ML20138J602

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Semiannual Effluent Release Rept,Jan-June 1985
ML20138J602
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 06/30/1985
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8510290399
Download: ML20138J602 (21)
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SEMIANNUAL EFFLUENT RELEASE REPORT FIRST AND SECOND QUARTERS, 1985 (JANUARY - JUNE) t-VERMONT YANKEE NUCLEAR POWER CORPORATION l

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TABLE 1 A VERMONT YANKEE

, EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST AND SECOND QUARTERS, 1985 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l Unit Quarter Quarter Est. total (1) (2) error, %

i A. Fission and activation gases

1. Total releases Ci < 7. 78E+02 < l . 02E+03
2. Average release rate for period 1.00E+02l pCi/sec < 9.98E+01 < l . 30E+02
3. Percent of tech. spec. limit *1  % <l.35E-01 <3.70E+00 B. Iodines i
1. Total iodine-131 Ci 3.89E-05 <5.12E-05
2. Average release rate for period 5.00E+0ll

' pCi/sec 4.95E-06 <6.51E-06

_ 3. Percent of tech. spec. limit"Z  % 1.03E-93 +

i C. Particulates

1. Particulates with Th >8 days Ci 1.71E-04 +
2. Average release rate for period 5.00E+01l uCi/sec 2.18E-05 +
3. Percent of tech. spec. limit  % 3.19E-03 *3
4. Gross alpha radioactivity Ci 1.38E-06 +

D. Tritium

1. Total release C1 3.36E+00 2.llE+00 l 2. Average release rate for period 5.00E+01l pCi/sec 4.28E-01 2.68E-01
3. Percent of tech. spec. limit  % * *3
  • Not applicable.
  • 1 First quarter percent of technical specification limit is based on i

-suppl9 mental information in Appendix A, section lA. Second quarter percent of technical specification limit is based on 5 mrad in a quarter l

gamma air dose limit (Appendix A, section IB).

*2 Second quarter percent of technical specification limit cased on a maximum l

dose of 7.5 mrem in a quarter (T.S. 3.8.G.1) from Iodine-131, Iodine-133, Tritium, j

and Particulates with T > 8 days.

+ Results of analyses (including strontium-89, 90) not received back from vendor laboratory.

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TABLE IB VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST AND SECOND QUARTERS, 1985 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode Batch Mode *1 lNuclides Released l Unit Quarter Quarter Quarter Quarter (1) (2) (1) (2)

1. Fission gases krypton-85 Ci *2 *2 krypton-85m Ci <l.84E+00 <7.62E+00 krypton-87 Ci <l.47E+0f <2.13E+01 krypton-88 i Ci <9.54E+00 <l.31E+01
  • xenon-133 Ci <1.82E+00 <2.75E+00 xenon-135 Ci <2.09E+01 <2.69E+01 xenon-135m Ci <l.47Et02 <l.89E+02 xenon-138 Ci <5.82E+02 <7.64E+02 unidentified Ci 1

Total for period i Ci < 7. 7 8 E+02 <1.02E+03 s

2. Iodines iodine-131 l Ci 3.89E-05 <5.12E-05 iodine-133 Ci 4. 22E-05 <3.04E-04

____ iodine-135 Ci 5.07E-04 <6.80E-03 Total for period Ci 5.88E-04 <7.16E-03

3. Particulates strontium-89 Ci 3.75E-05 +

strontium-90 Ci <3.06E-07 +

cesium-134 Ci <8.22E-05 <8.22E-05 cesium-137 Ci 9.26E-06 1.88E-05 barium-lanthanum-140 Ci <3.00E-04 <3.00E-04 cobalt-60 Ci 1.00E-04 4.85E-04 manganese-54 Ci <l.12E-04 zinc-b>

3.73E-05 Ci 6.20E-05 <3.02E-04

  • 1 There was no batch mode gaseous releases for this reporting period.
  • 2 Not detected in the offgas mix. Limit of detectability = 6.97E-07 pCi/cc

+ Results of analyses not received from vendor laboratory.

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TABLE IC VERMONT YANKEE i

i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST AND SECOND QUARTERS, 1985 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 1985.

