SNRC-1485, Semiannual Radioactive Effluent Release Rept,First & Second Quarters of 1988

Semiannual Radioactive Effluent Release Rept,First & Second Quarters of 1988

ML20153D642
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/30/1988
From:	Leonard J LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SNRC-1485, NUDOCS 8809020272
Download: ML20153D642 (15)

Text

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1st and 2nd Quarters of 1988 Facility: Shoreham Nuclear Power Station. Unft 1 Licensee Long Island Lighting Company..Inc.

TABLE OF CONTENTS Section g Introduction 1 A. Supplemental Information 1 B. Caseous Effluents 4 C. Liquid Effluents 8 D. Solid Waste 11 E. Not Required F. Not Required G. PCP and ODCM Revisions. REMP Non Compliances 12 and Major Changes to Radioactive Waste Treatment Systems H. Miscellaneous Special Reports 13

1. Section E. Radiological Impact on Man, and Section F. Meteorological Data are not required by Technical Specification to be included in this report.

l These sections will appear in the next report, due 60 days after January 1. 1989, and will encompass all of 1988 8809020272 090630 2 DR ADOCK 050 IEd aft

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l Introduction . l The Shoreham Nuclear Power Station (SNPS) received a license to operate at up to 5% power in July, 1985. Several series of tests have been conducted since then.

The plant, however, was in a cold shutdown condition for the entire first half of 1988.

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.

bac) Iodines and particulates with half-lives greater than 8 days in gaseous effluents are addressed in Technical Specifications 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 sampling and analysis program the following typical minimum detectable activities (MDA's) were achieved. These MDA's are less than the required lower limits of detection (LLD's).

Liquidt Ce-141 3.4 E-08 uCi/mi Co-58 3.9 E-08 uCi/ml Cs-137 3.2 E-08 uCi/ml Mo-99 1.9 E-08 uCi/ml Zn-65 7.4 E-08 uC1/mi Mn-54 3.7 E-08 uCi/mi Caseoust Cs-137 2.8 E-14 uCi/cc Hn-54 2.7 E-14 uCi/cc Zn-65 1.1 E-13 uCi/cc I-131 5.8 E-14 uC1/cc I-133 7.7 E-13 uCi/cc Xe-133 1.3 E-13 uCi/cc 1

2. Maximum Permissible Concentrations a-d) Maximum permissible concentrations are those specified in 10 CFR 20. Appendix B. Table II, Column 2. If an isotope is listed with values for SOLUBLE and INSOLUBLE states, 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 fission or activation gas isotopes above minimum detectable activities were measured in gaseous effluents. Therefore, there is no reportable average energy for this time period.

4. Measurements 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 types 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 Fe-55 and Sr-89,90. Samples analyzed for iron and strontium [

underwent a chemical separation prior to counting. Approved saeple 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 (LLD's) have been met. Any identifiable peaks j above background are quantified, i'

The methods above were used for batch releases. These eethods 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 (LLD's). Counting LLD's 4 reflect a two-sigma level of confidence. For liquid measurements, i a the overall error is estimated from the tank sampling error and j from counting error at values close to minimum detectable activities to be approximately 50%. I f

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S. Batch Releases a) Liquid 1st quarter 2nd Quarter

1. Number of batches 6.90 E+01 6.10 E+01

2. Total Time (minutes) 1.05 E+04 9.96 E+03

3. Maximum Time (minutes) 2.40 E+02 3.84 E+02

4. Average Time (minutes) 1.52 E+02 1.63 E+02

5. Minimum Time (minutes) 4.40 E+01 2.70 E+01

6. Average Flow (gpm) 2.39 E+04 2.36 E+04 (Dilution) b) Gaseous - None

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

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT B - GASEOUS EFFLUENTS lat and 2nd Quarters of 1988 All samples of gaseous effluents were analyzed and determined to be at or below minimum detectable activities (MDA's) for all radionuclides listed in Shoreham's Technical Specifications. These MDA's 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 lA IB or IC.

Composite sample results for the second quarter of this reporting period are not available at this time. First quarter composite results were used for the second quarter. 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.

