ML20064A435

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Semiannual Radioactive Effluent Release Rept,Jan-June 1990
ML20064A435
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/30/1990
From: Feigenbaum T
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90159, NUDOCS 9009040211
Download: ML20064A435 (20)
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. New. Hampshire Ted C. Foipenhovm Yg*, #'

Senior Vice President and Chief Operating Ofiker l

NYN. 90159 August 29, 1990 United States Nuclear Regulatory Commission i Washington, DC 20555  ;

Attention: Document Control Desk i i

References:

a) Facility Operating License NPF 67, Docket No. 50-443 b) Facility Operating License NPF 86, Jocket No. 50 443 I i

c) Seabrook Station Technical Specification 6.8.1.4, "Semlannual Radioactive Effluent Release Report" i

Subject:

Seabrook Station Semiannual Radioactive Effluent Release Report Gentlemen:

l In accordance with the requirements of Reference (c), enclosed is the Seabrook Station Semiannual Radioactive Effluent Release Report. ~51s report is submitted for the reporting period beginning January 1,1990, and ending June 30, 1990.

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 (c) is provided as appendices to the report. l Should you have any questions regarding this report, please contact Mr. Richard R.

Ilcianger at (603) 474 9521, extension 4048.

Very ;ruly yours, ,

{/ 4 Ted C. Feigenbaum b" ^

Enclosure TCF:CLII/ss!

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8S"28!A ?>88$3 New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
  • Seabrook, NH 03874
  • Telephone (603) 474 9521 (b p

,3 United States Nuclear Regulatory Commhslon August 29, 1990 Attention: Document Control Desk Page two cc: Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia,' PA 19406 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 i

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TAM 2 1A EFFIRINT AllB WASTE DISPOSAL S1HIAMIUAL REFCPT 1990 GASEIOS EITWBITS-SG90ATION OF ALL RELEA9ES Unit Quarter Quarter Est. Total l SEABROOK STATION 1 1 2 Error, 2 A. Fissian & activation gases

1. Total release Ci ND. E 4.06 E-10 1.70 E01 Average release rate for period pCi/sec ND. E 5.16 E-11
3. Percent of technical specification limit I NA. E 1.57 E-03 (1)

B. Iodines

1. Total iodine-131 Ci ND. E ND. E 1.50 E01
2. Average release rats for period pai/sec ND. E ND. E
3. Percent of technical specification limit I HA. E NA. E C. Particulates
1. Particulates with half-lives >8 days C1 ND. E ND. E 1.80 E01
2. Average release rate for period Ci/sec ND. E ND. E
3. Percent of technical specification limit  ! ND. E ND. E
4. Gross alpha radioactivity Ci NA. E NA. E D. Trititan
1. Total release Ci ND. E 1.85 E-02 1.60 E01
2. Average release rate for period pC1/sec ND. E 2.35 E-03
3. Percent of technical specification limit I NA. E 1.12 E-03 ND = none detected (1) Based on ganna air dose. The percent of applicable limit is 5.87E-042 based on the beta-air dose.

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TABLE 1A .

1 EFFIRMT AE MASTE DISP 0BAL SIDEAISIGAL REP 0tf 1990 '

cAnarnR EFFIDMTS-ELEVATED RELJEASES l l

CONTINU0US HODE BATCH MODE

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l Unit Quarter Quarter Quarter Quarter Nuclides Released 1 1 2 1 2

1. Fission gases krypton-85 Ci ND. E ND. E ND. E ND. E krypton-85m Ci ND. E ND. E ND. E ND. E krypton-87 C1 ND. E ND. E ND. E ND, E krypton-88 Ci "ND. E ND. E ND. E ND. E j xenon-133 Ci ND. E ND. E ND. E ND. E

__ xenon-135 C1 ND. E ND. E ND. E ND. E xenon-135m C1 ND, E ND. E ND. E ND. E '

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xenon-138 Ci ND. E ND. E ND. E ND. E ,

