ML20114C035

Semiannual Radioactive Effluent Release Rept,First & Second Quarters 1992

ML20114C035
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/30/1992
From:	LONG ISLAND POWER AUTHORITY
To:
Shared Package
ML20114C033	List: ML20114C035 SNRC-1987, Forwards Semiannual Radioactive Effluent Release Rept, First & Second Quarters 1992. No Solid Waste Shipped Offsite to Burial Site During Reporting Period.Solid Waste Shipped to Vol Reduction Facilities
References
NUDOCS 9209010109
Download: ML20114C035 (20)

Text

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- SEMIANNUAL RAD;'.. ACTIVE EFFLUENT RELEASE REPORT ,

i 1st and 2nd Quarters of 1992 Facility: Shoreham Nuclear Power Station, Unit 1 .

Licensee: Long Island Power Authority l TABL'l OF CONTENTS f

Section P_ana

, Intreduction 1 A. Supplemental information 1 B. Gaseous Effluents 4 C. Liquid Effluents 8 D. - Solid Waste 12 E. Radiolo0l calImpact on Man (Not Required')

F. Meteorological Data (Not Required')

G. ODCM Revisions, REMP Location Changes 19 and. Major Changes to Radioactive Waste Treatment Systems-i

' Section E'and Section F are not required by ODCM to be-included in this report. These sections will appear in the next report, due within 60 days after January 1',1993, and will encompass all of 1992.

920901o309-920827'

{DR- ADOCK 05000322-PDR

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INTRODUCTION

- This Semlannual Radioactive Effluent Release Report, submitted in accordance with Technical Specification 6.8.1.4, Offsite Dose Calculation Manual (OC'.tM) 6.8.1.4

. and 6.15.1, and Sections 9.3.1 and 9.4 of the Process Control Program (PCP),

covers the period from January 1,1992 through June 30, 1992. During the period covered by this report, the Shoreham Nuclear Power Station License (NPF-

82) was transferred, by order of the Nuclear Regulatory Commission (NRC), from the Long Island Li 0hting Company (LILCO) to the Long Island Power Authority (LIPA) on February 29, 1992. On June 11, 1992, the NRC approved LIPA's application of January 2,1991, as supplemented August 26, Nover ber 27, and  ;

December 6,1991, for decommissioning of the Shoreham Nuclear Power Station.

- A. SUPPLEMENTAL INFORM ATION

1. flegulatorv Limits Shoreham's offluent regulatory limits are defined in the Possession Only License NPF-82, Shoreham Nuclear Power Station, Appendix A, Technical Specifications, a) Limits for gaseous effluents and noble gases are covered by Technical Speci'ication 6.7.4 and ODCM Controls 3.11.2.1 and 3 11.2.2.

b&c) ' Tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous offluents are addressed in Technical Specification 6.7.4 and ODCM Control 3.11.2.3.

d) Liquid effluent limits are described in Technical Specification 6.7.4 and ODCM Controis 3.11.1.1 and 3.11.1.2.

e) in addition, with Shoreham's sampling and analysis program the following average minimum detectable activitier (MDAs) were l achieved or exceeded for the first and second quarters in 1992.

These MDAs are less than the required lower limits of detection (LLDs):

Liquid:

Co-141 3.69 E-8 uCi/ml Ce-144 1.61 E-7 uCi/mi Co-58 3.28 E-8 uCi/ml Co-60 - 4.28 E-8 uCl/ml Cs-134 4.04 E-8 uCi/mi Cs-137_ 3.61 E-8 uCi/ml Mn 54 3.45 E-8 uCi/ml E

l- . .

Mo 99 2.05 E-8 uCi/ml Zn 7.96 E-8 uCi/ml Gaseous:

Cs-137 7.23 E 14 uCi/cc Cs 134 8.05 E-14 uCi/cc Co-60 8.32 E-14 uCi/cc Mn 54 7.35 E-14 uCi/cc Xe-133 3.86 E-08 uCi/cc Zn.65 1.26 E-13 uCi/cc Ce-144 2.11 E-13 uCi/cc

2. Maximum Permissible Concentrations a d) Maximum permissible liquid effluent concentrations (MPCs) are those specified in 10 CFR 20, Appendix B, Tabic II, Column 2.

