BVY-92-101, Effluent & Waste Disposal Semiannual Rept for First & Second Quarters,1992

Effluent & Waste Disposal Semiannual Rept for First & Second Quarters,1992

ML20118A380
Person / Time
Site:	Vermont Yankee
Issue date:	06/30/1992
From:	Tremblay L VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-92-101, NUDOCS 9209020232
Download: ML20118A380 (33)

Text

_ _ _ _ _

i VERMONT YANKEE -

NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301 7002 C Q;?

~

~[j N N fJsGINEE RING OFFICE 2r.uanar e

-G ..J 0 01 7 (% t,84 o ?e ewo August 28,1992 IIVY 92101 United States Nuclear Regulatory Commission A1TN: Document Control Desk Washington, DC 20555

References:

a. License .No, DPR-28 (Docket No. 50-271)

Subject:

Vermont Yankee Effluent and Waste Disposal Semiannual Report for the First and Second Quarters,1992

Dear Sir:

Enclosed herewith please find one copy of the Vennont Yankee Nuclear Power Corporation subject trport. This repon covers the period beginning January 1,1992 and ending June 30,1992 and is submitted 'in.-accordance with our Technical Specification 6.7.C.I.a and 10CFR50.36a(a)(2).

We trust that the enclosed information is satisfactory; however, should you have any questions, please contact this office.

Very truly yours, VERMONT YANKEE NUCLEAR POWER ORPORATION

\t: , >p Y, Leonard A. Tremblay, Jr. V Senior Licensing Engineer cc: USNRC Region I Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager- VYNPS

\

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EFFLUINT AND WASTE DISPOSAL SEM1 ANNUAL REPORT

( FOR FIRST AND SECOND QUARTERS, 1992 VERMONT YANKEE NUC1. EAR POWER STATION l

8851R

' IAELElA VermonLYankee s

E L Llue nt_ani.Wa a1 LDis pas u LSemi ann uaLhs ra rl Eirs tand_S e c on d_ Quar.t et s ,_lLQ.2

(

GahUnk'LEfilutn1E_ __fuGGQLi0n of All.leiragxs y

Unit Quarter Quarter Est. Total 1 L EIrnr _%

(

A. Fission and Activation Gases

~~

1. Total releace C1 1.66E+03 1.32E403 1.00E+02

._2._AYe r a ge_I.e le as e_I nt e _f o r_pe r io d_uCilh e c__._L.l l Et02 li b 8Et0 L.

___J. Pe r.ncuk_pllechi_Stsculimit  %

f.

B. Iodines

^

1. Total Iodine-131 Ci 3.18E-02 3.57E-03 15.00E+01

_._.luAreta ge_ttl e a ar_IntcJntrerle d___utila c c 4 DlE:03 i 4.31 E -0A_

___li._hr e nn LoLI n c hi.J t ec2_ limiL._.  %

C. Particulates

1. Particulates with T-1/2 > 8 days C1 1.05E-02 4.57E-03 5.00E+01

2. AYcrnac._rticaan_.Ialc_tpr_ period uC1Lse d 3hE-03 5.J1E 04,_

3. Perrent of Tech. Sptc. limit i _

4. crna t alpha _tadioactivity Ci L13E-06 2. 6 4E-DL D. Tritium

1. Total release Ci 1.03E+01 4.49E+00 15.00E401 1.32E+0D 5,11E-Ol_

2 . Av e raEC_Lcl tAEt_IAltlnLDeriOL.___.uCi/. s e c

3. Parccut.9L_ Inch 2_Spcri_1imi.t  %

8851R

ZhhLLlh hrmonLlante_c EIiluent an dlasic _Di&ER_Eal_S cminnnuallernr_1.

