ML20114D385

Semiannual Monitoring Rept for Jan-June 1992 for Point Beach Nuclear Plant Units 1 & 2

ML20114D385
Person / Time
Site:	Point Beach
Issue date:	06/30/1992
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-92-99 VPNPD-92-293, NUDOCS 9209080154
Download: ML20114D385 (18)

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VPHPD-92-293 NRC-92-99 August 31, 1992 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mall Station P1-137 Washington, D.C. 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 SEMIANNUAL HQLIITORIN.Q REPORT IftINT BEACIL,lI.QCLEAR PLANT. UNITS 1 AND 2 Enclosed is the Semiannual Monitoring Repart for Point Beach Nuclear Plant, Units 1 and 2, for the period January 1 through June 30, 1992. This report is submitted in accordance with Technical Specification 15.7.8.4.A and contains information regarding plant releases, solid waste shipmente, new and spent fuel shipments, environmental monitoring, circulating water system operations, leak testing of sources, and other reportable items from this reporting period. Three copies of this report are provided for your convenience.

Sincerely, f

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-Vice President Nuclear Power 39 Enclosures copics to: NRC Regi'>nal Administrator, Region III NRC Resident Inspector 92090801S4 920630 040038

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I WISCONSIN ELECTRIC l SEMIANNUAL MONITORING REPORT JANUARY,1992 through JUNE,1992 I POWER COMPANY I

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1 l emen I This Sensiannual Monitoring Report for the period of January 1,1992, through Juno 30,1992, is submitted in accordance with Point Beach fJuclear Plant Unit fJos.1 and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50-266 and 50-301 tor Facility Operation License Nos. DPR 24 and DPR 27, respectively.

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TABLE OF CONTEfJTS r

L Ecttinn Iule Pane l 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 l

3.0 Radioactive Solid Waste Shipments 8 4.0 New and Spent Fuel Shipments 8 5.0 Radiolocical Environmental Monitonny 8 0.0 Nonradioactive Chemical Releases 13 7.0 Circulating Water System Operation 13 8.0 Leak Testino of Radioactive Sources 14 9.0 M;scellaneous Reporting Requirements 14 1

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SEMIANNUA1, MONITORING REPORT

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January 1, 1992 to June 30, 1992 L

L0 P1ALOMILYLhlWllLFIMMFM The total radioactive liquid release, excludir.g tritium f or this reporting period, was 9.68h 02 curien. This included 2.00E-4 curies in procevoed radioactive wanto and prin,ary coo'.t nt system 1<tdown, 3.50E-04 curies in Unit 1 steam generator blowdown, 9.59E 02 eurien in Unit 2 steam generator blowdown ari 3.35E 04 cution in retention pond effluent, The total tritium release for this reporting period was 1.9')E+02 curies.

Thio included 1.96E d2 curien in processed radioactive waute and ptiteary coolant system letdown, 1.09E402 curion in Unit i steam generator blowdown, 9.73E 01 curies in Unit 2 uteam generator blowdown and 4.01E-01 curieu in I retention pond effluent.

1.1 CirntlatJng_ Epf,a Wadicnittliddriundzma ty 1.1.1 P.eleases During Current Reporting Period Eadioactive liquid releaser, via the circulating water discharge are surwarized by individual cource, total and equivalene curie telease on a monthly basis and presented in Tablo 1*1.

1.1.2 Addit ions to Pr aviot,a Semiannual Monitoring Report I The f ollowing iniortnation was not available at the time of the previous report preparation and should be added to Table 1-1 of the Semiannual M:nitoring Report for July 1 1991, through Decernber ?l, 1991. Please note that the average diluted discharge concentration of Strontium for the month of October 1991 was incorrectly reported as 5.40h 05 ;.C1/cc. The correct value is 1.7E 13 pCi/cc.

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1.2 1EntoniC._CQtnQniLLen_gl _C_iIrilaLin1_.KAttL D.iECh a L920 1.2.1 Releasen During Current Reporting Period The isotopic composition of circulating water discharges during the current reporting period is presented in Table 1-2.

1.2.2 Mditions to Pr evious Semiannual Monitoring Report The following informatinn was not available at the time I of report preparation and chould be added to Table 1-2 of the Semiannual Monitoring Report for July 1, 1991, thrcugh December 31, 1991.

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I Sr-89 (Ci) (MDA < tCA 2.5E-04 Sr 90 (C1) 1.1E-05 (MDA 9.3E-05

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1.3 Euhnq_i.J_y_1_Airdystem Rglgeses of Trilipa 1.3.1 Releases During Current Reporting Period The raleases of tritium via the subsoil drain system I during the current reporting period is presented in Table 1-3.

