Text

Company Semi-Annual Radioactive Effluent Release Rept for Jan-June 1992
	ML20127C973
Person / Time
Site:	Maine Yankee
Issue date:	06/30/1992
From:	Hebert J; Maine Yankee
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	JRH-92-94, MN-92-87, NUDOCS 9209110071
	Download: ML20127C973 (22)
	v • d • e

. .

4 MaineYankee HELIARt.L ILECTRICITY FOR MAlid SWCL 19M EDIGON DRIVE

AUGUSTA MAINC 04330 e (207) 622-4%8 August 31, 1992 HN-92-87 'JRH-92-94 UNITED STATES NUCLEAR REGULATORY COMMISSION

. Attention: Document Control' Desk Washington, DC 20555

Reference:

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

Suoject:- Semiannual Radioactive Effluent Release Report Gentlemen:

Enclosed, in accordance with the requirements of Maine- Yankee Technical

.. Specification 5.9.1.6, is the Maine Yankee Semiannual Effluent Release Report for the period January to June 1992.-

'Please contact John Arnold if you have questions or comments.

Very truly yours,

+1 fha "

James R. Hebert, Acting Manager Licensing & Engineering Support Department JHA/ jag-Enclosures-

- c:- Mr. Charles S. Marschall.

Mr.-E. H,-Trottier Mr. Patrick J.-Dostie.

Mr. Thomas T. Martin Mr- Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Waste n American Nuclear Insurers ti\Jeh\itts\fr W 94,ite P.

- -. . . _ . ~ _.. - - _ . . - . -- . , - -

MAINE YANKEE ATOMIC POWER COMPANY SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992

'l.0 INTRODUCTION _

Tables I and 2 summarize the quantity of radie rtt gaseous and liquid effluents, respectively, for the first and second qt.arters of 1992. Table 3 summarizes the solid waste shipped off-site for burial or disposal during the first half of 1992. Table 4 contains supplementary information.

Appendices A through D_ indicate the status of reportable items per the requirements of Offsite Dose Calculation Manual (ODCM) sections 2.1.5, 2.2.6, 2.3.3, 2.3.4,-2.5 and Appendix C.

.The new ODCM issued 02/18/92 was submitted with the previous semiannual release

,eport [MY letter to NRC of 02/28/92 (MN-92-18)].

A May.1992 change (please see changed pages in Appendix E) indicates modified environmental sampling locations.

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6 JABLE lA L Maine Yankee Atomic Power Statior.

Effluent and Waste Disposal Semiannual Report First and Second Ouarters. 1992 G3seous Effluents - Summation of All Releases

