-09 1.95E-09 3.90E-09

, TOTAL ~--' ' ' ~~~ -~3. 40E-0 7 2.37E-04'~ 1.26E ~

1.95E-09 1.95E-09 -1.95E-09 4.02E-05 2.95E-07 3.10E-07 7.13E-05 2.E5E-05

~

USAGE EKG/YR,HR/YR) DILUTICBI FISM TIEllel SHORENIDTM FACTOR =0.5 6.9 i _ . _ ._ - - . , , , 8.9 _._,._24.00.-. _. .

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LOCATION 13 SNORELIE A0 ULT D0SES'~~~ ~~ ~

DOSE _ttutEM PER YEAR INTAKEI PATlee4Y SKIN BOE ' LIVER TOTAL 900Y THYROIO KIDE Y FILM 5.76E-06 4.23E-06 LtMG GI-LLI 1.13E-06 6.20E-10 1:10E-07 2.18E 06 INVERTE9AATE 8.90E-06 6.25E-06 1.60E-06 3.35E-06 SNORELINE 3.23E-08 7.39E-10 1.74E-08 3.43E-06 5.20E-06 2.76E-08 2.76E-08 2.76E-08 2.76E-08 2.76E-08 SNItttING O.0 ~ ~ ~ 2.06E-09 2.76E-08 2.76E-06 SOATING 2.06E-09 ' ~ ~ 2.06E-09 ~ ~ 2.06E-09 2.06E-09 2.06E 2.06E-09 ~

0.0 1.03E-09 1.03E-09 1.03E-09 1.03E-09 TOTAL 3.23E-08 1.47E-05 1.03E-09 1.03E-09 1.03E-09 1.05E-05 2. 77E-06 3.21E-08 1.58E-07

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8.9 24.00 INVERTEBRATE 5.0 8.9 24.00 SHORELIE ~ '~

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0.0 LOCATION IS SHORELINE TEENAGER 003ES OuSE_tPWtEM PER YEAR INTAKEl DJ.T>eu,Y SKIN ..

BONE LIVER TOTAL 800Y THYROIO KIDE Y g F10if 6.04E-06 LtDG GI-LLI o 4.52E-06 1.14E-06 5.95E-10 1.13E-07 2.67E-06 INVERTEBRATE 2.54E-06 9.30E-06 ~ ' 6.69E-06 1.70E-06 7.06E-10 1.78E-08 4.18E-06 3.98E-06

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FISM 16.0 SHOREMIOTH FACTUR=0.5 8.9 24.00 INYERTEBRATE 3.8 SHORELI E 67.0

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$NIf9 TING 52.0 8.9 0.0 80ATING 52.0 8.9 0.0 g -

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PAT M Y SKIN SOE LIVER FISH TOTAL 900Y THYROIO KIONEY LtMG 7.91E-06 4.40E-06 GI-LLI

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- SEMIANNUAL ~ RADIOACTIVE EFFLUEN' RELEASE REPORT F - METEOROLOGICAL DATA 1987 N

' Tables of ' cumulative joint frequency distribution of wind speed, wind direction, and atmospheric stability are given by quarter for release heights of 33 feet.

- and-150 feet. The directional sector limits were changed during 1987 to correspond to those used by the computerized Radiation Monitoring System, ie, N=-ll.25' to +11.25', etc. The presented joint frequency distributions reflect the new limits.

During 1987 two Special Reports (LER's 87a005 and 87-028, Rev.1) were submitted 7 to the Commission persuar.t to Technical Specifications 3.3.7.3, Action Statement a, and 6.9.2, describing malfunctions in the delta temperature system. In the Reports it was noted that the problem was intermittent and occurred only during ,

periods of driving precipitation. It was stated that although the system was declared inoperable, all valid data, as. determined by meteorological review, [

would be reported in this Seminannual Radioactive Effluent Release Report.

. One of the Special Reports also described intermittent malfunctions of the 150' wind direction system. Again it was stated that all valid data as determined by meteorological review would be presented here.

l The joint frequency distributions reflect all data that was determined to be valid by a meteorological consultant. Due to the delta temperature system malfunctions, a data recovery rate of only 89% was achieved for 1987.

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HOURS AT EACH MI N SPEE) AND EIRECTION ,

- PERIDO OF RECORD *. 7/ 1/87 TO 9/30/87- - - --- ---- ----. -- -- -- --- .--- ---

STABILITY CLASS

  • C ELEVATION 33

_ - . MIN SPEED (MPH ) - -- -- - - -- - -- -- - - - --

MIM l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TUTALS l

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SSH 43 32 0 0 0 0 75 SH 24 5 0 0 0 0 30 PCM 9 5 0 0 0 0 16 M -

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peM S 2 1 0 0 0 9 NH 0 5 0 0 0 0 5 t#H 0 4 0 0 0 0 4 VARIABLE - - - - - . - - - - - - - - -- - -- - - -- -

TOTAL 355 &

PERIODS OF CALM IHOURSI 6 e.--= we-- -m- --e -..mi. .-4 ..-a m e-mem aee

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_ _ _ . PERIOD OF RECORD *- .,10/ 1/87.TO 12/32/is7 -- -

STASILITY CLASS D ELEVATION: 33

._ . MDG - SPEED E M8H I -

1 MM DIRECTI(DI 1-3 4-7 8-12 13-18 19-24 >24 TOTALS M - 1 4 -- 5 .-~. 4 0- 0_ _ _ _ _ . - ._ _~ ,

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___ . VARIABLE - _ _ _ . - . - . _ -

O TOTAL 429 W PERICOS OF CALM (HOURS 32 0

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STASILITY CLAS$t E ELEVATION: 33

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Beel 3 19 51 75 13 0 161 M4 0 12 26 61 14 7 120 Met 4 15 14 19 0 5 57

-_- _. VARIABLE _ .- -___ - - - - - - . . _ - - ---.

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HOURS AT EACH HIlm SPEE) Afe CIRECTION PERICO OF RECORD

  • 4/1/87 TO 6/30/87 --- --- . -. . --- -- - . -- .. . . -

ELEVATION: 150

-_ .. - - - - . - - - .. MIPs .SP.EED (PFH)

DIRECTION 1-3 4-7 6-12 13-18 19-24 >24 TOTALS N .O 24 _%_ 2__. 1 _ 0_.._ 30 _ _ . _ - __ . _ .. ._. -_- -. - . .... ---. .__

PE I a 19 12 1 0 41 EPE 3 1 11 15 0 0 30 E 1 2 7 4 2 0 16 '~~'- -~ ' -- ' ' ~~~" ~~ - ~ ~ ~

4 ---' 1 ' ~ 0 - ~ ~ ~ 0 --' ~ 11 5

SE 1 3 3 1 0 0 8 SSt 0 9 16 0 0 0 25 S _

1 .- 5---_ 12 _ 22 -_.-.4_ _ 0...__ 44 .__ _-- . _ -_ _ _ ._ ._ . ~_- ._ .__ --- - - . .

SH 0 4 12 4 0 0 20 PCM 0 1 18 5 0 0 24 H O 7 42 4 3 1 57 ~ ~ ' - ~' ' --^^

leet 0 16 12 ~ 6 ' O " ~~ 0 " -~ 34 - ^ ~ ~--- ~~~~ ~ - --'-~~~~~ ' ' ~ ~ ~

PM 0 9 5 1 0 0 15 f*M 1 13 2 3 1 0 20 VARIABLE _, _ _ _ ___ __ _ _ __ ___ ,_ .__ __, . _ _ _ __ _ __ , ____

TOTAL 428 PERIDOS OF CALM iHOURSI* O $

.- -we *e>wm- e= m- ma -w .mame--wie. e-w -- .* -e o - are wa= =*eew=was* **- = eelp.ermh ew

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%. NOLMS ET EAC98 DEIts SPEE3 Age DIRECTItst -

- - PERIOD OF REComes . 4/1/87 TO-6/30/87. _- -_ . . - - - . - - ._~ ._... .- . , _ . - .. __.., _

{ < .. ELEVATION 150

,__ . _. Its__S. M PEED._t1946 _1_ . ._ _ , _ __. ___ _ . _ _ ___ ___ .._. ._ _ _ _.

DIstECTION 1-3 4-7 8-12 13-18 19-24 228, TOTALS M 1 7 6 14 15 1 44 -- . .. . ...

DE O 15 35 24 7 0 81 ENE 1 11 33 11 0 0 56

___ _ _. T 2 6 _ 167 . . . 5 . ..__1 _ 0 30 7

SE 1 6 2 1 0 S 10 SSE 1 7 7 4 0 0 19 5 - 6 . __ 7 _ 24 _ 50 15 0 96 _- _ ___. .__.-

SM e 4 13 11 0 0 28 MSN O 7 16 6 4 0 33 M _ _ . . -____ 1 _ 7_._ 27 _ 10 _ ._7 0 52__ __.

Det 1 8 10 to 2 0 41 feet 1 5 6 16 3 1 32 VARIASLE___ _ _ _ - _ ____ _ _ _. . _ _ . .

to TOTAL 698 m PERIGOS OF CALM tHOURSI8 0 w-m, asms.m w e. .MM.y w hashh4 m-.-Am.e=44_i aw.- e. __munque-h ,-mm.m_ w. was ,e m.4

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HOURS CT EACH MIIC SPEED Afe DIRECTION 6 PERIOD OF RECORDt 4/ 1/87 TO 6/30/87 _ _.-__ ._ .- . - _ _ + .~__

ELEVATIONI 150

__ _.___ __ _ _ _ . . . __._ MIPe SPEED._t#9HI _. _ .. . _ ___ _ . _-. ,__ . .

DIRECTION 1-3 4-7 6-12 13-18 19-24 >24 TOTALS N 1 2 2 0 2 0 7 f*C 2 9 4 2 0 0 17

  1. E 2 10 16 5 1 0 35 ENE 1 7 20 1 0 0 29 o 7 . 0 ,.-. 0 . - 0 E

4 . -. 11 . -. . - --. _ -. . . - - --- .. ..- -.-. . _ - _

SE o 2 2 0 0 0 4 SSE 1 1 9 3 0 0 14 S 1 1 21 _ 13_ _ .1. _. 0 _ _ . 3 7 _ _.

SH 0 5 10 8 0 0 23 K.J4 1 3 7 3 0 0 14 H C G 9 O 9 0 9

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ted 0 3 15 3 0 0 21 tem 3 9 6  ? O S 20 e VARIABLE G TOTAL 314 PtRIODS OF CALM 4HOURSI 0 p_ -

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STABILITY CLASS E ELEVATION! 150

- NI>G SPEED (WH D- - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - -- - --- - -

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N TOTAL 607 o d

PERIODS OF CALM EHOURSis 2

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- . . - - . PERICO OF RECORBt 10/1/87 TO 12/31/87e- - . - . .

ELEVATION 8 150

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-- - - -..w-- .-MDS. SPEED E WM i - -

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eIRECTION 1-3 4-7 6-12 13-18 19-24 >24 TOTALS -

- e N .---

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. VARIABLE _ _ . . . - - . . --. .. . .- . - . -- - .. - - . ... . .

