ML20064A337

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Semiannual Radioactive Effluent Release Rept for First & Second Quarters 1990.
ML20064A337
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/30/1990
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20064A336 List:
References
NUDOCS 9009040051
Download: ML20064A337 (17)
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1; S2ttANNUAL RADICN:TIVE EFFLUEtC RELEASE REKRP let and 2nd Quarters of 1990 >

.. l Facility: Shdreham' Nuclear Pwei St4'...u , Unit 1 .[

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TABIE CF 00tEENTS .'

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_Section Pge - , / )

1 Introduction- 1- .

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'f A .' Supplanental Information 1 B. Gaseous Effluents- 4 i

. 1 C; Liquid Effluents 8 '

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,D. ' Solid Waste .11 a E. ' Ndt Required 1 F. Not Required i

' G. ! PCP and ODCN Revisions, REMP. Non Cmpliances . 14 1

'and Major Changes to RM4rar tive Waste Treet:L*Jit Systems 3t H.' - Miscellaneous Special Reorts 15

1. Section E, Radiological Inpact on Man, and Section F, Meteorological Data i are not requiled by 'nchnical Specification to be.inclMM in this report.  ;

'Ibese sections will appear in the next reru.i., due 60-days after i January '1; 1991, and will eWas all of 1990.

9009040051 900823 i PDR ADOCK 05000322 R PDC i f-4

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1 5 Introduction. [

- This Sminannual Radioactive Effluent Release Report, subnitted in accordrnce '

with Technical Specification 6.9.1.7, covers the periods frczn January 1,1990, through March 31, 1990, and April 1, 1990, through June 30, 1990.' -By contractual agreenent with New York State, the Inng Island Lighting Ccmpany

, (LTTm) will transfer the Shoreham Nuclear Power Station to the Iong Island . .

-Power Authority. LIILO cannot Wate the plant in the interim. 'the plant has s been in cold shutdown for over two years. )

A. SUPPlaOHRL INEDRMATION j

1. Regulatory Limits ,;

1 Shoreham's effluent regulatory limits-are defined in Facility Operating License NPF-82, Shoreham Nuclear Power Station, Appendix A, Tbchnical .

Specifications. -

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

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

d) Liquid effluent limits are described in Technical Specifications 3.11.1.1 and 3.11.1.2  ;

e) -In addition, 'with Shoreham's sanpling and analysis program the following typical mininum detectable activities (MDA's) were i achieved. These MDA's are less than the required lower limits of detection (LID's) .

Liquid _

Ce-141 3.0 E-08 uCi/ml Co-58 2.7 E-08 uCi/ml Cs-137 3.3 E-08 uCi/ml Mo-99 1.6 E-08 uCi/ml Zn-65 7.3 E-08 uCi/ml i Mn-54 2.4 E-08 uCi/ml I

Gaseous:

Cs-137 3.9 E-14 uCi/oc Mn-54 3.7 E-14 uCi/cc En-65 9.7 E-14 uCi/oc I-131 5.3 E-14 uCi/oc I-133 7.2 E-13 uCi/oc Xe-133 4.6 E-08 uCi/oc

2. Maximan Pemissible concentrations (a-d) Mav4== permissible concentrations ('ecs) are those specified in >

10 CPR 20, Appendix B, Table II, Cohann 2. If an isotope is listed with values for wnnmR an(, IN90WRIE states, the more conservative value is utilized. ibr gaseous effluents MPCs were not used. Direct calculaxions of dose were utilized to satisfy the dose rate limitations of %chnical Specification 3.11.2.1.

3. Average Energy No fission or activation gas isotopes above mininan detectable activities were measured in gasecus effluents. S crefore, there is no reportable average energy for this time period.
4. Measurenants and Approximations of Total Radioactivity (a-d) Sanples were collected in the manner and with the frequency prescribed in % chnical Specifications Surveillance Requirements 4.11.1.1.1 and 4.11.2.1.2. Sanples 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. Wat sanples were analyzed by ganma spectroscopy with a Germanium detector. A liquid scintillation counter was used to analyze for !!-3 and Fe-55 while Sr-89, 90 analyses were done by proportional counter. Sanples analyzed for iron and strontium underwent a chesnical separation prior to counting.

Approved sanple collection and analysis procedures were followed.

Analytical results are examined to ensure that the miniman sensitivity levels required by Technical Specificat'.ons lower limits of detection (IID's) have been met. Any identifiable peaks above background are quantified.

W e methods above were used for hatch releases. %ese methods combired with gross activity measurcunents on process streams and total flow fcar these streams were used for continuous discharges.

c.

.I No estimate of percent total error is' prwided in either Table 1A or 2A because all values for gaseous effluents were determined to be less than required lower limits of detection (12D's) .

