ML20153B758

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Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1988
ML20153B758
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 06/30/1988
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FVY-88-68, NUDOCS 8808310077
Download: ML20153B758 (34)
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS, 1988 I

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I Vermont Yankee Nuclear Power Station 4827R/18.62 l

i 8808310077 880630 PDR ADCCK 05000271 R PDC

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VEIOlONT YANKEE NUCLEAll POWEll COllPOllATION VEIDIONT YANKEE NUCLEAlt POWEll STATION

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I TABLE 1A Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Gaseous Ef fluents - Su;nmation of All Releases s

Unit Quarter Quarter Est. Total 1 2 Error, %

A. Fission and Activation Cases

1. Total release Ci ND ND 1.00E+02
2. Average release rate for period uCi/sec ND ND
3. Percent of Tech. Spec. limit (1)  % - -

B. Iodines

1. Total Iodine-131 ~ Ci 4.41E-05 6.23E-04 25.00E+01

_ 2. Average release rate for -iod uCi/sec 5.61E-06 7.93E-05

3. Percent of Tech. Spec. i ii. (2)(4) % 1.31E-01 5.28E-01 C. Particulates
1. Particulates with T-1/2 ) 8 days Ci 1.27E-03 1.12E-03 25.00E+01
2. Average release rate for period uCi/sec 1.62E-04 1. 4 7.E-04 I 3.

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Percent of Tech. Spec. limit Gross alpha radioactivity Ci (3) 7.11E-06 (3) 3.34E-06 D. Tritium

1. Total release Ci 3.91E+00 1.07E+01 25.00E+01 I 2. Average release rate for period
3. Percent of Tech. Spec. limit uCi/sec 4.97E-01 (3) 1.37E+00 (3)

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

I (2) Technical Specification 3.8.G.1 for dose f rom I-131, I-133. Tritium, and radionuclides in particulate form.

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

l l g (4) The first and second quarter percent of Technical Specification limits are E ba'*d a c "'ar"*'i"* P "' 9"^r'*r Y do' detarat"^'t "*-

ND Not detected at the plant stack.

4827R/18.62

I TABLE IB Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Gaseous Effluents - Elevated Release I Nuclides Released Unit Continuous Mode Quarter Quarter Batch Mode Quarter (f)

Quarter 1 2 1 2

1. Fission Gases Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND I Xenon-133 Xenon-135 Xenon-135m Ci Ci Ci ND ND ND ND ND ND I Xenon-138 Unidentified Ci Ci Ci ND ND Total for period Ci
2. Iodines Iodine-131 Ci 4.41E-05 6.23E-04 I Iodine-133 Iodine-135 Total for period Ci Ci Ci 3.28E-04 ND 3.72E-04 3.87E-04 ND 1.05E-03
3. Particulates Strontium-89 Ci 2.44E-05 7.93E-06 , j Strontium-90 Ci 1.16E-06 1.37E-06 I Cesium-134 Cesium-137 Barium-Lanthanum-140 Ci Ci Ci ND 6.51E-05 ND ND 6.04E-05 ND I Cobalt-60 Manganese-54 Zine-65 Ci Ci Ci 1.06E-03 4.91E-05 6.51E-05 1.03E-03 2.14E-05 ND Unidentified Ci (1) There were no batch mode gaseous releases for this reporting period.

ND Not detected at the plant stack.

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TABLE IC Vermont Yankee l Effluent and Waste Disposal Semiannual Report l

First and Second Quarters, 1988 I Caseous Effluents - Ground Level Releases I

There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1988.

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I T_ABLE ID Vermont Yankee Ef fluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Gaseous Effluents - Nonroutine Releases I

There were no nonroutine or accidental gaseous releases during the first or second quarters of 1988.

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TABLE 2A Vermont Yankee 1 Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 I Liquid Effluents - Nonroutine Releases I There were no liquid releases during the first or second quarters of 1988.

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I T_ABLE 2B Ve rnen t Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Liquid Effluents - Nonroutine Releases I

4 I There were no nonroutine or accidental releases during the first or second quarters of 1988.

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I TABLE 3 Verment Yankee Effluent and Waste Disposal Semlannual Report First and Second Quarters, 1988 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

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

1. Type of Waste
a. Spent resins, filter sludges, evaporator m3 3.17E+01 bottoms, etc. Ci 1.66E+02 7.50E+01 I b. Dry comtressible waste, contaminated equipment, etc.
c. Irradiated components, control rods, m3 Ci m3 5.10E+01 4.36E+00 27.50E+01 etc. Ci
2. Estimate of Major Nuclide Composition (By Type of Waste)
a. Zinc-65  % 3.14E+01 Hydrogen-3  % 1.12E-01 Cobalt-60  % 1.93E+01 Strontium-92  % 7.15E-02 Cesium-137  % 1.42E+01 Carbon-14  % 5.73E-02 I Iron-55 Cesium-134 Manganese-54

% 1.05E+01

% 9.98E+00

% 7.22E+00 b.