TOTAL 448 "

o PERIODS OF CALM IMOURSIs 0 W

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.._. . STABILITY CLASSt it ~ - ~ ' ~ ~

ELEVATIOMs 150

_ _ . Mile SPEED _IIM I DIRECTIEW 1-3 4-7 S-12 13-14 19-24 >24 TOTALS N 2 9 6.- 73_--

._y. 3 g . _ 25 33 _ 28,g y _ ... , . .. ... . . - . . .- .-.. ~ .---

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_ _ _ _. ESE- e e 5 2 2 ~~~5 - ~ 15 ' -~~~

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117 ~~

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500 3 10 15 33 49 23 133 feet 0 2 8 28 23 8 69 VARIABLE . . - - _ - - ~ . . _ - - .-

TOTAL 1943 m PERIGOS OF CALM iIERRSI 0 O l m -e_%,. -pm .w.< e-e.en - we.- a a.m. ii -mem-. m .-.pu-m '_ .em- s Wa - me d~_. 4h.e+a4.a.6

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f ., -SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT y

G - PCP & ODCM REVISIONS, REMP NON COMPLIANCES AND MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS l l

l According to Technical Specification 6.9.1.7 the Semiannual Radioactive Effluent Release -Report shall include any. changes to the Process Control . Program (PCP)

.and to the Offsite Dose Calculation Manual (ODCM) made during the reporting period.

The following changes are hereby submitted in compliance with these requirements.

'A. 1. Revision 4 of the PCP was issued to generalize the method for determining radwaste oil content and specify the units of the results.

Several administrative corrections were also made. Oil content was previously determined by visual inspection to be less than 1% by volume. ,

2. This revision did not cause a reduction in the overall conformance of the solidified waste product to existing PCP requirements; it allowed more accurate methods to be used to determine oil content and required the results to be reported as % by volume.
3. The revised PCP and the document cover, indicating review and acceptance by the Review of Operations Committee (ROC), follow.

B. 1. Revision 10 of the ODCM was issued to

a. incorporate editorial changas and corrections,
b. revise figures and tables to comply with the most recent environmental monitoring data  ;

y c. Mention the use of HRC computer codes in dose calculations prepared  ;

-for the Semiannual Radioactive Effluent Release Reports  ;

d. Change the critical dose location to reflect a newly identified milk animal and incorporate specific parameters relating to the location (ie, time on pasture, X/Q values),

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2. The accuracy and reliability of the dose calculations will not be reduced since the changes made reflect current actual conditions and data to be used in dose calculations.
3. The affected pages of the ODCM and the signature page, indicating ROC t review and acceptance, follow. l I

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Action Statement C of Technical Specification 3.12.1 and a and b of Technical Specification 3.12.2 require certain items of REMP noncompliance to be reported in the Semiannual Radioactive Effluent Release Report.

C. Milk samples at Technical Specification indicator location Ial became unavailable in August 1987, due to a) the owners moved (taking the goats) from the primary location 6B2, and b) the owner's extended travel plans at the secondary location, 6Bl. At that time, no replacement milking animals were available for the indicator location. In lieu of milk sampling, fresh leafy vegetables were sampled at tire of harvest at three locations as specified in the Technical Specification and the ODCM.

Technical Specification 6.15 states that the Seminannual Radioactive Effluent Release Report shall include major changes to radioactive waste treatment systems.

D. There were no major changes to radioactive waste treatment systems during this reporting period.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT H - MISCELLANEOUS SPECIAL REPORTS 3rd & 4th Quarters of 1987 Action Statement b of Technical Specification 3.3.7.10 requires that when -

certain liquid effluent monitoring instrumentation remains inoperable beyond a specified period of tire, the reason why the inoperability was not corrected within that time should be explained in this Report.

~ The RHR' heat exchanger service water radiation monitor 1D11*RE23A was declared inoperable on 8-11-87_ due"to a scheduled outage of Bus 101. It was returned to service on 10-13-87 after 62 days when the Bus 101 outage was over. Monitor 1Dll*RE23B was declared inoperable on 9-30-87 because of low sample flow and a Maintenance Work Request was written. However, the prob'.em was not corrected within 30 days, due to inaccessibility of the system fet testing and repair.

In the previous Semiannual Radioactive Effluent Palease Report it was stated that milk samples from a location meeting all the requirements of the indicator location specified in Technical Specification Tabls 3.12.1-1.4a were being collected to satisfy Technical Specification requiremer.t 91though the location was not yet in the ODCM. This was again the case for July 1987 Samples from this location became unavailable in August 1987 (see Section G) however, a new

, milk location was identified in December 1987. It meets all the requirements of the Technical Specification indicator location. A sample from this location, identified as 13B1 was used to satisfy the December sample requirements. The ODCM will be updated to include this new location and presented in the next Report.

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Effective Date: 8/14/87-

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SOLID NPSIE i

PROCESS CCNDOL PROGRAM 70R i SiOREHAM NUCLEAR POWER STATION - LNIT 1I >

RENISION 4 IWG ISIAND LIGfrING OCHPANY Docket No. 50-322

[

August 5, 1987 Prepred by: /'/ ., -f Nuclear EngirJleering Departnant Dater 6[SI6 7 PeViewed by: .

Date 8[T[87 KC Quiman Approved by: _

a b hv Date F[$/M7 Plant Manager ****CM  :

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. TABIE OF CCtmNIS

(- PAGE4 1.0 WRPOSE 1 2.0 RADIOACTIVE WAS'IT SOURCES 2 2.1 Evaporator Bottma 2 2.2 Floor Drain Filter 2 2.3 Radwaste Filter 3 2.4 Spent Resin Tank 4 2.5 Cartridge Filters 4 2.6 Trash Ccmpactor 4 3.0 Radioactive Waste Streams 4 4.0 In-House Solidification System 6 i

5.0 In-House Dewatering 6 6.0 Mobile Solidification and Dewatering Services 7 7.0 Solidification Process Control Parameter Determination 7 8.0 Solidification and Dewatering Process Control 7 8.1 Sanpling and Analysis 7 O'- 8.2 Conditioning 8 8.3 Batch Test Solidification 9 8.4 Waste Classification 10 8.5 Container Control 10 8.6 Decentamination 11 8.7 Changes to the Process Control Program 11 8.8 Records and Inventory Control 11 9.0 Responsibilities 11 10.0 References 13 10.1 LIIf0 Operating Procedures 13 10.2 Mobile Services Contractor Doctments 13 10.3 General References 14 Appendix A Solidification Record Sheet 16 Appendix B Dewatering Record Sheet 21 FIGURE 1 Solid Radwaste Systern 22 e

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l 1.0 PURPOSE l

'Ihe Shoreham Nuclear Power Station (SNPS) Process Control Program (PCP) i describes the administrative and process controls which provide reasonable  ;

assurance of a consistent quality radioactive waste product which is acceptable for shipent and burial. Ir.pleentation of this PCP wills o Provide assurance that waste types produced at SNPS will be classified satisfactorily in accordance with the requirements of 10CFR61.

o Provide assurance that the requirernents of 10CFR61 and specific disposal site criteria for Class A unstable waste to be solidified are  ;

met by the use of a stobile solidification system supplied by a

qualified contractor, khen additional sanple solidification data becmes available, this PCP will be nodified to dernonstrate the '

qualification of the in-house solidification system that may be used, in addition to a mobile solidification syst s supplied by a qualified contractor, for processing of Class A unstable waste.

o Provide assurance that the waste fom stability requirerents of 10CFR61 for Class B and C wastes are met. 'Ihis will be accmplished through l the use of a nobile solidification syste supplied by a qualified  :

contractor or use of approved High Integrity Containers (HICs). Lhtil O such timo as the contractor's Topical Report has been approved by the NBC, qualification will be based on the contractor's past record of producing acceptable BWR waste packages for waste streams similar to those produced at SNPS. The contractor's Process Control Prcgrams are referenced in the "Fbbile Service Contracter Documents" Section of this document. SSPS nanagment shall ensure that the contracter's waste processing cperations are perfomed in accordance with procedures.

o Provide assurance that dewatered Class A, B or C waste products meet the applicable burial site criteria for free standing water when the in-house or contractor's dewatering equipent and procedures are used.

o Provide assurance that the processing and packaging of solid radioactive wastes meet the requirments of federal and state regulations and disposal site criteria.  !

o Ensure that the quality assurance requirerents delineated in 10 CFR

71.101, 71.103 and 71.105 are met for both in-house and nobile

! contractor processing.

2.0 RADIorcrIVE WASIE SCUBCES Iow-level radioa'ctive wastes are produced as a result of routine plant cperation and maintenance of plant systems. 'Ihe major contributing sources of ,

radioactive waste are listed below:  ;

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Page 2 of 22 2.1 EVAPORNIOR DCTI'IGS 2.1.1 Waste Evaporator The waste Evaporator receives high conductivity waste primrily frcm the ficer drains.

The design concentration of the Waste Evaporator is an 18 wight percent concentrate of dissolved and suspended solids.

2.1.2 Pegenerant Evaporator The Regenerant Evaporator receives primarily liquid chenical wastes produced by the acid / caustic regeneration of the condensate danineralizer resins.

The waste is collected, neutralized, and sampled in the Regenerant Liquid and Evaporator Feed Tanks, and then purped to the Regenerant Evaporator for concentration to a 25 weight percent mixture of sodium sulfate and other dissolved and suspended solids.

2.1.3 Bottms Transfer Each evaporator is a forced circulatico design with a reboiler providing process heat and an overhead entraiment separator and rectifying column which minimizes liquid droplets in the vapor. hhen the desired solid content has been reached, the concentrated evaporator bottms are eccled and sent to the Evaporator Bottms Tanx or directly to the Evapcrator Bottms Ma+-im kno for solidification according to the contractor's procedure F458-P-002, "Operating Procedures for Fbbile In-Container Solidification of Sodium Sulfate Slurries."

In order to provide maximum ficxibility, each evaporator can be used as a back-up for the other.

2.2 FIDOR DRAIN FILTER The filter is a horizontal traveling screen, precoat type, designed for air drying and air-aided discharge of the cake (withcut backflushing) into a shipping container for further dewatering. The waste my contain filter nodia such as diatmaceous earth or a powdered resin / fiber blend type mterial. ,

The ficer drain filter is used to process the follcwing ccrbined liquid radwaste streams:

Page 3 of 22 o Reactor Bldg Floor Drains o Turbine Bldg. Floor Drains o Radwaste Bldg. Floor Drains o Machine Shop Floor Drains o Sanple Tank Area Floor Drains o Turbine Bldg. Decon Area Floor Drains {

o Condensate Domin. System Waste Sutp Patp Disch. and tac Backwash.

o Cond. Storage and Transfer System overficw Sutp Putps discharge, o Laundry Drains Tank Class A, B and C waste which is dewatered using in-house e',,11ptent is processed according to SP R3.710.02, "Dewatering of Spent Radwaste Media".

Waste which is dewatered by the contractor's stobile equiptent will be processed according to his procedures, (see "REFERD CES" Section).

