ML20209F573

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Effluent & Waste Disposal Semiannual Rept for Jan-June 1986
ML20209F573
Person / Time
Site: Maine Yankee
Issue date: 06/30/1986
From: Whittier G
Maine Yankee
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
GDW-86-204, MN-86-112, NUDOCS 8609120199
Download: ML20209F573 (12)
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MAINE YANKEE ATOMIC POWER COMPANY EFFLUENT AND HASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY - J'JNE 1986 FACILITY: MAINE YANKEE ATOMIC P0HER COMPANY LICENSEE: MAINE YANKEE ATOMIC P0HER COMPANY

1. Regulatory Limits
a. Fission and activation gases: 10 CFR 20; Paragraph 20.106
b. Iodines: 10 CFR 20; Paragraph 20.106
c. Particulates, (with half lives greater than 8 days): 10 CFR 20; Paragraph 20.106
d. Liquid effluents: 10 CFR 20; Paragraph 20.106
2. Maxinum Permissible Concentrations
a. Fission and actuation gases: 10 CFR 20; App. B. Table 2 Col. I
b. Iodines: 10 CFR 20; App. B. Table 2 Col. 1
c. Particulates, (with half lives greater than 8 days) 10 CFR 20; App. B. Table 2 Col. I
d. Liquid effluents: 10 CFR 20; App. B. Table 2 Col. 2
3. Average Energy - Not Applicable
4. Measurement and Approximations of Radioactivity
a. Fission and activation gases:

Continuous discharge - Vent stack samples are analyzed monthly.

Activity levels determined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency. Air ejector is sampled monthly and on any increase in continuous air ejector monitor reading.

Batch discharges - Direct measurements of the waste gas holdup drums are taken prior to discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during discharge.

b. Iodines: Primary vent stack iodine totals are taken from weekly measurements of an in-line charcoal filter.
c. Particulates: Primary vent stack particulate totals are taken from weekly measurements of an in-line particulate filter.

K O 00 M

pg AD 8014L-DS

r MOIPCE VANKEE ATOMIC POWER COMPANY

d. Liquid Effluents Samples of secondary systems liquid effluents are analyzed weekly for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes.

Each batch release is analyzed for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes prior to discharge.

Composite samples are made of secondary and primary systems liquid effluents for a quarterly analysis of Strontium -90 and -89.

5. Batch Release
a. Liquid
1. Number of batch releases: 61
2. Total time for batch releases: 375 hrs 18 min
3. Maximum time for batch releases: 17 hrs 25 min
4. Average time for batch releases: 6 hrs 9 min
5. Minimum time for batch releases: I hrs 38 min
6. Average stream flow during periods of release of effluent into a flowing stream: N/A
7. Maximum gross release concentration (uci/ml): 6.14E-08
b. Gaseous
1. Number of batch releases: 16
2. Total time period for batch releases: 90 hrs I min
3. Maximum time period for a batch release: 14 hrs 56 min
4. Average time period for a batch release: 5 hrs 37 min
5. Minimum time for a batch release: 5 min
6. Maximum gross release rate (uci/sec): 6.12E+03
6. Abnormal Releases l
a. Liquid There were no abnormal liquid effluent releases during the reporting period. )
b. Gaseous There were no abnormal gaseous effluent releases during the reporting period.

8014L-DS

MAINE YANKEE ATOMIC POWER COMPANV

c. The following table is not attached since there was no applicable release during this reporting period.

Table IC - Gaseous Effluents, Ground Level Releases

7. On-Line Containment Purges During the period, on-line containment purging was conducted for 85 hours9.837963e-4 days <br />0.0236 hours <br />1.405423e-4 weeks <br />3.23425e-5 months <br />, 52 minutes.

l 8014L-DS

r MAINE YANKEE ATOMIC POWER COMPONY 4-RELEASE OF WASTE GAS STORAGE DRUMS BEFORE 60-DAY HOLDUP PERIOD Technical Specification 3.17.B(3) requires submittal of a special effluent report should the average holdup time of waste gas be less than 60 days.

No waste gas storage drums had a holdup time of less than 60 days during ,

normal operations in the first half of 1986.

The average holdup time for the first half of 1986, of all decay drums during normal operation, was 77 days.