L ElttLand_Secend_ Quarters 2_1H2 Gasenus Einutats - Elcyatedlelease

(

(1)

CCD11DnRME 11 gds Pctchlade

_RutlidtElC12aEcd Un11_ Quarter Quarter Quarter Quarter 1 2 1 2 L_Iisalen_Sasua

_ _lryat.nn-85 31 ND _ND 1*rypton-85m Ci .5.91E QQ LSSE1QO

_ Kryatsn-87 Ci 32 81E401 3.44EtQ.1

( ___ JJyttrn:BS Ci 2.22E 01 1.82E 01

_ _lenon-133 C i_ 3,301t00 1.94ttp0 Y.cngn-135 CJ _.3d2Et01 2,3111Q1

.hnnn:135m Ci 2 il5E1Q2_ _L.84E+02

_.__lenon-136_ Ci 1.HZLt03 m 3Att02 t'ni_ den 1111ed. C1 -

Totakint_ period- Ci LhhE103 1,3;E103 2a__Indines Indine-131 C1 2dlE:D2 3,DhE 03

._ Iodine __132__ C1 9.42E-02 1,25E-01__

lodine-135 C1 1.61E-01 8 311_02 _._

TotaLign,.geriod Ci _2111E--01 1. 06E--01

3. Particulaims

_ _Sirontium-89 C1 12tt1E-03 1.181-03

. . . StLQDtium-90 Ci 1.991-Q5 1.28E-05 Ccaium-134 Ci ND 11p Celiumd31 Ci. L52E-Q1 9.99E-06 Barium-lanthanumell0 t Ci 4 22E-03 1.SSE-03 Mantaneig-14 Ci ND_ 2. 70E-0.5 Chromium-51 C1 8113E-05 ND Cobal t-58 Ci ND 1.33E-06 Cabal t-60 Ci _3 8hE-QS 91 QlE-05 Ceriutit-1hl Ci l t0hE-04 fiD _ , _

Zin e-6.5 C1 2.BSE-05 ND Unidtatified C1 (1) There were no batch mode gaseous releases for this reporting period.

ND Not detected at the plant stack.

8851R

~

IAILElO

, YermenLlankes EtLluent and Wasic._Dispasal_lemtannuallersri firs Lan d_.Ees and._Qua ticIs4._1912 G a a e cua_ E fil.uen ta_ - Gr2und_lrYel_Ac1 en tir s  ;

I L

(1)

Continuous _11 ode tatshlladt l ?iuclides_Ielsas ed "nLL Quarter Quarter Quarter Quarter I 1 2 -- 1 2 id.ission_Gaa.cs Ktynton-33 Ci FD . lid l Ci 4.01E-01

__.It:ygtenzS5nt 1.36E100 Kryntan-87 C1 8d2E+00 2 dlItto YJtyntrnzSB C1 St03E+00 1 1.4.1t00 -_

I Jenon-133 Ci 7.ASE-D1 6 36Ez02

__ lensn-135 Ci LllE 00 14 10E+00 _

___lenenzl33m ti 4 JL9E Q1- Li.21E101 Xcnnn.- 138 C1 2.43E+02 6.2EE+01 Unidratiliti _.__C1 J.otaLfar_retiod . Ci AdlI102 8 41LE301 L_.lodinss ladine-131 - C1 1.1 hE:02.__ __5.J0 E-04

_ _lndine-ll3 Ci 5.BZE-02 I dQE-03 lodine-135 Ci 9.65.I-02 2.161-Q2___

_IntaLint_.ncried C1 1.h2E-01 2 -02 Llarlienlat.ts

_._.Strcatlum-8 9 Ci 12 221:02 9_.91E-t4 -

Strontium-90 Ci J .13E-05 82h2E-Ob.

Cesium-134 Ci ND ND Cesium-137 C1 12 331-05 ND

. 11arium . Lanthanum-140 Ci L12Izo3 3.331-04 J sIlum-141 Ci 1 291-0.4 ND l

l Chrsmium-51 C1 1.31E-04 fiD Zine-65 C1 1.26E-05 ND

__Manganeae-54 Ci fiD J2.011-0k (1) Th-re were no batch mode gaseous releases for this reporting period.

ND Not detected at the plant stack.

I ses1e l

l

IABLE._lD Vermont _Jankee E Lf.lu en t_.and_L sleJi s p o s a LS emiann u a LR e p ort Eirs Land Se tend _ Quat.t ers ._l??l Dastouslfiluents - tionrnwtine_ Releases F

L (1) (3)

Continuous _ Mode IatsitJ1 ode _

[

liuclides Rgleaggd Unit _ Quarter Quarter Quarter Quartet 1 _2 1 2

(

h lisalon_Sases Kryplon-85 Ci ND

[ Krynt.ca-35m Ci ND 4 d 3 E-Q 4__

Kryritn-87 C1 9.74E-01 2.31E-03__.

