ML20246N213

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Semiannual Radioactive Effluent Release Rept,890130-0630
ML20246N213
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/30/1989
From: Feigenbaum T
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89107, NUDOCS 8909080062
Download: ML20246N213 (17)
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, August 30, 1989 United States Nuclear Regulatory Commission Washington, DC- 20555 Attention:~ Document Control Desk

References:

a)' Facility Operating 'icense NPF-67, Docket No. 50-443 b) Seabrook Station Technic $1 Specification 6.8.1.4, " Semiannual Radioactive Effluent Reltsee Report"

Subject:

Leabrook Station Semiannual Radioactive Effluent Release Report Gentlemen:

In accordance with the requirements of reference (b), enclosed is the Seabrook Station Semiannual Radioactive Effluent Release Report. This report

'is submitted for the reporting period beginning with the initial criticality of Seabrook. Station, which was achieved on June 13, 1989, and ending

. June 30, 1989.

'The effluent and waste disposal information contained in this report is submitted in the format specified by Appendix B to Regulatory Guide 1.21 Revision 1 (June 1974). The additional information required by Reference (b)

'is provided as appendices to the report.

Should you have any questions regarding this report, please contact Mr. Richard R. Belanger at (603) 474-9521, extension 4048. #

V ry truly your ,

/,M &

Ted C. Feigenb Senior Vice President and Chief Operating Officer Enclosure 8909080062 890630 [

PDR ADOCK 05000443 PDC R / l i

New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

  • Seabrook, NH 03874
  • Telephone (603) 474-9521

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1 United States Nuclear Regultstory Commission- ' August 30, 19891

. Attention: -Document Control' Desk Page 2 L

cc Mr. William T. Russell Regional Administrator United' States Nuclear Regulatory Conmission Region I. .

475 Allendale Road King 7f Prussia, PA 19406 Mr.1 Victor Nerses,' Project Manager Project Directorate I-3' United States Nuclear Regulatory Connission Division of. Reactor Projects Washinston, DC 20555 Mr. Antone C.'Cerne NRC' Senior Resident Inspector

..P.O.~ Box 1149 Seabrook, NH 03874

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m- ,. q TABLE 1A EEFLDENT AND WASTE DISPOSAL SIBGAIEIDAL REPORT 1989 GASE00S EFPLUllNTS-SWORTION OF ALL RELEASE Unit Quarter quarter Est. Total SEABROOK STATION 1 1 2 Error, I A. Fission & activation gases lc 1. Total release f Ci . E ND. .E . E l 2. Average release rate for period pCi/sec . E ND. E l .

3. Percent of technical specification limit i . E ND. E B. tam nas
1. Total iodine-131 Ci . E ND. E' . E
2. Average release rate for period Ci/sec . E ND. E
3. 'ercent of technical specification limit Z . E ND, E C. Particulate
1. Particulate with half-lives >8 days Ci . E ND. E . E
2. Average release rate for period pCi/sec . E ND. E
3. Percent of technical specification limit I . E ND. E
4. Gross alpha radioactivity Ci . E ND. E D. Trititua
1. Total release Ci . E 1.05 E-05 3.0 E01
2. Average release rate for period pCi/sec . E 1.35 E-06
3. Percent of technical specification limit I . E ND. E NOTE: Initial criticality occurred on June 13, 1989.

ND = none detected

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9 TABLE IB EFFLUENT AND WASTE DIS 196AL SEMIANNUAL REPORT 1989 GASE00S EFFLUENTS-StBHLTION OF ALL RELFASES l ..

l CONTINUOUS MODE BATCH MODE j Unit Quarter Quarter Quarter Quarter '

i->, Nuclides Released- u 1 1 2 1 2

.1. Fission gases ]

'r.rypton-85 Ci . E ND. E . E ND. E krypton-85m _ Ci . E ND. E . E ND. E krypton-87 ,

