ML20135H497

Effluent & Waste Disposal Semiannual Rept,Jan-June 1985

ML20135H497
Person / Time
Site:	Maine Yankee
Issue date:	06/30/1985
From:	Whittier G Maine Yankee
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
5098L-FWS, GDW-85-230, MN-85-157, NUDOCS 8509230691
Download: ML20135H497 (12)

Text

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I MAINE YANKEE ATOMIC POWER COMPANY EFFLUENT Af0 WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY - JUNE 1985' 4

FACILITY: MAIE YA?EEE ATOMIC' POWER COMPANY  !

LICENSEE: MAIE YAtKEE ATOMIC POWER COWANY

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 i d. Liquid effluents: 10 CFR 20; Paragraph 20.106

, 2. Maximum Permissible Concentrations

a. Fission and actuation gases: 10 CFR 20; App. B. Table 2 Col.1

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. 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 1 sampled monthly and on any increase in continuous air ejector monitor ,

i reading. t 4

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 j weekly measurements of an in-line particulate filter.

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MAINE YANKEE 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: 54

2. Total time for batch releases: 274 hrs 20 min

3. Maximum time for batch releases: 8 hrs 15 min

4. Average time for batch releases: 3 hrs 42 min

5. Minimum time for batch releases: I hrs 40 min

6. Average stream flow during periods of release of effluent,into a flowing stream: N/A

7. Maximum gross release concentration (uci/ml) 7.40E-09

b. Gaseous

1. Nunber of batch releases: 10

2. Total time period for batch releases: 29 hrs 45 min

3. Maximum time period for a batch release: 4 hrs 36 min

4. Average time period for a batch release: I hrs 34 min

5. Minimum time for a batch release: 5 min

6. Maximum gross release rate (uci/sec): 1.42E42

6. Abnormal Releases

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

b. Gaseous -

On February 1,1985, a packing gland on a sanple valve on waste gas holdup tank (decay drum) TK-600 was discovered leaking to atmosphere.

The valve was expeditiously repaired and the leak secured. Since internal valve leakage between drums has been a problem within the system, it was impossible to ascertain when the external leak began.

The activity released was, therefore, conservatively calculated based on volume lost from the drum since isolation and decay correcting activity back to the same date. It was, thus, estimated that 3.71E-2 uci was released. This activity ar.d the specific isotopes involved have been included in Tables 1A and 18.

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, , MAINE YANKEE ATOMIC POWED COMPANY

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

Table IC - Gaseous Effluents, Ground Level Releases 5098L-FWS

, MA.NE YANKEE ATOMIC POWER COMPANY

_4 RELEASE OF WASTE GAS STORAGE DRUMS BEFORE 60-DAY HOLDLP 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 first half of 1985.

Holdup Time Release No. Decay Drum Date Isolated Date Released (In Days) Cu.Ft.

791 E 03/10/85 05/03/85 53 1047 793 A 03/27/85 05/11/85 45 36 795 8 04/30/85 05/18/85 18 1047 796 C 05/08/85 05/30/85 22 1071 797 E 05/30/85 06/01/85 2 1142 798 A See Discussion 06/01/85 - 809 799 8 05/31/85 05/31/85 - 762 800 0 05/21/85 06/01/85 11 928 801 C 06/01/85 06/01/85 - 559 The average holdup time for the first half of 1985, of all decay drums during normal operation, was 38.8 days.

Prior to May, the average holdup time was 88.5 days. During that month, however, an abnormally fast fill rate of the drums was detected. Various measures were taken to minimize gas generation and determine the cause.

In the interim, the fill rate forced the early release of three drums in order to maintain a minimum storage capacity to support reactor coolant system dilution operations (RP #791, 795, and 796). A fourth release (RP #793) was terminated almost imediately after initiation when it was determined that the isolation valves from the surge tank to the decay drum, TK-60A, were leaking by. The decision not to release that drum after that discovery further aggravated the gas storage capacity /high fill rate problem.

On May 31, while continuing to investigate the problem, an elemental analysis of the decay drums detected abnormal levels of oxygen (on the order of 7 to 8%) throughout the hydrogenated system. It was determined that a potentially explosive mixture existed,, and steps were taken to expeditiously release all drums and thoroughly purge the system. Releases RP #797 through 801 were released early in this effort. Extensive investigation identified various possible sources, and corrective action was taken. Following the incident, routine elemental sampling was initiated. Although no single root cause could be isolated, operation during the subsequent two months showed a normal fill rate for plant operating evolutions, and oxygen remained out of the system.

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MAINE Y ANKEE ATOMIC POWER COMPANY TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 GASEOUS EFFLUENTS.St}iMATION OF ALL RELEASES IST 2to EST.