1 8014L-DS

Y MAINE YANKEE ATOMIC POWER COMPANY TABLE 1A EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT 1986 GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES IST 2ND EST.

UNIT QUARTER QUARTER TOTAL ERROR %

k$ FISSIbN b~ACTIVkTIbN GASES

1. Total Release CI 6.32E+02 1.67E+01 3.00E+00 l
2. Average Release Rate for Period UCI/SEC 8.04E401 2.12E+00 ---- =
3.  % of Tech. Specification Limit  % 6.96E-01 1.80E-02
8. IODINES
1. Total Iodine-131 CI 4.91E-04 9.31E-04 2.77E+01
2. Average Release Rate for Period UCI/SEC 6.25E-05 1.18E-04 ----------
3.  % of Tech. Specification Limit  % 1.62E-03 3.07E-03 4

C. PARTICULATES

1. Particulates with T 1/2 8 Days CI 4.91E-05 4.07E-04 2.77E+01
2. Average Release Rate for Period UCI/SEC 6.25E-06 5.18E-05 ----
3.  % of Tech. Specification Limit  % 1.62E-04 3.07E-04
4. Gross Alpha Radioactivity CI N/D' 3.14E-07

_ == - _---------- ---------

D. TRITIUM

1. Total Release CI 1.84E+00 1.57E+00 2.50E+01
2. Average Release Rate for Period UCI/SEC 2.34E-01 2.00E-01 ----------
3.  % of Tech. Specification Limit  % 3.03E-03 2.59E-03
  • N/D = Not Detected 8014L-DS

MAINE YANKEE ATOMIC POWER COMPANY TABLE IB EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT 1986 GASE0US EFFLUENTS-ELEVATED RELEASE

==- -------------- -----------------

CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER

1. FISSION GASES

--=_ _=__ --

- - ------------------ =-

KR-85 CI N/D* N/D* N/D* 1.34E+01 KR-85M CI N/D* N/D* N/D* N/D*

KR-87 CI N/D* N/D* N/D* N/D*

KR-88 CI N/D* N/D* N/D* N/D*

XE-133 CI N/D* N/D* 6.30E+02 2.15E+00 XE-135 CI N/D* N/D* 1.54E+00 1.04E-02 XE-135M CI N/D* N/D* N/D* N/D*

XE-138 CI N/D* N/D* N/D* N/D*

XE-131M CI N/D* N/D* N/D* 1.11E+00 XE-133M CI N/D* N/D* 3.11E-03 3.67E-03 AR-41 CI N/D* N/D* N/D* N/D*

UNIDENTIFIED CI N/D* N/D* N/D* N/D*

TOTAL FOR PERIOD CI N/D* N/D* 6.32E+02 1.67E+01

2. 10 DINES I-131 CI 4.91E-04 9.31E-04 N/D* N/D*

I-132 CI N/D* N/D* N/D* N/D*

I-133 CI 1.70E-04 2.95E-04 N/D* N/D*

I-134 CI N/D* N/D* N/D* N/D*

I-135 CI N/D* N/D* N/D* N/D' TOTAL FOR PERIOD CI 6.61E-04 1.23E-03 N/D* N/D*

.. ------ ------- ------ --- =

3. PARTICULATES

- -=- _ - - - - - - - - - - ------= - -------------- --------

SR-89 CI N/D* N/D* N/D* N/D*

SR-90 CI N/D* N/D* N/D* N/D*

CS-134 CI N/D* N/D* N/D* N/D*

CS-137 CI N/D* N/D* N/D* N/D*

BA-140 CI N/D* N/D* N/D* N/D*

OTHERS CI N/D* N/D' N/D* N/D*

C0-60 CI N/D* 2.06E-07 N/D* N/D*

ZR-97 CI N/D* 3.14E-04 N/D* N/D*

UNIDENTIFIED CI N/D* N/D* N/D* N/D'

  • N/D - NOT DETECTED 8014L-DS

F

~

1 l

i MAINE YANKEE ATOMIC POWER COMPANY TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1986 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES IST 2ND EST. TOTAL UNIT QUARTER QUARTER ERROR %