Ci . E ND. E - E ND. E krypton-88 ,

Ci . E ND. E . E ND. E xenon-133 Ci . E ND. E . E ND. E

- xenon-135 Ci . E ED. E . E ND. E xenon-135m Ci . E. ND. E . 'E ND. E xenon-133 Ci' . E ND. E . E ND. E OthetT(specify) Ci . E ND, E . E ND. E Ci . E . E . E . E Ci . E . E . E . E unidentified Ci . E ND. E . E ND. E Total for period Ci . E ND. E . E ND, E B. Iodines iodine-131 Ci . E ND. E . E ND. E iodine-133 Ci . E ND. E . E ND. E iodine-135 Ci . E ND. E . E ND. E Total for period Ci . E ND. E . E ND. F l C. Particulate strontium Ci . E ND. E . E ND. E strontium-90 Ci . E ND. E . E NE. E

- cesium-134 Ci . E ND. E . E ND. E cesiur,137 Ci . E ND. E . E ND. E barium-lanthanum-140 Ci . E ND. E . E ND. E Others (specify) Ci . E ND. E . E ND. E Ci . E . E . E . E Ci . E- . E , E . E

- unidentified Ci . E ND. E . E 10. E NOTE: Initial criticality occurred on June 13, 1989. No activity was detected during this period.

ND = none detected

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,  ;/4" ' TABLE 1C EITIRENT RED WASTE DISPOSAL SEMIANNUAL REPORT 1989 GASB00S EFFIRENTS-GitutMD LEVEL RELEASES CONTINUOUS MODE BATCH MODE Unit Quarter Quarter -Quarter Quarter Nuclides 1 Released 1 1 2 1 2

1. Fission gases krypton-85 Ci . E- ND. E .. E ND. E krypton-85m Ci . E ND. ,,E . E ND. E krypton-87 Ci . E ND. E . E ND. E krypton-88 Ci ,,

. E ND. E . E ND. E xenon-133 Ci . E ND. E . E ND. E xenon-135 Ci . E ND. E . E ND. E-xenon-135m Ci . E ND. E . E- ND. -E xenon-138 Ci . E ND. E . E ND. E Others (specify) Ci- . .E ND. E . E ND. E Ci . E . E . E . E Ci . E . E . E . E unidentified __~

Ci . E ND. E . E ND. E Total for period Ci . E ND. E . E ND. E B. Iodines iodine-131 Ci . E ND. E . E ND. E iodine-133 Ci . E ND. E . E ND. E iodine-135 Ci . E ND. E . E ND. E Total for period Ci . E ND. E . E ND. E C. Particulate l -strontium-89 Ci . E ND. E . E ND. E

'i strontium-90 Ci . E ND. E . E ND, E cesium-134 Ci . E ND. E . E ND. E nesium-137 Ci . E ND. E . E ND. E barium-lanthanum-140 Ci . E ND. E . E ND. E Others (specify) Ci . E ND. E . E ND. E Ci . E . E . E . E Ci E , E . E . E unidentified Ci . E ND, E . E ND. E NOTEt: Initial criticality occurred on June 13, 1989. No activity was detected during this period.

HD = none de.tected l

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EFFLUENT AND WASTE DISPOSAL SEMIAlWGAL REPCET 1989 LIQUID EFFLDENTS-StBSETIGi W ALL RELEASES Unit Quarter Quarter Est'. Total 1 1- 2 Error, !-

'A. Fission and activation rod i.s -

l'. Total release (not including tritium, Ci . E ND. E . -E' gases, alpha)~

p

2. Average diluted concentration during period Ci/ml . E ND. E
3. Percent of applicable limit I . E ND .- E B. Trititan
1. Total release- Ci . E ND, E . E.

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2. Average diluted concentration during period' pCi/ml . E ND. E
3. Percent of applicable limit.  % . E ND. E C. Masolved and entr=i==i gases
1. Total release Ci . E ND. E . E
2. Average diluted concentration during period Ci/ml . E ND. E
3. Percent of applicable limit ~ I . E ND. E.

-D. Gross alpha. radioactivity

1. Total Release Ci . E ND. E . E E. Volume of waste released (prior to dilution) liters . E 3.56 E6 1.0 E01 F. Volume of dilution water used during periol liters . E 3.35 E10 1.0 E01 NOTE -' Initial criticality occurred on June 13, 1989. No activity was detected during this period.