Kryrion-EB C1 __ iiD ld3E03_

__lenon-133 ci JiD 2.30E-04

__ lennn-135 Ci 9.62E 01 3. 83C.-f L_

Xenon-133p Ci 9.40EfD0D_ _ 6.01E-03 ,

Xenon-138 Ci_. 2.QAE3M. 2.45E-02 Unidentified Cl

__lolaLiar_ neriod Ci 3 d2EiO1  ? 32E-QL _

2. Iodings Indine:131 C1 1,DHE 04 _

odine-131 Ci lid Iodinnsl15_. Ci JiD IolaLinr_rnriod Ci 1.03E-04 3

h_Iar.ticulales Ruh.idium-89 Ci ND 1.47E-QS

... . . .Niohium-9 7 Ci ND 6.93E-Q7 Ceslum-13h Ci ND 1.63E-04 Eariu n-139 Ci ND 2 dbl-0 ft_.

Barium-lanthanum-140 Ci 3JQE-Q4 Cerium-141 Ci 9.00E-06 Unidentified Ci (1) There were no continuous mode nonroutine gaseous releases for this reporting period.

(2) The values in this table are conservative estimates of the actual releases.

(3) The release points are the plant stack and the A0G Building for the first and the second quarters, respectively.

ND Not detected at the plant stack.

8851R

IABLE 2A VensnLJankee Ef fluentandJ a s t e_Ri s po s a LS emi nunu a LRe p o rt firstand__Setend_Quatterru_1122 L Li_ quid _ Effluents - Summatica_ nf_ALLReleases

[ There were no liquid releases during the first or second quarters of 1992.

l 4

m 5

4 8851R

TMLL2B VermonLXankee Elfluentand_Ma s t elis pas aLS emiannualle rort EiraLand_lecend_ Quar.ters _1292 LiquiLE111sents_ .lionrant.ine_ Releases L  !

There were no nonroutine or accidental releases during the first or second j i quarters of 1992.

1 4

+

8851R

IAl>LE_3

, VermonLlankee ELiluent_anLWasic_Ris no taLS emiannuaLRe pstt Eirs LA.LSerond_ Quarte ri._1122 S olid_W asle_ansLlrradiateLEnel_Ehirment s A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

Unit 6-Month Est. Total hIlo_d IItcr ul _

1. Type of Waste

a. Spent resins, f11ter sludge.N evaporator m3 3.87E+01 bottoms, etc. Ci 3.10E+02 7.50E+01

b. Dry comprossible waste, contaminated m3 4.70E+01 equipmerc, etc. Ci 7.27E+00 7.50E+01

c. Irra/iated components, control rods, m3

} Ci

) ch- 4

2. Estinate of Major Nuclide Composition (By Type of Waste):

.__n. Zine - 6L  % L18 E+01 Cab. alt - 60 1 1.12E 91 Cggium - 137  % LQ2E+01 Iron - 35 .% 8.10Et00 Crsin:n - 134  % 5.40E+00

{

Manganese - 54 % 4 1QEiDD j  %

b. Iron - 55  % 6 DhEiO1 CQ bsit - 60  % 1.81E+01 2ing_- 55  % 7.70E+00 Manganese - 54 % 4.SDI+00 Cesium - 137  % 4.DDEtD0 8851R

IAE1.L3

, (Continued)

3. solid Waste Disposition:

Nwohnr_oLJ hipments dade_oL_Itanspottation 12es11nt.ttien 11 Truck Barnwell, SC B. Irrad'ated Fuel Shipments (Disposition): None C. Supple;aental inf ormation

1) Class of solid waste containers shipped: 16A (Unstable). 5A, 4B

2) Types of containers used: 9 Type A, 16 Strong-Tight Cents.iner

3) Solidification agent or absorbent: None

}

P 8851R

AM'ENDDLA EEILt'ENT AW_WAEILDISI.Q!i.61JI211tRiUAkitEECRI SupplettentaLinformatica Eiratand_Second_Quarius.32M Facilityt Vc mpn LYan k te_Nu;1e oIlf.Ke t_S t a t io n Licensee: EersenLYc uk e e_Rutic 0I_f R Ee r_C RIPo tat icn IA. Technical Specification Limits - Dose and Dose Rate Icchnicallpucifica.tirn_.and_Catexory Limit

a. Huhh_.Hasu 3.8.E.1 Tctal body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Garma air dose 5 nirad in a quarter .