Others (specify) Ci . E . E . E . E Argon - 41 C1 ND. E ND. E ND. E 4.06 E-10 C1 . E . E . E . E unidentified C1 ND. E ND. E ND. E ND. E Total for period Ci ND. E ND. E ND. E 4.06 E-10 B. Iodines iodine-131 Ci ND. E ND. E ND. E ND. E iodine-133 C1 ND. E ND. E ND. E ND, E iodine-135 Ci ND. E ND. E ND. E ND. E Total for period Cl- ND. E ND. E ND. E ND. E C. Particulates strontium-69 Ci ND. E ND. E ND. E ND. E strontium-90 Ci ND. E ND. E ND. E ND. E cesium-134 Ci ND. E ND. E ND. E ND. E cesitan-137 C1 ND, E ND. E ND. E ND. E barium-lanthantan-140 Ci ND. E ND. E ND. E ND. E Others (specify) Ci ND. E ND. E ND. E ND. E Ci . E . E . E . E Ci . E . E . E , E unidentified Ci ND. E ND. E ND. E ND, E ND = none detected

e TAM 2 10 EFFLUBrF AIW WASTE DISPOSAL SBEAIGIGAL REPORT 1990 GASEQUS EFFLUBfTS-GRatBID 12 VEL RELEASES CONTINUOUS MODE BATCH HODE Unit Quarter Quarter Qaarter Quarter Nuclides Released 1 1 2 1 2 l

1. Fission gases krypton-85 Ci ND. E ND. E ND. E ND. E

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krypton-85m Ci HD. E ND. E ND. E ND. E krypton-87 Ci ND. E ND. E ND. E ND. E krypton-88 Ci ND. E ND. E ND. E ND. E xenon-133 Ci ND. E ND. E ND. E ND. E ,

xenE.35 Ci ND. E ND. E ND. E ND. E xenon-it'en C1 ND. E ND. E ND. E ND. E xenon-138 Ci ND. E ND. E ND. E ND. E Others (s.weify) C1 ND. E ND. E ND. E ND. E Ci . E . E . E , E Ci . E . E . E . E unidentified Ci ND, E ND. E ND. E ND. E Total for perloc. Ci ND. E ND. E ND. E ND. E B. InM nas iodine-131 C1 ND. E ND. E ND, E ND. E iodine-133 C1 ND. E ND. E ND. E ND. E lodine-135 Ci ND. E ND. E ND. E ND. E Total for period Ci ND. E ND. E ND. E ND. E l C. Particulates strontium-89 C1 ND. E ND. E ND. E ND. E strontium-90 C1 ND. E ND. E ND. E ND. E cesitun-134 C1 ND. E ND. E ND. E ND. E l

cesitun-137 Ci ND. E ND. E ND. E ND. E baritan-lanthantsn-140 Ci ND. E ND. E ND. E ND. E  !

Others (specify) Ci ND. E "_ ND, E ND. E ND. E Ci . E . E . E . E Ci . E . E . E . E unidentified C1 ND. E ND. E ND. E ND. E ND = none detected l l l

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. 6 TAM 2 2A EFFLDEFF AW UASTE DISPOSAL SMIAMUAL REPMT 1990 LIQUID EFF12BrTS-SGGETICEI W ALL RELEASES ,

Unit Quarter Quarter Est. Total 1 1 2 Error, 2 A. Fission and activation prodw;ts

1. Total release (not including trititsa, C1 ND. E 1.28 E-05 6.00 E00 gases, alpha)
2. Average diluted concentration during period C1/ml ND. E 6.60 E-11 ,
3. Percent of applicable limit  ! NA. E 1.19 E-07 (1)

B. Trititan  ;

1. Total release C1 3.76 E-03 8.65 E-02 8.00 E00
2. Average diluted concentration during period nCi/ml 2.52 E-11 4.46 E-10 '
3. Percent of applicable limit  ! 9.93 E-08 1.19 E-07 (1) [

C. Dissolved and entrairmi nases

1. Total release Ci ND. E ND. E 1.90 E01
2. Average diluted concentration during period C1/ml ND. E ND. E
3. Percent of applicable limit I NA. E NA. E

- D. Gros; tlpha radiosctaaty l

1. Total Release Ci ND. E ND. E 1.00 E01 E. Volume of waste released (prior to dilution) liters 1.42 E07 2.96 E07 1.30 E00 l

P. Volume of dilution water used during period liters 1.49 Ell 1.94 E11 9.00 E00 ND = none detected l (1) Based on the maxir.un organ dose. The percent of applicable limit is 3.97E-082 based on l

total body dose.

