Text

Semiannual Effluent Release Rept for Jul-Dec 1988
	ML20235W862
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1988
From:	Whittier G; Maine Yankee
To:	Russell W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	GDW-89-74, MN-89-25, NUDOCS 8903130221
	Download: ML20235W862 (15)
	v • d • e

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a MAINE YANKEE ATOMIC POWER COMPANY- 1 l

SEMIANNUAL EFFLUENT RELEASE REPORT July - December,.1988

1.0 INTRODUCTION

Tables 1 through 4 list the recorded' radioactive liquid nnd gaseous effluents and solid waste for the second six months of the year, with data summarized on a' quarterly basis.

Appendices A through E indicate the status of reportable items per the requirements of Technical Specifications 3.16.C 3.17.D, 3.28. A 3.28.B. 4.8. A, 4.13 and 5.9.1.6.

B 8903130221 881231 PDR R

ADOCK 05000309 PDC

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d TABLE 1A

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. .Haine Yankee Atomic Power Station j Effluent and Haste Discosal Semiannual Reoort q Third and Fourth Ouarters. 1988 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3rd 4th Error. %

A. Fission and Activation Gases

! 1. Total release Ci 1.49 E+01 5.69 E+01 2.50 E+01 i

2. Averace release rate for oeriod UCi/sec 1.90 E+00 7.24 E+00

3. Percent of reaulatory limit % 6.48 E-03 2.31 E-02 l

B. Iodines

1. Total Iodine-131 C1 1.06 E-05 4.33 E-04 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 1.35 E-06 5.51 E-05

3. Percent of reaulatory limit- % 1.18 E-05 4.83 E3Q4_

C. Particulate

1. Particulate with T-1/2 l 8 days Ci N/D* 2.32 E-05 2.50 E+01

2. Average release rate for oeriod uCi/sec N/A 2.95 E-06

3. Percent of reaulatory limit % N/A 7.21 E-08

4. Gross aloha radioactivity Cl_. 5.98 E-08 4.37 E-07

0. Tritium

1. Total release C1 1.25 E+00 2.24 E+00 2.50 E+01

2. Average release rate for oeriod UCi/sec 1.58 E-01 2.85 E-01

3. Percent of reaulatory limit % 6.97 E-04 1.25 E-03

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o TA8LE 18 Maine Yankee Atomic Power Station Effluent and Waste Discosal Semiannual Reoort l Third and Fourth Ouarters. 1988 l Gaseous Effluents - Elevated Release I

Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

1. Fission Gases Krvoton-85 Ci N/D* N/D* 6.53 E-02 1.42 E+00 Krvoton-85m Ci N/D* N/D* 5.71 E-05 3.46 E-03 Krvoton-87 Ci N/D* N/D* N/D* N/D*

Krvoton-88 Ci N/D* N/D* 7.00 E-05 N/D*

Xenon-133 Ci 1.37 E+01 2.95 E+00 7.74 E-02 5.03 E+01 Xenon-135 Ci 1.05 E+00 N/D* 1.43 E-03 1.68 E+00 Xenon-135m Ci N/D* N/D* N/D* N/D*

Xenon-138 Ci N/D* N/D* N/D* N/D*

Xenon-133m Ci N/D* N/D* N/D* 4.94 E-01 Xenon-131m Ci N/D* N/D* N/D* 9.04 E-02 Araon-41 Ci N/D* N/D* N/D* N/D*

Unidentified Ci N/D* N/D* N/D* N/D*

Total for oeriod Ci 1.48 E+01 2.95 E+00 1.44 E-01 5.40 E+01

2. Iodines Iodine-131 Ci 1.06 E-05 2.d4 E-05 2.96 E-08 4.13 E-04 Iodine-133 Ci 5.83 E-05 3.58 E-06 3.83 E-08 4.62 E-05 Iodine-135 Ci N/D* N/D* N/D* N/D*

Total for oeriod Ci 6.89 E-05 2.40E-05 6.79 E-08 4.59 E-04

3. Particulate Strontium-89 Ci N/D* N/D* N/D* N/D*

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

Cesium-134 Ci N/D* N/D* N/D* N/D*

Cesium-137 Ci N/D* 2.80 E-07 N/D* N/D*

Bari um-Lanthanum-140 Ci N/D* N/D* N/D* N/D*

Others Cobalt-58 Ci N/D* 2.76 E-06 N/D* N/D*

Cobalt-60 Ci N/D* 4.58 E-06 N/D* 1.39 E-05 Cadmium-109 Ci N/D* N/D* N/D* 1.70 E-06

N/D - Not Detected 8510L-OS

o TABLE 1C Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort Third and Fourth Ouarters 1988 Gaseous Effluents - Ground Level Releases There.uere no routine measured ground' level continuous or batch mode gaseous

releases during the Third and Fourth quarters of 1988.