~~Dnit Quarter Quarter Est. Total 1st 2nd Error. %

A. Fission and Activation Gases

1. Total release Ci 4.01 E+02 9.33 E-02 2.50 E+01

-2. Averaae release rate for oeriod UCi/sec 5.10 E+01 1.19 E-02

3. Percent of reaulatory limit % 1.54 E-01 3.68 E-05 B. Iodines

1. Total lodine-131 Ci 3.82 E-03 5.63 E-06 2.50 E+01

2. Averace release rate for period uti/sgs 4.86 E-04 7.16 E-07

3. Percent of reaulatory limit % 4.26 E-03 6.28 E-06 C. Particulates

~~~l' Particulates with T-l/2 > 8 days Ci 9.31 E-04 4.40 E-04 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 1.18 E-04 5.60 E-05

3. P?rcent of reaulatory limit % 1.94 E-04 1.42 E-04

4. Gross alpha radioactivity Ci 1,67 E-07 7.64 E-08 D.-Tritium

1. Total-release Ci 1.75 E+00 9.71 E-01 2.50 E+01

2. Averaae release rale for Det lod uCi/sec 2.23 E-01 1.23 E-01

3. Percent of reaulatory limit % 9.7f "-04 5.42 E-04

-CN/D = Not Detected I

l tr\jrh\1trs\Jrh9294.Itr l

j ..

TABLE IB Maine Yankee Atomic Power Station Effluent and Waste DisDosal Semiannual Report First and Second Ouarters. 1992 Caseous Effluents - Elevated Release Cqntinuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd

1. Fission Gases Krypton-85 Ci N/D* N/D* 1.52 E+01 N/D*

Kryoton-85m Ci 3.66 E-03 2.01 E-05 1.79 E-02 N/D*

Krvoton-87 Ci 2.80 E-03 N/D* N/D* N/D*

Krvolpn-88 Ci 4.16 E-03 N/D* N/D* N/D* 1 Xenon-133 Ci 4.46 E+01 9.17 E-02 3.26 E+02 1.80 E-04 Xenon-135 Ci 1.74 E+00 1.36 E-03 6.36 E-01 1.00 E-05 Xenon-135m Ci 4.73 E-03 N/D* N/D* N/D*

Xenon-138 Ci 1.59 E-03 N/D* N/D* N/D*

Xenon-133m Ci 1,32 E-03 N/D* 1.09 E+00 N/D*

Arcon-41 Ci 5.41 E-04 N/D* 1,42 E-03 5.64 E-06 Ci N/D* N/D* 1.10 E+01 N/D* 5 Xenon-131m Unidentified Ci N/D* N/D* N/D* N/D* ~

Total for period Ci 4.64 E+01 9.31 E-02 3.54 E+02 1.96 E-04

2. lodines Iodine-131 Ci 4.16 E-04 5.63 E-06 3.40 E-03 4.77 E-09 lodine-133 Ci 1.48 E-04 3.72 E-04 1.93 E-04 N/D*

Iodine-135 Ci N/D* N/D* 9.21 E-09 1.33 E-08 Total for period Ci 5.64 E-04 3.78 E-04 3.59 E-03 1.81 E-08

3. Particulates Strontium-89 Ci 3.48 E-04 N/D* N/D* N/D*

Strontium-90 Ci 8.63 E-07 N/D* N/D* N/D*

Cesium-134 Ci N/D* N/D* 4.54 E-06 N/D*

Cesium-137 Ci 2.42 E-06 1.35 E-04 8.81 E-06 N/D*

Barium-Lantnanum-i40 Ci N/D* N/D* N/D* N/D*

Zinc-65 Ci N/D* N/D* N/D* N/D*

Cobalt-58 Ci 1.16 E-05 8.23 E-06 N/D* N/D*

Cobalt-60 Ci 9.63 E-06 2.97 E-04 9.83 E-05 N/D*

Others-Chromium 51 Ci 2.84 E-35 N/D* N/D* N/D*

Selenium-75 Ci N/D* N/D* 1.99 E-06 N/D*

Ruthenium-103 Ci 4.16 E-04 N/D* N/D* N/D*

cN/D = Not Detected I

ou,su,.u,,n..u.

TABLE 10 4

Maine Yankee Atomic Power Station Effluent and Waste Discosal Semiannual Report )

First and Second Quarters 1992 Gaseous Effluents - Ground Level Releasqs i

There were no routine measured ground level continuous or batch mode gaseous releases during the first and second quarters of 1992.

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1 -.

. TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disoosal Semiannual Report First and Second Quarters. 1992 Liouid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 1st 2nd Error. %

A. Fission and Activation Products

1. Total release (not including tritium. aases. alpha) .

Ci 1.25 E-01 9.80 E-02 12 50 E+01

2. Average diluted concentration m durina Deriod uCi/ml 1.20 E-09 6.09 E-10