TABLE 1-3 StT8 SOIL SYSTEM DRAINS - TRIT 1UM

SUMMARY

January 1, 1992 through June 30, 1992 fief 1_. QUELL 2I E-1 EL1 S. -l 12LalE I

S __1.Q II- 3 (pCi/ce) (MDA < tOA <MDA <!CA Ave. Flow (gpd) 2.36E+04 2.18E403 22 1.52E404 22.29Ild_QUAlt1E

!!-3 (pCi/ce) <!CA (MDA No Sample <MDA Ave. Flow (gpd) 1.16E+03 8.91E+03 No Flow 4.29E+02 Semiannutil Total.g Total Releaned (C1) (MDh <MDA MDA 1A < tCA Total Flow (gals) 2.2SE+06 1.01E+06 4.00E+03 42E+06 4.6BE+06 I

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Trace amounts of radionuclides rnay be land applied with eewage sludgte on various Department of Natural Resources approved Wiuconsin Electric Power Company propetities currounding the Point Beach Nuclear Plant in accord.snce with approved methodologies pursuant to 10 CFR 20.302. The amounts discharged in the sowage

' during this reporting period are presented in iable 1-4. Please note ti.at the volume of land applied sewage aladge was

( incorrectly reported as 23,100 gallons for the period July 2,

( 1991 through December 31, 1991. The correct volume is 13,100 gallons.

TADLE l 4 SEWAGE SLUDGE IJJJD APPLICAT iJNS January 1, 1991 through June 30, 1992 QAlf_QLlDR1lIi!LtIf2D Qall.CD.fl SlLS h?_Li'Lill_11112MRIlld1

= June 15, 1992 13,800 PB-02 (MDA 2.0 Eld 11QhCIIVE AIEI10EliE RELEASIS I The release paths contributing to radicactive airborne release totals during this reporting period were the auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit 1 containment purge stack, Unit 2 containment purge stack, combined air I ejector decay duct exhaust tand turbine building ventilation exhaust.

There were two gau decay tank reletoes curing this reporting period. ,

r 2.1 Eading c t 1 y e Ai than1LEf.lenne_.lumary 2.1.1 Release During Current Reporting Deriod l Radioactivity released in airborne effluent for the current reporting period are summarized in Table 2-1.

2.1.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the lost report preparrtion and should be added to lF Table 2-1 of the Semiannual Monitoring Report for July 1, 1991 through December 31, 1991, 6-MONTH QCI HQY Il!EC ..IDIhk.

Strontium (Ci) <MDA dtDL <!CA dDA 2.2 lEQ.trEir_ldr.D2IDLEe1e a se B 2.2.1 Releases During Current Reporting Period lp The mcnthly isotopic airborne releases for the current reporting period are presented in Table 2+2.

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2.2,2 Ad. lit. ions to Previous Semiannual Monitoring Pepcrt The following information was not available at the time of previous repcrt preparation and should be added to Table 2-2 of the Semiannual toonitoring Rnport, covering the period July 1, 1991, thr ough Deceruber 31, 1991.

6-MONTH W1 U2.Y Of.C _{Wd_t_

Sr- 89 (Ci) dDA cMDA eMDA < tOA Sr-90(Ci) dCA <!CA (MDA < tCA 3.0 PA21CXTJJE_XDLJ1LWAHEEJ PMEttrH Selid wastes shipped f or burial during titi' 'eporting pericd were as .

folicwo:

DATE OF SHIFMENT VOLUME TO7AL ACTIVITY TQ JiUBJAh _ .1GTHIC EEXII ispadar) ERIrd SLTJE 3/13/92 120.3 (S) 3.39E+02 Barnwell SC

, 3/19/92 240.3 (1) 1.04E 01 Barnwell SC 3/19/32 428.3 (1) 1.83E+00 Barnwell SC 3/25/92 48.0 (3) 1.8cE 02 Barr.well SC 3/26/97 48.0 (3) 7.00E-03 3arnwel2. SC 3/20/92 6.2 (1) 3.10E 02 Barnwell SC 4/10/92 180.1 (4) 2.05E+31 Barnwell SC 4 / f.0 / 92 13.8 (3) 1.00E-02 Harnwell SC

