ML20238A500

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Semiannual Radioactive Effluent Release Rept,First & Second Quarters of 1987
ML20238A500
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/30/1987
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20238A498 List:
References
NUDOCS 8708310100
Download: ML20238A500 (15)
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'l SEMIANNUAL RADIOACTIVE EFFLUENT- k RELEASE REPORT I i

.lst'and 2nd Quarters'of-1987 Facility: Shoreham Nuclear Power Station, Unit 1 Licensee: Long Island Lighting Company, Inc.. .

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TABLE OF CONTENTS i

Section Page, Introduction 1 A. Supplemental Information 1 B. Gaseous 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 14 i

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

These sections will appear in the next report, due 60 days after 1 January 1, 1988, and will encompass all of 1987.

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B708310100 870828 PDR ADOCM 05000322 R PDR ,

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. Introduction The Shoreham Nuclear Power Station (SN?S) conducted testing below 5% power between 5-26-87 and 6-8-87, and was shutde'"n for the remainder of the first half ,

of 1987.

A.- SUPPLEMENTAL INFORMATION

1. Regulatory Limits i

Shoreham's effluent regulatory limits are defined in Facility Operating {

License NPF-36, Shoreham Nuclear Power Station, Appendix A, Technical l Specifications. j a) Limits for gaseous effluents and nobic gases are covered by Technical Specifications 3.11.2.1 and 3.11.2.2.

b&c) Iodines and particulate with half-lifes greater than 8 days in gaseous effluents are addressed in Technical Specifications i 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, the following radionuclides in liquid effluents had typical minimum detectable activities of:

Cr-51 1.9 E-07 pCi/ml Co-58 6.9 E-08 pCi/ml Zr-95 4.1 E-08 pCi/ml Nb-95 2.7 E-08 pCi/ml Tc-99m 1.7 E-08 pCi/ml Ba-140 1.1 E-07 pCi/ml La-140 2.5 E-08 pCi/ml Mn-54 3.4 E-08 pCi/ml The following radionuclides in gaseous effluents had typical minimum detectable activities of:

Kr-85 2.3 E-11 pCi/cc Kr-85m 5.5 E-14 pCi/cc Xe-135 5.4 E-14 pCi/cc I-131 5.4 E-14 pCi/cc I-133 5.6 E-14 pC1/cc I-135 2.5 E-13 pCi/cc Ba-140 1.9 E-13 pCi/cc La-140 6.1 E-14 pCi/cc i

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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 isotopes above minimum detectable activities were measured in I gaseous effluents. Therefore, there is no reportable average energy for this time period.
4. Measurements and Approximations of Total Radioactivity a-d) Samples were collect'ed 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 Germanium detector. A liquid scintillation counter was used to analyze for H3, Fe-55 and Sr-89,90. Samples analyzed for iron and strontium underwent 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 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 esti" ate 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 level 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%. j i

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5. Batch Releases 1 a) Liquid 1st quarter 2nd Quarter
1. Nursber of batches 50 77
2. Total Time (minutes) 7891 11357
3. Maximum Time (minutes) 220 185 ,
4. Average Time (minutes) 158 147
5. Minimum Time (minutes) 18 5
6. Average Flow (gpm) 2.14 E+05 3.37E+05 (Dilution) b) Gaseous - None
6. Abnormal Releases a) Liquid - None b) Gaseous - None I

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i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT B - CASEOUS EFFLUENTS 1st and 2nd Quarters of 1987 All samples of gaseous effluents were analyzed and determined to be at or below minimum detectable activities (MDA) 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 1C.

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

1987 Unit Qwanet Owener Est. Tow 1 2 E rrW. %

A. Fision & activation pses i

1. Total release Ci E . E . E
2. Average release rate for period uCi/see . E- . E
3. Percent of Technical specification limit M E E]

B. Iodines

1. Total iodine.131 Ci . E . E . E
2. Average relcaw rate for period. uCi/uc . E . E
3. Percent of technical specification liinit  % . E . E C. Particulate -
l. Particulate with halflives >8 days Ci . E . E . E
2. Average release rate for period uCi/sec . E . E
3. Percent of technical specification lirrut  % . E . E .
4. Gross alpha radioactivity Ci . E . E  !