2.3 RADWAS'IE FILTER

'Ihe Radwaste Filter is used to process the following ccribined liquid radwaste streams: ,

o Ior conductivity equipment drains o Reactor B1.dg. Equip. Drains, drywell equip, draita, Radwaste Bldg equip drains, and 'nirbine Bldg equip. drains o Solid Waste Systern dewatering tank decanted liquid o RW filters displacement and prefiltration liquid o Decanted liquid frcn t'w Phase Separator and the Spent Fesin Tank o Blowdom frcn the reactor water cleanup and residual heat removal systes

' o Blowdown frcm the Fuel Pool Cboling and Clean-up System o Ultrasonic Resin Cleaner Backwash

'Ihe radwaste filter units are each ccriposed of stacked horizontal filter discs assernbled on an axially located hollow shaft. After draining the filter vessel and air-drying the filter cake, the filter assertbly is spun to rertove the filter cake frca the filter discs and discharged directly into a waste shipping container for i

dewatering and disposal, jt

'Ihe waste resulting frca the filters my contain diatcznaceous earth, F W or similar powdered resin / fiber blend material. If Class A, B or C waste is being dewatered using in-house equipreent, it is processed according to SP R3.710.02, "Dewatering of Spent Radwaste ,

Media". All classes of waste may also be dewatered by the contractor using procedures referewwi in the "REERDCES" Section.

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Page 4 of 22 2.4 SPDC RESIN TANK (SRT)

'Ihe Spent Resin Tank accepts resin / filter media (via the Phase +

Separator Tanks) frm the reactor water cleanup (PHCU) filter -

dernineralizers, the sludge frm the backwash storage tank of the Ibel Pool Clean-u? etched-disc type filter, in addition to spent bead resin frce tw condensate domineralizers, the fuel pool l deineralizers, and the radwaste deineralizers. 'Ihe resin is allowed to settle before excess water is decanted to the waste collector tanks.

Mixed powdered and bead resin in the SRT can be transferred directly into a HIC frce the SRT for dewatering by the in-house equipt or the contractors' M: bile unit using the procedures in the ,

"REFERENCES" section of this PCP.

2.5 CARrRIDGE FILTr#

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'Ihe Iaundzy D:.ain System and the Control Drive System use a cartridge type filter for processing, 'Ihese cartridges my be imobilized in a cement mixture which includes evaporator bottcns concentrates or spent resins. 'Ihese may also be empacted as Dry Active Waste (DAW) using SP R3.075.01 (provided the filter cartridge 0, is dry). Liners that contain solid cbjects are specifically identified.

2.6 TPASH COMPAC'IOR

'Ihe drun ccatpactor is used to empress low level dzy waste such as rags, paper, shoe covers, ficer sweepings, dry filters, HEPA  ;

filters, strainers ard plastic gloves into 55 gallon steel dnrs for i ship'ent offsite . Ccrpaction force is rated at 18,000 lbs for an  ;

approximate 4:1 capaction ratio.

A box capactor will be installed which capresses waste into 96 cu.

ft. rnetal boxes. 'Ihis is a self-contained unit with its own HEPA filtering systs. 'Ihe empaction force is rated at 60,000 lbs.

3.0 RADIOACTIVE WAS'IT STRERiS l 3.1 EVAPOPA'IOR BOI'KMS CCtCDUPATES

'Ihis my be a mixture of :

! 3.1.1 Owunical regeneration concentrates frcn the Regenerant '

Evaporator process, t 3.1.2 Floor Drain concentrates frcm the Waste Evaporator process.

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3.2 SPDir RESIN TANK NASE

'Ihis might be a mixture of the following:

3.2.1 Condensate Domineralizer Resins .

3.2.2 Radwaste Denineralizer Resins 3.2.3 Fuel Pool Demineralizer Resins 3.2.4 Phase Separator Resin 3.2.5 Vacco Filter Backw sh Sludges 3.3 ITNDA FILER GINERATID WASE t

3.4 FIDOR DRAIN FILTER GE2aAITD WASE 3.5 DRY ACTIVE WASE (DAW) I 3.5.1 ccs:pactible i

3.5.2 Non-Ccrpactible p 3.6 FILER CARTRIDGES 3.6.1 HEPA Filters 3.6.2 laundry Drain Filter Cartridges i  :

3.6.3 CRD Filter Cartridges 3.7 RADIOACTIVELY OCtfrAMINATID LIQUIDS AND SOLIDS a

Due to varying burial site regulations, each will be handled on a case by case basis in accordance with the burial site criteria and federal regulations.  !

4 3.7.1 Organics (including oils) i 3.7.2 Charcoal (Filters, Charcoal Beds) l l

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Page 6 of 22 4.0 IN-HOUSE SOLIDIFICATICN SYSTDi SNPS has a pemanently installed Atcor radioactive waste solidification system which, when additional test data is available, may be used to package either radioactive evaporator bottcms or resins / sludges for disposal as Class A waste. Until that time, all wastes for solidification will be transferred to the contractor's mobile equipent.

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'Ihe follwing is a description of the in-house system. Waste and cement flows are fixed by preset metering punps using flw rates reccmended by Atcor ard verified by full scale testing. Flews are also nonitored by tackmeters installed on the control panel. 'Ihe resin / sludge is processed frce the Waste Dewatering Tank and evaporator bottms are processed frce the evaporator bottcms system or directly frcn the evaporators.

Cement and evaporator bottcms or resin / sludge are introduced into the -

mixer feeder unit for through mixing and discharge into a container. The small-volume continuous mixer limits the surface contact of the wet cement and also limits the quantity of wet cement in the system at any time. A mnual handcrank is provided to pemit erptying the mixer / feeder by the operator in case of power loss or equiptent malfunction.

Flush water connections are provided inside the mixer / feeder to rencve

coment residue.

Safety features include o An interlock to prevent filling unless the pipe is preserly inserted I into the container fill opening, o An ultrasonic level sensor, and a timer to monitor waste level in the container to prevent overflowing. Cenent-bearing flush water cannot be discharged unless a receptacle is in place.

o Failure to initiate a flush sequence within 20 minutes after filling i steps prcepts an alarm. '

hten operational the system will be cperated according to SP 23.713.01, "Solid Padwaste Systen." A sirplified functional diagram appears in Figure 1.

J 5.0 IN-HCUSE DDGTERUG As an alternative to solidification, Class A, B, and C dewaterable waste ray be dewatered in High Integrity Containers (HIC). Non high integrity containers can be used for C1sss A waste. All of these containers are i equipped with internal filters to which a pmp may be attached. Pmping continues until burial site criteria for free starding non corrosive

, liquid are met as described in SP R3.710.02.

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Page 7 of 22 Dewatering is conducted in accordance with plant pn:cedure SP R3.710.02, "Dewatering of Spent Radwaste Media," to assure a consistently acceptable product.

6.0 FOBILE SOLIDIFICATION AND DBGTERING SERVICES 6.1 Wastes to be solidified nust be transferred to the trobile solidification / dewatering equipmnt which is provided and cperated by a qualified contractor. Class A, B or C dowatered wastes may be processed by the mobile services contractor or the in-house dewatering system at the discretion of the Radwaste Engineer.

Class A solidified wastes my be processed by the contractor or by the in-house solidification system after qualification is ccrnpleted.

6.2 The "Fbbile Service Contractor Dccuments" in the "FEFERDCES" Section lists those prccedures which IMy be used by the trobile services contractor to ensure that waste products meet all requirerents for shipnent and burial offsite, 6.3 Provisions have been rude for the mobile solidification equipmnt to be installed on Elevation 19' of the Padwaste Building wittch is a seismic category I Structure. This equipmnt will be installed and utilized as required. Spill are centained iy installing the O1 equipmnt in areas where slopire floors will carry liquids to flcer drain sumps. The building ventilation system provides for filtering of particulate airborne contamination and tronitoring of radiation before it enters the station vent.

7.0 SOLIDIFICATIO2 PPOCESS CXIITPOL PAPAv.ETER DETEPMINATIOi hhen additional sarples have been tested for solidification, this section will contain a sumury of qualification test results for the in-house solidification systen. During the interim, the in-house system will not be used to solidify vaste for shipmnt offsite.

8.0 SOLIDIFICATION AND DDGTERDiG PPODLET CO7IPOL 8.1 SAMPLING AND ANALYSIS 8.1.1 Samples shall be obtained ard analyzed according to SP 72.002.18, "Padwaste Sarpling for Disposal," prior to each solidification or dewatering operation and SP R4.014.01, "Padwaste Sarple Solidification Test," prior to solidification.

8.1.1.1 Sa pling for Solidification i

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1. 'Ihe waste tank to be sanpled shall be  :

recirculated for a mininun of three tank volumes  !

prior to supling, unless the tank had been on  :

rocirculation continuously since it began i filling.

2. An exception to the above is the Waste Dowatering Tank which is equipiwi with an agitator rather than a recirculating punp.

Agitation is continued for at least 25 minutes prior to sanpling.

3. 'Ihe waste tank sampled shall. remain isolated and in recirculation or agitation, as applicable, until the solidification process is started, If it beccnes necessary to add material to the tank l' being processed, a new b ,tch nunber will be initiated and a new sanple will be taken after i an appropriate mixing time.

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4. Test solidification will be performed according to the schedule described in the "Batch Test Solidification" Section.
5. Solidification sanpl requirements apply to all waste, whether it s being processed by permanently installed equipent or by the  :

contractor's mobile equipnent.

8.1.1.2 Sarpling for Dewatering Funda, Spent Resin Tank and flat bed filter wastes [

nust be sanpled frca the liner. 'these will not be  :

mixed prior to sanpling.  !

8.1.2 'Ihe following applies to both Dewatering and Solidificatist.

1. Sanples will be analyzed for pH and ganna emitters.  !
2. Oil content will be verified to be less than it by volume i c

prior to shipnent, i

3. 'Ihe analysis nunter will be added to the Solidification or Dewatering Record Sheet which is prepared for each  !

waste container (liner or HIC).  !

8.2 CINDITICNING I l

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  • 8.2.1 Waste conditioning for solidification is required when any of the following conditions exist:
1. The pH is outside of the acceptable range according to the contractor's PCP.
2. Liquid content of the batch is abcne or below the acceptable envelope for solidification as indicated in the Contractor's PCP in the "REFDENCES" Section documents.

8.2.2 pH shall be determined on the decanted liquid im each container which has been dewatered. If pH is k;,s than 4 or greater than 11 it wi'l be detemined on a case-by-case basis if any further action is required prior to shipment.

l 8.3 BA70{ TEST SOLIDIFICATICN 8.3.1 'Nst solidification shall be perfomed according to the following schedule

1. One sanple initially frca each type of wet waste, and  !

then frm every tenth batch of each type of wet waste.

WrE: Batch is defined as the total voltrus of waste contained in a waste mixing tank that has been r prepared for solidification.

2. When sample analyses fall outside the acceptable envelope establis m3 by the mobile services contractor, indicating a change in the waste t3pe.