3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dcse 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrud in a year

b. Ic dine-131 _.lc.d ine:133mIr111um_an d_R adionu t11de s in_f ar_ticulat elo m_With_lial_f -liyes f.irrater_lhan__B_Dayra 75' 3.8 E.1 Organ dese rate 1500 mrem /yr (

? t;.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year

c. Lisuids 3.8.B.1 Total body dose 1.5 nrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year A-1 8851P

t s' a. Fission and Activation Gases Continuous stack inoultors monitor gross Noble Gas radioactivity g released from the plant stack. 10tal Noble Gas relcase rates are calculated using this tuonitor. On days the monitor shows less than ,

(, detectable release of fission gases, a sero release is considered.

79 determine the isotopic breakdown of she releasa, samples are taktn of the Steam Jet Air Ejector, which it the source gas for the

,. re'enses. These samples are enalyr.ed by gansna spectroscopy to determitte the isotopic composition. The isotopic composition is then proportiontd to the gross releases determi'.ned from the stack

% nitor to quantify the individual isotopic releases. These are I indicated in Table 1B and the etals of Table 1A.

Beginning in the fourth quarter of 1991. grab samples were obtained f: rom the Turbine hilding roof vents. In January, c.ily Xe-135 was detected in these samples. The remainder of the <,ases indicated were calculated by ratioing the indicated Xe-13', to the other gases using the Steam Jet Air Ejector samples as mentioned above. For the remainder of this reporting period, only Cs-138 was detected in these samples. The remainder of the gases indicated were calculated by assuming Cs-138 solely irom the decay of Xe-138 and then ratioing Xe-138 to the other gases using the Steam Jet Air Ejector samples as mentioned above. These results are indicated in Table 10 and the totals of Table 1A. -

The error involved in these steps may be approximately 1100 percent.

b. lodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. Beginning in the fourth quarter of 1991, continuous particulate and charcoal samples were also taken at the Turbine Building roof vents. The filters and cartridges are normally removed weekly and are analyzed t- for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately 150 percent.

A-3

. 8851R

c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involv:d in this ample is also approximately 50 percent.

d. IJ quid Ef fluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents

1. released. For each batch, station records are retained of the

1. total activity (mci) released, concentration (uci/ml) of gross _

radioactivity, volume (liters), and approximate total quantity of watar ($1ters) used to dilute the liquid effluent prior to release to the Connecticut River.

Each batch of radioactive liquid effluent released is analyzed for gross gamma and gamma isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition tc gamma spactroscopy. l There were no liquid releasea during the reporting period.

5. Eatch Releases

a. Liquid There were no routine liquid batch releases during the reporting period.

A-4 8851R

b.

Caseous s

s There were no routine geseous batch releases during the reporting period.

l 6. Abnormal Releases

a. Liquid There were no nonroutine liquid releases during the reporting pcriod.

b. Gaseous There were two batch mode nonroutine gaseous releases during the reporting period. The total curies of radioactive materials released as a result of these two releases was conservatively .

estimated to be 3.17E+01 curies. The activity values are included in Table 1D.

A-$

8851R

j .

l APPENDIX B i

j LIQUID 110LDUP TMES Technical Specification 3.8.D.1 limits the quantity of Requiremenu radioactive material contained in any outside tank. With the

[

quantity of radioactive materi.1 in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a descripti n of k the events leading to this condition is required in the next Semiannual Etfluent Relense Report per Technical Specification 6.7.C.1.

Responset The limits of Technical Specification 3.8.D.1 were not exceeded during this reporting period, l .

1 L

B-1 8851R

/.FPDiDIX C

. RADIDACTIVE LIQUID EFFLUDiT MONITORING INSTRUMENTATION s

Ecquir.ement Radioact've liquid effluent monitoring instrumentation channels are required to be operable in accordance with T -hnical

(

Specification Table 3.9.1. If an inoperable radit>.ctive lig ad effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1, an explanation in the next Semiannuni Ef fluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1. -_

RcKPnnsc Since the requirements of Technical Specification Tabic 3.9.1 governing the operability of radioactive liquid ef fluent monitoring instrumentation were met for this reporting period, no response is required. .