Iodine-129 Cobalt-60 Iron-55

% 1.43E-02

% 5.37E+01

% 3.41E+01 Cobalt-58 I Chromium-51 Silver-110m

% 2.20E+00

% 1.02E+00

% 9.99E-01 Cesium-137 Zine-65 Manganese-54

% 6.86E+00

% 2.30E+00_

% 2.22E+00 Technetium-99  % 8.32E-01 Hydrogen-3  % 2.69E-01 I Nickel-63 Niobium-95 Iron-59

% 6.63E-01

% 5.83E-01

% 3.22E-01 Cesium-134 Cobalt-58 Zirconium-95

% 2.59E-01

% 9.60E-02

% 9.20E-02 I Strontium-90 Zirconium-95

%,2.53E-01

% 2.31E-01 Plutonium-241 Technetium-99

% 6.40E-02

% 2.10E-0?

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 9 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
1) Class of solid waste containers shipped: 2A (Unstable) 5A, 1B, 1C
2) Types of containers used: 7 Type A, 2 Strong-Tight Container
3) Solidification agent or absorbant: None 4827R/18.62 I -

I l APPENDIX A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l Supplemental Information First and Second Quarters, 1988 1 Facility: Vetmont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation 1A. Technical Specification Limits - Dose and Dose Rate Technical Specification and Category Limit I a. Noble Cases 3.8.E.1 Total body dose rate 500 mrem /yr I 3.8.E.1 3.8.F.1 Skin dose rate 3000 mrem /yr Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrad in a year I b. Iodine-131, Iodine-133 Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days I

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 i

I c. Liquids .

I 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 I 1.8.B.1 Organ dose 5 mrem in a quarter 2

3.8.B.1 Organ dose 10 mrem in a year I

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I 2A. Technical Specification Limits - Concentration Technical Specification and Category Limit I a. Noble Cases No MPC limits

b. Iodine-131, Iodine-133, Tritium and I

Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days: No MPC limits

c. Liquids I 3.8.A.1 Total fraction of MPC excluding noble gases (10CFR20, Appendix B, I

Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uCi/cc

3. Average Energy 1 Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.

I a. Average gamma energy: 1st Quarter 1.05E+00 MeV/ dis l

1 2nd Quarter 9.00E-01 MeV/ dis

b. Average beta energy: Not Applicable
4. Measurements and Approximationc of Total Radioactivity I Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

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a. Fission and Activation Cases Daily samples are drawn at the discharge of the air ejector.

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

off-gas system the error of release rates may be approximately i100 percent.

b. Iodines I 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 I 4 percent of the Tech Spec limit), or daily (if they are greater than 4 percent of the limit), and are analyzed for radiciodine 131, 132, 133, 134, and 135. The error involved in these steps may be approximately 150 percent.
c. Particulates The particulate filters described in b. above are *. iso counted for particulate radioactivity. The error involved in this sample it also approximately 150 percent.
d. Liquid Effluents l I Radioactive liquid effluents released from the facility are 1

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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 (uCi/ml) of gross l R

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I radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.

Each batch of radioactive liquid ef fluent released is analyzed for gross gamma and gamma isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch I 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.

I 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.

I 6. Abnormal Releases

a. Liquid E r"- - -- + - u ," c c a - c ~ ~ '~

perlod.

b. Gaseous period.

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I APPENDIX B LIQUID HOLDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive inaterial contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding I the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7.C.l.

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

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I APPENDIX C RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical I 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.

e s non s e :

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

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l APPENDIX D RADIOACTIVE CASE 00S EFFLUENT MONITORING INSTRUMENTATION 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 I

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 I monitoring instrumentation were met for this reporting period, no response is required.

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I APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requi rement_: The Radiological Environmental Monitoring Program is conducted in accordance with Technical Specification 3.9.C. With milk ramples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3 Technical Specffication 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report:

(1) identify the causc(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: Moore Farm (TM-21), the control milk sampling location in I Dummerston, Vermont, was liquidated in March 1988. The Ranney Farm (TM-20) in Dummerston, Vermont was added to the program as its replacement. The revised ODCM figure and table are attached in Appendix H.

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I 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 location (s) which yields at least a 20 percent greater dose o,r I dose coaraitment than the values currently being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requirer the identification of the new location (s) in the next Semiannual Effluent Release Report.

Response: The 1988 land use census was not performed during this reporting periou.

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APPENDIX G PROCESS CONTROL PROGRAM 1

Requirement: Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Semiannual Radioactive I

Ef fluent 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.

