ML20210D306
| ML20210D306 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1985 |
| From: | Whittier G Maine Yankee |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 7269L-DS, GDW-86-59, MN-86-37, NUDOCS 8603260407 | |
| Download: ML20210D306 (12) | |
Text
V' M AINE YANKEE ATOMIC POWER COMPANY EFFLUENT Ato WASTE DIPOSAL' SEMI-ANMJAL REPORT JULY - DECEMBER 1985 FACILITY: MIE YAtKEE ATOMIC POWER COWANY LICENSEE: MAIE YANKEE ATOMIC POWER COWANY
- 1. Regulatory Limits
- a. Fission and activation gases: -10 CFR 20; Paragraph 20.106
- c. Particulates, (with half
~.l ives greater than 8 days): 10 CFR 20; Paragraph 20.106-
- d. Liquid effluents: 10 CFR 20; Paragraph 20.106
- 2. Maximum Permissible Concentrations
- a. Fission and actuation gases: 10 CFR 26; App. B. Table 2 Col.1
- c. Particulates, (with half lives greater than 8 days) 10 CFR 20; App. B' Table _2 Col.1
- 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 dJring discharge.
- b. Iodines: Primary vent stack iodine totals are taken from weekly measurements of an irwline charcoal filter.
- c. Particulates: Primary vent. stack particulate totals are taken from weekly measurements of an in-line particulate filter.
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.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 Number of batch releases: 92 1.
- 2. Total' time for batch releases: 346 hrs 39 min
- 3. Maximum time for batch releases: 24 hrs 7 min
- 4. Average-time for batch releases: 3 hrs 46 min
- 5. Minimum time for batch releases: hrs 37 min
- 6. Average stream flow during periods of release of effluent.into a flowing stream: N/A
- 7. Maximum gross release concentration (uci/ml) 1.00E-07 .
- b. Gaseous-
-1. Number of batch releases: 50
- 2. Total time period for batch releases:' 1709 hrs 15 min
- 3. Maximum time period for a batch release: 617 hrs 35 min
- 4. . Average time period for a batch release: 34 hrs 11 min
- 5. Minimum time for a batch release: 12 min
- 6. Maximum gross release rate (uci/sec): 2.42E+03
- 6. Abnormal Releases
- 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.
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- c. . The following table is not attached since' there was' no applicable
- release' during this reporting period.
Table 1C - Gaseous Effluents, Ground Level Releases
- 7. On-Line Containment Purges During the period,- on-line containment purging was conducted for 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />, 42 minutes. This is the total on-line purge time for 1985.
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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.
The following drums had a holdup time of less than 60 days during normal operations in the second half of 1985. .
Holcbp Time Release No. Decay Drum Date Isolated Date Released (In Days) Cu .F t .
805 B 07/06/85 '08/12/85 37 1011 The average holdup time for the second half of 1985, of all decay drums during normal operation, was 48.5 days.
Early release of Decay Drum B (RP #805) was required to provide adequate gas storage space to support scheduled shutdown degassification operations.
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TABLE 1A EFFLUENT Ato WASTE DISPOSAL SEMIANNUAL REPORT 1985 GASEOUS EFFLUENTS-SlM4ATION OF ALL RELEASES 3RD ATH EST.