C-1 8851R

< APPD4 DIX D s

, RADIOACTIVE GASEQUS EFFLUENT MONITORING INSTRtMENTATION Etquitrinrnt : Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Tabic 3.9.2. If inoperable gaseous effluent rnonitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Semiannual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.1. -

Response: Since the requirements of Technical Specification Table 3.9.:'

governing the operability of radioactive gaseous ef fluent monitoring instrumentation were met for this reporting period, no response is required.

The Turbine Building Ef fluent Sampling System was inoperable for two short intervals of time totaling seven hours approximately.

The reporting of this inoperability is not required by the Technical Specifications, but is noted here for information only.

h D-1 8851R

APPDiDIX E RADIOLOGICAL DiV1RONMDJTAL MONITORING Ph00RA'1

)

] Requirmen.t : The Radiological Environmental Monitorir.; .rogram is conducted I in accordance with Technical Specification 3.9.C. With milk samples no longer available from one or more of the sample locations required by Technical Specification Tabic 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Reports (1) identify the cause(s) of the sample (s) no longer being available. (2) identify the new location (s) for obtaining available replacement samples, and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s).

Re.spims e : Although several changes were made in the radiological environmental monitoring program as identifled in the ODCM, none were in responce to the unavailability of milk samples. These change, are described in Appendix H "Off-Site Dose Calculation Manual," of this report.

E-1 8851R

APPDJDIX T IMD USE CD; SUS J Re.quirrmeD1 A land use census is conducted in c.ccordance with Technical Specification 3.9.D. Jith a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose :enenitment than the valuew currently being calculated in Technical Specification 4.8.G.I. Technical Specification (1.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.

Etapeute The 1992 land use census was not perfortned during this repot ting

. period. It will be completed during the next reporting period (second half of 1992).

( -

(

t i

F-1 8851R

1 AFF124D1X G ikOCESS CONTROL Ph0GPJJ1 ficquirement: Technical Specification 6.12.A.1 requires that licensee l initiated changes to the Pr ocess Control Program (PCP) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

Pasp2nse: There were no licensee-initiated changes to the Process Control Progrtun durism this reporting period.

4 G-1 8851R

1 APPENDIX H OFF-SITE DOSE C' LCUIATION MANUAL E_cquirencnt: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (0DCM) he submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which +he change (s) was made effs cive.

ReAponte: In Revision 13, the licensee-initiated changes to the ODCM were Q as follows: __-

1. Doses were re-evaluated for all milk animal locations following the dise,very that milk animals at one farm were kept at a different location than previously believed.

Following the evaluation, several changes were made in the -

milk sampling program. Specif~ ally, the Miller (m-11),

Brown (m -14), and Blodgett (m-18) farms were identified as the three locations that would be used to satisfy Technical Specification 4.9.C.1. The Cayland Farm (m-15) was changed in ODCM Table 4.1 to an "unofficaal" sampling location. The Dominick Farm (IN-12) remained unchanged in the program. The same changes were made to the silage sampling locations. _

2. Seversi minor corrections were made to Table 4.1 of the ODCM. The distance to the Brown Farm ('IY-14) was corrected from 2.6 to 2.1 km, and the sector for the N. Hinsdale mixed vegetation sampling location (TC-12) was changed f rom NNE to NNW,

3. The sector designatiori f or the Vernon Pot.d fish sampling location (FH-ll) was changed from "on-site" to a more detailed footnote explanation. The sectors for the sediment sampling locations (SE-11 and SE-12) were changed from "on-site" to an actual sector designation.

H-1 8851R

1 4. Footnote (2) to Table 4.1 of the ODCM was reworded for clarification.

5. A typographical error on Table 5.2-1 was corrected.

The above-noted changes have no relationship to the performance of dose or setpoint calculations, and therefore, will not reduce the accuracy or reliability of dose or setpoint determinations.

The revised ODCM pages for the above revision are attached.

