ML20011F386

Semiannual Radioactive Effluent Release Rept,Third & Fourth Quarters 1989

ML20011F386
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	12/31/1989
From:	LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20011F385	List: ML20011F386 SNRC-1678, Forwards Semiannual Radioactive Effluent Release Rept,Third & Fourth Quarters of 1989. Rept Includes Info for Each Type of Solid Waste Shipped Offsite During Period & Meteorological & Dose Assessment Data for Entire Yr
References
NUDOCS 9003050268
Download: ML20011F386 (73)

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{{#Wiki_filter:w p-I d' s -t, t-s SFMIANNUAL PADIOM3'IVE EFFIUDC l REITASE M: PORT .v 3rd and 4th Quarters of 1989 [ 1989 Meteorological Sumary and offsite Dose Assessment r Facility: Shoreham Nuclear Power Stationj Unit 1 y ' Licensee: Long Island Lighting Cmpany, Inc. E b l f .i ..w[ t v. (b TABLE OF 00NTDUS p IC Section. Page I y Introduction. 1 e l -A.. Supplemental Information 1 B.- Gaseous Effluents' 4 8 i C.-l Liquid Effluents. 8 i i l' D. Solid Waste 11 i o

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[. E. Radiological Inpact on Man H 13~ -f F. Meteorological Data 14 i. p. E 'G; - PCP and ODCM Revisionsi RD@ Non Conpliances ! 71 and Major manges to Radioactive Waste j - Treatment Systems t ?H.'. Miscellaneous Special~ Reports 72 y l* l-l 19o03050268 900227 1 u.

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c p. INTICULUTIN This Semiannual Radioactive Effluent Release Report, submitted in accordance 'with % chnical Specification 6.9.1.7, covers the periods from July 1, 1989, through Septenber 30, 1989, and October 1,1989, through December 31, 1989, i Meteorological data sunmaries for the whole of 1989 are included as is an assessment of offsite doses due to liquid and gaseous effluents for the whole' ( year. By contractual agreer9ent with New York State the long Island Lighting Canpany (LIICO).will transfer the Shoreham Nuclear Power Station to the long Island Power Authority. LIICO cannot operate the plant in the interim. In ~: order to protect plant systems and ready the plant for deconmissioning, the fuel was transferred to the spent fuel pool in August,1989 and plant layup 4 F: ' activities began.. Prior to defueling, the plant was in a cold shutdown j condition for almast two years. ] [ i A. SUPPIJNTNTAL INFDINATION l 1. Regulatory Limits I Shoreham's effluent regulatory limits are defined in Facility Operating i License NPF-82, Shoreham Nuclear Power Station, Appendix A, Technical. l Specifications. 4 a) Limits for gaseous eftluents and noble gases are covered by Technical Specificatione 3.11.2.1 and 3.11.2.2. b&c) Iodines and particulates with half-lives greater than 8 days'in i gaseous effluents are addressed in hchnical Specification 't '3.11.2.3. d) Liquid effluent'11mits are described in Technical Specifications 3.11.1.1 and 3.11.1.2 L e) In. addition, with Shoreham's sampling and analysis program the ~ r following typical minimum detectable activities (MDA's) were achieved. 'Ihese MDA's are less than the required lower limits of detection (LLD's) Liquid F Ce-141 '3.3 E-8 uCi/ml .Co-58' 3.3 E-8 uCi/ml-Cs-137 3.2 E-8 uCi/ml Mn-54 2.9 E-8 uCi/ml Mo-99 1.8 E-8 uC1/ml + s En-65 7.3 E-8 uCi/ml Gaseous: j Cs-137 1.1 E-13 uCi/cc i I-131 1.2 E-13 uCi/cc' I-133 7.5 E-13 uCi/cc Mn-54 2.0 E-13 uCi/cc Xe-133 2.5 E-13 uCi/cc i Zn-65 3.0 E-13 uC1/cc k