D. Tritium

1. Total release Ci . E . E- -E

. 2. Average release rate for period uCi/see . E . E_

3. Percent of technical specification hrnit  % . E .

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TABLE 18 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-ELEVATED RELEASE 1987 CONTINUOUS MODE 8ATCH MODE Nucluses Reisesed Unit Quener Quener Quener 1 2 3 Quene' 2

1. Fission pass
4 krypton 45 Ci . E . E . E . E krypton 45m Ci . E . E . E . E krypton 87 Ci . E . E . E . E krypton 48 Ci . E . E . E . E xenon.133 Ci . E . E . E . E xenon.135 C . E' . E . E . E i menon.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 i Total for period Ci . E . E . E . E
2. lodines iodine.131 Ci . E . E . E . E iodine.133 Cs . E . E . E . E iodine.135 Ci . E . E . E . E Total for period Ci . E . E . E . E
3. Particulate i t .

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

. cesium.134 Ci . E . E . E . E cesium.137 Ci . E . E . E . E barium lanthanum ITO Ci . E . E . E . E Others (specify) " Ci . E . E . E . E Ci . E . E . E . E C . E . E . E . I unidentified Ci . E . E . E . E TABLE 1C j EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES 1987 CONTINU0US MODE BATCH MODE welio., nei e unit oneser . oaner2 1 0""*'l 0 "i }

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1. Fision gases krypton.85 Ci E

. . E . E E krypt on.65m Ci E

. . E . E E krypt on.87 Ci E

. . E E E l krypton 88 Ci . E . E . E . E menon.133 Ci E E

. . . E . E xenon.135 Ci E E

. . . E . E xenon.135m Ci E E E

. . . . E xenon.138

  • Ci E E E

. . . . E Others (specify) C 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. lodines iodine.131 Ci E E E

. . . . E

, iodine.133 Ci E E E

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

. . . . E Tota) for period Ci 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 C E E I

. . . E . E barium. lanthanum 140 C . 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

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l SEMIANNUAL RADIOACTIVE EFFLUENT j RELEASE REPORT C - LIQUID EFFLUENTS I 1 j l' ist and 2nd Quarters of 1987 I

Tables 2A and 2B contain information on the liquid batch releases for the first  ;

and second quarters of 1987. There were periods during the first and second l quarters when there was no circulating water and dilution was by service water  ;

only. There were no radionuclides above MDA in continuous liquid releases, i therefore liquid discharge data for the continuous releases are not included in the table. Isotopes that were at or below the MDA's are not included in the Tables. Percent of applicable limit was eniculated as a sum of the fractions of individual isotopic limits instead of using the average diluted concentration.

An error in the compositing techniques used for composite samples of cont.tnuous liquid releases prior to 1987 was discovered and corrected. A review of the results has concluded that any " masked" activity would have been slight since all sample results were below MDA.

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TABLE 2A .  :

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT  !

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1987 U ut Quarter Quarter E st. Total 1 2 Error. %

A. Fisior; and activation products l

1. Total release (not including tritium, gases, alpha) Ci 3.24 E -4 2.55E_3: s 00 E .g

. 2. Average diluted concentration  !

durina period - yCi/ml 5.06 E-13 1.76E-10

3. Percent of applicable limit  % 5.05 E5 1. 28E_4 -
B. Tritium
1. Total release Ci 6.04 E_3 . E s oo E.n l
2. Average diluted concentration during period pCi/ml 9. 43 E-10 ;

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3. Percent of applicable limit 9 3.14 E-5 . E C. Dissolved and entrained gases
1. Total release - Ci . E . E . E l
2. Average diluted concentration during period pCi/ml . E . E
3. Percent of applicable limit Fe . E . E D. Gross alpha radioactivity

[ 1. Total release l Ci j . E l .

El . E l E. Volume of waste released (prior to dilution) liters 3.52 E+6 5.07 E+d 1.00 E+1 F. Volume of dil:itioriwater used during period liters ' 6.40 E+9 j 1.45 E+/p 2.ooE+1 i

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. TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUlO EFFLUENTS CONTINUOUS MODE BATCH MODE 1987 Nuclides Released - Unit Quarter Cuaner/ Quener y l Quarter2 l strontium.89 Ci \. E' . Ef . E . E E

strontium.90 Ci \. E .

17 ! . E .

E E cesium 134 Ci \. E . E . .

cesium 137 Ci \ E . E . E . E iodine.131 C .\ E . /E . E . E .

I cobalt.58 I Ci . \ E- ./E 2.87 E-4 2. 21E-4 Ci \E ./ E E 8.42E-5 cobalt.60 . .

iron.59 Ci . \E / E- . E I . E-Ci U /. E . E . E zinc.65 .

manganese.54 - Ci . 4 /. E . E 6. 36 E-6,

. chromium.51 Ci .