)

'l 1

1 _

i l

r L

H-2 8851R

VELMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REVISION # 13 RevLeved W $2~ E9 71 ant (Gperations Review

/ 4l2?l92 Date' cc=ittee Approved [7 se-3 d & / */d 1[92 Date Q Plant M,anager Approved !bd N / Y!8d 91 Date Serao Vice Pypsicant, perati .'s O

a e

]

THIS PAGE INTENTIONALLY LEFT SLANK Revision 13 Date 5/1/92 11 8855R d

LIST OF AFFECTED PAGES Revision No. Date Page 13 05/01/92 'l 11 09/19/91 12 til 0 03/01/84

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B C39 Revision 13 Date 5/1/92

-111-8855R e

- - - _ ~ _ _ _ _ .

Table 4.1 Radiolecical Environmental Menitcrine Statiens(I) ,

Exposure Pathway sample Lccatien Distance and/or Samole and Desicnated Ccde(2) (km)(0} Directien(5)

1. AIRECRNE (Radicicdine ated Particulate)

AP/CF-11 River Statien 1.9 SSE No. 3.3 AP/CF-12 N. Hinsdale, NH 3.5 NNW AP/CF-13 Hinsdale Substation 3.1 E AP/CF-14 Northfield, MA 11.1 SSE

[

AR/CF-15 Tyler Hill ReadC4} 3.2 WNW l AP/CF-21 Spofford Lake 16.1 NNE

2. WATERECRNE .

a. Surface WR-11 River Station 1.9 Ccwnriver Nc 3.3 HR-21 Rt. 9 Bridge 12.5 Upriver .

b. Grcund  !;G-11 Plant Well -- On-Site WG-12 Vernen Nursing Well 2.0 . SSE #

WC-22 Skibniewsky Well 14.3 N I c. Sediment SE-11 Shoraline Ocwnriver 0.8 SSE i

--' Frc= SE-12 North Stcr: C.15 E Shereline Drain Cutf111(3)

3. INGEST!CN

a. Milk TM-11 Hiller Farn 0.8 WNW l TM-12 Ocminick(5) 5.2 E IM-14 Brown Farm 2.1 5 TM-1E Gayland Far-C') 4.7 WNW/NW

, TM-18 Bicdcett Far.n 3.4 SE TM-24 Ccunty Fara 22.5 N

b. Mixed TG-11 River Station 1.9 SSE Grasses No. 3.3

TG-12 N. Hinsdale, NH 3.6 NNW l TG-13 Hinsdale Substatien 3.1 E TG-14 Northfield, MA '1.3 SSE l

TG-15 Tyler Hill Rd.<?) 3.2 WNW TG-21 Spcfford Laka 16.1 NNE i

Revision 13 Date 5 /o1/1992 4-1

(

I .', 5713R/ 20,74 ,

Table 4.1 (continuec)

Radic1cgical Environmental Henitorina Stations (l)

-Exposure Pathway Sample Location Distance and/cr Samole and Deticnated Cede (2) (km)(6) Directien(6)

c. Silage TC-11 Miller Farm 0.8 WNW {

TC-12 OcminicKCE) 5.2 E TC-14 Brewn Farm 2.1 S TC-15 Gayland Farm (4) 4.7 WNW/NW l Bicdgett Farm 3.4 SE TC-18 TC-24 County Farm 22.5 N

d. Fish Fh-11 Vernen Pond '(7) (7) l FH-21 Rt. 9 Bridge 12.5 Upriver 4 DIRECT RADIATION 9 DR-1 River Staticn 1.5 SSE No. 3.3 '

OR-2 N. Hinsdale, NH 3.9 NNW .

DR-3 Hinsdale Substatien 3.0 E DR-4 Mcrthfield, MA 11.0 SSE OR-5 Sccfford Lake 16.3 NME

.. OR-6 Vernen Scheci 0.45 WSW DR-7 Sits Ecundary 0.27 W DR-E Sita Scundary 0.25 SW OR-9 Inner Ring 2.1 N OR-10 Cutar Ring 4.6 N OR-11 Inner Ring 2.0 NNE OR-12 Cuter Ring 3.5 NH F.