ND -.none detected

TABLE 2B EFFLUENT AND WASTE DISPOSAL Sf!MIANNUAL REPORT 1989 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter Nuclides Released 1 1 2 1 2 strontium-89 Ci . E ND. E . E ND. E strontium-90 Ci . E ND. E . ~3 ND. E cesium-134 Ci . E ND. E . E ND. E cesium-137 Ci . E ND. E . E ND. E iodine-131 Ci . E ND. E . E ND. E

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cobalt-58 Ci . E ND. E . E ND. E cobalt-60 Ci . E ND. E . E ND. E iron-59 Ci . E ND. E . E ND. E zinc-65 Ci . E ND. E . E ND. E manganese-54 Ci . E ND. E . E ND. E chromium-51 Ci . E ND. E . E ND. E zirconium-niobium-95 Ci . E ND. E . E ND. E molybdenum-99 Ci . E ND. E . E o ND. E technetium-99m Ci . E ND. E ._____ E ND. E barium-lanthanum-140 Ci . E ND. E . E ND. E cerium-141 Ci . E ND. E . E ND. E Other (specify) Ci . E ND. E . E ND. E Ci . E . E . E .

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Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E . E l unidentified Ci . E ND. E . E ND. E l Total for period (abov7) l Ci l .

E lND. E l . E lND. E l l xenon-133 Ci . E lND. E . E ND. E l xenon-135 Ci . E l ND. E . E ND. E l NOTE: Initial criticality occurred on June 13, 1989. No activity was detected during this period.

I ND = none detected l

TABLE 3 EFFLUDfT AND WASTE DISPOSAL SDfIANNUAL REPORT 1989 SOLID WASTE AND IRRADIATED FUEL SHIIMDfTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Unit First Est. Total 6-month Error, I

1. Type of waste (No shipnents made) Period
a. Spent resins, filter sludges, evaporator m3 . E bottms, etc. Ci . E . E
b. Dry compressible waste, contaminated m3 . E equip, etc. Ci . E . E
c. Irradiated c mponents, control rods etc. m3 . E Ci . E . E
d. Other (described) m3 . E Ci . E . E
2. Estimate of major nuclide composition (by type of waste) l l l B* s s n l l l l l l
b. -

l l l l l l l l

c. l l l l l l l l l
d. l l l l l l t I i
3. Solid Waste Disposition Number of Shitrnents Mode of Transportation Destination None B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shitxnents Mode of Transportation Destination None NOTES

1) Class A waste
2) Class B waste
3) Class C waste
4) Type of container =
5) Type of container -
6) Solidification agent =

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  • Page 1 EFFLUENT AND WASTE DISPOSAL SD4IANNUAL REPORT Supplemental Information 1989 Second Quarter Facility: Seatrrook Unit 1 Licensee: New Hampshire Yankee
1. Reculatory Limits
a. Fission and activation gases: 0.5 inrad per quarter gama air dose, 1.0 mrad per quarter beta air dose.

See note 1.

b. Iodines: 0.75 mrem per quarter to any organ.

See note 1.

c. Particulate, half-lives > 8 days: Particulate and lodines are included in step b.

. d. Liquid effluents: 1.5 mrem per quarter whole body and 5 mrem per quarter to any organ.

2. Maximum Permissible Concentrations Provide the MPC's used in detemining allowable releases rates or concentrations.
a. Fission and activation gases: 1 MPC
b. Iodines: 1 MPC
c. Particulate, half-lives > 8 days: 1 MPC
d. Liquid effluents: 1 MPC
3. Averste Energy Not calculated at this time, fission and activation gases were not released this period.
4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclides composition.
a. Fission and activation gases: Determined by gama spectroscopy.
b. Iodines Determined by collection on charcoal with subsequent gamma spectroscopy analysis.
c. Particulate: Determined by collection on fixed filter with subsequent gama spectroscopy analysis, strontium is determined by composite analysis of filters by liquid scintillation, gross alpha by proportional counter, and iron 55 by liquid scintillation.
d. Liquid Effluents: Determined by gama spectroscopy, strontium of ecxnposite by liquid scintillation, tritium by liquid scintillation, alpha by proportional counter, and iron 55 by liquid scintillation.