8.3.2 If any test speciwn fails to solidify, the solidification .

of the batch under test shall be deferred until such time as additional test specimens can be obtained, alternatim solidification parameters can be detemined, end a  ;

subsequent test verifies solidification. Soliciification of the batch may then be performed using the alternative solidification parameters detemined.

Pepresentative sanples shall be obtained and tested frcn  !

each consecutive batch of the same type of wet waste until  ;

at least three consecutive initial test specinens dem:r. strate solidification. The process control program shall ba modified as required to assure solidification of subsequent batches of waste. The ccotractor shall modify his cwn PCP as necessary to acccrmodate unusual waste i streams, t

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8.3.3 The test speciron sM ll be judged to have solidified successfully if, when its ccntainer has been roomod,-it remins a free standing renolith with no visible free liquid.

8.3.4 If a cement and water mixture (without waste) is used to solidify miscellanecus objects, this mixture will be tested for solidification prior to use.

8.4 WASTE CLASSIFICATICXi 8.4.1 In ccepliance with 10 cm 20.311, wastes are classified as Class A, B or C, or greater than Class C, based on the presence of particular radionuclides and their activities as specified in 10 CFR 61.55. Plant procedures SP R2.713.06, "Calculations for Padwaste Curie Content," or SP R3.713.02 "PADfWi Ccrputer Program" prcvide the metMdology for this determination as usod at S.'PS.

8.4.2 Waste streams will be sarpled based upon the Branc.h Technical Position requirecents (or more frequently, if plant parareters irdicate a change in waste characteristics) and analyzed fcr fission and activation products, including transuranics. Scaling factors develcped frcn these cceplete analyses will to used with gara spectra frca each batch of waste to infer the concentrations of non-gama (nittirn radionuclides.

8.4.3 During initial plcat operation when the results of actual analyses are not yet available, radionuclide concentrations will be used in accordance with "FAttWi - Data Base Analysis Peport".

8.4.4 TN curie content of waste streams (such as trash) for wttich representative sanpling is difficult may be inferred based on ganna analysis of representative smears and external dose rate reasurment (SP R2.713.06 or SP R3.713.02) .

8.5 CEtEADER CCtiTPOL 8.5.1 A quality assurance prcgram shall be establishcd to inspect the container to be used for devatering (and solidification) using SP R2.713.30, "Pr%aste Container Control".

1 8.5.2 This prcgram shall assure that prior to use, the containers to be used for dewatering are intact and free of any visual darage that would prevent the dewatering of waste to required limits, i

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Page 11 of 22 8.6 DECOtTIAMINATICN Prior to shipmnt, containers will be swiped for renovable cantamination and examined for general condition. Decontamination will be conducted as necessary to meet shipping requirements.

8.7 OIANGES 'IO 'IEE PROCESS COtTTEL PROGPAM Any changes to the Solid Waste Process Control Program for the Shoreham Nuclear Power Station shall be re/iewed and found acceptable by the Paview of Operations Ccmnittee and approved by the Plant Manager and reported to the NRC in the Seniannual Radioactive Effluent Pelease Peport.

8.8 PEDRDS AND INVDTIORY COtfrROL 8.8.1 Solidification

1. A Solidification Pecord Sheet (Appendix A) shall be capleted for each liner filled for solidification.
2. If nure than one liner results frcm a batch, then the initial liners will not be shipped until all liners for that batch have verified solidification. Those liners O. will be identified by a comen analysis ni.mber.

8.8.2 Dewatering Radiochemistry Analysis Sheet and Post Dewatering Survey Sheet (see Appendix B and Appendices 12.4 and 12.5 of SP R3.710.02) shall be carpleted for each container filled with dewatered waste.

8.8.3 Solidification and Dewatering

1. The Solidification or Dewatering Pecord Sheets and the attached isotopic analysis shall be forwarded to the Radwaste Engineer for retention until such time as the liner identified on the Pecord Sheet is shipped for final disposition.
2. When the identified liner is shipped and then verified received, the Solidification or Dewatering Pecord Sheets and other documents concerning the shiprent shall be forwarded to SR2 for permanent record storage.

9.0 RESPONSIBILITIES i

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'Ihe following outlines departmental responsibilities and interfaces to impleent and support all activities associated with the SNPS PCP.

IUrE: All service contractor procedures inplemnting the PCP which will be used at SNPS, prior to their utilization and inpleentation, nust be approved by the Review of Operations Camittee as per SNPS Tech. Spec.

6.8.1.h.

9.1 NOC Policy 25 (Managment of Icw Ievel Radioactive Waste) identifies the following departments as having direct responsibilities for the inplementation, maintenance, licensing and regulatory interface of the SNPS PCP.

9.1.1 Nuclear Engineering Department, as also described in NED 1.02.

9.1.2 Shoreham Operation Departe nt, as also described in SP Rl.001.01.

9.1.3 Nuclear Operations Support Department.

9.1.4 Nuclear Quality Assurance Department (CA) as described in the CA Manual, Section 1.

9.1.5 Nuclear Peview Board (NRB) as also described in the "Charter of the Shoreham Nuclear Power Review Board".

See NOC Policy 25 for more details.

9.2 Procedure NED 6.04, "Change Control", in conjunction with the 10SD 6, "Control of License Documents" shall be used to review, approve, control and disposition prcposed changes and revisions to the SNPS PCP".

9.3 NED is responsible for preparing and maintaining the PCP current per NED Procedures 6.04 and 6.01, 9.4 'Ihe Paview of Operations Ccmittee (POC) is responsible to review

and find acceptable any changes to this program and the associated l

inpleenting procedures, i

9.5 The Plant Manager's approval shall be obtained for every PCP revision.

9.6 RCC review and Plant Manager approval signatures shall be indicated on the cover page of the PCP, 9.7 PCP inpimentation is acccuplished through station procedures and is

, the responsibility of the Radiological Controls and operations Divisions.

Page 13 of 22 4

10.0 m ue2CES 10.1 LIICO OPERATING PRCCEDURES 10.1.1 SP 23.710.01, Iow Conductivity Liquid Radwaste 10.1.2 SP R3.710.02, Dewatering of Spent Radwaste Media 10.1.3 SP 23.711.01, High Conductivity Liquid Radvaste 10.1.4 S? 23.712.01, Regenerant Chemical Liquid Radwaste 10.1.5 3P 23.713.01, Solid Radwaste System 10.1.6 SP 23.718.01, Liquid Radwaste Spent Resin 10.1.7 SP 23.719.01, Liquid Radwaste Evaporator Bottctns 10.1.8 SP R2.713.06, Calculations of Radwaste Curie Content 10.1.9 SP R2.713.24, Sanpling, Treatment and Disposal of Radioactive Waste Oil 10.1.10 SP R2.713.30, Radwuste Container Control 10.1.11 SP R2.713.35, Storage of Packaged Radwaste Liners and DAW 10.1.12 SP R4.014.01, Radwaste Sanple Solidification Test 10.1.13 SP 72.002.18, Radwaste Sanpling for Disposal 10.1.14 SP R?. 713.02, RADt%N Computer Program 10.1.15 SP R3.075.01, Ccrapaction of Contaminated Waste 10.1.16 SP R1.020.01, Liquid Radwaste Process Control 10.1.17 SP R1.001.01, Radwaste Program-Policy & Cbjectives 10.2 MOBILE SERVICES CCNTRACIOR DOCUMZtfrS 10.2.1 S7D-R-05-007, 'Ibpical Feport, Cement Solidified Wastes to Meet the Stability Requirements of 10CFR61, Westinghcuse Hittnan Nuclear, Inc.

10.2.2 F458-P-001, Process Control Program for the In-Container Solidification of 20-25 Weight Percent Sodium Sulfate Slurries 10.2.3 F458-P-002, Operating Procedure for Mobile Incontainer Solidification of Sodium Sulfate Slurries 10.2.4 F458-P-003, Process Control Program for Incontainer Solidification of Bead Pesin - Powered Pesin Mix 10.2.5 F458-P-004, Dewatering Powdered Resin Slurries in Hittman HN-100 Steel Liners with a 'Ihree layer Flexible Underdrain '

Assenbly to less Than 1/2% Drainable Liquid 10.2.6 F458-P-005, Dewatering Bead Pesins Mixed with Powered Pesin in Hittman HN-100 Steel Liners with a 'Ihree layer Flexible Underdrain Asserably to Iess 'Ihan 1/2% Drainable Liquid l

10.2.7 F458-Pf06, Dewatering Podered Pesin Slurries in Hittman

, PADICK - 100 Container with a 'Ihree Layer Flexible 4

Underdrain Assenbly to less Than 1% Drainable Liquid t

Page 14 of 22 1

10.2.8 F458-P-007, Dewat p Bead Pesin Mixed with Powdered Pesin in Hittman RADIOK - 100 Containers with a 'Ihree Layer Flexible Underdrain Assmbly to Iess 'Ihan 1% Drainable l Liquid 10.2.9 F458-P-008, Process Control Program for Incontainer Solidification of Powdered Pesin 10.2.10 F458-P-009, Process control Program for the Incontainer 5 Solidification of Padwaste Filter Cake. (50 weight percent powdered resin - 50 weight percent Diatmaceous Earth) 10.2.11 F458-P-010, Operating Procedure for bbbile Incontainer -

Solidification of Mixed Bead Resin - Powdered Pesin Slurry '

(Maximum 28 weight percent powdered resin) 10.2.12 F458-P-011, Operating Procedure for Mobile Incontainer f Solidification of Powdered Pasin Slurry  ;

10.2.13 F458-P-012, Operating Procedure for Fbbile Incontainer -

Solidification of 50% Powdered Pesin/50% Diatcmacious Earth  !

Filter Sludge j 10.2.14 F458-P-013, Dewatering Filter Sludge Cakes in Hittman HN-100 0 Steel Liners with a Three Layer Flexible Underdrain Assembly to less than 1/2% Drainable Liquid l'

10.2.15 STD-P-05-025, Process Control Program for Incontainer Solidification of Sodium Sulfate Slurries Containing Mixed Solids 10.2.16 S7D-P-05-014, Sodium Slufate Solidification 10.3 GE2EPAL mwiNCES 10.3.1 NRC Standard Peview Plan 11.4, "Solid Waste Management Systems" (NUREG-0800) 10.3.2 NPC Branch ibchnical Position ETSB 11-3, "Design Guidance fx Solid Waste Management Systes Installed in Light-Water-<coled Nuclear Pcwer Peactor Plants", July 1981 10.3.3 Code of Federal Pegulations, Title 10, Part 61, "Licensing Requirements for Land Disposal for Padioactive Waste" 10.3.4 Code of Federal Pegulations, Title 49, "Transportation" 10.3.5 South Carolina Department of Health and Environmental Control, Padioactive Material License No. 097, as a:mnded.

]

1 Page 15 of 22 4

10.3.7 State of Washington Radioactive Materials License thW-IO19-2, as amended, for Richland, Washington.

10.3.8 NRC Special Nuclear Material License No. 16-19204-01, as amended for Richland, Washington.

10.3.9 ANSI /ANS-55.1/1979, American National Standard for Solid Radioactive Waste Processing System for Light Water Cooled Peactor Plants.