, 3. Percent of aoolicable limit %- 1.28 E-02 3.06 E-03 B. Tritium 1.-Total release Ci 1.44 E+01 3.17 E+01 1.50 E+01

2. Average diluted concentration

.durina ceriod uCi/ml 1.38 E-07 1.97 E-07

3. Dercent of applicable limit % 4.62 E-03 6.56 E-03 C. Dissolved and Entrained Gases

1. Total release Ci 3.43 E-01 1.56 E-03 1.50 E+01

2. Average diluted concentration durina ceriod uti/ml 3.s0 E-09 9.69 E-12

3. Percent of apolicable limit % 1.65 E-03 4.86 E-06 D. Gross Alpha Radioactivity

1. Total 'elease Ci 8.ll-E-07 4.12 E-06 1.50 E+01

2. Average diluted concentration durina ceriod uti/ml 7.80 E-15 2.56 E-14 E. Volume of waste released (prior to dilution) liters 3.73 E+07 4.69 E+07 1.00 E+01__

F. Volume of dilution water used durina Deriod liters 1.04 E+11 1.61 E+11 1.00 E+01

-cN/D - Not Detected 1

- Lt\Jeh\1troij r*9294. K - l

1ABLE 2B i

- litine Yankee Atomic P0xer Statiqn Effluent and_Wiste Disppjal Semiannual Rep _Qr_t.

first and Second Ouarters.19.jl1 Liquid Effluenti CQE.tlAV_o3J_tigde Batch Mo@

Nuclides Released Jjnit Quarter Quarter Quarter Quarter 1st 2nd ist 2nd

_S.trontium-83 Ci N/D* f(/D* N/D* N/D*

Strontium-90 Ci N/D* t1/R N/D* N/D*

_Lglium-LL4 Ci 2.20 E-04 1. 79_L-04 3.73 E-04 6.Q}_EQL

_(ejium-137 _Ci 4.137 E-04_ 4.54 E-04 1.80 E-0) 6.22 E-03

_Jr. dine-131 Ci 6 13 E-04 N/D* 2.48 E-03 7.k9_L- q4_

_0_gp3Lt._53 Ci 1.70 L-05 5 2LE96 4.12 E-02 1.44 E-0L

_ Cobalt-60 Ci 1. 6fLE-05 1.76 E-04 8. M l-Q3 IJQ E-02

_[ron-59 Ci 6.02 E-06 N/D* 5.84 E-04 1.78 E-04 Zinc-65 Ci il/D* N/0* N/D* N]D*

Manganese-54 Ci N/D* N/D* 1.07 E-04 4.89 E-04 Chromium-51 Ci N/D* N/D* 5.79 E-03 7.QLL-qL Zirconium-Niobium-M CJ N / D.* N/D* 2.95 E-04 1.33 E- 03 Molvidenum-99 Ci N/D* N/D* N/D* 8.46 E-00_

1echnetium-99m (1 N/D* N/Q* 1.86 E-05 tilD*

_Jarjum-Lanthanum-140 _Q.1 N/D* N/D* 2.30 E-04 L1Lf-05 Cerium-141 ri N/D* N/.D* 1.34 E-04 9.23_E-01_

_Dthers l,at hanum_141 li N/D* N/D* 1.17 L_Q4 3.03_J.-04 lodine-1;f Ci N/D* N/D* = 1 3] E-05 N/D*

lodjnc-133 Ci 6.4LE04 NLD* 1.12 E-04 5.dQl-Qf_

Antimony-122 Ci N/D* N/D* 2 . 83._E- 04 1.QLE-%, .

Antimony-124 Ci N/D* N/D* 1.87 E-Q2 1m 0 LE-J u Antigony-125 Ci N/D* N/D* 1.46 E-02 9.59 E-03

_ dilver-llDM Ci N/D* N/Q* 1,29 F-03 1.16 E-02_

Ruthenium-101 Ci N/0,* N/D* luSO E-04 14 66 f_Q4_

Tellurium-132 Ci 4.41 E-06 N/D* 4.52 E-05 N/D* .

Cerium-141 Ci N/D* N/D* 2.91 E-05 3J7 E-04 Cobalt-57 _ _ _ _

(1___,4.87 E-05 N/D* 6.00 E-05 2.64 E-05 Tin-ll3 Ci N/D* tilD* E.71 E-05 1.36 E-04 51dium-24 C1 N/D* N/D* 1.53 E-QS N/D*

Selenty3-75 Ci N/D* NIQ* LDL E-05 L,90 E-O L tr)p-55 Ci N/D* N/D* 2.60 -02 1. 571-JL Qn_

n identified .Cj VD* __jiLQ_*,___ _ N/D* N/D*

Total for neriod Qb_ove) Ci _

E-03 8. 0LE-04 1.23 E-01 9.72 E-02 XenoJ1_133 Ci- ?.31 E-03 _ 8.21 E-06 3.33 E-01 1.45 E-Q1_.

,_ Xenon-J35 Ci

J- 0.s 4.54 E-06 4.23 E-05 6.02 E-QL Xenon-131m .Ci n/Q* N/D*

97 E-0.3

. 1.44 E-05 Jenon-133m Ci 3.48 E-05 N/D* 1.54 E-03 N/D*

Krvoton-85 (.i N/D* _ N/D* 1.21 E-05 N/D*

Krvoton-8Jm Ci 5.08 L-06 N/D* N/D* N/D*

Xenon-135m Ci N/D* 2.67 E-05 N/D* N/D*

N/D* - Hot Detected ourmir uriim.nr l

)

TABLE 3 Maine Yankee Atomic Power Station Effluent _ and Waste Disposal Semiannual Report first and Second Ouarters. 1931 Solid Waste and Irradiated. Fuel Shioment.s. '