[ f s 2.- Maxinum Permissible Concentrations - a-d) Maxinum pennissible ocncentrations (MPC's) are those specified in 10 CFR 20, Appendix B, Table II, Column 2. If an isotope is listed with values for SOWBLE and INSOWBLE states, the nore conservative value is utilized. For gaseous effluents, MPC's were not used. Direct calculations of dose were utilized to satisfy ' the dose rate _ limitations of Technical Specification 3.11.2.1. L j 3. Average Enenry No isotopes above mininum detectable activities were neasured in gaseous effluents. W erefore, there is no reportable average energy for this tine period. 4.; Measurmenti and Approximtions of Total Radioactivity e a-d) Simples were collected in the manner and with the frequency l-prescribed ~in Technical Specifications Surveillance Requirements 4.11.1.1.1 and 4.11.2.1.2. Sanples were analyzed in accordance g with Technical Specification Tables 4.11.1.1.1-1 and 4.11.2.1.2-1 regarding both type of analysis and level of sensitivity. &>st canples were analyzed by ga'tra epectroscopy with a Germanium detector. A liquid scintillation counter was used to analyze for i H-3 and Fe-55 while Sr-89,90 analyses were done by proportional counter. Sanples analyzed for iron and strontium underwent a chanical separation prior to counting. Approved sample collection and analysis procedures were follcwed. Analytical results are examined to ensure that the mininum sensitivity levels required by Technical Specifications lower limits of detection (LLD's) have been met. Any identifiable peaks L above background are quantified. The nethods above were used for batch releases. The sane nethods were used for continuous discharges, but were cambined with gross activity neasurements on proceso streams and total flow for these streams. No estimate of percent total error is provided in Table 1A because all values for gaseous effluents were detennined to be less than required LLD's. For liquid measurements, the overall error is r estimated from the tank sanpling error 'and from counting error at i - values close to mininum detectable activities. Wis overall error is estimated to be approximately 50%. 2

m-n. 2 g, i sm 1- - e. sg t, o 7; -- 1 a h \\ 5.- Bat & Releases-a)' ' Liquid 3rd quarter. 4th Quarter g )

1. Number of batches.

5.20 E+1 7.00 E+1 _~

2. h tal-Time

. (minutes) ' 8.06 E+3 1.15 E+4

3. Maxinum Time (minutes) -

1.82 E+2 2.25 E+2 ~ 4. Average Time (minutes) 1.55 E+2 1.64 E+2

5. Minimmt Time (minutes) 2.00 E+1-3.40 E+1' 6._ Average Flow (gpn) 7.04 E+4-1.48 E+5-

-(Dilution) b) ~ Gaseous - None . 6. - Abnormal Releases ' a) ( Liquid' - None g. b) ~ Gaseous'- None e e i-1 5 i i pi.' h; [. Pe k. a 9-t E i.,~ { 3 y :g

SD41AhHUAL SADIOTCTIVE ITFIUDfT RELrASE REPORT B - GASDDUS DTUJDfTS 3rd and 4th Quarters of 1989 All samples of gaseous effluents were analyzed and detennined to be at or beim mininum detectable activities (MDA's) for all radionuclides listed in Shoreham's Technical Specifications. These MDA's were be1N tie lwer limits of detection required in Technical Specification Table 4.11.2.1.2-1. In addition, no other radianuclides were identified. Therefore, no entries were made in Tables 1A, 1B i or 1C that follw. Caposite sample results for the fourth quarter of this reyrting period are not available at this tine, niird quarter composite results were used for the fourth quarter. When the actual results are available, any significant differences will be noted in supplemente to this report, llowever, as stated previously, all results are at or bel m MDA's. No significant differences have been noted between previously reported cmposite results and actual results. All results have been at or belm MDA's. I 4

i i L-l I TABLE 1 A j i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ] unit owner owner tit. v.w 3 4 I"*'% A. Fision & acdvstion goes

1. Total telease Ci E

E E

2. Averate release rate forpnod WCi/see E

E l

3. Pescent of Technical specification hmit 9

E E s.ioen.