~lr 5/11/92 100.1 (2) 1.74E+00 Barnwell SC S/15/92 140.9 (1) 1.40E-02 Barnwell SC 5/16/92 322.2 s1) 9.SCE-04 eArnwell SC S/10/92 7. 31. G (5) 1.74E-01 Bernwell SC j u 5/19/92 180.1 (2) t,74E+00 Barnwell SC 5/21/92 85.2 (1) 1.00E-05 Barnwell SC 6/17/92 94.0 (3) 5.32E-02 Barnwell SC lI 6/20/92 4.2 I3) 2,70E 03 Barnwell SC 6/29/32 66.0 (3) 2.60E-03 Ba rnwe'. . SC E/30/92 93,0 (3) 1.62E 02 ba:nwell SC TOTAL 2382.3 3.65E+02 (1) D r/* Active Waste (2) "vaporator Concentrates j (3) Scrap Matal

[ (4) Encapsulated Filtera (5) Resin Beads 4.0 JEW ND_ EEERIEEfdiI.DIElT,TS AND RSCElGH During this reporting period, a total of ~9 new D el assemblies were 1 received f rom Westinghouse l's ectric Corpo. stion ior Unit 1. The new l fuel assemblies received for Unit 1 were used for the Spring 1992

_l refueling. .

There were no opent fuel chipments made f rom Poir;' Beach I'uclea: Plant A during this reporting period.

5.0 RAJIp2<QCdCAk E!E1F074UIAk..tt2HI.I.QRWa 5.1 Introduction Tln results in this Semiannual Report are presented in a new format which now in available because of software changen made by the analytical laboratory contracted to do the REMP analysec.

The new software no lenger reports results below the LLD as less than the specifie i LLD value. Instead, the results are reported 9

directly as measured, including negative and zero salues. This eliminates the distortion of the results and long-term trendn which occurs when the LLD is used to censor results that are below t.ae LLD. This reporting convention follows thet recorrmended in Health Physica Societ y ComW ttee Report HPSR-1

'1980) released as document EPA 520/1-80-012.

~

The RSMP results are presented in Table 5.1. This table contrins the following infurmation:

Sample: the type of the sacp)e medium

=

Description:

the type of measurement LLr: th A_prip3,1 lowv limit of detection E N: the number of samt i analyzed Low: the 1. west measures slue i its arsociated 2e

' counting error Average: the average value i the standard deviation of N

~ -

samples High: the highest measured value i its associated 20 m counting error 'e Uni t r. : the units of measurement c a

Additional information also in preceited in Table 5.1,

. Not all ,

of the results in Table 5.1 are required by the PBNP radiological l

effluent technical specificationn (RETS) Non-RETS items .nd (

values are noted by an asterisk P). For certain analyses. an

LLD which is lower than that required by RETS is used. For these analysen, ooth LLDs are listed with the RETS LLD given in parentheses. Occasicdally, anomaloun rasults are obteined which lie tiell outside of the range of expected values. If, upon investigation, thene values are found not to be the result of PLNP Operations they will not be listed in the table. In this l case, the highest reported value will be footnoted and the I omitted value discu; sed in the narrative portion of this section.

__ 5.0 Discession i Radiological environmental monitoring cc.iducted at the Point

Beach Nuclear Plant from January 1, 1L92 through June 30, 1992 conciated of air filtern, milk, lake water, well water, soil, q fish, shcreline sediments, algae vegetation, and TLDs. g Five new TLD siten were added in January, E-28 through E-32.

These uites were added to increase the coverage of sectors within a one (1) mile radius of PBNP. All TTD results, except one, for I I the reporting period were within the normal range. An anomalous value of 13,03 1 0.08 mR/7 days was obtained for the second quarter at site E-32. This value was not used ir calculating the average TLD value. Results from two sites within 1600 feet of E-32 were within the normal range found in previcua quarters.

. Ocmparison of quarterly noble gas effluent indicate, that the amounts released during the second quarter are comparable to dg those for the first quarter when no high TLD value occurred at E-32. Therefore, it is concluded that the ancmaly did not result from PBNF operations.

The analyses for individual radienuclides in environmental samples-doea not reveal any unexpected results. Measured concentratione of individual radionuclides occur as positive and negative values scattered arocnd zero, The positivo values are unually smaller t+tv their associated errer. Also, for radio-nuclides such as I-131 and Sr-89 with positive values in milk and water, the reported concentrations f all within the range of results obtair.ed f rom tha analysis of " blanks." Typical blank values for I-131 range fi -- -0.18 a 0.19 to 0.33 1 0.12 pCi/l in milk and from -0.05 3 0.01 to 0.30 2 0.29 pCi/l in water. Sr-89 blanks ra.mc from 6.86 1 1.63 to 1.0 1 1.3 pCi/l in milk and

from 0.34 1 2.48 to 1.17 1 1.20 pCi/1 in water. Blank values have not been subtracted f rcra the result s presented in Table 5.1.