UNIT QUARTER QUARTER TOTAL ERROR %

A. FISSION & ACTIVATION GASES

1. Total Release CI 3.80E-02 1.15E+00 2.89E-01

2. Average Release Rate for Period UCI/SEC 4.89E-03 1.46E-01 ----------

3.  % of Tech. Specification Limit  % 3.79E-05 1.38E-03 B. 10 DINES

1. Total Iodine.131 CI 3.82E-07 2.25E_06 1.90E+01 l

2. Average Release Rate for Period UCI/SEC 4.91E-08 2.86E_07 ----------

3.  % of Tech. Specification Limit  % 1.26E-06 7. 41E-06 C. PARTICULATES

l. Particulates with T 1/2 8 Days CI 7.65E-05 2.25E-07 1.90E+01

2. Average Release Rate for Period UCI/SEC 9.72E-06 2.86E-08 ..---. --_

3.  % of Tech. Specification Limit  % 4. 21E-05 7. 41E-07 4 Gross Alpha Radioactivity CI 6.74E-08 N/D D. TRITIUM

1. Total Release CI 1.06E+00 6.12E-01 7. 91E.01

2. Average Release Rate for Period UCI/SEC 1.36E_01 7.78E-02 _.--------

3.  % of Tech. Specification Limit  % 1.75E-03 1.01E-03 5098L-FWS

, , MAINE YANKEE ATOMIC POWER COMPANY

. TABLE IB

. EFFLUENT AIO WASTE DIS)0 SAL SEMIANNUAL REPORT 1985 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE IST 2to IST 2to

, NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER

1. FISSION GASES I KR 85 CI WD* WD* 8.82E-03 WD*

KR-85M- CI N/D' N/D* N/D' 6.73E-04 KR-87 CI WD* WD* WD* WD*

KR-88 C1 WD* N/D* WD* WD*

XE-133 CI WD* WD* 1.54E-02 1.08E 40 XE-135 CI N/D* N/D* N/D* 4.55E-02 XE-135M CI WD* WD* WD* WD*

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

_ XE-13]M CI WD* WD* 1.37E-02 WD' XE-133M CI N/D' N/D* N/D* 1.63E.02 AR-41 CI WD* WD* WD* 2.85E-03 UNIDENTIFIED CI N/D* N/D* N/D* WD' TDTAL FOR PERIOD CI N/D* WD* 3.80E 02 1.15E 40 1

6 7

2. 10 DINES 1 131 CI 3.82E-07 2.25E-06 WD* WD*

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

I-133 CI WD* WD* WD* WD*

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

I-135 CI WD* WD* WD* WD* '

TOTAL FOR PERIOD CI 3.82E-07 2.25E-06 N/D* N/D*

3. PARTICULATES SR 89 'C1 WD* ~ ~ WD* WD* WD*

SR-90 CI. N/D' N/D* WD* WD*

i CS-134 CI 1.55E 06 N/D* WD* WD*

CS-137 CI 3.86E-06 N/D' N/D* WD*

BA-140 CI WD' WD* WD* WD*

, OTHERS C0658 CI 4.07E-05 N/D* N/D* WD' CD-60 CI 7. 81E-06 N/D* WD* WD*

W-54 CI 2.30E-06 N/D* N/D* WD' i

AG 110M CI 2.02E 05 WD* WD* WD' I

• N/D = NDT DETECTED 5098L.FWS

, , M AINE YANKEE ATOMIC POWER COMPANY TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 LIQUID EFFLUENTS--SLNMATION OF ALL RELEASES -

1ST 2ND EST. TOTAL UNIT QUARTER QUARTER ERROR %

A. FISSION AND ACTIVATION PRODUCTS *

1. Total Release CI 2.00E-03 2.58E-03 3.40E+00

2. Average Oiluted Concentration During Period UCI/ML 1.01E-11 1.25E-ll

3.  % Applicable Limit  % 2.62E-03 5.32E-03 B. TRITIUM

1. Totrl Release CI 8.58E+01 6.58E+01 1. llE-01

2. Average Diluted Concentration During Period UCI/ML 4.31E_07 3.18E.07

3.  % Applicable Limit  % 1.44E-02 1.06E 02 C. DISSOLVED AND ENTRAINED GASES 1

1. Total Release CI 8.21E-05 2.97E.03 1.34E+01

2. Average Diluted Concentration During Period UCI/PL 4.13E-13 1.44E-ll

3.  % Applicable Limit  % 1.38E-05 4.80E-04 D. GROSS ALPHA RADI0 ACTIVITY

l. Total Release CI 3. 80E-0 7 1.92E_05 4.67E+01 E. VOLUME OF WASTE LITERS 9.06E+06 2.64E+07 1.00E+01 F. VOLUNE OF DILUTION LITERS 1.99E+11 2.07E+11 1.00E+01 OTOTAL RELEASE EXCLUDIt0 TRITIlN, GASES, Ato ALPHA.