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TARM 2B EFFIDNrf AM) MASTE DISMISAL SBEADEUAL REFWT 1990 LIQUID EFFIRMrFS CONTINUOUS HODE BATCH HODE Unit Quarter Quarter Quarter Quarter Nuclides Released 1 1 2 1 2 strontium-89 Ci ND. E ND. E ND. E ND. E strontium-90 Ci ND. E ND. E ND. E ND. E cesium-134 Ci ND. E ND. E ND. E ND. E cesitun-137 Ci ND. E ND. E ND. E ND. E lodine-131 Ci ND. E ND. E ND. E ND. E cobalt-58 Ci ND. E ND. E ND E 1.28 E-05 cobalt-60 Ci ND. E ND. E ND. E ND. E 1ron-59 C1 ND. E ND. E ND. E ND. E zinc-65 Ci ND. E ND. E ND. E ND. E manganese-54 Ci ND. E ND. E ND. E ND. E chrcanium-51 Ci ND. E ND. E ND, E ND. E zirconium-niobium-95 ~

Ci ND. E ND. E- ND, E ND. E molybdenum-99 C1 ND. E ND. E ND. E ND. E technetium-99m C1 ND. E ND. E ND. E ND. E baritun-lanthantsn-140 Ci ND. E ND. E ND. E ND. E cerium-141 C1 ND. E ND. E ND. E ND. E ,

Other (specify) Ci ND. E ND. E ND. E ND. E i Ci . E . E . 3 . E I

Ci . E , E . E . E Ci . E . E . E . E Ci . E . E . E . E

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unidentified C1 ND. E ND. E ND. E ND. E [

l l Total for period (above) I Ci lND. E lND. E [T E I1.28E-05l l xenon-133 C1 ND. E ND. E ND. E ND. E l xenon-135 Ci ND. E ND. E ND. E ND, E l ND = none detected

TAM 2 3 M M 11&BTE DISPOS &L Egrrmt EEfMT 1990 SOLID if4STE AND IIRADIATED PUEL EIIWWFS A SOLID ifASTE SHIPPED OFFSITE P0g nm CE DISPOS &L (Not irradiated fuel)

Unit First Est. Total 6-month Error, 2 1.' Type of vaste (No shipnents made) Period

a. Spent resins, filter sludges, evaporator m3 . E bottoms, etc. C1 . E , E
b. Dry compressible waste, contaminated m3 . E equip, etc. Ci . E . E
c. Irradiated ccanponents, 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)
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3. Solid Waste Disposition i

l Number of Shirunents Mode of Transportation Destination None l' B. IRRADIATED FUEL SHIPMENTS (Disposition) i 1

Number of Shloments Destination l Mode of TranspoJtgign 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 S1HIANNUAL REPORT Supplemental Information 1990 First and Second Q2arters Facility: Seabrook Unit 1 Licensee: New Hampshire Yankee

1. Regulatory Limits
a. Fission and activation gases: 0.5 mrad per quarter g na air dose, 1.0 mrad per quarter beta air dose.

See note 1.

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

See note 1.

c. Particulates, hale lives > 8 days: Particulates and iodines are included in step b.
d. Liquid effluents: 1.5 mram per quarter total body and 5 mrem per quarter to any organ.
2. Maxim.im Pennissible Concentrations Protide the HPC's used in determining allowable releases rates or concentrations,
a. Fission and activation gases: 1 MPC
b. Iodines: 1 MFC
c. Particulates, half-lives > 8 days: 1 MPC
d. Liquid effluents: 1 MPC
3. Average Energy Not calculated at this time.
4. Measurements and Approximations of Total Radinactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition,
a. Fission and activation gases: Determined by gacuna spectroscopy.

Tote.1 error based on stack flow error, analytical error and calculated sampling error.

b. Iodines D.ntermined by collection on charcoal with subsequent ganna t,pectroscopy analysis. Total error based on stack flow error, analytical error and calculated sampling error.

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______.___m.___-._.______._______._______.__.__.--____.___.-___.-.___._._.______..-_.,.-_-_mmm _m_ - _______-__- __.__. _____m_____.__ _

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c. Particulates: Detersiined by colle% ion on fixed filter with subsequent ganen spectroscopy analysis, strontium is detet.'d.ned by ccunposite analysis of filters by liquid scinti nation, grose alpha by proportional counter, and iron 55 Lv liquid scintillation. Total error based on stack flow e.ror, analytical error and calculated sampling er.or.
d. 1.iquid Effluents: Determined by gansna spectroscopy, strontium of ccunposite/ b- liquid scintillation, tritium by liquid scintillation, alpha by proportional counter, and iron SS by liquid scintillation.

