ML20237H153

Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1987

ML20237H153
Person / Time
Site:	Vermont Yankee
Issue date:	06/30/1987
From:	Capstick R VERMONT YANKEE NUCLEAR POWER CORP.
To:	Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
FVY-87-83, NUDOCS 8709030138
Download: ML20237H153 (23)

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l EFFLUENT AND WASTE DISPOSAL i

SEMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS, 1987 A

i l

Vermont Yankee Nuclear Power Station I

l I

4827R/18.62 l'

1

7j x l TABLE 1A J Vermont Yankee Effluent and Waste Disposal Semiannual Report l

First and Second Quarters, 1987 l

-Gaseous Effluents - Summation of All Releases Unit Quarter- Quarter- Est. Total 1 2 Error, %

'A. Fission and Activation Gases

1. T7tal release Ci- ND: ND el.00E+02'

2. A'verage release rate for period uCi/sec ND ND

3. Percent of Tech. Spec. limit (1)  % - -

.B. Iodines 1.-Total Iodine-131 Ci 8.41E-05 9.22E-04 e5.00E+01

2. Average release rate for-period uCi/sec- 1.07E-05 1.17E-04

3. Percent of Tech. Spec. limit (2)(4) % 2.33E-02 1.09E-01 C. Particulate

1. Particulate with T-1/2 > 8 days Ci- 5.14E-04 4.40E-04 5.00E+01

2. Averr-e release rate for period uCi/sec 6.54E-05 5.59E-05

3. Percent of Tech. Spec. limit  % (3) (3)

'4. Gross alpha radioactivity Ci ND ND D. Tritium

1. Total release Ci 1.26E+00 3.67E+00 e5.00E+01

2. Average release rate for period uCi/see 1.60E-01 4.28E-01

3. Percent of Tech. Spec, limit  % (3) (3)

(1) Technica1' Specification 3.8 F.1.a for gamma air dose. Percent values for Technical Specification 3.8.F.1.a for beta air dose are approximately the same.

(2) Technica1' Specification 3.8.G.1 for dose from I-131, I-133 Tritium, and radionuclides in pa~rticulate form.

(3) Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulate are included-with I-131 above in Part B.

(4).-The first and second quarter. percent of Technical Specification limits are based on conservative plant quarterly dose determinations.

ND Not detected at the plant stack.

I. 4827R/18.62

TABLE IB Vermont Yankee Effluent and Waste Disposa1' Semiannual Report First and Second Quarters, 1987 Caseous Effluents - Elevated Release (1)

Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 1.. Fission Cases

-Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 C1 - ND PC)

Xenon-133 Ci ND ND Xenon-135 Ci' ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Ci Unidentified- Ci Total for period Ci

2. Iodines Iodine-131 Ci 8.41E-05 9.22E-04

. Iodine-133 C1 1.87E-04 7.90E-04 Iodine-135 Ci ND ND Total for period Ci 2.71E-04 1.71E-03

3. Particulate Strontium-89' C1 4.17E-05 1.50E-04 Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND 6.85E-05 Barium-Lanthanum-140 Ci ND ND Cobalt-60 Ci 4.72E-04 2.21E-04 Ci Ci Unidentified Ci (1) There were no batch mode gaseous releases for this reporting period.

ND. Not detected at the plant stack.

4827R/18.62 l

TABLE 1C Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters 1987 Gaseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1987.

l 1

1 4827R/18.62 i

l

TABLE 1D Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters 1987 Gaseous Effluents - Nonroutine Releases There were no nonroutine or accidental gaseous releasts during the first or second quarters of 1987, J

4827R/18.62

TABLE 2A Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters 1987 Liquid Effluents - Nonroutine Releases There were no liquid releases during the first or second quarters of 1987.

i l

4827R/18.62 i

I

. _ _ _ . _______--____________-____D

i l

l TABLE 2B l j

1 Vermont Yankee j Effluent and Waste Disposal Semiannual Report First and Second Quarters 1987 i Liquid Effluents - Nonroutine Releases There were no nonroutine or accidental releases during the first or second quarters of-1987.

i 1

4827R/18.62 l

l l

TABLE 3 Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1987 i Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

Unit- 6-Month Est. Total Period Error, %

ic Type of Waste

a. Spent resins, filter sludges, evaporator L

m3 4.37E+01 bottoms, etc. C1 7.33E+01 27.50E+01

b. Dry compressible waste, contaminated m3 2.97E+01 equipment, etc. Ci 3.44E+00 z7.50E+01

c. Irradiated components, control rods, m3 6.34E-01 etc. Ci 1.18E+01 27.50E+01 2, Estimate of Major Nuclide Composition (By Type of Waste)

a. Cobalt-60  % 3.41E+01- Antimony-113  % 1.70E-01 Zine-65  % 2.13E+01 Iodine-131  % 1.20E-01 Cesium-137  % 1.48E+01 b. Iron-55  % 7.29E+01 Iron-55  % 1.05E+01 Cobalt-60  % 2.09E+01 Manganese-54  % 6.11E+00 Manganese-54  % 3.20E+00  ;