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TA8LE 2A Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort .

Third and Fcurth Ouarters. 1988 Liauid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total l 3rd 4th Error. %

'A. Fission and Activation Products

1. . Total release (not including tritium. aases. aloha) Ci 1.56 E-02 2.99 E-01 1.50 E+01

2. Average diluted concentration durina Deriod UCi/mi 7.84 E-11 4.31 E-09

3. Percent of aoolicable limit 7. 2.53 E-03 1.40 E-02 l B. Tritium

1. Total release Ci 7.91 E+01 1.00 E+01 1.50 E+01

2. Average diluted concentration durina ceriod UCi/ml 3.97 E-07 1.44 E-07

3. Percent of aoolicable limit % 1.32 E-02 4.81 E-03 C. Dissolved and Entrained Gases

1. Total release Ci 9.88 E-03 8.02 E-03 1.50 E+01

2. Average diluted concentration i durina ceriod UCi/ml 4.96 E-11 1.16 E-10 l

3. Percent of aoolicable limit % 2.48 E-05 5.78 E-05 i D. Gross Alpha Radioactivity

1. Total release C1 2.73 E-06 1.34 E-C4 1.50 E+01

2. Average diluted concentration durina Deriod UCi/ml 1.37 E- 14 1.93 E-12 E. Volume of waste released (prior to dilution) liters 2.18 E+07 1.63 E+07 1.00 E+01 i

F. Volume of dilution water used f durina ceriod liters 1.99 E+11 6.93 E+10 1.00 E+01 l

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- IAELE RR Haine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort Third and Fourth Ouarters. 1988 l l

Liauid Effluents !

Batch Mode i Continuous Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th Strontium-89 Ci 3.29 E-03 N/D* 3.40 E-03 2.46 E-04 Strontium-90 Ci N/D* N/D* 5.01 E-05 N/D*

Cesium-134 Ci N/D* N/D* 4.56 E-05 4.20 E-03 Cesium-137 Ci 2.46 E-05 6.83 E-08 6.90 E-04 2.53 E-02

_lpdine-131 Ci N/D* N/D* 7.55 E-04 1.56 E-04 Cobalt-58 Ci N/D* N/D* 7.19 E-05 6.25 E-02 Cobalt-60 Ci N/D* N/D' 1.65 E-03 4.53 E-02 Iron-59 Ci N/D* N/D* N/D* 2.44 E-04 Zinc-65 Ci N/D* N/D* N/D* N/D*

Manaanese-54 Ci N/D* N/D* N/D* 5.85 E-04 Chromium-51 Ci N/D* N/D* 8.07 E-05 1.47 E-02 Zirconium-Niobium-95 Ci N/D* N/D* N/D* 1.04 E-03 Molybdenum-99 Ci N/D* N/D* N/D* N/D*

Technetium-99m Ci N/D* N/D* N/D* N/D*

Barium-Lanthanum-140 Ci N/D* N/D* 2.60 E-04 1.02 E-03 Cerium-141 Ci N/D* N/D* N/D* 6.74 E-05 Others Iron-55 Ci N/D* N/D* 4.17 E-03 1.70 E-02 Silver-110m Ci N/D* N/D* 2.02 E-04 4.53 E-03 Iodine-133 Ci N/D* N/D* 5.99 E-06 8.25 E-06_

Antiraony-124 Ci N/D* N/D* N/D* 9.20 E-02 Antimonv-125 Ci N/D* N/D' 8.78 E-04 2.96 E-02 Ruthenium-103 Ci N/D* N/D* N/D* 5.86 E-04 Ceri um-144 Ci N/D* N/D* N/D* 4.64 E-05 Cobalt-57 Ci N/D* N/D* N/D* 8.36 E-05 Tin-113 Ci N/D* N/D* N/D* 2.52 E-04 Ci N/D* N/D* N/D* N/D'

_Unidenti fi ed Total for oeriod (above)(1)Ci 3.31 E-03 6.83 E-08 1.23 E-02 2.99 E-01 Xenon-133 Ci 2.00 E-05 N/D* 8.55 E-03 7.99 E-03 Xenon-135 Ci 1.48 E-06 3.10 E-05 1.31 E-03 3.15 E-06 N/D* - Not Detected (1) - Total for period does not include unidentified in this summation but is included in Table 2A, Item A1.