UNIT QUARTER QUARTER TOTAL ERROR %
A. FISSION & ACTIVATION GASES
- l. Total Release CI 2.17E+01 4.18E+02 1.41E-00
- 2. Average Release Rate for Period UCI/SEC 2.75E+00 5.31E+01 ___---__-
- 3. % of Tech. , Specification Limit % 1.2]E_01 5.26E-01
- 8. IODItES
- 1. Total Iodine _131~ CI 6.94E_05 2.30E-04 1.12E+01 Average Release Rate for Period 2.93E-05
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- 2. UCI/SEC 8.83E_06 - ---
- 3. % of Tech. Specification Limit ~% 2.29E-04 7.60E-04 C. PARTICULATES
- l. Parti.-11ates with T 1/2 8 Days CI 1.29E-05 2.30E_05' l.12E+01-
- 2. Average Release Rate for Period UCI/SEC 1.65E-06' 2.93E-06 ______----
- 3. % of Tech. Specification Limit % 2.67E-05 7.60E-05
- 4. Gross Alpha Radioactivity CI 5.83E-08 2.47E-08 D. TRITIlH
- 1. Total Release CI 4.13E-01 6.44E-01 2.37E_01
- 2. Average Release Rate for Period UCI/SEC 5.25E-02 8.20E_02'- ----------
- 3. % of Tech. Specification Limit %. 6.80E-04 1.06E-03 L . 7269L-DS
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MAINE YANKEE ATOMIC POWER COMPANY TABLE IB-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 GASEOUS-EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED -UNIT QUARTER . QUARTER QUARTER QUARTER 1.- FISSION GASES KR-85. CI WD* WD* WD* N/D*
KR-85M CI N/D* WD* - N/D* WD*
KR-87 CI WD* ' WD* WD* N/D*
KR-88 CI- WD* WD* WD* WD*
XE-133 CI N/D* WD* 1.17E+01 3.87E+02 XE-135 CI N/D* WD* 3.40E-02 3.08E+01 XE-135M CI WD* WD* N/D* WD*
XE_138 CI N/D* N/D*- WD*. WD*
XE-131M CI N/D* WD* WD* N/D*
XE-133M CI N/D* N/D* 2.28E-02 WD*
AR-41 CI WD* WD* WD* WD*
UNIDENTIFIED CI N/D* WD* 9.86E+00 N/D*
TOTAL FOR PERIOD CI N/D* WD* 1.18E+01 4.18E+02
- 2. IODItES I_131 CI 6.94E-05 2.30E-04 WD* N/D*
I_132 CI N/D* N/D* N/D* WD*
I-133 CI WD* 2.64E_04 N/D* N/D*
I-134 CI N/D* WD* ' WD* WD*
I-135 CI WD* WD* WD* N/D*
TOTAL FOR PERIOD CI 6.94E-05 4.94E N/D* WD*
- 3. .PARTICULATES SR-89 CI WD* WD* WD* -N/D*
SR-90 CI WD* WD* WD* WD*
CS-134 CI N/D* WD* WD* N/D*
CS_137 .CI 6.01E-06 N/D* N/D* WD*
. BA-140 CI N/D* WD* WD* N/D*
OTERS CI
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~TA8_E 2A EFFLINT AND WASTE DISPOSAL SEMIABNUAL REPORT 1985 LIQUID EFFLUENTS _-SIMMATION OF ALL siELEASES 3RD -4TH EST. TOTAL UNIT QUARTER QUARTER ERROR %
A. FIMION Ato ACTIVATION PRODUCTS *
- l. 1otal Release CI 2.08E-02' 5.77E-03 3.17E+00
- 2. Average Diluted Concentration During Period UCI/M. 1.44E-10 3.%E-ll
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- 3. % Applicable Limit % 1.88E_02 8.91E_03 B. TRITIUM
- l. Total Release CI 9.61E+00 2.26E+01 2.25E-01
- 2. Average Diluted Concentration During Period UCI/M. 6.77E-08 1.39E-07
- 3. % Applicable Limit % 2.26E-03 4.64E-03
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C. DISSOLVED AND ENTRAIED GASES
- l. Total Release CI 2.02E-02 1.40E-01 1.02E+00
- 2. Average Diluted Concentration During Period UCI/M. 1.42E-10 8.64E-10
- 3. % Applicable Limit % 7.13E-03 4.33E-02 D. GROSS ALPHA RADIOACTIVITY
- l. Total Release CI 1.35E-06 4.82E-07 4.50E+01 E. VOLUE OF WASTE LITERS 1.42E+07 2.41E+07 1.00E+01 F. VOLUE OF DILUTION LITERS 1.42E+11 1.62E+11. 1.00E+01
- TOTAL RELEASE EXCLlDING TRITIUM, GASES, Ato ALPHA.