10.3.10 AIF/IESP-027, Methodologies for Classification of Iow-level Radioactive Wastes form Nuclear Power Plants, Inpell Corporation, January 1984.

10.3.11 NBC Im-Ievel Waste Licer : u, Branch, Final Waste Classification and Waste Dra Technical Position Papers May 11, 1983 10.3.12 FAu%N-Data Base Analysis Report - Shoreham tbclear Pcwer Station - Waste Management Group, Inc., August, 1985 10.3.13 OA Manual , App. K, "Packaging and Transport of Radioactive Material".

O I

e Page 16 of 22 Appendix A Page 1 of 4 SOLIDIFICATICH RECORD SHEET PART I Sanpling and Pre-Solidification Analysis

1. Type of Waste
2. Waste tank placed on recire.

Date/ Time

3. Waste Tank sanpled analysis IDI Date/ Time
4. Waste Stream pH
5. Oil Content  % by volume
6. Isotopic Analysis Attached Check
7. Estimated Curie content (SP R2.713.06) y ci/cc
8. Test Solidification Required O Yes tb
9. Acceptable Test Solidification performed (if required)

Initials

10. 'Ihe above waste tank has been analyzed and is acceptable for solidification.

Radiochemistry Engineer Date or designee

.5 *. A

Page 17 of 22 Appendix A Page 2.of 4 SOLIDIFICATICN RECOFD SHEET PART II Systen Preparation and Processing (Use Part iia. if vendor supplied system is used)

1. Container and (SP R2.713.30).

Type IDW

2. Centainer Properly Positioned Under Fill Pipe Check
3. Fill Flange Properly Mated to Container Check
4. Sufficient Cernent Available Check
5. Waste Dewatering Tank level inches Evap. Bottms Tank level inches
6. Authorization to carence process O I*B"E Badwaste Supervisor Date U
7. Tine process started
8. Time process stopped
9. Tachcmeter reading (Metering Ptnp)
10. Waste Dewatering Tank Level inches
11. Evap. Bottans Tank Level inches
12. Process C mpleted Operator Date Tirre
13. Waste Class: A B C,
14. Liner Check for free standing water Initials Date/ Time
15. Liner Capped Date Time
16. Container Weight lbs.

m Page 18 of 22 Appendix A Page 3 of 4 SOLIDIFICATICN REDRD SIEEP PART iia Contractor System Preparation and Processing

1. Container ID Nurber Type
2. Applicable connections trade to liner for transferring waste and cernent to liner Initials
3. Connections made to liner for mb:ing contents, if applicable Initials-
4. Process parameters Waste to be added to liner cf Cement to be added to liner cf Water to be added to liner cf
5. Authorizaticn to comence processing O Padwaste Supervision Date Time
6. Time processing started
7. Time processing stopped
8. Waste Class Class A Class B Class C 9.

Container checked for free standing water In _ Ttials _

Tine /Date

10. Lirer capped
11. Liner Weight lbs.

Page 19 of 22 Appendix A Page 4 of 4 SOLIDIFICATION RECORD SHEET PART III Filled Liner Data

1. Filler Liner Radiation levels
a. Contact Dose Rate 1 Meter Dose Rate mR/hr mR/hr
b. Smearable Activity 4 Quadrants 1 dpn/100 py 1 dpn/100 (Use actual 2 dpn/100 of 3r2 dpn/100 9 .

ntmber) 3 dpn/100 ?r3 dyn/100 cf 4 dyn/100 an ar 4 dpn/100 an et

c. Liner decon perfonned Yes/No
d. 2 Smearable activity after decon (if performed) dpn/100cn
e. Liner ready for shipping or transfer to storage 0

Health Physics Supervision Date Time

2. Storage location Radwaste Supervision SAMPLE 4

l

a Page 20 of 22 i

Appendix B Page 1 of 2 DBGTERING RECORD SHEE'r PADIOCHEMISTRY ANALYSIS SHEE7F

1. Type of Waste
2. Waste Tank (or Liner) Sampled Analysis ID#

Date/ Tine

3. pH of Decant
4. Oil Content  % by volume l

( 5. Isotopic Analysis of filter media and or bead resin attached i

Check

6. The above waste tank / container has been sampled and found to contain the isotopes and properties as indicated on the attached data sheets. -

O Radiochanistry Supervision Date SAMPLE l

.1 i

e .

Page 21 of 22 l

Appendix B l Page 2 of 2 i D M TERING RTORD SHEET POST DDGTERING SURVEY SHEEE

1. Container and Type IDt
2. Container Radiation Ievels
a. Contact Dose Rate mR/hr 1 Meter Dose Pate mR/hr
b. Snearable Activity 4 Quadrants 1 dpm/100 y1 dpn/100 on2 "

(Use actual 2 dpn/100 or 2 dpn/100 'Y rumber) 3 dpn/100 aY 3 dyn/100 K 4 dpn/100 cm W 4 dpn/100 x

c. Container Decon Performed Yes/lb
d. Smearable activity after washdown/decon dnp/100cm 2 O e. Liner ready for shipping or transfer to storage Health Physics Supervision Date " Time
3. Waste Class A B C Initials
4. Storage 1ccation Radwaste Supervision 8 AMP!.E l

b page 22 of 22 tit 9 0EWillElER IIGURE 1 i

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TITLE OF DOCUMENT SHOREHAM NUCLEAR POWER STATION - UNIT 1 OFFsITE DOSE CALCULATION MANUAL l

l l

)'l- 0 9 O- Wl NOll. B

4

4. ' ,

OFFSITE DOSE CALCULATION MANUAL Revision 10 - August 1987 Insertion Instructions .

Remove Old Pages(s) and Replace by the Corresponding New Page(s)

Title Page Signature Page EP-1 EP-2.

2.1-1 T2.2-1, p. 1/2 T2.2-1, p. 2/2 3.0-1 F3.1-2 F3.3-1 3.3-8 3.5-2 3.5-7 thru 3.5-9 3.5-12 and 3.5-13 T3.5-1, p. 1/3 T3.5-8, p. 1/1 T4-1, p. 1/2 T4-1, p. 2/2 5.1 TS-1, p. 1/5 T5-2, p. 1/1 T5-3, p. 1/2 T5-3, p. 2/2 T5-4, p. 1/1 T5-5, p. 1/1 F5-1 FS-2 T

_ ,. -. -- , - - - ~ ' "

LONG ISLAND LIGHTING COMPANY OFFSITE DOSE CALCULATION MANUAL Revision 10 - Augunt 1987

0FFSITE DOSE CALCULATION MANUAL

,, List of Effective Pages Page, Table *(T). Revision or Figure (F) Number EP-1 10 EP-2 10 i- 3 iii thru iv 3 y thru vii 4 viii 1 1-1 8 2.1-1 10 2.1-2 2 2.1-3 8 2.1-4 8 2.1-5 8 2.1-6 thru 2.1-7 8 F2.1-1 thru F2.1-4 3 2.2-1 1 2.2-2 thru 2.2-5 3 2.2-6 thru 2.2-8 6 T2.2-1 10 F2.2-1 10 F2.2-2 thru F2.2-4 1 F2.2-5 thru F2.2-6 7 3.0-1 10 3.1-1 8 3.1-2 8 3.1-3 thru 3.1-5 8 3.1-6 1 T3.1-1 3 T3.1-2 3 F3.1-1 1 F3.1-2 10 3.2-1 1 F3.2-1 1 3.3-1 4 3.3-2 thru 3.3-4 3 3.3-5 thru 3.3-8 9 3.3-8 10 F3.3-1 10 3.4-1 4 3.4-2 3 3.4-3 thru 3.4-5 9 T3.4-1 1 3.5-1 4 3.5-2 10 3.5-3 thru 3.5-6 3 3.5-7 thru 3.5-9 10 3.5-10 {

4 3.5-11 9 3.5-12 thru 3.5-13 10 EP-1 Revision 10 - August 1987

~

OFFSITE DOSE CALCULATION MANUAL

. List of Effective Pages (Cont'd.)

Page, Table (T), Revision or Figure (F) Number T3.5-1, p. 1/3 10 T3.5-1, pp. 2/3 and 3/3 1 T3.5-2 1 ,

T3.5-3 1 T3.5-4 1 T3.5-5 3 T3.5-6 1 T3.5-7 1 T3.5-8 10 T3.5-9 3 T3.5-10 3 T3.5-11 3 T3.5-12 3 T3.5-13 3 T3.5-14 3 T3.5-15 3 T3.5-16 3 T3.5-17 4  !'

3.6-1 1 F3.6-1 1 3.7-1 2  !

4-1 10  !

4-2 thru 4-3 4 T4-1 4  ;

T4-2 4 5-1 10 c T5-1, p. 1/5 10 TS-1, pp. 2/5 thru 5/5 4 i TS-2 10 l

TS-3 10 TS-4 10 l

TS-5 10

  • FS-1 10 F5-2 10 6-1 3 A-1 3 -

B-1 3 e

i EP-2 Revision 10 - August 1987

. SNPS-1 ODCM SECTION 2 SET POINTS 2.1 LIQUID EFFLUENT MONITOR SET POINTS (Compliance with Section 3.11.1.1 of the Radiological Ef fluent Technical Specification (RETS))

The radionuclide concentrations released via liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B.

Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved r entrained noble gases, the total concentration shall ,

4 be limited to 2 x 10 pCi/ml. l The set points of the effluent monitors are dependent on circulating or service water as follows:

1. a. With the circulating water system (a once-through system) in use, the circulating water flow rate (the circulating water system is composed of four pumps and circulates sea water at a rate of 574,000 spm).
b. The service water flow rate, if the circulating water system is not in use but service water is in use. (The service water system is composed of four reacter building service water pumps, each having a capacity of 8600 gpm and thine turbine building service water pumps each having a capacity of 8000 gpt.)
2. Flow rates of affluents from tanks and/or from the RHR heat exchanger ,

service water outlet, and/or yard piping drain sump.

3. Individual concentrations of gamma emitters (other than dissolved or entrained noble gases) and Sr-89, Sr-90 Fe-55, and H-3; and the total concentration of dissolved or entrained noble gases and gross concentration of the alpha emitters in the liquids to be discharged.

~4

4. Maximum allowable concentration of 2 x 10 pCi/ml for the total l concentration of dissolved or entrained noble gases and maximum pe.rmissible concentrations (MPCs) of other gamma emitters, Sr-89, Sr-90, Fe-55, H-3, and alpha emitters in the affluents as specified in 10CFR20, Appendix B, Table II, Column 2 for an unrestricted area.

NOTE: Precautions should be taken to assure that the circulating water system flow rate or the service water system flow rate used in determining the set point remains constant during the period of discharge. If the circulating or service water flow rate during discharge becomes less than the flow rate that was used in calculating the discharge set point, the discharge must be terminated and a new set point calculated.

Service water via the RHR heat exchanger service water outlet will be released continuously to the environment when the RHR heat exchanger is in operation.