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1 APPENDIX H OFF-SITE DOSE CALCUI).fION MANUAL l

I Requirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (0DCM) I be submitted to the Commission in the Semiannual Radioactive ,

I Effluent Release Report for the period in which the change (s) was made effective.

I R_es_p ase: The control milk sampling location (TM-21) was replaced with a new location (TM-20) in March 1988. Full det ils may be found in Appendix E. The ODCM was revised to reflect this change, and the revised figure and table are attached. l I

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I VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REV. #5 I

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y Reviewed  ?._.Lw'CJf 3?33 / G/2;/fg Plant Operat{onal Review Date' Committee Approved fnt Manager

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'l Approved d )' ) .i f u f ) / /a 4 r /f- p i Vice/ P t'e 9 dyt and Manager of Date /

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Radiological Environmental Monitoring Stations

  • l I Exposure Pathway and/or Samole Sample Lo.ation and Designated Code **

Distance From the Plant Stack (km)

Direction From the Plant

1. AIRBORNE (Radiciodine and Particulate)

AP/CF-11 River Station 1.9 SSE No. 3.3 I AP/CF-12 N. Hinsdale, NH AP/CF-13 Hinsdale Substation 3.1 3.6 NNW E

AP/CF-14 Northfield, MA 11.3 SSE I *1AP/CF-15 Tyler Hill Rd.

AP/CF-21 Spofford Lake 3.2 16.1 WNW NNE

2. WATERBORNE
a. Surface WR-11 River Station 1.9 Downriver No. 3.3 WR-21 9t. 9 Bridge 12.8 Upriver
b. Ground WG-11 Plant Well --

On-site I WG-12 WG-21 Vernon Nursing Wil Brattleboro CC 2.0 12.1 SSE NNW

c. Sediment SE-11 Shorline Ocwnriver 0.8 On-site From SE-12 North Storm *** 0.15 On-site Shorline Orain Outfall
3. INGESTION
a. Milk *1TM-11 Miller Farm 0.8 WNW I TM-14
  • 1TM-13 TM-15 Brown Farm Newton Farm Coombs Farm 2.6 5.1 4.5 S

SSE NW I TM-16 TM-20 Tall Oaks Farm Ranney Farm 4.7 17-0 WNW N ,

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b. Mixed TG-11 River Station 1.9 SSE I Grasses TG-12 No. 3.3 N. Hinsdale. NH 3.6 NNE TG-13 Hinsdale Substation 3.1 E l I TG-14
  • 1TG-15 TG-21 Northfield, MA Tyler Hill Rd.

Spofford Lake 11.3 3.2 16.1 SSE WNW NNE I

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_ Table 4.1 (Continuedj Radiological Enviernmental Monitorino Stations

  • Exposure Pathway Sample Location Distance Faom the 9irection From E and/or Sample and Designated Code ** Plant Stack (km) the Plant I c. Silage *1TC-11 TC-14
  • 1TC-13 Miller Farm Brown Farm Newton Farm 0.8 2.6 5.1 WNW S

SSE TC-15 Coombs rarm 4.5 I

NW TC-16 Tall Oaks Farm 4.7 WNW TC-20 Ranney Farm 17.0 N I d. Fish

  • 1 FH-11 FH-21 Vernon Pond Rt. 9 Bridge Non-Tech Spec Station 12.6 On-site Upriver E

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APPENDIX I RADI0 ACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREA MFUT 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 I

Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Comittee. 1 I

Response: There were no licensee initiated major changes to the l

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radioactive waste systems (liquid, gaseous, and solid) during this reporting period. '

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NERMONT YANKEE NUCLEAR. POWER CORPORATION

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

  • FRAMINGH AM, M ASSACHUSET7 3 01701

. Y tLt >MONi si?4?aatoo r

i August 26, 1988 FVY 88-68 s

United States Nuclear Regulatory Commission Attention
Document Control Desk Washington, DC 20555 References (a) License No. DPR-28 (Docket No. 50-271)

Subject:

Vermont Yankee Nuclear Potter Station Effluent and Waste Disposal Semiannual Report for First and Second Quarters,1988 j Dear Sir  ;

Enclosed herewith please find one copy of the subject Vermont Yankee l Nuclear Power Corporation semiannual report. This report covers the period beginning January 1, 1988 and ending June 30, 1988, and is submitted in  ;

accordance with our Technical Specifications 6.7.C.1.a.

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

j Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION 6.1 R. W. Capstick Licensing Engineer RWC/25.94 i

.i Enclosure j cct USNRC ,

i Region I 475 Allendale Road i King of Prussia, PA 19406 l

j USNRC Resident Inspector, VYNPS ,

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