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TABLE ID VER5'Gr YANKEE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 4

FIRST AND SECOND QUARTERS, 1985 CASEOUS EFFLUENTS - NONROUTINE RELEASES t

l There were no nonroutine or accidental gaseous releases during the first or second quarters of 1985.-

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t TABLE 2A VERMONT YANKEr:

EFFLUENT AND WASTE DISPOSAL Si'NINANNUAL REPORT FIRST AND SECOND QUARTERS,1985 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES There were no liquid releases during the first or second quarters of 1985.

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TABLE 2B VERMONT YANKEE .

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST AND SECOND QUARTERS, 1985 LIQUID EFFLUENTS There were no liquid releases during the first or second quarters of 1985.

TABLE 3 VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SDfIANNUAL REPORT FIRST AND SECOND QUARTERS, 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste Unit 6-month Est. Total period error, T.
a. Spent resins, filter sludges. m3 4.33E+01
b. Ci 4.63E+01 I.7.50E+01 Dry compressible waste, contaminated mJ 5.65E+01 equipment, e't c . 2.79E+00 Ci 17.50E+01
c. Irradiated companents, control rods, mJ 2.23E+00 etc.

Ci 1.70E+04

2. E's timate of major nuclide composition (by type of waste)
a. cesium-134  % 3.94E+00 zinc-65 Y 1.34E+01 cesuim-137  % 5.04E+01 plutonium-241 cobalt-60

% 9.00E-01

% 2.35E+01 hydronen-3  % 5.10E-01 cobalt-58  % 5.10E-01 nickel-63  % 5.30E-01 mannanese-54  % 5.15E+00 strontium-90  % 3.60E-01

b. cesium-134  % 1.84E+00 mancanese-54  % 4.58E+00 cesium-137  % 3.95E+01 zine-65  % 1.24E+01 cobalt-60  % 3.59E+01 zirconium-95  % 6.10E-01 cobalt-58  % 1.34E+00 hydronen-3 plutonium-241

% l.01E+00

% 2.06E+00 carbon-14  % 3.80E-01

c. cobalt-60  % 4.58E+01 hydrogen-3 iron-55

% 2.98E+00

% 4.55E+01 manganese-54  % 2.58E+00 nickel-63  % 3.10E+00 nickel-59  % 2.00E-02 cesium-137  % 2.00E-02

3. Solid waste disposition Number of shipments Mode of Transportation Destination 12 Truck Barnwell, S.C.

2 fruck Richland, Washington B. IRRADIATED FUEL SHIPMENTS (Disposition) : NO SHIP!!ENTS Supplemental information for second quarter -

1) Class of solid waste containers shipped: 4 C, 1A (stable), and 1 A (unstable)
2) Types of containers used: 2 Type A, 3 Type B, and i LSA.

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3) No solidification agents were used in the 2nd quarter of 1985.

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APPENDIX A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information January - June 1985 Facility: Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation lA. Technical Specification Limits - First Quarter

a. Fission and activation gases: 0.08/E Ci/sec 7
b. Iodines: 0.48 uti/sec
c. Particulates, half-lives > 8 days: 1.6E+3 MPC, Ci/sec
d. Liquid effluents: 1.0E-07 uti/ml (HTO: 3.0E-03 vCi/ml, dissolved noble gases:

4.0E-05 uC1/ml) Isotopic limits are found in 10CFR20, App. B Table II, Column 2.

18. Technical Specification Limits - Dose and Dose Rate - Second Quarter Technical Specification and CateQory Limit
a. Noble Gases 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 3.8.F.1 8 eta air dose 10 mrad in a quarter 3.8.F.1 8 eta air dose 20 mrad in a year

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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 rate 7.5 mrem in a quarter 3.8.G.1 Organ dose rate 15 mrem in a year
c. Liquids 3.8.B.1 Total body dose i.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 3.8.8.1 Organ dose 10 mrem in'a year 2A.

Maximum Permissible Concentrations - First Quarter Provided below are the MPC's used in determining allowable release rates or concentrations.

a. Fission and activation gases: No MPC limits
b. Iodines: No MPC limits c.