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TAB LE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1988 G ASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES unit caner o ner tii. Tow 1 2 E nw. s A. Fizkn & actintion gases

1. Total teleau Ci . E . E . E ,

2. Ayerate release rate for unod pCi/tec . E . E

3. Pesceni of Technical specincatior, bmit  % . E . E B. lodines

1. Tot al iodine.131 Ci . E . E . E

2. Averate releau rate for period

~

FC /sec . E . E' Descent of technica] speci0 cation litnit  % . E . ER C. Particulates

~

1. Particulates with halflives >S days Ci E E E

2. Age releau rate for pened MCilwe E E 37Percentif technical specincition brmt  % E E~

47 Cross alpha ra6oactinty C E E ~

D. Tritiurn

1. Total teleau Ci . E . E . E l 2. Averste release rate for pened FCilwe . E . E

3. Percent of technical specincation istnit 9- . E . E l

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TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1988 GASEOUS EFFLUENTS-ELEVATED RELEASE CANTINUOUS MODE S ATCH MODE Nelm Mekaw Unit ownyl Owner 2 Qwner 1 Cane,2

1. Thion paa krypton 45 Ci . E . E . E . E krypton 45m Ci . E E krypt on4_'l E_ __. EZ Ci . E . E E krypton 48 Ci E_

. E . E . E . E xenon.133 Cl E_ E

_ . . . E . E x eno n.13_5 Ci . E . _E . E_ . E menon.f35m C E E__ . . E .

EE xenon.135 C E E

. . . E . E=

Othen (specify) Ci E E

. . . E_ . E Ci . E . E . E . E

_Ci E E E E_I wudentified Ci E E E

. . . . E Totaflor penod Ci E E

. . . E . E

2. lodines iodine 131 Ci E E

. . . E . E iodine.133 C E E

. . . E . E iodine.13'$ Ci E E E

Total for period Ci

_E~

. E . E . E . E

3. Particulates .

strontium 49 Ci E E E

. . . . E strontium.90 Ci . E . E . E' . E I cesium.f)4 l C . E . E , E . E l oetium.D7 C . E~ . E . E . E ba num.la n tha.n um.f40

~

C . E . E E . .E '

Others (spe:ify) C . E . E . E . E~

C . E . E . E . E Ci . E . E~ . E . I wddentified C . E . E . E . E 6

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TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT " 88 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINU0US MODE B ATCH MODE

)

Nwelion PleWW uni Owenet i Q ue n e'2 Owen" 1 Owne' 2

1. Fision pses krypton.85 Ci E

. . E . E E krypt on.55m C E

. . E E E-krypton 87 Ci . E . E . E E krypton.85 Ci E

. . E . E . E menon.133 Ci E E

. . . E . E xenon.135 C E E

. . . E . E~

menon.135m Ci E E

. . . E . E menon.138 Ci E

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

. . . E Ci . E . E ~ . E . E~

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

. . . E

TotalTor period C E E

. . . E . E

2. lodines

! 6edine.131

' Ci . E . E . E . E io&ne.133 C . E E E

. . . E sodine.135 Ci E E

. . . E . E Total for period C E E E

. . . . E

3. Particulatn n rontium.89 Ci E E E i

nrontium 90 Ci E_

! . n . E . E' . E c40 um.134 C . E . E , E , E_

ce b um.13 *) Ci E E

. . . E . E ba n u m.la ntha num.140 Ci . E E E' Others (specify)

E__

Ci . E . E . E ,

E_

Cs . E . E . E . E Ci . E . E ,1 . E~

unidentifwd Ci . E . E . E . E 7

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l SEHIANNUAL RADI0 ACTIVE EFFLUENT r RELEASE REPORT C - LIQUID EFFLUENTS lat and 2nd Quarters of 1988 Tables 2A and 2B contain information on the liquid batch releases for the first i and second quarters of 1988. There was no circulating water during the first and second quarters so dilution was by service vatwr only. There were no radionuclides above MDA in continuous liquid releases, thnrefore. liquid >

discharge data for the continuous releases are not included in the table. .

Radionuclides that were at or below HDA. which were below the LLD's required in

• Technical Specification Table 4.11.1.1.1-1 are not included in the Tables.

Composite sample results for the second quarter are not available at this time, so the composite results for the first quarter were used for the second quarter, t When actual results are available any significant differences will be noted in  !

l supplements to this report. Due to low concentrations and resulting doses no '

significant differences between previously reported composite results and actual I results have occurred.  ;

An error was discovered in the sample location for the RHR heat exchanger  ;

j service water discharge (Reference LER 88-010). Based on previous heat -

exchanger leak rate test results and plant operating conditions. reasonable i l assurance can be provided that continuous liquid discharges were indeed below detectable activity as reported. A leak rate test will be performed and a  !

supplemental Licensee Event Report issued. [

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C TABLE 2A EFFLUENT . ASTE DISPOSt ; 3EMIANNUAL REPOR'( 1983 LIOD JENTS-SUMMATION OF ALL RELEAGES Unit Ougrier Oujrter E st. Toto Error %

A. Fission and sethation products 1.. Total release (not including tritium,

__ gases, alpha) _ Ci E 1.98 E -5 5.00 E +1

2. Average diluted concentration during period pCi/ml E- 2.22 E.-1 1

3. Percent of appbeable limit G E 2.47 E. 3 B. Tritium

1. Tot al release Ci . E- . E . E l

2. Avetage diluted concentration during period pCi/ml . E . E

3. Percent of appbeable limi; 9 . E . E

~_ C. Dissolved and entrained gases

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

2. Average diluted concentration during period _

pCi/ml . E , E l 3. Percent of appbcable limit W . E . E D. Gros.s alp [.2 radioacthity l l 1. Total release l Ci l . E l .