If an isotope is listed with values for SOLUBLE and INSOLUBLE states, the more conservative value is utihzed. For gaseous offirents, MPCs were not used. Direct calculations of dose were utilized to satisfy the dose rate limitations of Technical Specification 6.7.4 and ODCM Control 3.11.2.1.

3. Averaae Enerav No isotopes above minimum detectable activities were measured in gaseous effluents. Therefore, there is no reportable average energy for this time period.

4. Measurements and Anoroximations of Total Radioactivitv_

a-d) Samples were collected in the manner and with the frequency prescribed in Technical Specification 6.7.4 and ODCM Controls 4.11.1.1.1 and 4.11.2.1.2. Samples were analyzed in accordance with ODCM Controls Tables 4.11.1.1.1-1 (liquid) and 4.11.2.1.2-1 (Gaseous) regardin0 both type of analysis and level of sensitivity. Most samples were-analyzed by gamma spectroscopy with a germanium detector. A liquid scintillation counter.was used to analyze for H-3 and 'Fe 55 while Sr-89, Sr-90 analyses were done by propordonal counter. Samples analyzed for iron and strontium Jnderwent a Chemical separation prior to counting. Approved sample collection and analysis procedures were followed.

Analytical results 'are examined to ensure that the minimum sensitivity levels required by ODCM. lower limits of detection (LLDs) have been met. Any identifiable peaks above background are quantified.

The methods above were used-for batch releases. The same nwthods .were used for continuous discharges, but were combined with gross activity measurements on process streams and total flow for these streams.

No estimate of percent total error is provided in Table 1 A )

because all values for gaseous effluents were determined to be

+ s than required LLDs. Basis for the estimated percent total for entries in Table 2A is given in Section C.

5. Batch Releases a) Liquid 1st Osnet 2nd Quarter

1. Number of batches 17 17

2. Total Time (minutes) 2,371 2,563

3. Maximum Time (minutes) 176 176

4. Minimum Time (minutes) 10 15

5. Average Time (minutes) 139 151

6. Total Volume Discharged (Dal) 2.82 E + 5 3,04 E + 5

7. Total Dilution Water - (gal) ' 2.04 E + 7 2.20 E + 7

8. Average Flow (Opm) 8.72 E + 3 8.70 E + 3 (with dilution) b) Gaseous - Nnne

6. Abnormal Releases a) Liquid - None b) Gaseous -- None 3-

. . . . =. . - .. . . ..- - - - ...

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT B - GASEOUS EFFL.JENTS 1st and 2nd Quarters of 1992 All samples of gaseous effluents were analyzed and determined to be at or below minimum detectable activities IMDAs) for all radionuclides listed in Shoreham's ODCM. These MDAs were below the lower limits of detection required in ODCM Controls Tabie 4.11.2.1.2-1. In audition, no other radionuclides were identified.

Therefore, no entries were made in Tables 1 A,18 or 1C that follow.

Composite sample results for the first and second quarters of this reporting period are all at or below MDAs.

t TABLE 1 A 1

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1992 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES t; nit Quarter Quarter Est. Total 1 2 E rror. %

A. Fision & actintien gases

1. Tota 1 release Ci . E . E . E

2. Aserage release rate for penod pCi/sec . E . E

3. Percent of Technical specification lirnit  % . E . E B lodines 5

1. Total icdine.131 Cl . E . E . E 2 Aserage release rate for period uCi/sec . E . E

3. Percent of techrucal specification hmit  % . E . E C. Particulates

1. Particulates with half lives >8 days Ci . E . E . E

2. Averate release rate forperiod uCi/sec . E . E

3. Percent of technical specification limit  % .

E__ . E

4. Gross alpha radioactivity Ci . E . E l D. Tritium

1. Total release Ci . E . E . E

2. Average release rate for period uCi/sec . E . E

3. Percent of technical specification limit -  % . E . E l

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TABLE 1B 1992 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 2 Quarter Quarter Quarter) 2