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TABLE 3

! Haine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort First and Second Ouarters. 1988 Solid Haste and Irradiated Fuel Shioments A. Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*

Unit 6-Honth Est. Total

_ Period Error. %

! 1. Type of Haste

a. Spent resins, filter sludges, evaporator m3 9.41 10 bottoms. etc. - LSA container **.+++ Ci 33.90

b. Dry compressible waste, contaminated m3 77.72 10 eauipment. etc. - LSA container +.++ Ci 4.69

c. Irradiated components, control rods, m3 etc. Ci d. m3 Ci

e. m3 Ci

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

a. Fe-55 32% olus or minus 10%

Ni-63 45% olus or minus 10%

Co-60 23% otus or minus 10%

b. Cs-137 10% olus or minus 10%

Co-60 23% olus or minus 10%

Co-58 11% olus or minus 10%

Cs-134 3% olus or minus 10%

Ni-63 14% olus or minus 10%

Fe-55 27% olus or minus 10%

Zr-95 5% olus or minus 10%

Sb-125 2% olus or minus 10%

3. Solid Haste Disposition Number of Shioments Mode of Transportation Destination 5 from Maine Yankee Trucking over Highway Chem-Nuclear, Barnwell, S.C.

24 from SEG # Trucking over Highway Chem-Nuclear, Barnwell, S.C.

B. Irradiated Fuel Shipments (Disposition)

+ Container volume equal to 55 gallons (drums).

++ Container volume equal to 110 f t3 (boxes).

+++ Container volume equal to 170 ft3 (liners) (HIC)

Solid waste is Class A, as defined in 10CFR61.55. 84.0 m3 82.08 Ci

Solid waste is Class B, as defined in 10CFR61.55 2.35 m3,, 12.76 Ci

Solid waste is Class C, as defined in 10CFR61.55 .78 m3, 16.78 Ci

- Solidification agent is cement.

- - Excluding nuclides with half-lives less than 12.8 days.

SEG performs super compacting of DAH.

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. TABLE 4 Sunnlemental Information l

l .1. Reculatory Limits l

Maximum Permissible Concentration

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

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

c. Particulate, (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 uC1/mi

2. Averaae Enerav - Not Acolicable

.3. Measurements and Acoroximations of Radioactivity

a. Fission and Activation Cases 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.

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. Iodines Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.

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

d. Liauid 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 system liquid effluents for a quarterly analysis of Strontium-90 and Strontium-89.

Primary system liquid effluents are also analyzed quarterly for Iron-55.

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. TABLE 4 (Continued)

4. Batch Releases

a. Liouids

1. Number of batch releases: 123

2. Total time period for. batch releases: 340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months , 40 minutes

3. Maximum time period for a batch release: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 28 minutes

4. Average time period for batch releases: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 46 minutes

5. Minimum time period for a batch release: 15 minutes

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

7. Maximum gross release concentration (uCi/ml): 6.35 E-06

b. Gaseous

1. Number of batch releases: 38

2. Total time period for batch releases: 1609 hours0.0186 days 0.447 hours 0.00266 weeks 6.122245e-4 months , 58 minutes

3. Maximum time period for a batch release: 1007 hours0.0117 days 0.28 hours 0.00167 weeks 3.831635e-4 months , 39 minutes ,

4. Average time period for batch releases: 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months , 22 minutes !

5. Minimum time period for a batch release: 1 minute

6. Maximum gross release rate (uCi/sec): 2.16 E+03

5. Ahnormal Releases

, a. Liouid.

There were no abnormal liquid releases during the reporting period.

b. Gaseous There was one abnormal gaseous release during this reporting period. On August 19, 1988 while recharging a letdown demineralized, an estimated 0.0044C1 of noble gas activity escaped from the vessel. It was concluded that reactor coolant leaked by a shut valve during this iteration, resulting in the release. Activity associated with this event has been included in Tables 1A and B.