1. Total iodine.131 Ci E

E E

2. Averate release rate for period FCi/sec E

E_ i Tercent of technical specification hmit 5 E E1 C. Particulates i

1. Particulates with half bves >8 days Ci E

E E

2. Averate releau rate for period pCilue E

E

3. Percent of technical specification bmit E

E E __

4. Gross alpha radJoactivity Ci E

E_ D. Tridwn

1. Total release ci E

E E

2. Averste release rate for period uCiltee E

E

3. Percent of technical specification hmit 9

E E ) I 5

TABLtis EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 G ASEOUS E FFLUENTS-ELEVATED RELEASE CONTINDOWS WODE SATCHidODE Nwlen Renung Una

Owne, Owner Owner Genee g

y

1. Fhdon pas krypton _45 0

E E E E krypton 45m Ci E E E E krypt on.5'l C E E E E krypton 48 Ci E E E E menon.133 Ci E E E E z'enon.135 C E _E E E menon.135m O E E E__ E i menon.138 Ci E E E E Chhen (specify) Ci E .- E E E Ci E E E E Ci E E E E unidentified Ci E E E E Toi~affor period Ci E E E E 2.lodines lodine.13) Ci E E E E 2 dine 133 Ci E E E E iodine.135 Ci E E E E Total for period Ci E E E T""

3. Phrticulates strontium 49 Ci E

E E E strontium.90 Ci E E E E sesium.l M Ci E E E E cesium 137 Ci E E E E barium lanthanum.140 Ci E E' _E .E Others (specify) Ci E E E E _Ci E E _E ER i Ci E__ _ _ _E 'E EE l_ unidentified -Ci E E E 6

i I i i TAsLEic EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 L GASEQUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE SATCM MODE 1 HvalMehtm Unis Ownw Ownw Ommw Ownc4 3 4 3 I. Fision pies krypton 45 Ci E E E E ,, krypt on45m Cs E E E E krypton 47 Ci E E E E l krypton 46 Ci E E E E l xenon.133 Ci E E E E xenon.135 C E E E E menon.135m Ci E E E E senon.136 C E E E E Oth:rs (specify) C E E E E Ci E E E E i Ci E E E E l-unidentified Ci E E E E Total for period _ Ci E E E .' T

2. lodines iodine.131 Ci E

E E E 6odme.133 Ci E E E iodine.135 Ci E E E Total for period i Ci E E l E E

3. Particulates

( strontium 49 Ci E E E E strontium 90 Ci E E E E cedum.134 Ci E E E E cedum.137 C E E E E barium lanthanum 140 Ci E E E E Others (specify) Ci E E E E_ , Ci E E E -E Ci E E E E unidentifwd Cs E E E E 7

l% e ' l

1. =

c SD4IANNUAL BADIOACI'IVE EFFIDINT' REIFASE REPORT q. C - LIQUID EFFLUENT 3rd and 4th Quarters of 1989 l Tabira 2A and 2B1contain information on the liquid batch releases for the fourth 1 quarter of 1989 'Ibere were no radionuclides above MDA in third and fourth i quarter continuous liquid releases or third quarter batch releases, therefore, ' liquid discharge data for these releases are not included in the Table. Radionuclides that were at or below MDA, which were below the LLD's required in i Technical Specification Table-4.11.1.1.1-1, are not included-in the Tables. I Composite sample results for the fourth quarter are not available at this time. . t 'Ihird quarter composite results were used for the fourth quarter. When actual results are available, any significant differences will be noted in supplements to this report. No significant differences have been noted between 1989 first . and second quarter reported cmposite results and actual results.- All results have been at or below MDA's. l -l i i 1 1 i ;\\ ) 1 l \\ VN. :i ; 'k f i J ' i ' - t. t - '; j h d i 8