El . E l l

( _

l E. Volume of waste released (prior to dilution) liters E e 31 E+5 1.00 E +1 l ..

I F. Volume of dilution water used during period liters E

_g E +8 2.00 E +1 l

l l

l ')

r j

I TAB LE 2B 988 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclidn Releawd Unit Ovaner i Cwans' 2 Owaiteri Owan*'2 strontium 89 Ci _ . E . E . E . E strontium 90 Ci . E . E . E . E cesium II3[4 Ci . _ E_ . E__ . E . E~

cesium 137

~

Ci . E . E . E . E~

iodEieT3I Ci . E . E . E . E cobalt.58 Ci . E . E . E 1. 98 E-5 cobaJt.60 Ci . E , E . E . E fron.59 Ci . E , E . E . E~

rine.65 Ci _

.  !! . E . E . E~

mgan anese 54 Ci . .E . _E . E , E chromjum 5) Ci . E . 'E , E , E~

~

zirconium.nfoblum.95 Ci . E . E . E . E molybdenum.99 ~

Ci . E_ . E . E , E t techtletium 99m Ci . E . E . E' . E l

barium lanthanum 140 Ci . E . E . E , E~

cerium!f4'l Ci . E , E . E . E Other (specify) Ci . E . E . E . E___

Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E . ED I

Ci . E , E . E . E I

l unidentified C [. E .

E_ . E ._ 1, Total for period (above) Ci . E . E E 1.98 E-5 xenon.133 Ci . E . E . E . E xenon.IIS Ci . E , E . E . E 10

f t

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT D - SOLID WASTE let and 2nd Quarters of 1988 There were no solid waste shipments during the first and second quarters of 1988. There were no irradiated fuel shipments.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT G - PCP & ODCM REVISIONS REMP NON COMPLIANCES AND MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Acc.ording to Technical Specifications 6.9.1.7, 6.13.2a and 6.14.2a, the Semiannual Radioacti'e 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.

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 requires certain items of REMP noncompliance to be reported in the Semiannual Radioactive Effluent Release Report.

There were no such REMP noncompliances during this reporting period.

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

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

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE RE'JRT H - MISCELLANEOUS SPECIAL REPORTS ist and 2nd Quarters of 1988 In the previous Semiannual Radioactive Effluent Release Report it was re a>rted that a new indicator milk sample location was identified in December,1;d7.

Samples have been collected whenever available at this location, identified as 13B1, and used to satisfy the Technical Specification requirement instead of leafy vegetables. An ODCM revision is in process.

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 time, the reascn why the inoperability was not corrected within that time should be explained in this report.

On 4-21-88 the RHR heat exchanger service water radiation monitor ID11PNL-23B was declared inopersble due to a flow switch problem and remained so for greater than 30 days. In past Seuiannual Radioactive Effluent Release Reports when similar ever.ts occurred, it was reported that a design problem was found to exist in the sample line size and monitor control logic. A design modification was initiated; however, due to the lead time necessary to prepare, document and implement the modification, completion is not scheduled until 1989.

On 5-12-88 the RHR heat exchanger service water radiation monitor ID11-PNL-23A was declared inoperable due to a failed detector. The detector crystal and preamp were replaced, but a return to service surveillance could not be completed due to flow problems, and the monitor was inoperable for greater than 30 days.

Applicable Technical Specification Action Statements were implemented and temporary modifications will continue to be implemented whenever possible to allow the monitors to operate.

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SHO AM NU A POWE ST T P.O. BOX 618, NORTH COUNTRY RO AO + WADING RIVER, N.Y.11792 JOHN D. LECHARD,JR.

VICL pat $1 DENT .f;0Ctt AA OPE A ATH)NS SNRC-1485 AUG 24 'M U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Semiannual Radioactive Effluent Release Report Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 Reterence: Facility Operating License NPF-36 (Shoreham)

Gentlemen:

Enclosed is a copy of our Semiannual Radioactive Effluent Release Report covering the first and second calendar quarters of 1988.

This report was prepared according to Technical Specification 6.9.1.7. There were no solid waste shipments nor were there any changes to the Offsite Dose Calculation Manual or the Process Control Program during the period.

If you require additional information, please contact this office.

Very truly yours, l

3) nard, Dr.

P ,

'O Vice President - Nuclear Operations i

MAP /lh Enclosure

'ti cca S. Brown W. T. Russell I F. Crescenro

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