- N/D = NOT DETECTED
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- TABLE'2B-EFFLUENT AND WASTE DISPOSAL SEMIAPNUAL' REPORT 1985 LIQUID EFFLUENTS
-CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED ~^ UNIT ' QUARTER-3 QUARTER-4 QUARTER-3 ' . QUARTER-4 SR-89 CI N/D* - WD* WD* WD* ~
SR-90 CI. N/D* N/D* WD* WD*
CS-134' CI N/D* WD* WD* N/D*
CS_137 CI N/D* WD* 3.02E-03 1.78E-04 I-131 CI -N/D* 'N/D* 6.36E_03 4.25E-03 CO-58 CI WD* WD* . WD* 1.04E-04 CO-60 CI 3.30E_04 N/D* 5.55E_03 6.60E-04 FE-59 CI N/D* N/D* N/D* N/D*
ZN-65 CI WD* N/D* WD* WD*
MN-54 CI N/D* N/D* N/D* WD*
CR-51 CI N/De WD* N/D* N/D*
ZR-95 .CI N/D* WD* N/D* N/D*
- M0-99 CI N/D* N/D*- N/D* N/D*
TC-99M CI N/D* ' WD* N/D* N/D*
BA-140 CI N/D* N/D* WD* WD*
CE-141 CI N/D* WD* WD* WD*
OTHER I-133 CI WD* WD* 5.lE_03 -2.14E-04 NA-24 CI' WD* WD* WD* 3.23E-04 CE.139 CI WD* WD* N/D* 4.0E-05 UNIDENTIFIED CI WD* N/D* N/D* .N/D*-
- TOTAL FOR PERIOD ** CI N/D*- W D* - 2.00E-02 5.77E-03 XE-133 C1 WD* N/D*. 8.74E-03 1.37E-Ol=
XE-135 CI 'N/D* - WD* 1.15E-02 1.96E-03 XE-133M CI WD* WD* WD* 1.48E - ___________ .. __________________________ ._______________________________________.
~ NOTE: ACTIVITIES'0F ZR-95 AND BA-140 INCLUDE CONTRIBUTIONS OF DAUGHTERS.
- WD = NOT. DETECTED .
- Total'for period _ does;not. include unidentified in this summation but is included in Table 2A Item Al. .
- _ _ _ _ _ _ _ - _ _ _ - - _ - =_ =
- MAINE YANKEE ATOMIC POWER COMPANY LOWER LIMITS OF DETECTABILITY FOR GASEOUS EFFLUENTS Lower Limit of Detectability (LLD)
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NUCLIDE.
(Microcurie / Cubic Centimeter)
Kr-85 8.00E-05 Kr-85m .l.00E-07 Kr-87 3.00E-07.
Kr-88 3.50E-07 Xe-133 3.50E-07 Xe-135 7.00E-07 I 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 !
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, , , MAINE YANKEE ATOMIC POWER COMPANY LOE LIMITS OF DETECTABILITY FOR LIQUID 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-D3m 1.00E-07 1.00E-06 Na-24 1.00E-08 1.00E-07 Ce-139 6.00E-08 6.00E-07
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TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIAPNUAL REPORT '(YEAR)
SOLID WASTE AND IPRADIATED FUEL SHIPENTS January - June 1985 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) l I I I l l1. Type of waste l l 6 month l Est. Totall l Unit l Period l Error % -l l l l l l-l a. Spent resins, filter sludges, I m3 -l 6.74 El 'l l l evaporator' bottoms, etc. I Ci '
8.31 El- l 1.0 E l . l 1- 1 i l l l b. Dry compressible. waste, I m3 l .2.15 E2 l l l- contaminated equip. etc. I Ci l 7.68 E0 1.0 E 1 l 1 1 I l l c. Irradiated components, control I m3 1 0 l l l rods, etc. I -Ci l 0 l N.A. l l- 1 l l l l d. Other (describe) l m3 1 0 l l l l 'Ci l O' l N.A. l
- 2. Estimate of major nuclide composition (by type of waste)
- c. I % i .- E l
% 'l . E l
- d. % i . E l
% l . E l
% l . E l 3; Solid Waste Disposition Number of Shipments Mode of Transportation Destination 16 Truck Chem-Nuclear, Barnwell, S.C.
- 8. IRRADIATED FUEL- SHIPENTS (Disposition)
Number of Shipments. Mode of Transportation Destination 7269L-DS
EDISON DRIVE MAIRE HARHEE 'ATOMICPOWERCOMPARUe AUGUSTA, MAINE 04336 (207) 623-3521 e
March 4, 1986 FN-86-37 GDW-86-59 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. OPR-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 July 1,1985, to December 31, 1985.
Very truly yours, MAIE YANKEE ATOMIC POWER C0hPANY
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G. D. Whittier, Manager Nuclear Engineering and Licensing GDW/bjp
Enclosure:
(11 pages) cc: Mr. Ashok C. Thadani Mr. Cornelius F. Holden Mr. Pat Sears Mr. Donald Hoxie - DHE Mr. John Brochu - DEP American Nuclear Insurers Document Control Desk United States Nuclear Regulatory Connission Washington, D. C. 20555 7269L-DS \ l