TABLE 2A-EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 1989 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES uniti ousner oo.rse, eit. Toisi 3 4 E0'. % A.' Fision and activation products

1. Total release (not including tritium, teses, alpha).

Ci E 1.18 E-3 3.nn E*i j

2. Average diluted concentration during period

1. Ci/ml E-1.84 E-1 1

3. Percent of applicable limit Q

E 6.12 E-6 B. Tritium

1. Total release Ci E-E E

l

2. Average diluted concentration during period uCi/mi E

E

3. Percent of appbcablel_iuVi W

E E C. Dissolved and entrained gases

1. Total telease C

E E E l L2, Average diluted concentration during period uCi/ml-E E

3. Percent of appbcable limit W

E E D. Gross alpha radioacthity 1-

1. Totai release 1

Ci I E l E 1~. E l - E. Volume of waste released (prior to dilution) liters E 3,11 E +6 1.00 E+1 o . F. Volume of dilution water used during period liters E E+9 E3 6.43 2.00 l 9

b ~ TABLE 28 ' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 L L LIQUID EFFLUENTS CONTINUOUS MODE SATCH MODE r Nuclidn Reisewd Unit _ Owenet Cuaner 4 Owene' 3 Owene4 3 i g strontium 49 Ci _E E E E strontiurn.90 Ci E E E E o cesium.134 Ci - E E E E cesium 137 Ci E E E E iodine.131 C E E E E p cobalt.58 l Ci E E E E cobalt.60 Ci E E E 1 18 ES iron.59 C E E E'. E sine.65 Ci E E E - E manganese.54 Ci E E E I E chromium.51 Ci E E E E zirconium. niobium.95 Ci E E E E 1 molybdenum.99 Ci E_ E E E technetium.99m Ci E __ E E E barium lanthanum.140 Ci E E E E cerium.141 Ci E E E E ? Other (specify) Ci E E E-E Ci E E E E Ci E E E E-Cs E E E E i-L Ci E E E E unidentified C E E E E Total for period (above) Ci E E l E 1.1_s E -r xenon.133 Ci E E__ E E xenon.135 Ci E E E E 10

I

t-SD4IANNUAL PADIOACTIVE FEFIDENT RELFA9E REPORT D - SOLID 1RSTE 3rd and 4th Quarters of 1989

. Table-3 provides information on shipinnts of solid waste for the third and fourth quarters of 1989.. All shipmnts consisted of dewatered Class A Resins, Filters and Evaporator Bottesus. There were no irradiated fuel shipmnts. Waste was shipped in 158.1 ft8 DOT Spec 7A 111gh Integrity Containers (HIC's), approved by the South Carolina Departrtent of Health and Envitumental Conservation. 11

V[ v h' ?; p. , TABLE 3' U . *** RDGUIKIORY GUIDE 1.21 REPORT **** E- . SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL

• • DURING PERIOD FRQ4 7/1/89 to 12/31/89**

) WASTE STREAM: Resins, Filters, & Evaporator Bottms' WASTE CLASS CUBIC METERS . CURIES % ERROR- (CI) A' .17.9 3.51E-02 f25% r .[\\ I

• • ESTIMATES OF MAJOR NUCLIDES BY. WASTE CIASS & STREAM **

WASTE STREAM: Besins, Filters & Evaporator.Bottms with.0% CLTIDFF d WASTE CLASS NUCLIDE-ABUNDANCE CURIES ' A 00-60 27.912% 9.01E-03 Fe 23.873% 8.39E-03 Cr-51 ~18.634% .6.55E-03 3 Co-58 14.054% 4.94E-03 Li ,7 Zn-65 -4.590% 1.61E-03 Ag-110m 3.690%' 1.30E-03 Mn-54 2.632% 9.25E-04 Fe-59 1.707% 6.00E-04 Ni-63 1.094% 3.85E-04 Pu-241' .817% 2.87E-04 N, H-3 .281% 9.86E-05 -I Ce-144 275% 9.67E-05 4 C Sb-124 .138% 4.86E-05 -Nb-95 .116% 4.06E-05 Cs-137' 083%