Reactor building salt water drain tank contento may be released to the environment either as a batch process or continously. The discharge vaste sample tanks, recovery sample tanks, and yard piping drain sump contents will always be released to the environment as batch processes.

BN1-11600.02-92 2.1-1 Revision 10 - August 1987

SNPS-1 ODCM TABLE 2.2-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES K K (

si sin n 1 e S-Air ( (DFb ) 6-Skin (}(DFSj) y-Air ( (DF ) y-Body ( Skin Dose ( } Skin Dose ( }

(DFB;)

Kr-83m 2.88E-04 I} 1.93E-05 7.56E- 08 1.5E-05 2.1E-05 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E- 03 14E-03 2.8 E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E- 05 1.4E-03 1.4E-03 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E- 03 1.5E-02 1.7E-02

, Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E- 02 1.4E-02 1.9E-02

Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E- 02 2.4E-02 2.9E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E- 02 2.0E-02 2.5E-02 Xe-131m 1.llE-03 4.76E-04 1.56E-04 9.15E- 05 6.0E-04 6.5E-04 I -133m 1.48E-03 9.94E-04 3.27E-04 2.51E- 04 1.2E-03 1.4E-03
Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E- 04 5.8E-04 7.0E-04

)

X2-135e 7.39E-04 7.11E-04 3.36E-03 3.12E- 03 3.3E-03 4.4E-03 I Ie-135 2.46E-03 1.86E-03 1.92E-03 1.81E- 03 3.4E-03 4.0E-03

! X2-137 1.27E-02 1.22E-02 1.51E-03 1.42E- 03 1.3E-02 1.4E-02 1

)

BN1-11600.02-93 1 of 2 Revision 10 - August 1987 2

7 ._ .- - - - - , , ,,

  • ]o TABLE 2.2-1.(CONT'D)

K (} K (5)

Radio- si sis nuclide 8-Air } (DFb,) B-Skin ( } (DFS,) y-Air ( } (DF ) l y-Body ( } (DFB,) Skin Dose ( } Skin Dose ( }

Xe-138 4.75E-03 4.13E-03

  • 9.21E-03 8.83E- 03 1.1E-02 1.4E-02 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E- 03 9.9E-03 1.3E-02 (1) erad-m 3 pCi-yr i

(2) aree-m 3 pCi-yr (3) 2.88E 2.88

  • 10 (4) K, - (0.7
  • 3.11
  • DFf) + DFS (5) K,g,=(1.11*DFf)+DFS g i

i 1

BN1-11600.02-93 2 of 2 1

Revision 10 - August 1987

i i

i SNPS-1 ODCM SECTION 3 l

DOSE CALCULATION METHODS '

l This section presents the calculational specifics required to demonstrate compliance with the following Radiological Effluent Technical Specifications .

(RETS) sections: '

3.11.1.2 - Liquid Effluen: Dose Calculation ,

3.11.1.3 - Operation of Liquid Radwaste Treatment System 3.11.2.1 - Caseous Effluent Dose Rate ,

3.11.2.2 - Noble Gas Air Dose 3.11.2.3 - Caseous Effluent Dose From Radioiodines, Tritium, and Radionuclides In Particulate Form 3.11.2.5 - Operation of Vent.11ation Exhaust Treatment System i 1

Calculation methods are based on the equation and calculational methods described in Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1".

I Two methods are provided for each analysis. The first method is the method '

used by the computerized radiation sonitoring system. Method 2 is a backup hand calculational method to be used only if the computer is not functional.

i The Semi-Annual Effluent Relesse Report is produced and the land use census is

! evaluated using NRC codes which implement Regulatory Guide 1.109.  !

j  !

b i

4 >

I j '

l }

E i

i  !

BN1-11600.02-92 3.0-1 Revision 10 - August 1987 l

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LIQUID RADWASTE SYSTEM MODEL l SHOREHAM NUCLEAR POWER STATION-UNIT I OFFSITE DOSE CALCULATION MANUAL

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FIGURE 3.5-1 l GASEOUS EFFLUENT MODEL SHOREHAM NUCLEAR POWER STATION-UNIT I OFFSITE DOSE CALCULATION MANUAL REVISION 10 - AUGUST 1987 Tm

SNPS-1 ODCM If main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the followNg equation should be used:

D

=10'*V*R,*X/Q*((P)*Cgy) g 7 g (area /yr) where:

D = total dose rate to organ, j , mres/yr.

P = the inhalation dose conversion factor, for radionuclides other 3

than noble gases, i, and organ, j , in arem per pCi from Table 3.5-3.

The dose factor P is based on the critical individual organ for theChildgroup,Michismostrestrictive. Inhalation dose factors for other age groups are given in Tables 3.5-1, 3.5-2, and 3.5-4.

R, = inhalation rate (m 3/yr), from Table 3.5-5.

C AI = the station ventilation exhaust duct release concentration of radionuclide, i,(pCi/cc) (from the isotopic analyses performed on i the filter paper and charcoal cartridge taken from the station j ventilation exhaust monitor),

C 12

= the air removal pump ventilation exhaust duct release concentration of radionuclide, i, (pci/ce) (from the isotopic l analyses performed on the iodine and particulate filters taken from the air removal pump discharge monitor),

, L g3 = the containment dryvell purge ventilation exhaust concentration of radionuclide, 1. (pci/cc) obtained from the iodione and particulate filters during a filtered release or from the containment dryvell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the

, isotopic analyses performed on the iodine and particulate filters.),

Vg = 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V

2

= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V

3

= 5.70E+05 cc/sec (1200 cfa), containment dryvell purge ventilation exhaust flow rate, X /Q g = annual average X/Q at 2253 meters ESE due to relegses via the station ventilation exhaust point (1.74E-07 sec/m ),

X /Q 2 = short term X/Q at 2253 noters ESE due to condenser air removal pumpgeleaseviathestationventilationexhaustpoint (4.65E-07 sec/a ),

X /Q 3

= via short theterm X/Q station at 2253 exhaust ventilation meters point ESE (4.65E-07 due to containment sec/m .

dryw!)l P"'8" BN1-11600.02-92 3.3-8 Revision 10 - August 1987 l

SNPS-1 ODCM o

- 3.5.1.2- Total Body Dose D.

wo . = D*b w

+ D wb

+ DF ""

wb where:

D = (X /0)y"* F' 2.22 x 10 E fg DFB g nobles D = (x/0)** F' 3.17 x 10 R ad f iDFA ij,ad part+1

  1. "" ~

D = (D/Q) T' 7 x 10 I f DFGg [1 - e b 1]/A g part+I D = total body dose due to direct radiation from the radioactive cloud [arem/hr] (Ref.: Reg. Guide 1.109 Eq. B-8; also similar to Eq. B-6 if one makes use of the gamma (X/Q) and the DFB g instead of Df { dose conversion factor)

D" = total body dose (j = total body) due to inhalation

[arem/hr) (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4, for an adult)

I# "" = total body dose due to particulate and iodine D

wb radioactivity depositing on the ground [ ares /hr)

(Ref.: Reg. Guide 1.109 Eqs. C-1 and C-2 with the product 8760 [hr/yr] (1/ A ) [yr) replaced by (1/ A )

[hr) and paraceter 6g (r,0 reprennted by the (D/ ))

DFB g

=gans:adosetobodg)conversionfactor

[(mrem /yr)/(pCi/m ) (from Table B-1 of the Reg.

Guide)

DFA = dose conversion f actor for nuclide i to organ j of an ij,ad adult individual [ mrem /pCi inhaled] (from Table E-7 of Reg. Guide 1.109) l DFG gy

=totalbodyconversionfactorforstanj)ingon contaminated ground [(arem/hr)/(pC1/m ) (from Table E-6 of Reg. Guide 1.109) l (x/Q)sa = concentration dispersion factor (sector-average I f model)3)or (sec/a the period of Yelease (site boundary only)

BN1-11600.02-112 3.5-2 Revision 10 August 1987

SNPS-1 ODCM L

U, = ingestion rate of leafy vegetables by individual in age group a (from Table E-5 of the Guide, maximum

' individual) [kg/yr)

B I* = concentration factor for uptake of radionuclide i from soil by edible parts of crops [(pCi/kg)(wat weight)/ (pCi/kg) (dry scil)) (Ref.: Reg. Guide 1.109, Table E-1 and included cn Table 3.5-6)

DFI = dose conversion factor for nuclide i to organ j of D* individual in age group a due to ingestion of contaminated food [ ares /pC1 ingested) (from Tables E-11 through E-14 of the Guide)

DFI C14,j a "" ija f r Carbon-14 DFig3 = DFI for tritium F "

CM i f r Carbon-14 (see Section 3.5.1.1 above) f H3

"# I ' "'I*I""

1 E

= absolute of interest humidity)of

[g/m (See theTable atmosphere 3.5-7) at the location (X/Q)'" = concentration dispersion factor (Sector - Average ,

model) for the period of 5'2'*** ("' 8d'" *"d nearest residence) [sec/m )

(D/Q) = particulate deposition gate (nearest garden and nearest residence) [1/m )

3.5.1.6 Infant Thyroid Dose due to Innescion of coat Milk and Inhalation Infant is used here as a default age group but in locations where.

there is no infant, such as 6B2 (see Table 5-5), child parameters will be substituted as appropriate.

D "

D thy inf th ,inf + D g,f l

where:

ailk ailk ailk D

thy,inf , [pthyinf) p t , [pthy.inf) iodines ailk uilk '

+

+ (Dthy,inf)C14 (Dthyinf)H3 D

thy inf = (d Q) T' 3.17 x 10' R ggf I f gDFA i, thy,inf part+I BN1-11600.02-112 3.5-7 Revision 10 - August 1987

_ _ _ _ _ _ - _ _ _ _ _ _ __ _. _ _ . - . _ _ t

\ .:

l l . SNPS-1 ODCM (D y g,g) = (D/Q) F' 1.1 x 10 8 g nf '1 1. thy inf part part I

0.2 iv -

x 6 F,1 g. Ri +g o.002TT- + 240 A }

  • 2 4A i g

7

= (D/0) F' 5.5 x 10 (D*i1",,1,g) iodines I fg DFI iodines (,g i, thy,inf

  • 0 1.0 iv -

240 A g I

  • 2 41i mi 0.7 (A + 0.0021)

(D ygeg) " (X/0)** F' 2.2x10 (f f C14 D1I C14, thy.inf x6F CM*XP(-24 AC14 i-(D yg,f) = (X /Q)** F' ( * *H ~) f H3 DTI H3, thy,inf I

x 6 F m,H3 #XP(-2 4 Ag3) inh = infant thyroid dose due to inhalation of airborne D

thy,inf radioactivity (arem/hr) (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4) uilk = infant thryoid dose due to ingestion of milk (pthy,inf) contaminated with radioactive particulates (arem/hr) part (Reg. Guide Eqe. C-5, C-6, C-10, C-11 and C-13) for milk, with the following:

o r (fraction of deposited activity r- 'ned on crops) = 0.2 (see pg 1.109-68 of the .uide) et (time period that crops are exposed to c8ntamination during growing season) = = (hrs) et g (time period over which accumulation is evaluated) = "[ hrs]

et h (time delay for ingestion of forage by animals)

= 0 (hrs) (see pg 1.109-69 of Reg. Guide) eY agricultural product aln(pathway)=0.7[kg/m{vity, ) (Reggrass-animal-milk- Guide 1.109. Rev.