1. ' ssion gases

~

l krypton 45 Ci . E . E . E . E-k ry pton.85 m Ci . E , E . E . E kryptonT87 Ci . E E E . E k rypton.88 Ci . E . E . E . E Ci E, E E E xenon.133 . . . .

Ci E E E E xen6n.135 . . .

~~

Ci E E E E xenon.135 m . .

~

xenon 138 Ci . E E . E . ~E~

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

Ci . E . E . E . E Ci . E . E E . E

~

Ci E E E E umdentiGed . . .

Total for pii~d C . El . E . E . E

2. lodines iodine.131 Ci . E . E . E . E iodine.133 Ci . E . E . E . E

^

iodine.135 '

Ci . E . E . E . E' Total for period Ci E . E . E . E

3. Pa.rticulates strontium.89 Ci . E . E . E . E strontium.90 Ci . E , E . E . T Ci E E E E cesium 134 . . . .

cesium 137 Ci , . E . E . E . E Ci E E E E barium. lanthanum 140 . . .

Others (sp:cify) Ci . E . E . E . E E

~~] Ci Ci E

E

. E E

E E

. E unidentified Ci . E . E . E . E~"

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l TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1992 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE towetides Reiseud Urdt Quanw Quenery Ownwy y 0 "*"" 2

.. Fission gases krypton.85 Ci . E . E . E . E kry pton45 m Ci . E . E . E . E krypton 47 Ci . E . E . E . E l kryptones Ci . E . E . E . E xenon.133 Ci . E . E . E . E xe non.135 Ci . E~ . E . E . ' t. ~

xe non.135 m Ci . E E . E . E xe non.138 Ci . E . E . E . E 0:hers (specify) Ci . E . E . E . E Ci ~

. E- . ~~E' . E . E Ci ^

. E . E . E . E unidentified Ci . E . E . E . E

, Total for penod Ci  ! . E . E . E . E1 t

2. Iodines i

1 iodine.131 Ci . E ,

E, . E l . E iodine.133 '

Ci . E . E . E . E

! iodme.135 Ci . E . E . E . E Total for perioc Ci E E E E l . . . .

! 3. Puticulates i

strontiume9 Ci . E . E . E . E st rontium.90 - Ci . E . E . E . E l cedum.134 TCi . E . E . E . E l

ced um.137 Ci . E . E , E . E banum.bnthanum.140 Ci . E E . E . E Ot ners (specif>) Ci . E . E . E . E L Ci . E- . E . E . E l Ci . E . E . E . E l unidentified Ci . E . E E . E l

4 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT C - LIQUID EFFLUENTS 1st and 2nd Quarters of 1992 All samples of liquid offluents were analyzed accordin0 to ODCM requirements and, except for one instance as noted below, dote mined to be at or below minirnum detectable activities (MOAS) for all radionuclides listed in the ODCM. These MDAs were be!ow the LLDa required in ODCM Controls Table 4.11.1.1.1-1. In addition, no other radionuclidos that are not specified in the aforementioned ODCM Tabie were identified.

Composite sample resuit; from batch discharges for tritium, alpha, noble gases, Sr-89, Sr-90, and Fe-55 in this reporting period are all at or below MDAs.

From the corninuous discharges however, the quarterly Reactor Building Salt Water Drain Tank i .3SWDT) composita sample for the first quarter shows Fe-55 activity 4 at a' very low trace level of 3.82E 7 uCi/ml'. Results for tritium, Sr-89, Sr-90, Oross alphas, and all other nuclides, including those. listed in the categories of principal gamma emitters and dissolved and entrained gases, are all at or below MDAs.