Except for a few rsdionuclides, the measured concentrations are not statistically different from zero and are less than the LI.D.

Tbs exceptions are Sr-90 and Cs 137 which continue to persist du

) milk, water, sediment, fish, algae, vegetation. and soil. These radionuclides routinely occur in environmental samples collected around the world. The occurrence of these radionuclides in the environment is attributable to the lar.je scale atmospheric weapons tenth of the 1960's and to the Chernobyl acetdent. The only result attributable to PBNP discharges is tne 845 1 84 pCi/l H-3 concentration measured in the dischage canal. This concent ation is four ordern of magnitude lower than the MPC cf 1E-03 pCi/ml.

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> J, 5,0 I!Q1Lfg!IQACIIVE CHOilCAL PELETE 6.1 ,;cheduled Chemjral Waste Pelgases*

Scheduled chemical waste releases to the circulating water system

^

from January 1, 1992. to June 30, 1992, included 5.30E+06 gallons of neutralized wastewater- The wastewater contained 5.96E+02 pounds of suspended solids and 5.10E+05 pounds of dissolved I' solids.

Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralising tanks.

6.2 liiArallaneous Chemical Waste Relee.pgg* ,

Miscellaneous chemical vaste releases from the retention pond (based on effluent ane?vses) to the circulating water for January 1, 1992, to June 30, 1992, included 1.89E+07 gallons cf clarified wastewater. The wastewater contained 2.21E+03 pounds of suspended solids.

I-

• Miacellaneous chemical waste released directly to the circulating water, based on amount of chemicals used for January 1, 1992, to June 30, 1992, included 2.66E+04 pounds of

~I Hodium bisulfite and 2.54E+04 pounds of sodium hypochlorite.

7,0 QlEfRL3 TING WilTEP,P SYSTEM OPERATIQ1!

.I The circulating water system operation during this reporting period for tw .da of plant operation is described in Tabls 7-1.

~

TABLE 7-1 CIRCULATING KATER SYSTEM OPERATION January 1, 1992 to June 30, 1992 JAN EER life APR l'J tY JUN Average Volume Cooling U1 282.2 282.2 313.7 408.8* 251.1* 430.8*

. Water Discharge .

- (Million gal / day) *

• U2 282.2 282.2 318.7 .481.6 502.3 491.1 Average Cooling Water U1 37 37 37 40* 47* 52*

Intake Temperature (Degrees F) U2 37 37 37 41 46 52 Average Cooling Water' U1 69 68 66 62* 4?* 70*

Discharge Temperature (Degrees Fi U2 70 58 66 60 65 72 Average Ambient Lake

. Temperature (Degrees F) 35 35 36 41 45 51

(* Unit 3. refueling shutdown from April.11, 1992 to June 5, 1992)

(**For daya with cooling water discharge flow)

LI LI

+.

13

.1 .

8.0 LE/2, TE31Jft1 OF PAfziQsCTT.{E SOUR.CES I~

L During this reporting period, all applicable sealed radioactive sources were leak tested in accordance with Technical Specification 15.4.12.

Leak test results .are all <0.005 pC1.

I' L 9.0 UlSff1LffEOUS REPORTING REOUIREMENTS 9.1 f;gYiE19DLto the PBNP Q{fiee ')2RCalcp.1atinD_liaHyaJm1,QRCli}._ and P.Lui.qn Control Pr.qgram ( PC P].

No revisions were made to either the ODCM, or the PCP during this reporting period. The Environmental Manual 'as been revised and submitted for approval.

9.2 Inic,;rlaboratory Comnarisor. Procram The analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.

9.3 psey4Ations f rom Sp3.nifi.esLynvironmentn]._sn;rple_Tvt,es. L_qsatigng.

, and FEeauencier Sample types, sampling locations, and collection frequencies complied with Technical Specification 15.7.7.A during this reporting period.

9.4 Spmmarv of UDagilievable_ Mcified Environm9D133_LLDA All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during this sampling period. )

l  !< . 5 Epecial Cirpumatanggg No special circumstances report regarding operation of the i

explosive gas monitor for the vaste gas holdup system was needed durinn this reporting period.

I .

1 I

I I

4 14