0) e P (soil effective surface density) = 240 [kg/m )

BN1-11600.02-112 3.5-8 Revision 10 - August 1987

SNPS-1 ODCM eA g =A i + 0.0021 [hr~I) (see pgs .109-4 and 1.109-69) e6 g (r,0) = (D/Q) [a-2) e t, (average transport time of activi y~ from the f&ed into the mili and to the receptur) = 24 [ hrs) ef (fraction of the year that animals graze on -

pIsture) = 0.5863 (based on survey data) ef weenthe (fractionofdailyfeedthatispasturegrass animal grazes on pasture) = 0.5 (based on survey data) ailk (Dthy,inf) iodines = infant thyroid dose due to ingestion of milk contaminated with radio-iodinea [arem/hr] (Ref.: i Reg. Guide Eqs. C-5, C-7, C-10, C-11, and C-13 for milk; similar to the infant thyroid dose due to the ingestion of particulates given above, with the exception of a different multiplying factor and r = 1.0) -

(D* thy,inf)C14 = infant thyroid dose due to ingestion of milk Reg. Guide contaminated with C14 (area /hr) (Ref.

1.109, Eqs. C-8, C-10, C-11 and C-13 for milk, with p (the ratio of the total annual release time to ,

the total annual time during which photosynthesis '

occurs) = 1, and t , f , and f as

  • given above for the particulates) I P ailk

= infant thyroid dose due to ingestion of milk (Dthy,inf)g3 contaminated with tritium (area /hr) (Ref.: Reg.

Guide 1.109. Eqs. C-9, C-10, C-11, and C-13 for .

milk, with t{, f , Pand f, as given above for the

. particulates R gg = infant breathing rate (m 3/yr] (from Table E-5 of the Guide, for maximum individual)

DFA 1 , thy.inf = dose conversion factor for nuclide i to the infant thyroid due to inhalation (area /pci inhaled] (from Table E-10 of the Guide)

Dy1 = dose conversion factor for nuclide i to the infant i thy.inf thyroid due to ingestion (ares /pci ingested] (from l Table E-14 of the Guida) '

DFI C14, thy.inf = DF1 1. thy.inf f r Carbon-14 Db3 thy,inf = DF1 1 . thy.inf I # **III'"'

BN1-11600.02-112 3.5-9 Revision 10 - August 1987 i

6 ;p SNPS-1 ODCM Note: For short tera releases such as from condenser air removal I pump or containment drywell purge F for C-14 must be adjusted (seenoteinTables3.5-15N3.5-16and3.5-17).

i 3

R, = inhalation rate (a /yr) f rom Table 3.5-5, P

oij

= the dose conversion factor for radionuclides, other than noble  !

gases,i,andorganj,fortheleafyvegetables,gtored vegetables, and contaminated ground pathways in n (area /yr per C1/sec) respectively, from Table 3.5-9 and goat milk from Table 3.5-11.

The dose factors P P are based on the critical individual organforthechilkd,ro0ksincethisgroupismostrestrictive.

g [

i t

g = 7.88E+06 see for quarterly dose calculation

= 3.15E+07 see for yearly dose calculation, t

2

" T818888 Period (sec) for condenser air removal pump, ,

t 3

= release period (sec) for containment drywell purge exhaust, C

il = the station ventilation uhaust duct release concentration of radionuclide, i, (pci/ce) (from the isotopic analyses performed on the iodine and filter cartridge taken from the station ventilation exhaust monitor), ,

, C 12

= the air removal pump vaatilation exhaust duct release I concentration of radionuclide, i, (pci/cc) (from the isotopic analyses performed on the iodine and perticulate filters taken from the air removs1 pump discharge monitor),

C g3 = the containment drywell purge ventilation exhaust concentration of radionuclide, i, (pCi/cc) obtained from the iodine and narticulate filters during a filtered release or from the containment dryvell 7 atmosphere monitor with the purge lines bypassing the primary '

c,ontainment purge filter (The concentration is obtained from the isotop:ic analyses performed on the iodine and particulate filters.),

i

! Vg = 1.73E+%8 cc/sec (3.66E+05 cfa), station ventilation exhaust duct

ventilation exhaust flow rate, 4

1 1 V 2

m 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventilation exhaust flow rate, V

3

= 5.70E+05 ce/sec (1200 cfa), containment drywell purse ventilation I exhaust flow rate, j X/Q g l

= station annual a m age X/Q ventilation exhauftat 2253 point meters ESE sec/m (1.74E-07 due to releg)ses via the i

j ,

l X/Q 2 = short tern X/Q at 2253 meters ESE due to condenser air removal l ,

j pumpgeleaseviathestationventilationexhaustpoint (4.'5E-07 sec/a ), l i BN1-11600.02-112 3.5-12 Revision 10 - August 1987 I

SNPS-1 ODCM X /Q 3 [

= via shortthetern X /Q at 2253 meters exhaust ESE point due to containment dryvg)li purge station ventilation (4.65E-07 sec/a ,

g D/Q g = annual average D/Q deposition ' actor at 2253 meters ESE due t I releases via the station ventilation exhaust point (3.86E-09 a-2), l D/Q 2 = short tera D/Q deposition factor at 2253 meters ESE due to g r

condenser exhaust air(1.03E-08 point removal apung2)eleases via the station ventilation l

D/Q 3 = short tern D/Q deposition factor at 2253 meters ESE due to l containmentdryvellpurge,gxhaustviathestationventilation exhaust point (1.03E-08 a ).

3.17E-08 = inverse of 3.15E+07 sec/yr, and NOTE:

If the land use census (see Table 3.5-8) changes, the critical location, i.e.,

the location where an individual would be exposed to the highest dose, must be reevaluated using Equation 3.5.2-1 for each of the following locations:

1. nearest residence,
2. nearest vegetable garden, and
3. nearest milk cow or goat.

P used in Equation 3.5.2-1 vill include the values in Tables 3.5-10 through 3?N14,ifthosepathwaysexist.

At each location, the following pathways must be considered and dose (dose rates) reevaluated if any actual pathway exists:

1. inhalation,
2. leafy vegetables (fresh),
3. stored vegetables,
4. goat's or cow's milk (if both exist choose the one resulting in the high'er dose), and l
5. deposition on ground.

Since a person will always be present, pathways 1 and 5 must always be evaluated.

Once the location of the critical individual is determined and found to be other than the one at 2253 meters ESE, the values of X/Q and D/Q at the l updated critical location must be used.

l BN1-11500.02-112 3.5-13 Revision 10 - August 1987

SNFS-1 DDCM TABLE 3.5-1 INHALATION DOSE FACTORS FOR ADULTS (arem per pCi inhaled)

Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI

~

H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.582-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 Na-24 4.26E-07 4.26E-07 4.26E-07 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-C6 P-32 1.65E-04 1.28E-06 1.28E-06 9.64E-06 6.26E-06 No Data No Data No Data Cr-51 ho Data No Data 1.08E-05 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Hn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-53 Wo Data 1.55E-10 2.29E-11 No Data F2-55 1.63E-10 1.18E-06 2.53E-06 3.07E-06 2.12E-06 No Data No Data Fa-59 1.47E-06 3.47E-06 4.93E-07l 9.01E-06 7.54E-07 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.03E-06 1.81E-06 No Data No Data Ni-65 1.92E-10 2.23E-05 1.67E-06 2.62E-11 1.14E-11 No Data No Data 7.C9E-07 Co-64 No Data 1.83E-10 1.54E-06 7.69E-11 No Data 3.78E-10 8.48E-07 6.12E-06 Zn-65 4.0$E-06 1.29E-05 5.82E-06 No Data Zn-69 8.62E-06 1.08E-04 6.68E-06 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 Br-03 No Data 1.15E-07 2.04E-09 No Data 3.01E-08 No Data No Data No Data 2.,90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data Br-85 No Data No Data 2.05E-13 No Data 1.60E-09 No Data No Data No Data Rb-86 No Data 1.COE-24 1.69E-05 7.37E-06 'o Data No Data No Data Rb-88 No Data 4.84E-08 2.08E-06 2.41E-08 N Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 - Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 Data No Data Sr-90 1.24E-02 1.75E-04 4.37E-05 No Data 7.62E-04 Wo Data No Data Sr-91 7.74E-09 No Data 1.20E-03 9.02E-05 3.13E-10 ti Data No Data 4.56E-06 2.39E-05 S0-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data Y-91m No Data 2.12E-05 6.32E-05 3.26E-11 No Data 1.27E-12 No Data No Data Y-91 5.78E-05 No Data 2.40E-07 1.66E-10 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-05 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 B21-11600.02-99 1 of 3 Revision 10 - August 1987

. .e SNPS-1 ODCM TABLE 3.5-8

  • LOCATION OF NEAREST RESIDENCE. VECETABLE CARDEN. AND SITE BOUNDARY BT SECTOR
  • Nearest
  • Nearest Residence Nearest Residence Residence Distance
  • Elevation ** Distance
  • Elevation **

Sectar (M)

Distance

  • Elevation **

(M) (M) (M) (M) (M)

D - - -

NNE 381 436 6.1 6.1 - -

365 NE 518 6.1 -

6.1 ENE 884 32 6.1 6.1 1.932 30 311 E 1.128 6.1 6.1 ESE 3.867 67 346 6.1 914 6.1 1.932 SE 25 457 6.1 1.097 26 2.091 50 SSE 914 1.105 26 30 1.771 40 S 610 876 30 25 1.771 37 SSW 518 610 25 28 7.080 58 SW 549 457 22 17 4.073 46 WSW 1.585 533 17 33 2.252 42 W 1.570 457 15 31 2.252 35 WNW 610 360 6.1 6.1 -

354 NW - -

6.1 NNW - - -

419 6.1 436 6.1 NOTES:

Dictances are given from the reactor center lines out to 8.046 meters.

Thero are no milk cows or meat animals within the 8.046 m radius of the site. The nearest milk cow is located 8.690 m cc t of the site.

cita. The nearest milk goats are located 2.253 m and 2.478 m east-southeast and 3.846 a southwest of the Corresponding elevations above mean sea level are 32 m 49 m and 46 m, respectively.

    • Elevations (meters) given are above mean sea level.

BN1-11600.02-150 1 of 1 Revision 10 - August 1987

SNFS-1 ODCM TABLE 4-1 .

CRITICAL RECEFTOR LOCATIONS FOR CASEOUS EFFLUENT CALCULATIONS Tcchnical Spccification 3.11.2.1 3.11.2.2 3.11.2.3 S ction 3.11.2.5 Sections in this Manual 3.3 3.4 3.5 Limiting Criteria 3.6 Ins,tantaneous Dose Quarterly and Annual Rate to Whole Body.