A. FISSION AND ACTIVATION PRODUCTS *

1. Total Release CI 2.54E-02 4.89E-02 1.50E+01
2. Average Diluted Concentration During Period UCI/ML 1.37E-10 2.45E-10
3. 1 Applicable Limit  % 4.50E-02 7.79E-02 B. TRITIUM
1. Total Release CI 9.31E+01 8.51E+01 5.00E+00
2. Average Diluted Concentration During Period UCI/ML 5.03E-07 4.25E-07
3.  % Applicable Limit  % 1.68E-02 1.42E-02 C. DISSOLVED AND ENTRAINED GASES
1. Total Release CI 1.77E-01 1.31E-01 1.50E+01
2. Average Diluted Concentration During Period UCI/HL 9.57E-10 6.55E-10
3.  % Applicable Limit  % 4.78E-02 3.28E-02 D. GROSS ALPHA RADI0 ACTIVITY
1. Total Release CI 1.27E-06 4.60E-07
2. Average Diluted Concentration During Period UCI/HL 6.86E-15 2.30E-15 E. VOLUME OF WASTE LITERS 3.42E+07 1.88E+07 1.00E+01 F. VOLUME OF DILUTION LITERS 1.85E+11 2.00E+11 1.00E+01

_____________________________________________________ ____ ____________ ==_

  • TOTAL RELEASE EXCLUDING TRITIUM, GASES, AND ALPHA.

i

    • N/D - NOT DETECTED I

8014L-DS e-e-.++,v.-_, -,.i.,# e.- -y--m------ww-,f,y,vv-,,--i--, ---,--+--e.- ., ,...wy.9---t , g ----7w---qm- -- y-w- 9.----.-w-

-<5 9-------w---

M AINE YANKEE ATOMIC POWEft COMPANY TABLE 28 EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT 1986 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER-1 QUARTER-2 QUARTER-1 QUARTER-2 SR-89 CI N/D* N/D* N/D* N/D*

SR-90 CI N/D* N/D* N/D* N/D*

CS-134 CI N/D* N/D* N/J* 1.03E-04 CS-137 CI N/D* 2.67E-05 2.94E-04 4.44E-04 I-131 CI N/D* N/D* 2.38E-02 4.61E-02 C0-58 CI N/D* N/D* N/D* N/D*

-== ---- - ----- -------------------- ----__ ----- --

C0-60 CI N/D* 3.21E-05 8.02E-04 2.87E-04 l FE-59 CI N/D* N/D* N/D* N/D*

l ZN-65 CI N/D* N/D* N/D* N/D* l

_---_ -------- ----- -_--- - -_-_. I MN-54 CI N/D* N/D* N/D* N/D*

--== --- --- ------ .---- ----------_.

CR-51 CI N/D' N/D* N/D* N/D*

ZR-95 CI N/D* N/D* N/D* N/D*

M0-99 CI N/D* N/D* 4.35E-05 N/D*

TC-99M CI N/D* N/D* N/D* N/D*

BA-140 CI N/D* N/D* N/D' N/D*

== ---_ -- ---- ----- _ -

CE-141 CI N/D* N/D* N/D* N/D* I OTHER I-133 CI N/D* N/D* 4.23E-04 1.79E-03

-- -----__ - ---_ ---== ==.

CS-136 CI N/D* N/D* 7.15E-05 5.26E-05 FE-55 CI N/D* N/D* 3.76E-05 N/D* l

\

UNIDENTIFIED CI 3.16E-04 N/D* N/D* N/D*

TOTAL FOR PERIOD ** CI N/D* 5.88E-05 2.54E-02 4.88E-02 XE-133 CI N/D* N/D* 1.75E-01 1.29E-01 XE-135 CI N/D* N/D* 1.51E-03 1.48E-03

=-- ----

XE-133M CI N/D* N/D* 4.23E-04 5.54E-04 NOTE: ACTIVITIES OF ZR-95 AND BA-140 INCLUDE CONTRIBUTIONS OF DAUGHTERS.

  • N/D - NOT DETECTED
    • Total for period does not include unidentified in this summation but is included in Table 2A Item A1.