. DR-13 Inner Ring 1.4 NE OR-14 Outer Ring 4.3 NE c DR-15 Inner Ring 1.a ENE -

OR-16 Outar Ring 2.9 ENE

. OR-17 Inner Ring 1.2 E

- OR-18 Outer Ring 3.0 E OR-19 Inner Ring 3.5 ESE CR-20 Outer Ring 5.3 E5E OR-21 Inner Ring 1.8 SE OR-22 Outar Ring 3.2 SE OR-23 Inner Ring 1.E SSE DR-2? Outer Ring 3.9 SSE OR-25 Inner Ring 2.0 5 Revision 13 Data 5 /01/199 2 4-2a

\

5713R/20.74

'o

,.o ,

Table 4.1 (Ednsinued)

Radioiccical Envircnmental Penitorino Statiens(I)

Exposure Pathway Sample 1.0 cation ' 01 stance and/or Samole and Designated Ceda(2) (km)(6) Directien(5)

DR-26 Outer Ring 3.7 S DR-27 Inner Ring 1.0 SSW DR-28 Outer Ring 2.2 55W DR-29 Inner Ring 0.7 WSW DR-20 Cuter Ring 2.3 .SW DR-21 Inner Ring C.B W DR-32 Cuter Ring 5.0 W5W __

DR-33 Inner Ring 0.9 WNW '

DR-34 Outer Ring 4.9 W DR-35 Inner Ring 1,4 WNW DR-36 Cuter Ring 4.7 WNW CR-27 Inner Rinc 3.0 NW DR-28 Outer Ring 7.7 NW f DR-39 Inner Ring 3.2 HNW

^

- DR-40 Cuter Ring 5.5 NNW f (I) Suple 1ccaticas are shcwn en Figur.es a.1 tc 4.6.

(2) Station Nes.10 through 19 are indicator stations. Station Nos. 20.

thrcugh 29 are control suticns (for all but the direct radiation stations).

(3) To be sampled and analyzed semiannually. -

(4) Ncn-Tech Spec statica, (5) Hcn-Tech Spec station. Sample will be collected as available.

(6) Distance and directicn frca the centar cf the Turbine Building for cirect radiation menitors; frem the plant stack for all others.

(7) Fish samples ara ecliected frca anywhere in Vernen Penc, which is adjacent to the plant (see Figure 4-1).

t l Revisten 13 Date 5 /01/1992 A-3 l

5712R/20,74

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t Fi;;c.re I.-2 F.::vbe= ental Sa= ling Locations Wid.in 5 km of Plan x

Rari.sion 13 nace 5/01/1992 b.

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A i K .

T- -

t s c a a C.

r 7

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l e 8 3 l

- 8 - - - - -

e v fa i

r 0 - - - - - - - - - - -

i l

K l

t a

l 5 e l f 1 4 5 7 4 6 8 2 8 2 5 0 R - 0 0 0 0 1 2 4 5 7 5 3 2 r 0 0 0 0 0 0 0 1 3 6 8 9 K .

2 m 9 5 3 3 9 8 4 0 - - 1 r

- 0 0 - - - - - - - - - - /

1 K

0

/

5 m e l 2 - -

i f

0 - - - - - - - - - - - t a

r D K

h d -

8 d d 4 5 d d d d d d 3 5 0 1 1

< 1 0 0 0 0 0 0 e < < 2 3 4 5 6 7 m i i h t t < < < < < < d n T < t o 4 ( c t- t t t t t 0 i 2 r <- 7 s R h h d

d f f <- < < f i

v 3

8 4 8 0 5 0 0 0 0 0 e 7 l 2 4 5 1 1 2 3 4 5 6 t R 4 I lf{IJI I!f ' l

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APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATiENT SYSTEMS n

RequireInenl: Technical Spec 3fication 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual

' Rad'.uactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Connittee.

Respanse: There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting _

period.

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APPDiDIX J ON-SITE DISPOSAL OF SEPTIC WASTE

' Requiremeitt: Off-Site Dose Calculational Manual, Appendix B requires that the dose impact due to on-site disposal of septic waste during the reporting year and from previous years be reported to the Commission in the Semiannual Radioactive Effluent Report filed after January 1, if dJsposals occur during the reporting year.

EcEp.onte : No response is required for this reporting period.

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