A. Solid Waste Shipped 'f-Site for Burial or Disposal (Not Irradiated fuel)

Unit 6-Month Est. Total

_ Period Error. %

1. Type of Waste

a. Spent resins, filter slud9es, etc. m' O.8 Ci' 27.2 25

b. Dry compressible waste, contaminated m' 25.3 eaginmenL DAW. dirt. cement. I Ci' P, 8 25

c. Irradiated components, control rods, m' 0 etc. Ci' 0 ;

d. Other Waste: Biological waste bird m' 2.3 cuano _ Ci' O.00185 25

2. Estimate of Major Nuclide Composition (By Type of Waste)*

a. Co-58 54.336% 1.48 E+01

,_ _ Ni-63 13.62J% 3.71 E+00 ,

,_ C9-10_ . 11.051% _3.01 E+00 .

C r- 5_1 8.885% 1.42 E+00_

Fe-55 2.754% 7.50 E-01 Cs-137 2.078% 5,hp_E-01 Zr 1.905% 5.19 E-01 Sb-124 1.013% 2.76 E-01

b. Co-60 42.333% 1.18 E400 Ni-Q3 2LS.46% 6J8_E-01 Fe-55 20.96sjL 5.86 E-01_ . . _ . .

C s - 15.' 8.609% 2.41 E-Ol _ _

[

Co-58 IJ12% 5.41f-02 Cs-134 1.678% __ 4.69 E-02 _ _ _

Sb-125 1.063% 2.97 E-02 .

d. 0f-144_ 10.851% 7.19 E-04 C1.137 32. 3 )].% 5.99 E-Q4 Pu ~d41 11.073% 2.05 E-04 fe-55 9.139% _. IJ9 E-04 Cs-134 4.5Ll% 8. 3]_ E-0 5 Cp-60 4.079% 7.55 E-05 l

l L ,

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. i e urn \t t e s\J -nwes.it e

TABLE 3 (Continued)

3. Solid Waste Disposition

-Number of Shioments Mode of.lu m oortation (Leitjntl2n 4 Trucking over highway Chem-Nuclear, Barnwell, S.C.

2 Trucking ove. highway Quadrex, Oak Ridge, 1N' 2 Tracking over highway Scientific Ecology Group (SEG), Oak Ridge, TN" B. Irradiated fuel Shipments (Disposition): None shipped Additional 0DCM Appendix C requirements.

Solid Waste _C.lin' yolume(n11 [Jt. Activity (Ci) fst. Tot.1)_trtit

~

A 27.6 2.8 +/- 25%

B 0.8 27.2 +/- 25% "

C 0 0 Package

[ontainer lyn 2 y.glyme(mh B-88' Strong Tight Container 2.9 55 gal. Drum (17H) Strong Tight Cantainer 0.2 85 gal. Drum Strong Tight Container 0.3 HN-100 Liner Strong Tight Container 3.4 Sealand' Strong Tight Container 38.3 Small 1)verpack High Integrity Container 0.8 _

Radloc-'95 High Iritegrity Container 5.5

Estimated

Extluding nuclides whose percent abundance is less than one percent.

Processor, Waste is intermittently shipped for disposal.

' As defined by 10 CFR 61.55.

Shipped to SEG only, ti\f rS\it ri\j ehorea , t t e

h 1ABl0 4 Supolemental Information

1. Egaulatory Limits Maximum Permissible Concentrali2D

a. Fission and activation gases: 10CFR20; Appendix B, Table 2, Column 1

b. lodines: 10CFR20; Appendix B, Table 2, Column 1

c. Particulates, (with half lives greater than 8 days) 10CFR20; Appendix B. Table 2, Column 1

d. Liquid effluents: 10CFR20; Appendix B, Table 2, Column 1

e. Total noble gas concentration 2E-04 uti/ml

2. Averaae Eneray -: Not Acolicable

3. Ugasurements and Anoroxim3tions of Radioactivity

a. Fission and Activation Casel Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels delcrmined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency.

Batch Discharges - Direct measurements of the waste gas hold-up 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. lodines Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.

c. Particulglas Primary vent stack particulate totals are taken from a minimum of weekly measurements of an in-line particulate filter.