5. Batd1 Releases a) Liquid- 1st Quarter 2nd Quarter
1. Nunbar of batches 2.70 E+01 1.40 E+01
2. 'Ibtal Tine (minutes) 4.18 E+03 2.22 E+03
3. Maximun Time (minutes) 2.23 E+02 1.71-E+02
4. Average Time (minutes) 1.55 E+02 1.58 E+02
5. Mininum Time (minutes) 3.80 E+01 1.01 E+02
6. Average Flow (gpm) - 1.37 E+04 1.30 E+05 (Dilution) b) Gaseous - None
6. - Abnormal Releases a) Liquid - None b) Gaseous - None SDCAIME RADIOPCTIVE DTURC RELEASE REPORP i D ~ GASEOUS ErnUINOS

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1st ard 2nd Quarters of 1990 All suples of gaseous effluents were analyzed ard determined to be at or below ndnian detectable activities (MDA's) for all radionuclides listed in Shoreham's :

Technical Specifications. 'Ihese n's were bels the lower limits of detection [

required in Technical Specification Table 4.11.2.1.2-1. In addition, no other i raMrmuclides were identified. 'Iherefore, no entries were made in Tables 1A,1B !

or IC that follw.

Caposite emple results for the second gaarter of this reporting period are not available at this time. First quarter exposite results were used for the second quarter. When the actual resultr, ,r.e available, any significant differences will be noted in supp1mente 'co this report. However, as stated i previously, all results are at or belw MDAs. No significant differences have been noted between previously reported conposite results and actual results.

All results have been at or below M's.

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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est, Total 1 2 E "*'. %

A. Fision & activation games

1. Total release Ci . E . E . E
2. Average release rate for penod mci /see . E . E
3. Pticent of Technical specification limit  % . E . E B. lodines
1. Total iodine 131 Cl . E . E . E
2. Average release rate for period pCi/sec . E . E
3. Percent of technical specification limit  % . E . E C. Particulates
1. Particulates with half.tives >8 days Ci . E . E , E
2. Average release rate for period pC /aec . E . E
3. Percent of technical specification limit  % . E . E
4. Gross alpha radioactivity Cl . E , E 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 1

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TABLEIB 1990 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Overtar)

Quetter 2 O u 1 0""'2

1. Fission gases krypton.85 Ci . E . E . E . E Ci E E E E krypton 85m . . . .

krypton.87 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 xeTi6n.135 . . . .

Ci E E E . E v.e non.135 m . . .

Ci E E E E xenon 138 . . . .

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

Total for period Ci . E . E . E , E

2. Bodine iodine.131 Ci . E . E . E . E iodine.133 Ci . E . E . E . E iodine 135 Ci . E . E . E . E i Total for period Cl . E , E , E . E
3. Particulate strontium.89 Ci . E , E . E , E strontium 90 Ci . E . E . E . E cesium.134 Ci . E . E , E , E cesium 137 Ci . E , E . E . E barium. lanthanum.140 Ci . E . E , E . E Others (soecify) Ci . E . E . E . E Ci . E , E . E , E Cl . E . E . E . E unidentified Ci . E . E . E . E i- .  ;
  • 1 TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES t

CONTINUOUS MODE BATCH WODE  !

Nuclides Meleemd UNt Ouwtw

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1. Fision gases l i

krypton.85 Cl E E E

. . . . E krypton 45m Ci E E E

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krypton 87 Cl E E E

. . . . E j krypton.88 Ci E E '

. . . E . E xenon.133 Ci . E . E . E . E ,

xenon.135 Ci E E E

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xenon 135m Cl . 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

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iodine.131 Ci E E E L

. . . . E lodirne 133 Ci E E E -

. . . . E iodine.135 Ci E E E

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

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3. Particulates '

strontiurn49 Ci . E . E . E . E strontium 90 Ci . E . E . E . E l cesium.134 Ci . E . E . E . E l casium 137 Ci . E . E E E barium. lanthanum.140

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

Ci . E . E . E , E l Ci . E . E . E . E unidentified Ci . E , E . E . E

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SEMIAINAL PADIQhCTIVE EITWENT R12 EASE REIORP C - LIQUID EFTWENPS ist ard 2rd Quarters of 1990 All sagles of liquid effluents were analyzed ard determined to be at or bels mininum detectable activities (!(As) for all radionuclides listed in Shorehan's hchnical Specifications. These Mtas were below the lower limits of detection required h % chnical Specification Table 4.11.2.1.1-1. In addition, no other radionuclides were identified. %erefore, no entries were nede in Tables 2A or 2B.