The amount of RBSWDT 9olume discharged durirag the first quarter of 1992 is 240 gallons; the resultant offsite maximum whole body and organ dose commitments' projected are 3.7E-4 mrom and 2.1E-3 mrem, respectively. They are well below the ODCM quarterly and annual limits and ere 2.5E-4 and 4.3E-4, as fractions, of the respective ODCM quarterly limits. That is, less than 0.05% of the ODCM quarterly limits.

For the second-quarter in 1992, the analysis results for the composite samples show that all activities- in the continuous discharges are at or below MDAs. ,

Therefore, no entries were made in Tables 2A and 28 for this quarter.

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-Tho' required LLD for Fo-55 for this quarterly RBSWDT samplo analysis is 1E-6 uCi/ml. The measured value therefore, is below the required LLC.

2 A radiological evaluation of the impact from the Fe-55 activities as found in these liquid

, effluents, notwithstanding their below LLD levels, wul be reported in Section E of the next 1

. Semi Annual Effluent Release Deport, as required by ODCM Control 6.8.1.4.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-C - LIQUID EFFLUENTS 1st and 2nd Quarters of 1_992 (cont.) <

Tha total error percentage entered 'into Table 2A for liquid measurements was estimated from the tank sampling error and from counting error at values close to minimum detectable activities. This overall error is esthnated to be approximately 50 %

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' TABLE 2A i EFFLUENT AND WASTE DISPOSALSEMIANNUAL REPORT 1992 LIQUID. EFFLUENTS-SUMMATION OF ALL RELEASES Urit Ouener Quener Est Toisi 1 2 E rror. s A. Fision and activation produto ,

j

l. Total release (not including tritium, i gases, alpha) _

Ci 3.47 E-7 . E 5. o E+1

2. Average diluted concentration dunng period mci /ml 3.82 E-7 ~

. E.

3. Pereent of appbcable lirnit  % 4 78 E-2 . E B. Tritiurn

1. Total elease ,', I Ci . F , E . E l

2. Average diluted conantrk'on during period . uCi/ml . E . E

3. Percent of appbcable limit ]  % . E l . E C. Dissolwd and entrained gases '

l. Total relea.;e Ci . E . E . E l 2 Average dduted conantration dunng period - ACi/ml E 'E

-l

3. Percent of applicable limit 'A . E . E ,

l

- D. Gross alphs radioactiity ~

1. Total release 1

l l Ci l . E l .

El . E l

~-_ _

m.

E. Volume of waste released (prior to dilution) liters 9 .08 E+2 . E 1.o E +1 l F. Volume of dilution water used during period ' lit ers o .o E+o . E 2.o E +1 H

l

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMlANNUAL REPORT 1992 LIQUID EFFLUENTS CONTINUOUS MODE B ATCH MODE Nwet.dn Releaud Unit Owarteri Owarter2 Quartery Own t" 2 E E E strontium 49 Ci . E .

E E E strontium 90 Ci . E .

cepum 134 E E E E Ci . .

E E E cesium.l b Ci . E . .

Ci E E E l . F.

iodine.13i . . .

~

cobalt.SS Ci . E , E . E .._El coba;t.60 Ci E E . E I Ej C E E . E 4 E

~ Ii5n-59 .

Ci E E E E iinc 65 .

Ci E E E . E mwganew 54 . . .

Ci E E E , E chromium.51 . , .

Ci E E E . E zirconium niobium.95 Ci E E E E molyt 1enum.99 . .

Ci E E E E technetium.99m .

Ci E E E E barium.lanthnum 140 .

Ci E E E E ce n um.14 ) . .

Ci E E E E Other (specify) . . . .

iron-55 Ci 3.47 E-7 E . E F Ci . E E . E ~

. E Ci . E . E E E Ci . E , E . E E Ci E E . E . E unidentiSed . .

Total for period (above) C 3.47 E-7 . E . E . E Ci E E E E xenon.133 Ci E E E E xenon.135 . . .