2.90E >

00. 055%- 1.92E-05 Zr-95 .023% 8.19E-06 Ni-59 020% 6.92E-06 Ce-141 005% 1.68E-06 Sr-90 .002% 8.17E-07 Nb-94 .000% 1.43E-07 C-14 .000% '1.12E-07 l, Cm-242 000% 0.00E+00 I-129 .000% 0.00E+00 j Tc-99 .000% 0.00E+00

• • SOLID WASTE DISPOSITION SUtHARY **

I NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATIO1 i' 1 Truck Barnwell 0 Truck Richland O Truck Beatty 0 Truck Other n f y c,' j _r n a ~., l

= 1 r[i ?.i l [ p" SD4IANNUAL RADIOACTIVE EETILDTP RELEASE REPORT 0 E - RADIO 1OGICAL IMPACT CN MAN p y 1989 (;; . During 1989 two liquid batch releases contained snall quantities of Co-60. In April, a batch containing 6.01 uCi's was released and in Decenber a batch P' containing 11.83 uCi's was released. There were no other radioactive effluent releases from Shoreham during 1989. lenthly dose calculations, perforned in [ . accordance with the ODCM, showed that the maximum whole body dose due to the-h fApril batch discharge was 4.4E-8 mrem for a child, and the maximum organ dose was 3.4E-7 mrm to the GI tract of an adult. The doses resulting from the O . Dec m ber batch release were similarly low:. 1.30 E-S mrem whole body for a child ' and 1.04 E-4 mrem, GI tract, for an adult.. Due to the insignificant doses involved,' detailed annual doses due to swinning, boating, etc. were not . calculated. Radiation doses to individuals and the population due to radioactive effluents frun Shoreham were negligible.

Direct radiation (as neasured on quarterly TLD's) rnade no contribution to

- offsite doses based on a cmparison of 1989 dose rates with 1984 (preoperational) dose rates. The highest dose neasured was 4.8 mrem / standard month (30.~4 days) at -indicator location 6Al cmpared to the 1984. dose at the L same maximuntlocation of 5.1 mrem / standard month. Similarly, the average for-all indicator locations was 3,6 mrem / standard nonth compared to a -1984 value of. 3.9 mren/ standard nonth. 'I I e t 13 8,

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N 1 SD4IANNUAL RADIOACTIVE EFT 73JENT RELEASE REPORT ._ G - PCP & OD04 REVISIONS,' RFNP NON OCMPLIANCES AND MAJOR CHANGES TO RADIOACTIVE WASTE TRFA7 MENT SYSTD4S . 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 (ODO4) made during.the reporting period. A..& B ;There were no changes made to the PCP or ODCM during this reporting. period. ~ Action Statement c of Technical Specification 3.12.1 and a and b of Technical. Specification 3.12.2 require certain items of RD4P nonempliance to be reported in the Semiannual Radioactive Effluent Release Report. C. There were no such RTMP noncampliances during this reporting period. 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.. l 71

[ [- s 1 i SD1IANNUAL'PADIOACTIVE EFTLUINT RFJEASE REPORT-H - MISCELLANEOUS SPECIAL REPORTS 3rd and 4th Quarters of 1989 Action Statement b. of Technical Specifications 3.3.7.10 requires that when certain liquid effluent nonitoring instrumentation remains inoperable beyond a l specified period time, the reason why the inoperablility was not corrected - within that time should be explained in this report. On September 15, 1989 the RHR Heat exchanger service water radiation monitors, 1D11PNIe23A and B, were declared inoperable. 'Ihe RHR Heat Exchangers were out of service at the time and they will remain out of service as part of the effort to protect the plant in its defueled condition. 'Ihere is, therefore, no [.- potential release path and the nonitors will continue to be inoperable. (c. f.' t I ' 72 -}}