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5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.
a. Liquid
1. Number of batch releases: 13
2. Total time for batch releases: 5685 minutes
3. Marine time period for batch releases: 1044 minutes
4. Average time period for batch release: 437 minutes
5. Minimum time period for a batch release: 85 minutes
6. Average stream flue during periods of release of effluent into a flowing stream: 1.35 E06 liters per minute.
b. Gaseous
1. Number of batch releases: 5
2. Total time period for batch releases: 6972 minutes
3. Marin e time period for a hatch release: 4588 minutes
4. Average time period fet batch releases: 1394 minutes
5. Minimum time period for a batch releases: 433 minutes
6. Abnormal Releases
a. Liquid
1. Number of releases: 0
2. Total activity releases: N/A
b. Gaseous
1. Number of releases: 0
2. Total activity released: N/A NOTES

' 1. Pending review and resolution of the staff's concern regarding applied dispersion parameters for Method I gaseous dose calculations, these limits reflect a reduction by a factor of 10.

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APPENDIX A Off-Site Dose Calculation fianual Requirement: Technical Specification 6.13.2.b requires that licensee initiated changes to the Off-Site Dose Calculation Manual be suhnitted to the Ccanission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

Include in this changes to the Radiological Environmental Program in accordance with Technical Specifications 3.12.1 and 3.12.2.

Responses No changes to the ODOi or Radiological Environmental Program were made during this reporting period.

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MPDEDE B Process Control Program IReouirement Technical Specification 6.12.2.a requires that licensee initiated changes to the Process Control' Program be suhaitted to the-Commission in the Semiannual Radioactive Effluent Release Report' for the period'in which the changes (s) were made.

-Response . No changes to the Process Control Program were made during this reporting period.

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APPENDIX C l

Radioactive Liould Effluent Monitorina Instrumentation 1

Requirement: Radioactive liquid effluent monitoring' instrumentation channel's are. required to.be operable in accordance with Technical Specification 3.3.3.9.b. With less than the min 4== number of channels operable for 30 days . Technical Specification 3.3.3.9.b~

requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report in

.accordance with Technical Specification 6.8.1.4.

' Responses No radioactive liquid effluent monitors were out of service for more than 30 days during this reporting period..

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j f l APPENDIX D i

Radioactive Gaseous Effluent Monitoring Instrumentation )

1 Requirement: Fedioactive gaseous effluent monitoring instrumentation channels )

are required to be operable in accordance with Technical '

Specification 3.3.3.10.b. With less than the min 4== number of channels operable for 30 days, Technical Specification 3.3.3.10.b requires an explanation for the delay in correcting the inoperabil.ity in the next Semiannual Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Response: The turbine gland seal condenser exhaust sampler (1-RM-CP-510) required by Technical Specification 3.3.3.10.b was out of service from May 6, 1989 through July 6, 1989, due to inadequate sample flow. A design change which adds a pump to this system will be completed prior to plant restart for power ascension.

,7 APPENU.~2 E I l

Liould Holduo Tanks Reonirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank.

With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.11.1.4, a description of the evente leading to this condition is required in the next Semiannual Effluent Release Report in accordance with Technical Specifiertion 6.8.1.4.

Response: The limits of Technical Specification 3.11.1.4 were not exceeded ,

during this reporting period. I i

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_ APPENDIX P i'

Radwaste Trestment Systems Requirement: Technical Specification 6.14.1 requires that licensee initiated major changes to thri Radwaste Treatment Systems (liquid, gaseous, 3 and solid) be suhnitted to the Coninission in the Semiannual ]

Radioactive Effluent Release Report for the period in which the change was made. ]

3 Response: No major changes to Radwaste Treatment Systems which would require reporting pursuant to Technical Specification 6.14.1 were made during th!: reporting period.

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finnlanned Releases l-

-1gpirement: Technical Specification 6.8.1.4 requires a' list and description-

, _of unplanned releases from the site to UNRESTRICTED AREAS of~

. radioactive saterials in gaseous and liquid effluents made during the reporting period.

', Response:- No unplanned releases to unrestricted areas were made during the reporting period.

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