Zine-65  % 2.37E+00 Niobium-95  % 4.15E+00 I

Zirconium-95  % 3.64E+00 Cesium-137  % 2.40E-01 Nickel-63  % 2.19E+00 Hydrogen-3  % 2.00E-01 Cobalt-58  % 1.47E+00 c. Cobalt-60  % 5.66E+01 Hydrogen-3  % 3.60E-01 Iron-55  % 3.85E+01 Iron-59  % 2.90E-01 Manganese-54  % 2.59E+00 Cesium-134  % 2.30E-01 Nickel-63  % 2.25E+00 ,

I Carbon-14  % 2.10E-01 Nickel-59  % 4.00E-02 Cerium-144  % 2.10E-01  % __

3. Solid Waste Disposition l Number of Shipments Mode of Transportation Destination 11 Truck Barnwell, SC 1 Truck Richland, WA B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information

. 1) Class of solid waste containers shipped: 4A (Unstable), 7A, 1C

2) Types of containers used: 9 Type A, 2 Type B, 1 Strong-Tight Container

3) Solidification agent or absorbant: None 4837R/18.62

l APPENDIX A i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT'

. Supplemental Information

l. First and Second Quarters, 1987 Facilitp: Vermont Yankee Nuclear Power Station

' Licensee: Vermont Yankee Nuclear Power Corporation

~1AL Technical Specification' Limits - Dose and. Dose Rate ,

Technical' Specification and Catem ory Limit

a. Noble Cases.

3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 . Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year 1

-3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20' mrad in a year

b. Iodine-131. Iodine-133. Tritium and Radionuclides

.in Particulate Form With Half-Lives Greater Than 8 Days

~

. 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose' 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a' year

c. Liquids 3.8.B.1 Total body dose 1.5 mrem 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 4827R/18.62

k Technica1' Specification Limits - Concentration

~

2A.

. Technical Specification and Category Limit 1 a.- . Noble Gases. No MPC limits

b. Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days: No MPC limits G

c. . Liquids 3.8.A.1 Total fraction of MFC

. excluding noble gases (10CFR20 Appendix B,

' Table'II.-Column 2): 11.0

.3.8.A.1 . Total noble gas concentration: 12E-04 uCi/cc

3. Average Energy Provided below are the average energy (E) of the radionuclides mixture in releases of fission and activation gases, if applicable.

A

a. Average gamma energy: 1st Quarter 1.90E+00 MeV/ dis 2nd Quarter 9.70E-01 MeV/ dis

b. ' Average beta energy: Not Applicable

4. . Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total t

. radioactivity in ef'fluents and the methods used to determine radionuclides

+.

composition.

A-2 4827R/18.62.

CE_______________-__ .

a.. Fission and Activation Gases 1

Daily samples'are drawn at the discharge of the air ejector. )

i

-Isotopic-breakdown of the releases are determined from these samples. A logarithmic chart of the stack gas monitor-is read- 1 daily to determine the gross release rate. At the very low release 1 rates normally encountered during operation with the augmented

)j off-gas system the error of release rates may be approximately 1100 percent.

l

b. Iodines

. Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and' cartridge are removed weekly (if releases are less than 4 percent of the Tech Spec limit), or daily (if they are greater

~

than 4 percent of the limit), and are analyzed for radioiodine 131, 132, 133, 134, and 135. The error involved in these steps may be approximately 250 percent.

c. Particul ates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately !50 percent.

d. Liquid Effluents 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 released. For each batch, station records are retained of the total activity (mci) released, concentration (uC1/ml) of. gross A-3 4827R/18.62 i

l l

i I

radioactivity, volume (liters), and approximate total quantity of j l

water (liters) used to dilute the liquid effluent prior to release i i

to the Connecticut River. )

1 i

Each batch of radioactive liquid effluent released is analyzed for I 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 to gamma spectroscopy.

There were no liquid releases during the reporting period.

5. Batch Releases

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

b. Gaseous There were no routine gaseous batch releases during the reporting period.

6. Abnormal Releases

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

b. Gaseous There were no nonroutine gaseous releases during the reporting period.

A-4 l

4827R/18.62

k APPENDIX B LIQUID HOLDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next l

Semiannual Effluent Release Report per Technical Specification l 6.7.C.1.

Response: The limits of Technical Specification 3.8.D.1 were not exceeded during this reporting period.

l l

B-1 4827R/18.62

___________i _ _

I

, 1 l

APPENDIX C f RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid 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 Semiannual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1.

Response: Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, i no response is required.

C-1 i j

4827R/18.62 l l

______ __ l

i APPENDIX D RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l i

Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.2. If inoperable gaseous effluent monitoring 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 3.9.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.

l i

l D-1 4837R/18.62

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement: The Radiological Environmental Monitoring Program is conducted 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 Table 3.9.3 Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report:  ;

(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).