Quarterly and Dose to any organ Air Doses due to Annual Dose due due to radionuclides and Skin due.to Caama and Beta to radionuclides Noble Cas and Dose radiation other than Noble Cas other than Noble for 31 day period to any organ due Cas to radionuclides other than Noble Gas Distance and Direction 1) Noble Cast 457 meters ESE of Receptor from the 366 meters NNE 2253 meters ESE l2253 meters,ESE Plant 2) Organ 2253 meters, ESE l Description of Location 1ocation of highest Location of highest Location of 1.ccation of highest Dose Rate Dose highest Dose Dose Long Tern Atmospheric 3 Dispersion Factor for

1) 6.6E-07 sec/m3( } 8.44E-07 sec/m (2) 1.74E-07 sec/m 3I3) 1.74E-07 sec/m ( }
2) 1.74E-07 sec/m (3 Station Ventilation Exhaust X/Q g Short Tern Atmospheric 3I
1) 3.6E-06 sec/m 1.83E-06 sec/m I} 3 4.65E-07 sec/m (3) 4.65E-07 sec/m ( }

Dicpersion Factor for 2) 4.65E-07 sec/m )

Air Removal Pump X/Q 2

1) 3.6E-06 sec/m3 g3) 1.83E-06 sec/m3I }

Short Tern Atmospheric ) 3 Dicpersion Factor for 4.65E-07 sec/m (3} 4.65E-07 sec/m ( }

2) 4.65E-07 sec/m Containment Drywell Purge X/Q 3 ,

BN1-ll600.02-109 1 of 2 Revision 10 - August 1987

SNFS-1 ODCM TABLE 4-1 (CONT'D) ~

Long Tern Relative 1) NA NA Deposition Factor for 2) 3.86E-09 m-2(3) 3.86E-09 m-2(3) l 3.86E-09m 2(3)

Station Ventilation l Exhaust D/Q g Short Tern Relative 1) NA NA -

Deposition Factor for ,

3) 1.03E-08 m 1.03E-08 m-(}
2) 1.03E-08 m l Air Removal Pump D/Q 2

Short Tern Relative 1) NA 1.03E-08 m-(}

NA 1.03E-08 m- I3}

Deposition Factor for 2) 1.03E-08 m-M3)

Containment Drywell l Purge D/Q 3

(1)

Long Island October Lighting 1977, DocketCompany, 50-322. Shoreham Nuclear Station - Unit One, FINAL ENVIRONMENTAL STATEMENT, NUREC ,

028 (2) "Compliance with 10CFR50 Appendix 1",

Docket 50-322. SNAC-119. July 30, 1976.Shoreham Nuclear Power Station - Unit One, Long Island Lighting Company .

(3)

Internal Calculation using methodology outlined in NRC Regulatory Guide 1.111, Revision 1. July 1977.

BN1-ll600.02-109 2 of 2 Revision 10 - August 1987

  • =

SNPS-1 ODCM SECTION 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The purpose of this section is to identify those sampling locations from which the radiological environmental monitoring samples shall be collected pursuant to Technical Specification 3/4.12.

Table 5-1, based on NUREG 0473, defines an acceptable Radiological Environmental Monitoring Program by providing guidelines for the sampling locations according to pathways. It specifies the number, location and frequency of sample collection and the required analyses.

The Shoreham-specific implementation of the program is given in Tables 5-2, 5-3, 5-4 and 5-5, corresponding to the four pathways of direct, airborne, waterborne and ingestion doses. The corresponding onsite and offsite sampling locations are shown in Pigures 5-1 and 5-2, respectively.

j 4

BN1-11600.02 5-1 Revision 10 - August 1987

SNPS-1 ODCM TABLE 5-1 .

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *

(TYPICAL SAMPLING AND COLLECTION FREQUENCY)

REFER TO TECHNICAL SPECIFICATIONS FOR CURRENT PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND AND/OR SAMPLE TYPE AND FREQUENCY SAMPLES AND SAMPLE LOCATION" COLLECTION FREQUENCY OF ANALYSIS

1. DICECT RADIATION 36 rout $ae monitoring stations. Quarterly.

DRl-DR35, either with two or Camma dose quarterly.

more donLaetors or with one instrument for measuring and recording dose rate continuously, placed as follows:

a. An inner ring of stations, one in each meteorological sector In the general area of the SITE BOUNDARY, DRI-DRf5;
b. An outer ring of stations, one in each metcorological sector in the 6- to 8-km range from the site, DR17-DR23;
c. The balance of the stations, DR26-DR3t, to be placed in special f.aterest areas such as populatica centers, nearby residences, schools, and in 1 or 2 arees to serve as control stations.
  • The number, me_dia, frequency, and location of samples may vary from site to site. This table presents an acceptc.ble minimum program for a site at which each entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose cnd should be included in the sampling program.

l BN1-11600.02-113 1 of 5 Revision 10 - August 1987

.?

SNPS-1 ODCM

.. TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (RD(P)

DIRECT RADIATION MONITORING STATIONS 4

Punctional Designation Location Code l i (NUREG-0473) (Shoreham REMP) location Description DR1 151 Beach east of intake. 0 3 mi. N DR2 2A2 West and of Creek Road. 0.2 mi. NNE DR3 351 Site Boundary. 0.1 mi. AE DR4 4S1 Site Boundary. 0.1 mi. ENE DR5 5S2 Site Boundary. 0.1 mi. E DR6 6S2 Site Boundary, 0.1 mi. ESE DR7 7A2 North Country Road, 0.7 mi. SE DR8 8A3 North Country Road. 0.6 mi. SSE DR9 9S1 Service Road SNPS, 0.2 mi. S DR10 l,

10A1 North Country Road. 0.3 mi. SSW DR11 11A1 Site Boundary. 0.3 mi. SW DR12 12A1 Meteorological Tower, 0.9 mi, WSW l

  • DR13 13S3 Site Boundary. 0.2 mi. W l DR14 14S2 St. Joseph's Villa, 0.4 mi. WNW DR15 15S1 Beach west of intake. 0.3 mi. NW DR16 16S2 Site Boundary 0.3 mi. NNW l DR17 5D3 Wildwood State Park, 3.1 mi. E DR18 6El LILCO ROW, 4.8 mi. ESE  :

l DR19 7El Calverton, 4.9 mi. SE DR20 8E1 Calverton, 4.4 mi. SSE

[ DR21 9El Brookhaven National Laboratory,

! 5.0 mi. S ,

DR22 10E1 Ridge Substation 4.0 mi. SSW l DR23 11El LILCO ROW. 4.7 mi. SW DR24 12D1 North Shore Beach Substation,  !

' 3.7 mi. WSW DR25 13E1 Sound Way Drive. 4.5 mi. W DR26 5D1 Wildwood State Park, 3.4 mi. E i

'. DR27 5F3 Dairy Farm, 7.8 mi. E l DR28 781 Overhill Road 1.4 mi. SE i DR29 12G2 Ploverfield Substation, j i 15.4 mi. WSW i l DR30 12G1 Central Islip Substation, 19.9 mi. WSW '

DR31 1101 MacArthur Substation, 16.6 mi. SW l DR32 8G1 Wading River Road, 10.1 mi. SSE L l DR33 6G1 Hampton Bays Substation, 19.0 mi. ESE

DR34 6Al Sound Road. 0.7 mi. ESE
DR35 2A3 Nearest Residence. 0.3 mi. NNE DR36 9S2 East Gate SNPS, 0.3 mi. S l

BN1-11600.02-112 1 of 1 Revision 10 - August 1987

. .o .

SNPS-1 ODCM e

. TABLE 5-3 l RADIOLOGICAL ENVIRobMENTAL MON 1TORING PROGRAM (REMP) s (PARTICULATES AND RADI0 IODINE Punctional Designation Location Code (NUREG-0473) (Shoreham REMP) Location Description A1 6S2 Site Boundary 0.1 mi. ESE A2 2A2 West and of Creek Road. 0.2 mi. NNE A3 3S1 Site Boundary. 0.1 mi. NE ,

A4 751 Overhill Road, 1.4 mi. SE A5 11G1 MacArthur Substation, 16.6 mi. SW l l

1 t

l BN1-11600.02-112 1 of 1 Revision 10 - August 1987 -

i

,P*

SNPS-1 ODCM

.. TABLE 5-4 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

WATERBORNE MONITORING STATIONS Functional Designation Location Code (NUREG-0473) (Shoreham REMP) Location Description WA1 13G2 Surface, background area, 13.2 mi. W WA2 14C1 Surface, outfall area, 2.1 mi. WNW WA3 301 Surface, outf all area, 2.9 mi. NE Wbl 251 Potable Water, well on site, 0.1 mi. NNE Wb2 13S2 Potable Water, well on site, 0.2 mi. W Wdl 2A4 Sediment, beach. 0.4 mi. NNE l

9 t

BN1-11600.02-112 1 of 1 Revisica 10 - August 1987

. P*

SNPS-1 ObCM 4

, TABLE 5-5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

INGESTION MONITORING STATIONS Functional Designation Location Code (NUREG-0473)_ (Shoreham REMP) location Description Ial* 6B1 Goat Farm, 1.55 mi. ESE [

6B2 Goat Farm, 1.40 mi. ESE {

Ia2* 10F1 Goat Farm, 9.2 mi. SSW 802 Dairy (Cov), 10.8 mi. SSE Ib1 3C1 Fish and Invertebrates, outfall area, 2.9 mi. NE l

Ib2 14C1 Fish and Invertebratta, outfall l area 2.1 mi. WNW I

Ib3 13G2 Fish and Invertebrates, background, 13.2 mi. W Ic1 8B1 *ocal

. Farm, 1.2 mi. SSE Ic2 5C2 Local Farm, 2.8 mi. E Ic3 12H1 Background Farm. 26 mi. WSW

  • Samples will be obtained from one of the locations listed as available. Priority will be given to the first of the two locations listed. If samples are unavailable from that location, substitution will be made from the second location listed.

3N1-11600.02-112 1 of 1 Revision 10 - August 1987 L . . . _ _ __

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ggg'@ LONG ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION P.O. DOX 618, NORTH COUNTRY RO AD + WADINO RIVER N.Y.11792

,OHN D. LE ON ARD. JR.

Vict patsiot NT . nucle Am ort m AttoNs S""C- 429 FEB 261988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Semiannual Radioactive Effluent Release Report Shoreham Nuclear Power Station Docket No. 50-322

Reference:

Facility Operating License NPF-36 (Shoreham)

Gentlemen Enclosed is a copy of our Semiannual Radioactive Effluent Release Report covering the third and fourth quarters of 1987 which was prepared according to Technical Specification 6.9.1.7. This report includes information for each type of solid waste shipped offsite and changes made to the Process Control Program and the Offsite Dose Calculation Manual during the period.

If you require additional informatiori, please contact this office.

Very truly yours, c /

J If O'hn b. ii conArd,)Mm r

7 V .e President - N lear Operations

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SM ck Enclosure cc: R. Lo/S. Brown W. Russell g' rih F. Crescenzo t I t a