Particulates, half-lives > 8 days: See 10CFR20, App. 8, lable II, Column 1.

d. Liquid effluents: See 10CFR20, App. B, Table II. Column 2.
28. Technical Specification Limits - Concentration - Second Quarter Technical Specification and Category Limit
a. Noble Gases No MPC liraits

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b. Iodine-131. Iodine-133. Tritium and Radion6clides  : No MPC limits in Particulate Form With Half-Lives Greater Than 8 Days
c. Liquids L

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

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

3. Average Energy Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable,
a. Average gamma energy: 1st Quarter 1.09E+00 MeV/ dis 2nd Quarter 1.09E+00 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 radioactivity in effluents and the methods used to determine radionuclide composition.
a. Fission and Activation Gases Daily samples are drawn at tt? discharge of the air ejector.

Isotopic breakdown of the releases are determined from these samples. A logarithmic chart 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 off-gas system the error of release rates may be approximately

  • 1100 percent.

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b. Iodines Continuous isokinetic samples are drawn f rom 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 iodines found on the filter are added to those on the charcoal cartridge. The error involved in these steps may be approximately 150 percent.
c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately ISO 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 radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.

i 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 to gamma spectroscopy.

There were no liquid releases during the reporting period.

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5. Batch Releases
a. Liquid There were no routine liquid batch releases during the reporting period.
b. baseous There were no routine' gaseous batch releases during the reporting period.
6. Abnormal Releases
a. Liquid 4

l There were no nonroutine liquid releases during the reporting period.

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

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APPENDIX B LIQUID HOLDUP TANKS Reouirement: 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 3.8.0.1, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7.C.1.

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

APPENDIX C RAPI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Reauirement: 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'noxt Semiannual Effluent Release Report of the reason (s) fo- delay in correcting the inoperability are required per Techaical Specification 6.7.C.l.

Response: Since the requireGents of Technical Specification Table 3.9.1 governing the 09erability of radioactive liquid ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Recuirement: 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.l.

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.

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APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Reauirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C. With milk samples no longer available f rom 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 sampic(s) no longer being available (2) identify the new location (s) for obtaining available replacement samples and (3) include revised 00CM figure (s) and table (s) reflecting the new location (s).

Response

All required milk samples were available during this reporting period.

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APPENDIX F LAND USE CENSUS Reauirement: A land use census is conducted in accordance with Technical Specification 3.9.0. With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.

Response: As permitted by Technical Specification 4.9.0.1, the annual land use census had not been completed before the end of this reporting period. The identification of any new locations of

( greater dose or dose commitment will be included in the next Semiannual Effluent Release Report.

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O APPENDIX G PROCESS CONTROL PROGRAM Reauirement: 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 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.

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j APPENDIX H OFF-SITE DOSE CALCULATION MANUAL Reauirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in'which the change (s) was made effective.

Response: There was no licensee initiated change (s) to the Off-Site Dose Calculation Manual during this reporting period, i

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VER$iONT YANKEE NUCLEAR POWER CORPORATION

. RD 5 "sx 169, Ferry Road, Brattleboro, VT 05301 g Y August 30, 1985 ENGINEERING OFFICE 1671 WORCESTER ROAD

  • TELE. PHONE 617-872-8100 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Dr. Thomas E. Murley Regional Administrator

Reference:

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

Subject:

Vermont Yankee Semi-Annual Effluent Release Report

Dear Sir:

Enclosed herewith please find two copies of the Vermont Yankee Nuclear Power Corporation Semi-Annual Effluent Release Report. This report covers the period beginning January 1, 1985, and ending June 30, 1985, and is submitted in accordance with our Technical Specification 6.7.c.1. Please note that the analysis for the second quarter strontium 89 and 90 release values for Table 1B have not been completed by our analytical laboratory contractor, but will be included in a surplemental report expected to be submitted by the end of September. To also be included in this supplemental report will be estimated doses resulting from measured plant effluents for the first half of 1985. These dose estimates are being prepared in compliance with the Technical Specification 6.7.c.1 which was in effect during the first quarter of this year.

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

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION R. W. Capstick Licensing Engineer RWC/lmf Enclosure cc: United States Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, DC 20555 Attention: Document Control Desk

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