Camposito sanple results for the second quarter are not available at this the.

First quarter camposite results were used for the second quarter. When actual results are available, any significant differences will be noted in supplements to this report. To date, no significant differences between reported c,cutposite results and the actual results have occurred.

TABLE 2A >

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 i LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES

! Unit Owrter Owrter Est. Toist 1 2 treo, %

I' A. Fision and activation products -

l. Total release (not including tntiba, gases, alpha) Ci . E . E . E
2. Average diluted concentration i durina period uCi/ml . E . E
3. Percent of applicable limit  % . E . E B. Tritium
1. Total release Ci . E . E . E l
2. Average diluted concentration during period uCi/mi . E . E
3. Percent of applicable limit  % ,

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C. Dimolwd and entrained anses

l. Total release C . E . E . E l Average diluted concentration during period uCi/ml . E . 'E
3. Percent of applicable limit  % . E . E h D. Gross alphs radioactivity ,

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

El . E l E. Volume of waste released (prior to dilution) liters . E . E , E F. Volume of dilution water used during period liters . E , E . E l --

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EFFL.UENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 1 l

LIQUID EFFLUENTS CONTINUOUS MODE S ATCH MODE Nuclides Releoned Urut Overieri Overter2 Quenery Owenn 2 l

strontium 49 Ci . E . E . E- . E  ;

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strontium.90 Ci . E . E . E . E i Ci E E E E i cesium 134 . . . .

cesium 137 Ci . E . E . E . E  !

iod iie.131 Ci . E . E . E . E l ,

1 cobalt SH Ci . E . E , E . E l Ci E E E E- )

cobalt.to . . . .

irdn.59 C . E . E . E . E  !

iine.65 Ci . E . E . E . E -

manganese.54 Ci . E . E . E . E j chromium.51 Ci . E . E . E . E l y

zirconium. niobium 95 Ci . E . E . E . E  !

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l molybdenum 99 Ci E . E . -E . E l technetium.99m Ci . E . E . E . E-I barium. lanthanum.140 Cl . E . E . E . E cerium.141 Ci . E . E . E . E ]

Other (specify) Ci E E  !. E E l

Ci _. E . E i. E . E i Ci . E . E . E . E l Ci . E . E E . E i Ci . E . E , E . E Ci E E E E unidentified . . . .

i Total for period (above) Ci . E , E . E , E -

xenon.133 Ci . E . E , E . E l xennn.135 Ci . E , E , E . E l 1

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i SDW@MP1 PADIOPCTIVE DTMHWT REMASE REPORP D - SOLID WSTE i'

ist and 2nd Quarters of 1990 i

l Table 3 prwides information on shipnents of solid waste for the first and socord quarters of 1990. The main and filter nedia waste was shig (no evaporator bottans waste was shipped during this period) in 158.1 ft Dor Spec 7A High Integrity Containers (HICs), while the dry active waste was shipped in ,

two B25 boxes. Both the HICs and the baxes are apprwed by the South Carolina l Depart 2nent of Health and Environmental Conserve. tion.

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'Ihere were no irradiated fuel shipnents during tle first and second quarters of 'I 1990. )

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t TABLE 3 (Sheet 1 of 2)

' *** RBGUIA70RY GUIEE 1.21 REPORT ***

SOLID HASTE SHIPPED OETSITE FOR DISPOSAL -

    • DURING PERIOD FKH 1/1/90 to 6/30/90 ** i WASTE STREAM: Desins, Filters, & Evaporator Bottcans  !

HASTE CIASS CUBIC METERS CURIES  % ERROR (CI)  !

A 17.9 2.89E-03 *25% ,

    • ESTIN.TES OF MMOR NUCLIDES BY HASTE CIASS & STREAM **

WASTE STREAM: Hesins, Filters & Evaporator Bottczns with .0% CUICET (

WASTE CIASS NUCLIDE ABUNDANCE CURIES A Co-60 26.740% 7.73E-04 re-55 21.858% 6.32E-04 Cr-51 17.158% 4.96E-04 Co-58 .2.583% 3.64E-04 -

En .t.400% 1.27E-04 >

Pu-241 4.239% 1.23E-04 H-3 3.638% 1.05E-04 Ag-110m 3.180% 1.04E-04 ,

Fe-59 1.491% 4.31E-05 Mn-54 1.341% 3.88E-05 Ce-144 1.269% 3.67E-05 Ni-63 1.033% 2.99E-05

Str124 .134% 3.87E-06 Co-57 .109% 3.16E-06 Co-141 .026% 7.49E-07 Ni-59 .019% 5.51E-07 Sr-90 .007% 1.89E-07 Nb-94 .000% - 1.14E-08 '