Response: There were no changes in the milk sampling locations durin6 this reporting period.

l E-1 4827R/18.62

APPENDIX F LAND USE CENSUS Requirement: A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a locatLon(s) which yields at least a 20 percent greater dose or ,

dose commitment than the values currently be'ing calcula'ted in d' i

^

Technical Specification 4.8.G.1, Technical Specification 6.7.0.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.  ; l Response: Tbe 1987 land use census was not performed during this reporting period.

)

i ')

i T-1 i

4827R/18.62 J

m 84Huum rasamuuur'7fs 43

't ., 1

+

', \ l

~

APPENDIX G '

PROCESS CONTROL PROGRAM s,

Requirement: Technical Specification 6.12.A.1 requires that licensee , i \.

Initiated changes to the Procese. Control Program (PCP) be ' 'x )! ~h

- b '-

submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

Response: There was no licensee initiated change (s) to the Process Control Program during this reporting period.

l r.

l 1

G-1 4827R/18.62

,,- m, , r .i.

.s -.- - w ..

S t

A (-

tj" "t

\\$ ,

U ['

' L '< t b

- (' '\ ) +o y

. s APPENDIX H

~,

k 4 t.o.

L , [' ,

^

% .\ . 0FF-SITE DOSE CALCULATION MANUAL s ,

s-3 .~t -

YL ,

, s Requirement: Technical Specification 6.13.A.1 requites that licensee initiated changes to the 011' Site Do[e Calculation Manual (0DCM) 7 besubmI'ttedtotheCoumissionintheSemiannualRadioactive

-\ g Effluent Release Report for the perf.od in which the change (s) -

vas made eff$ drive. ,

'; i hesp;nse: *here were no changes made to the ODCM during this reporting pariod.

s

\.

Iowever, Page 5-22 was inadvertently omitted in Revision 3 to tne ODCM which wats included in the 3rd and 4th Quarter 1986 Report. Page 5-22 is included in this section.

b H-1 i 4827R/18.62 i

017/150A and 5.2.3 Steam Jet Air Ejector (SJAE) Noble Gas Activity Monitors 17/150B1 The steam jet air ejector noble gas activity monitors are shown on _

Figure 6-2. -

5.2.2.1 Method to Determine the Setpoints of the Steam Jet Air Ejector Of foas Activity Monitors (17/150A and _1J/15081 The SJAE noble gas activity monitor response in counts per minute at the limiting release rate is the setpoint, denoted RSJAE p , and is determined as follows:

g SJAE 1

= 1.6E+05 S spt 0 F (m/hr) (1,ti) (mR-ce hr pCi ) (sec) cc See where:

g SJAE = Response of the monitor at the limiting release rate (mR/hr) spt 1.6E+05 Limiting release rate for the SJAE specified in Technical Specification 3.8.K.1 (pEi/sec)

S

= uetector counting efficiency from the most recent 9 calibration ((rtR/hr)/(uti/cc))

F

= SJAE gaseous discharge flow (cC/seC) 5.2.2.2 Basis for the SJAE Noble Gas Activity Monitor Setpoint Th'e SJAE noble gas activity monitor setpoint must ensure that Technical The derivation of Equation 5-21 is Specification 3.8.K.1 is not exceeded.

straightf orvard. Simply taking equation 5-16 and substituting the limiting release rate at the SJAE for h yields Equation 5-21, the setpoint equation f or the SJAE noble gas activity monitor.

JUN 1 5 1987 Aporoved ay: @"

Revision 3Date 5-22 (/

APPENDIX I RADIOACTIVE LIQUID, GASE0US, AND SOLID WASTE TREATMENT SYSTEMS Requirement: Technical Specification 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 Radioactive Eifluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response: There vere no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period.

l I-1 4827R/18.62

VERMONT YANKEE NUCLEAR-POWER CORPORATION

.. ~, RD 5, Box 169 Ferry Road, Brattleboro, VT 05301 ,,g ,o y ENGINEERING OFFICE N 1671 WORCESTER ROAD

• FRAMINGHAM, MASS ACHUSETTS 01701 e TELEPHONE 617 872 8100 August 28, 1987 FVY 87-83 l 1

United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. William T. Russell Regional Administrator

Reference:

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

Subject:

Vermont' Yankee Nuclear Power Station Effluent and Waste Disposal Semiannual Report for First and Second Quarters, 1987 ,

)

Dear Sir:

Enclosed herewith please find one copy of the subject Vermont Yankee Nuclear Power Corporation semiannual report. This report covers ~the period beginning January 1, 1987 and ending June 30, 1987, and is submitted in accordance with our Technical Specifications 6.7.C.1.a.

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

o

{

Very truly yours.

VERMONT YANKEE NUCLEAR POWER CORPORATION

$ ff R. W. C pstick Licensing Engineer RWC/25.94 Enclosure S E 4 8'

\

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