6. On-Line Containment Purae On-line containment purge was employed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months , 25 minutes during this period, which is the total time it was used during the year.

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APPENDIX A l

Radioactive Liauid Effluent Monitorina Instrumentation .

l Requirement: Radioactive liquid effluent monitoring instrumentation channels are l required to be operable in accordance with Technical Specification l 3.28.A. 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 Technical Specification 3.28.A requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resoonse: During this reporting period, three effluent monitors were inoperable in excess of 30 days when required to be operable.

As described in the previous semiannual report, the air ejector was out of service at the beginning of this reporting period.

Upon receipt of the required parts and calibration standards, the unit was successfully repaired, primary calibrated, and returned to service on September 1.

The service water monitor was declared inoperative on October 1

17. This was coincident with plant shutdown for refueling, and i loss of vacuum priming in the service water system which is required to supply flow through the monitor. Vacuum priming was restored, and the monitor was returned to service on December 12.

The primary vent stack noble gas monitor was taken out of service on November 8 for primary calibration. It remained out of service while all monitors in the primary vent stack monitoring system were likewise calibrated. The system and monitor were returned to service on December 29.

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APPENDIX B Licuid Radwaste Treatment System 1 Requirement: Hith radioactive liquid waste being-discharged without treatment with estimated ~ doses in excess of the limits in Technical Specification 3.17.C.1, a report must be submitted to the' Commission in the Semiannual Effluent Release Report for the period.

'Rpsoonse: -The requirements of Technical . Specification 3.17.C.1 were met during this period and, therefore, no report is required.

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APPENDIX C Gaseous Radwaste Treatment System

- Requirement: Hith radioactive gaseous waste being discharged _without treatment with doses in excess of the limits in Technical Specifications - 3.18.D.1, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period.

' Resoonse: The requirements of Technical Specification 3.18.D.1.were met during this period and, therefore...no report is required.

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APPENDIX D Lower Limit of Detection for Radiological Analyses Requirement: Technical Specification 4.13 requires that when unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.

Resoonse: Analyses were performed in such a manner that the stated LLD's were achievable under routine conditions. On occasion, with liquid samples, however, the presence of detected higher energy isotopes caused a compton background elevation. This interference was sufficient to make some of the specified LLD's in those liquid samples unattainable. This occurred in about 10% of'the samples for

. Zinc-65, and 4% for Iror-59. All other isotope LLD's were met.

During the period when 'tte. PVS monitoring system was out-of-service for primary calibratico, an alternate sampling system was in service. The lower sample flows through that system limited the attainment of the LLD's for those gas samples.

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J APPENDIX E Reactor Coolant System Activity Requirements: Technical Specification 5.9.1.3.B requires that a report, covering the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.2, be submitted annually for the previous calendar year.

The report.shall include (1) Reactor power history-starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the' first sample in which the limit was. exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each' result to include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 49 9

hours prior to the first sample in which the limit was exceeded; (4) Graph of the iodine-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

Resoonse: Primary coolnat activity did not exceed the limits of Specification 3.2 during the reporting period and, therefore, no report is required.

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MaineYankee AELIABLE ELECTRICITY FOR MAINE SINCE 1972 i

EDISON DRIVE . AUGUSTA. MAINE 04330 (207) 622 4868 February 28, 1989 HN-89-25 GDH-89-74 l

Region I UNITED STATES NUCLEAR REGULATORY COMMISSION 475 Allendale Road King of Prussia, Pennsylvania 19406 Attention: Mr. Hilliam T. Russell, 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 for the period July l', 1988 to December 31, 1988. The report includes the annual reactor coolant system activity report. There were no changes to the Off-Site Dose Calculation Manual. These reports are submitted in accordance with Technical Specifications 5.9.1.6 and 5.9.1.3B. ,

Very truly yours, HAINE YANKEE b 0 At/

G. D. Whittier, Manager Nuclear Engineering and Licensing GDH:B.JP Enclosure c: Mr. Richard H. Hessman Mr. Cornelius F. Holden Mr. Pat Sears Document Control Desk Mr. Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Haste American Nuclear Insurers m

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ML20235W862

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