d. Liouid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross beta-gamme, 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 system liquid effluents for-a quarterly analysis of Strontium-90 and Strontium-89. Primary system liquid effluents are also analyzed quarterly for Iron-55.

I I

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1 T_ABLE 4 (Continued) ,.

4. Hatch Releas.n

a. Liouids

1. Number of batch releases: 98 E. Total timo period for batch releases: 478 hours0.00553 days 0.133 hours 7.903439e-4 weeks 1.81879e-4 months , 12 minutes

3. Haximum time period for a batch release: 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months , 57 minutes

4. Average time period for batch releases: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 53 minutes

5. Minimum time period for a batch release: 43 minutes

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

7. Maximum gross release concentration (uti/ml): 4.67 E-06

b. EiL5 fan !

1. Number of batch releases: 45

2. Total time period for batch releases: 1260 hours0.0146 days 0.35 hours 0.00208 weeks 4.7943e-4 months , 36 minutes

3. Maximum time period for a batch release: 296 hours0.00343 days 0.0822 hours 4.89418e-4 weeks 1.12628e-4 months , 10 minutes

4. Average time period for batch releases: 28 hour3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months , 1 minutes

5. Minimum t he period for a batch release: 10 minutes

6. Maximulv prass release rate (uti/sec): 1.08 E+04

5. Unolanned Releases '

a. Liouid There were no unanticipated or unmonitored liquid releases during the reporting period.

b. Caseous At 0125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months on February 13 while the containment purge was in progress, gaseous radioactivity was found to be leaking from the shaft seal on the purge exhaust fan. Since the outside door of the fan room was blocked open, this resulted in an unmonitored release to the environment. It was assumed the release had been occurring since the initiation of the containment purge at~1805 hours on february 11. Upon identification of the leak, the purge was secured and the outside door was shut. Evaluation of the release found it to be well within regulatory release limits. Activity associated with this release is included in Tables IA and 18.

6. On-Line Containment Purae L

L On-line. containment purge was employed for a total of 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months , 47 minutes during

.this period.

I L t \j rhjit es \j rh 9794.1t r.

AEELtlalLA 1

Eadl#K11Y.e_IlfluenLMan.110rin9_In11rumenia11on Egguirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Sectior.s 2.3.3 and 2.3.4. With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, ODCM Sections 2.3.3 and 2.3.4 requires an explanation for the delay in correcting the inoperability in the next Semiannual Ef fluent Release Report.

Reipltnig: The requirements of ODCM Sections 2.3.3 and 2.3.4, governing operability of radioactive effluent monitoring instrumentation, were met for this reporting period and no report is required.

2 w,

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L r\jrb\it es\jtht294. It r

r' APPENDIX B LLgyld Radwaste Treatment System Et2Hittatati With radioactive liquid waste being discharged without treatment with estimated doses in excess of the limits in ODCH Section 2.1.5, a report mmt be submitted to the Comission in the Semiannual Effluent Release Report for-the period.