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT D - SOLID WASTE 1st and 2nd Quarters of 1992-

-There.was no shipment of solid waste offsite to a burial site dur.ag the first and the second quarters of 1992. H_owever, shipments of solid waste were made to

- two volume reduction vendors' processin0 sites. The entries in Table 3 represent the volume and curie contents of solid waste shipped from Shorcilam to such j_ sites.

TABLE 3

• *

• REGULATORY GUIDE 1.21 REPORT * * *

• SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION

• DURING PERIOD FROM 1/1/92 to 6/30/92

WASTE STREAM: Resins, Filters, & Evaporator Bottoms WASTE CLASS .CMBIC METERS CURIES  % ERROR (Cl)

A 63.9 2.86E-1 i 25 %

l

• ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM *

• WASTE STREAM: Resins, Filters & Evaporator Bottome ivith .'1% CUTOFF

-WASTE CLASS NUCLIDE A_BUNDANCE CURIES A Ni-63 42.993 % 1.23E-01 i Zn-65 3?.808 % 9.10E-02 'l Fe-55 22.475 % 6.43E-02 Co-60 1.919 % 5.49E-03 Ce-144 0.216 % 6.19E-04 Sr-90 0.204 % 5.83E-04

! C-14 0.138 % 3.95E-04 l Mn-54 0.123 % 3.53E-04

!- Cs-137 0.118 % 2.3? E-04 l

Cm243/244 0.005 % 1.4 E-05 L

l i

TABLE 3 (Cont'd)

REGULATORY GUIDE 1.21 REPORT * * *

• SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION

• DURING PERIOD FROM 1/1/92 to 6/30/92 *

• WASTE STREAM: Dry Active Waste WASTE CLASE fd)BIC METERS CURIES  % ERROR (C[l

.A 290.1 1.33E-2 25 %

EST! MATES OF MAJOR NUCLIDES BY WASTE CLASS & LTREAM *

• WASTE STREAlt Dry Active Waste with .0% CUTOFF WASTE CLASS _ NUCLIDE ABUNDANCE CURIES A Ni-63 64.42i % 8.60E-03 Co-60 18.502 % 2.47E 03 Fe 55 t 3. 783 % 1.84E-03 Zn 65 2.187 % 2.92E-04 Mn-54 0.736 % 9.83E-05 Cs-137 0.369 % 4.93E-05 L

L l

1,

. - . . . . . - . . - -- - _ c . _ . __

TABLE 3 (Cont'd)

• *

• REGULATORY GUIDE 1.21 REPORT * * *

• SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION

• DURING PERIOD FROM 1/1/92 to 6/30/92 *

• WASTE STREAM: Irradiated Components WASTE CLASS CUBIC METERS CURIES  % ERROR (Cl)

A 0 0.0 N/A

ESTIMATES OF MAJOR NUCLlDES BY WASTE CLASS & STREAM *

• WASTE STREAM: Irradiated Components with .0% CUTOFF

. WASTE CLASS NUCLIDE ABUNDANCE CURIES A FE-55 0% 0.0 Co-60 0% 0.0

.Ni-63 0% 0.0 Mn-54 0% 0.0 Ni 59 0% 0.0 C-14 0% 0.0 Nb-94 0% 0.0 Pu-241 0% 0.0 Pu239/40 0% 0.0 Pu-238 0% 0.0 Tc-99 0% 0.0 Np-237 0% 0.0' Cm-242 0% 0.0 L

Am-241 0% 0.0 Cr-51 0% 0.0 Cm243/44 0% 0.0 Pu-242 0% 0.0 Am-243 0% 0.0 Cs-137 0% 0.0 l- I129 0% 0.0 P

Sr-90 0% 0.0 H-3 Ook C.0 1

l:

9

,A. -

TABLE 3 (Cont'd)