C-14 . 0Gl% 4.38E-09 Cm.-242 .000% 0.00E+00 I-129 .000% 0.00E+00 Tc-99 .000% 0.00E+00 4

C ' i TABLE 3 (Sheet 2 of 2)

      • RDGUIMORY GUIDE 1.21 REPORT ***

SOLID hESTE SIIIPPED OFTSITE KR DISPOSAL

    • DURING PERIOD FRCH 1/1/90 to 6/30/90 **

WASTE STPEJM Dry Active Waste WASTE CLASS . CUBIC METERS CURIES  % EIUOR (CI)

A 5.4 1.15E-02 *25%

    • ESTIMATES OF MMOR NLCLIDES BY WASTE CLASS & STRETM **

NASTE S77EAM: Dry Active Waste WASTE CLASS _

NUCLIDE ABUNDANCE CURIES A Mn-54 24.074% 2.78E-03 Co-60 23.035% 2.66E-03 Fe-55 18.878% 2.18E-03 Cr-51 14.756% 1.70E-03 Co 58 10.807% 1.25E-03 Zn-65 3.793% 4.38E-04 ,

Ag-110m 3.066% 3.54E-04 Fe-59 1.282% 1.48E-04 H-3 3.56E-05

.308%

C-14 .000% 1.50E-08 On-242 .000% 0.00E+00 Pu-241 .000% 0.00E+00 Cs-137 .000% 0.00E+00 I-129 .000% 0.00E+00 Tc-99 .000% 0.00E+00 -i Sr-90 .000% 0.00E+00 Nb-94 .000% 0.00E+00 Ni-63 .000% 0.00D+00 i Ni-59 .000% 0.00E+00

    • SOLID k%STE DISPOSITICN SUM %RY ** .

NtNBER OF SKIPME!ES ) ODE OF THANSPORTATION DESTINATION 1 Truck Barnwell 0 Truck Richland 0 Truck Boatty  ;

O Truck Other

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SEMIA)MRL RADIQhCTIVE EITLUENT RDEASE REPORP G - PCP & ODCM REVISIONS, REMP NON CCEPLIANCES AND MMOR CHANGES TO RADIQACTIVE MASTE TRERIMENT SYS11MS 1st and 2nd Quarters of 1990 According to Wchnical Specifications 6.9.1.7, 6.13.2a and 6.14.2a, the Semiannual RMicartive Effluent Release Report shall include any changes to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (CDCM) made during the reporting period.

A. There were no changes made to the PCP during this reporting period.

B. The CIXE was revised to incorporate the most recent Land Use Survey Data, i.e., the nearest resident and the nearest garden 1ccations, a new RENP sanpling location, and correct tymn sical errors.

'1hese changes will enhance the accuracy and reliability of dose calculations and setpoint determinations since they will ensure that all such calculations and determinations are performed utilizing the most recent data.

The affected pages of the CDCM and the signature page, including BOC revieve and acceptance, are attached.

Action Statament c of %chnical Specification 3.12.1 and action statments a and b of Technical' Specification 3.12.2 requires certain itms of REMP re-yliance to be reported.in the S miannual Radioactive Effluent Release Report.

C. There were no such REMP noncmpliances during this reporting period.

%::hnical Specification 6.15 states that the Smiannual Radioactive Effluent Release Report shall include major changes to radioactive waste treatment Systes.

D. There were no Ir.ajor changes to radioactive waste treatment systems reviewed by the Review of operations Committee during this reporting period.

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SEMIANNUAL RADIOACTIVE 1FFLUI!NT RIHEASE REPORP 11 - MISCILIANDOUS SPl!CIAL REFORPS let and 2nd Quarters of 1990 Ub fulfill the requirements of Technical Specification location Ia2 the com provides two milk sanple locations (10F1 and 8G2). Cn May 31,~1990, neither of ,

these locations were available and a sanple was obtained frun new location 8F2 (9.5 mi SSE) which moetc 'nx:hnical Specification Table 3.12.1-1 requirements for location Ia2.

The requirement of Technical Specification location DR17 is met by the direct l radiation monitoring station at location 5E2 (4.5 mi. E), as indicated on ODCM Table 5-2. Iocation SE2 was inadvertently canitted fran the latest revision of OD W Figure 5-2. Attached is a markup of Figure 5-2 which shows the location of SE2. '1his will be included in the next GXM update.

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I / OFFSITE SAMPUNG LOCATIONS RA000 LOGICAL ENVIRONMENTAL MONITORING PROGRAM SHORDeMS MUCtDWI PUWER STAT 904-UNITf  ;

WFSITE DOSE CA4.CULAY104 ISAMUet.

Revision 15 - January 1990 l

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