8014L-DS

r MAINE VANKEE ATOMIC POWER COMPANV LOHER LIMITS OF DETECTABILITY FOR GASEOUS EFFLUENTS NUCLIDE Lower Limit of Detectability (LLD)

(Microcurie / Cubic Centimeter)

Kr-85 8.00E-05 Kr-85m 1.00E-07 Kr-87 3.00E-07 Kr-88 3.50E-07 Xe-133 3.50E-07 Xe-135 7.00E-07 Xe-135m 5.00E-07 Xe-138 1.70E-07 Xe-131m 1.00E-06 Xe-133m 5.00E-07 Ar-41 1.70E-06 I-131 1.00E-14 I-132 5.50E-13 I-133 4.60E-14 I-134 1.60E-12 I-135 4.50E-13 Sr-89 1.00E-16 Sr-90 4.70E-18 Cs-134 9.70E-15 Cs-137 1.10E-14 Ba-140 3.60E-14 l

h 8014L-DS

r MAINE YANKEE ATOMIC POWER COMPANV LOHER LIMITS OF DETECTABILITY FOR LIOUID EFFLUENTS NUCLIDE Lower Limit of Detectability (LLD)

(Microcurie / Milliliter)

Continuous Mode Batch Mode Sr-89 1.00E-09 1.00E-08 Sr-90 1.00E-09 1.00E-08 Cs-134 5.00E-08 5.00E-07 Cs-137 6.00E-08 6.00E-07 I-131 1.00E-08 1.00E-07 Co-58 5.00E-08 5.00E-07 Co-60 8.00E-08 8.00E-07 Fe-59 1.00E-07 1.00E-06 Zn-65 9.00E-08 9.00E-07 Mn-54 5.00E-08 5.00E-07 Cr-51 3.00E-07 3.00E-06 Zr-95 8.00E-08 8.00E-07 Mo-99 4.00E-08 4.00E-07 Tc-99m 4.00E-08 4.00E-07 Ba-140 2.00E-07 2.00E-06 Ce-141 5.00E-08 5.00E-07 I-133 4.00E-08 4.00E-07 Xe-133 1.00E-07 1.00E-06 Xe-135 3.00E-08 3.00E-07 Xe-133m 1.00E-07 1.00E-06 Fe-55 1.00E-06 1.00E-06 8014L-DS

MAINE YONKEE ATOMIC POWER COMPANY TABLE 3 EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

SOLID HASTE AND IRRADIATED FUEL SHIPMENTS January - June 1986 A. SOLID HASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel)

1. Type of waste 6 month Est. Total Unit Period Error %
a. Spent resins, filter sludges, m3 5.30 El evaporator bottoms. etc. Ci 7.53 El 1.0 E 1
b. Dry compressible waste, m3 4.98 El contaminated eaulo. etc. C1 3.13 E-1 1.0 E 1
c. Irradiated components, control m3 o rods. etc. Ci 0 N.A.
d. Other (describe) m3 o Ci 0 N.A.
2. Estimate of major nuclide composition (by type of waste)
a. CO-60  % 2.0E1 CS-137  % 1.5El Fe-55  % 1.5El Ni-63  % 4.0E1 CO-58  % 1.0E1
b. C0-60  % 1.5El CS-137  % 1.5El Ni-63  % 3.0E1 CO-58  % 1.0E1 Fe-55  % 3.0E1
c. '
d.  %
3. Solid Haste Disposition Number of Shioments Mode of Transoortation Destination 7 Trucking over Highway Chen-Nuclear, Barnwell, S.C.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shioments Mode of Transoortation Qgitination 8014L-DS

s~

EI N RIVE MAIRE HARHEE MOMICPOWERCOMPARUe AUGUSTA, MAINE 04336 (207) 623-3521 O September 3, 1986 MN-86-112 GDH-86-204 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator

References:

(a) License No. DPR-36 (Docket No. 50-309)

Subject:

Semiannual Effluent Release Report Gentlemen:

Enclosed is the Maine Yankee Semiannual Effluent Release Report which is submitted in accordance with Technical Specifications. This report covers the period from January 1, 1986 to June 30, 1986.

Very truly yours, MAINE YANKEE ATOMIC P0HER COMPANY

- lb At/

G. D. Whittier, Manager Nuclear Engineering and Licensing GDH/bjp

Enclosure:

(11 pages) 1 l

cc: Mr. Ashok C. Thadani Mr. Cornelius F. Holden Mr. Pat Sears Mr. Donald Hoxie - DHE Mr. John Brochu - DEP American Nuclear Insurers l Document Control Desk /

United States Nuclear Regulatory Commission /, /

Hashington, D. C. 20555 ,[ l

' i i 8014L-DS 1

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