' REGULATORY GUIDE 1.21 REPORT * * *

• SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION

• DURING PERIOD FROM 1/1/92 to 6/30/92 *

• WASTE STREAM: Other Waste WASTE CLASS CUBIC METERS C1LELigS  % ERROR (Cl)

A 0 0.0 N/A

• ESTIMATES OF MAJOR NUCLICES BY WASTE CLASS & STPEAM *

• WASTE STREAM: Irradiated Components with .0% CUTOFF

. WASTE CLASS NUCLIDE Mi&JDANCE C_UBJES A- FE-55 0% 0.0 Co-60 0% 0.0 Ni-63 .0% 0.0 Mn-54 0% 0.0 Ni-59 0% 0.0 C-14 0% 0.0 Nb-94 0% 0.0 L Pu-241 0% 0.0 Pu239/40 0% 0.0 Pu 238 0% 0.0 Tc-99 0% 0.0 Np-237 0% 0.0 Cm-242 0% 0.0 Am 241 0% 0.0 Cr-51 0% 0.0 Cm243/44 0%. 0.0 Pu-242 .0% 0.0 Am-243 0% 0.0 Cs-137 0% 0.0

. 1-129 0% 0.0 Sr 90 0% 0.0 H-3 0% 0.0

TABLE 3 (Cont'd)

• * ' REGULATORY GUIDE 1.21 REPORT * * * *

-SOL'D WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION

• DURING PERIOD FROM 1/1/92 to 6/30/92

WASTE STREAM: Sum of All Categories WASTE CLA_SS CUBIC METERS CURIES  % ERROR (Cl_)

A 354. 2.99E-1

• 25%

• ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM *

• WASTE STREAM: Sum of All Categories with .0% CUTOFF l

WASIE CLASS . NUCLIDE ABUNDANCE CURIES A Ni-63 43.948 % 1.32E-01 Zn-65 30.487 % 9.13E-02 Fe-55 22.088 % 6.61 E-02 Co-60 2.658 % 7.96E-03 Cc-144 0.207 % 6.19E-04

Sr-90 0.195 % 5.83E-04 Mn-54 0.151 % 4.51 E-04 C-14 0.132 % 3,95 E-04 Cs-137 0.129 % 3.87E-04 Cm243/244 0.005 % 1.46E-05 L

L *

• SOLID WASTE VOLUME REDUCTION SHIPMENT

SUMMARY

L L

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 5 Truck Quadrex (Oak Ridge, TN)-

l -- 2 Truck SEG (Oak Ridge, TN) l.

f- ..

TABLE 3 (Cont'd,

REGULATORY GUIDE 1.21 REPORT * * *

• j SOLID WASTE SHIPPED FOR OFFSITE BURIAL DISPOSAL

• DURING PERIOD FROM 1/1/92 to 6/30/92 *

• l

SOLID WASTE OFFSITE BURIAL DISPOSITION

SUMMARY

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION O N/A Barnwell O N/A Richland 0 N/A Beatty 0 N/A Other

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t.

G - ODCM REVISIONS, REMP LOCATION CHANGES AND MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS A. Changes to the ODCM:

- According to Technical Specification G.13.c and ODCM Control 6.8.1.4, changes to the Offsite Dose Calculation Manual (ODCM) made during the reporting period shall be submitted with tho Somiannual Radioactive Effluent Release Report in the form of a comploto copy of the entire ODCM, with changes identified by markings in the margin of the pages that contain them.

There was no change made to the ODCM, during this reporting period.

B. REMP Location Changes:

Action Statements c of ODCM Control 3.12.1 and a and b of ODCM Control 3.12.2 require REMP location changes to be reported in the Semiannual Radioactive Effluent Release Report.

There were no such REMP location changes during this reporting period.

C. Major Changes to Radioactive Waste Treatment Systems:

, Solid Waste Process Co'ntrol Program (PCP) L.3.1 and 9.4.4 state that the

l. Semiannual Radioactive Effluent Release Report shall include major changes to u radioactive waste treatment systems.

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

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