E\ /. E E 1.46E-6l zirconium. niobium.95 Ci . E \l . E . E . E molybdenum.99 Ci . E /i . E -. E 1.97 E.6 technetium.99m Ci . E/ \. E . E 2.18 E 6 Ci E/ \. E E . E barium. lanthanum.140 . .

cerium.141 Ci . If \. E . E . E I V Other (specify) Ci .

/E \ E . E . E ;

iron - 55 Ci . /E .\ E 3.68 E-s 2. 23 E-3 Ci ./E .\E . E . E

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Ci ./ E .\E . E . E Ci ./ E .

\E . E . E E

unidentified Ci / E .

W . E .

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Total for period (above) Ci 1

/. E .

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3.24E -4 2. 55 E-3 xenon.133 Ci / . E . E\ . E . E xenon.135 Ci / . E . E\ . E . E 1

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT D - SOLID WASTE let and 2nd Quarters of 1987

. There were no solid waste shipments during the first and second quarters of 1987. There were no irradiated fuel shipments.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT G - PCP & ODCM REVISIONS, REMP

'NON COMPLIANCES AND MAJOR CHANCES.TO RADIOACTIVE WASTE TREATMENT SYSTEMS

' According to Technical Specifications 6.9.1.7, 6.13.2a and 6.14.2a, the Semiannual Radioactive Effluent: Release Report shall include any changes to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (0DCM) made during the reporting period. The following changes and the affected pages

, ' are.hereby submitted in compliance with these requirements.

A. 1. Revision 3;of the1PCP was issued to:

a. describe solidification by a contractor only; O b., describe waste stream classification;
c. describe processing of Spent Resin Tank Waste by dewatering in a HIC;
d. . achieve consistency among administrative documents.
2. The changes to the PCP will not reduce the overall conformance of the solidified waste product to existing PCP requirements; the changes are

. clarifications of existing conditions, and processed waste is not changed.

3. The revised PCP and the document cover, indicating Review of Operations Committee (ROC) approval, follow.

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B. 1. Revision 9 of the ODCM modified backup method dose and dose rate equations for gaseous effluents to allow sample data from station vent (Panel 41) to be used when the mechanical vacuum pump is in use and the main condenser air removal pump discharge monitor (Panel 51) is out of se rvice.

2. The accuracy and reliability of the dose calculations will not be reduced since the primary method of dose calculations, the computerized method, uses Station Vent telease data to perform the same calculations.
3. The affected pages of the ODCM and the signature page, indicating ROC approval, follow.

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.

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

Technical Specification 6.15 statu,' that the Semiannual Radioactive Effluent Release Report shall include major c'anges to radioactive vaste treatment systems.

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

SEMIANNUAL RADI0 ACTIVE EFFLUENT REIEASE REPORT I

H - MISCELLANEOUS SPECIAL REPORTS ist and 2nd Quarters of 1987 A. New REMP Milk Location In the previons Semiannual Radioactive Effluent Release Report it was reported that a new milk sample location was identified but not added to the ODCM,during the reporting period. A sample from this new location was used to satisfy the December, 1986 Technical Specification requirement for a milk / leafy vegetable sample since there were no vegetables in harvest at that time. Although the new location was not added to the ODCM during the period covered by this report, samples were collected whenever available and used to satisfy the Technical Specification requirement instead of leafy vegetables.

B. Radiation Monitors Inoperable 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 reason why the inoperability was not corrected within that time should be explained in this report.

RHR Heat Exchanger Service Water Radiation Monitors 1D11-PNL-23A and B In the previous Semiannual Radioactive Effluent Release Report it was reported that the RHR heat exchanger service water radiation monitors 1D11-PNL-23A and B were declared inoperable and they remained so for more than 30 days. The solution to the problem required design modifications to the system and, due to the lead time necessary to prepare, document and implement these modifications, the inoperability was not corrected within the specified 30 day period.

A temporary modification was implemented to increase flow to the panels and the monitors were declared operable on 4/22/87. They were declared inoperable again on 5/7/87 1D11-PNL-23B was returned to service within a week but 1D11-PNL-23A remained inoperable for more than 30 days. The reason for this inoperability was a valve failure and delays in return to service testing due to a RHR heat exchanger A service water outage. Grab samples were collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analysed for radioactivity at an LLD of at least 1.0 E-7 pCi/ml, in accordance with Technical Specification requirements.

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