cN/D o NOT DETECTED 5098L.FWS

, MAINE YANMEE ATOMIC POWER COMPANY TABLE 28 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 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* W D*

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

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

CS-137 CI N/D* W D* 5.64E-05 1.45E.05 I-131 CI N/D* W D* N/D* 3.62E-04 CO-58 CI WO' WD* WD* 1.53E-04 CO-60 CI WD* WD l.39E-03 1.70E-04 FE-59 CI WD* WD* WD* WD*

ZN-65 CI WD* WD* WD WD*

MN.54 CI WD* WD* WD* WD*

CR-51 CI WD* WD* WD* WD*

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

MO-99 CI N/D* WD* N/D* N/D*

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

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

CE.141 CI N/D* W D* N/D* N/ D*

OTHER I-133 CI WO' WO* WO* 7.6SE-04 TE-133M CI WD* WD* 3.88E_05 WD*

CI UNICENTIFIED CI 3.28E-06 3.68E_05 5.10E-04 1.07E-03 TOTAL FOR PERIOD" CI N/D* W D' l.49E-03 1.4 7E-03 XE-133 GI WD* N/0* WD* 1. ole-03 XE-133 CI WD* WD* 8.21E-05 1.96E-03 NOTE: ACTIVITIES OF ZR-95 AfD BA-140 INCLUDE CONTRIBUTIONS OF DAUGHTERS.

• W D = NOT DETECTED co Total for period does not include unidentified in this summation but is included in Table 2A Item A1.

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? MAINE YANKEE ATOMIC POWER COMPANY LOWER 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 00-60 1.40E-14 Co-58 1.70E-14 Mn-54 2.10E-14 Agrilom 1.60E-14

, , MAINE YANKEE ATOMIC POWER COMPANY LOWER LIMITS OF DETECTABILITY FOR LIQUID EFFLUENTS NUCLIDE Lower Limit of Detectability (LLD)

(Microcurle/ 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 Cc-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 Te-133m 5.00E-08 5.00E-07 iW 9

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, ,, MAINE YANKEE ATOMIC POWER COMPANY TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

SOLIO WASTE AND IRRADIATED FUEL SHIPWNTS January - JJne 1985 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DIS'OSAL (not irradiated fuel) l l l l l

11. Type of waste l l 6 month l Est. Totall l l Unit l Period l Error % l l l l l l l a. Spent resins, filter sludges, I m3 l 1.44 El l l l evaporator bottoms, etc. I Ci l 1.15 E0 l 1.0 E 1 l l l l l l l b. Dry conpressible waste, I m3 1 6.23 El l l l contaminated equip. etc. I Ci l 1.89 El l 1.0 E 1 l l l l l 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 1 I i l d. Other (describe) l m3 1 0 l l l l C1 l 0 i N.A. l

2. Estimate of major nuclide composition (by type of waste)

a. Co-60 1  % 3.0 El l Cs-137  % 2.0 El l Ni-63  % 1 3.0 El l H3 i  % l 2.0 El I

b. Co-60  % i 3.5 El l Cs-137 i  % l 3.0 El l Ni-63 1  % 1 3.5 El I

c.  % i . E l

% i , E l

d. '

% I . E l 4 I . E l i  % i . E l

3. Solid Waste Disposition Nurber of Shipments Mode of Transportation Destination 6 Truck 01em-Nuclear, Barnwell, S.C.

B. IRRADIATED FUEL SHIPENTS (Disposition) '

Number of Shipments Mode of Transportation Destination None WA N/A 5098L-FWS

r EDISON DRIVE MAIRE HARHEE ATOMIOPol1/ERCOMPARUe avausra. ualne oa33s (207) 623-3521 9

September 3, 1985 MN-85-157 GDW-85-230 Region I United States Nuclear Regulatory Commission Office of Inspection and Eriforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator

References:

(a) License No. CPR-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 witn Technical Specifications. This report covers the period from January 1, 1985, to June 30, 1985.

Very truly yours, MAINE YANKEE ATOMIC POWER COWANY bh W G. D. Whittler, Manager Nuclear Engineering and Licensing GDW/Djp

Enclosure:

(11 pages) cc: Mr. Edward J. Butcher, Jr.

Mr. Cornelius F. Ibiden Mr. Donald Hoxie - DIE Mr. John Brochu - DEP American Nuclear Insurers Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555 vfI 5098L-FWS \ p "f I