Response: The requirements of ODCH Section 2.1.5 were met during this period and, therefore, no report is required.

L

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APPENDIX C (UtstayLRitdwaste TreattrJnt System Requiteten11 With radioactive gaseous waste being discharged without treatment with doses in excess of the limits in ODCM Sec', ion 2.2.6, a reprt must be submitted to the Commission in the Semiannual Effluent Release Report for the period.

Etsp.gnigi The requirements of ODCM Section 2.2.6 were met during this period and, therefore, no report is required.

Li\jrh\ltes\jrh9294.1tr

1 b.

[2w_gr limit _of Detection for Radioloaical Analyses B.e_auirement : ODCM Section 2.5 requires that when unusual circumstances result in LLD's higher than required, tne reasons shall be documented in the Semiannual Radioactive Eifluent Release Report.

ER.iRQnig: Al's samples were counted in such a manner as to satisfy the specified a priori lower limits of detection.

d

[

Li\jeh\1tes\jrb9294.1tr

APPENDIX E ODCH pages which have been change since the current manual was issued in february 1992 are attached.

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7 Y :I L I \j eh\lt es\j rh9294.1t r

l MAINE YAt4KEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 5.1 (Continued)

Radiological Environmental Monitorina Stations

Distance Direction Exposure Pathway Sample Location From the From the Plant (km) pl an_t _

and_/or Sample ad Desig_natedj o_df

4. INGESTION

a. Milk TM-15 Mitman Farm 5.8 S

[ j TM-16 Baker Farm 7.2 W TM-18 Chewonki Foundation 1.2 WSW

[

TM-25 Hanson Farm 16.0 W

[

b. Fish and FH/MU/CA/HA-11 Long Ledge Area 1.1 S Invertebrates

MU/CA/HA/24 Sheepscot River 11.2 S

~

Indicator - -

c. Food Crop

TV-1X Vegetation (to be determined) -

TV-1X Indicator -

(to be determined) -

TV-2X to be determined -

Footnotas:

a Sample locations are shown on Figures 5.1 to 5.6.

b Station-lX's are indicator stations and Station 2-X's are control stations, c A dilution f actor of 10 shall be applied to any radioactivity detected in a

. sample at this station.

d The station code letters will vary with the sample media collected. The sampling of all four media types is not required during each sampling period.

e Food crop sampling is not required while milk sampling is being done.

53 5/92

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(

l Malt 4E YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MAIJUAL FIGUI,E 5.1

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Environmental Radiological Sampling Locations Within 1 Kilome_tf_r,_of Maine Yankee NN., ~

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MAlllE YANKEE ATOMIC POWER COMPAt4Y OFF-SITE DOSE CALCULAT10tt MANUAL flGURE 5,2

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Environmental Radiological Samplinq locations Within 12 Kilometers of Maine Yankee

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1 MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE 00$E CALCULATION MANUAL FIGURE 5.3

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MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL

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