Total error based on the volume discharge error and analytical error.

5. Batch Releases.

Provide the following infonnation relating to batch releases of radioactive materials in liquid and gaseous effluents.

a. 1.iquid
1. Number of batch releases: 31
2. Total time for batch releases: 5749 minutes
3. Maxinu . time period for batch releases: 439 minutes
4. Average time period for batch release: 185.5 minutes
5. Mininnan time period for a batch release: 75 minutes
6. Average stream flow during periods of release of effluent into a flowing stream: 1.48 E06 liters per minute.
b. Gaseous
1. Number oi batch releases 44
2. Total tim 4 period for batch releases: 50137 minutes
3. Maxinann time period for a batch release 5901 minutes
4. Average time period for batch releases: 1139.5 minutes
5. Mininum time period for a batch releases: 6 minutes
6. Abnonnal Releases
a. 1.iquid
1. Number of releases: 0
2. Total activity releases: N/A
b. Gaseous
1. Number of releases: 0
2. Total activity released: N/A

-- x --- - - - - - - - - . _ . - - - - . -----.---_a -----._.___-.---------------_.----__--.-----,.__,__,_-_,_-____-_.__,,___,n__- -

_a__ .:__._a __ A____

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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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1 APPENDIX A i l

Off-Site Dose Calculation Manual .

I Reavirempnt: Technical Specification 6.13.2.b requires that licensee initiated i changes to the Off-Site Dose Calculation Manual be subnitted to the Ccumission in the Samiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. j Include in this changes to the Radiological Environmental Program j in accordance with Technical Specifications 3.12.1 and 3.12.2.

Resp mse: No changes were made to the Radiological Environmental Program or j to the Off-site Dose calculation Manual during this reporting i period.

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l APPENDIX B i Process Control Program Reauirement: Technical Specification 6.12.2.a requires that licensee initiated changes to the Process Control Program be submitted to the Consnission in the Samiannual 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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s APPENDIX C

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

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. APPENDIX D Radioactive Gaseous Effluent Monitorina Instrumentation Reauirement: Radioactive gaseous effluent mordtoring instrtsnentation channels are required to be op3rable in accordance with Technical Specification 3.3.3.10.b. With less than the mininun number of channels operable for 30 days. Technical Specification 3.3.3.10.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 gaseous effluent monitors were out of service for more than 30 days during this reporting period.

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Liould Holduo Tanks Reauirement: Technical Specification 3.11.1.4 limits the quantity of j radioactive saterial contained in any outside temporary tank. ,

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

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

during this reporting period. ]

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l APPENDIX F i

I Radweste Treatment Systems '

Reauirement: Technical Specification 6.14.1 tequires that licensee initiated major changes to the Radweste Treatment Systeens (liquid, gaseous, and solid) ba submitted to the Conmission in the Semiannual i Radioactive Effluent Release Report for the period in which the change was made.

Response: The following change to Radwaste Treatment Systems was .;

implemented during this report period.

I 88-TMOD-0034 Rev. 1 'Temoorary Liauld Vaste Domineralization Skid' This temporary modification is a revision to a temporary  ;

modification previously reported via New Hampshire Yankee Letter NYN-90053, dated March 1,1990, 'Seabrook Station Semiannual 3 Radioactive Effluent Release Report" 7.C. Feigenbaum to USNRC. i This temporary modification was made to provide additional flexibility in processing of liquid effluents. The change  :

provides process tie-in and support services for a mobile waste  ;

11guld treatment skid to process potentially radioactive liquid i effluent directly to the vaste test tanks. The temporary installation consista of hose connections in the permanent liquid waste system piping rpstream of the waste test tanks inlet isolation valves WL-V-166 and 16E, and vendor (Chem-Nuclear) supplied reinforced non-collapsible rubber hoses, waste liquid demineralization skid, and portable booster pump to return '

processed fluid to the waste test tanks. The skid and booster  ;

ptanp will be located in the solid waste storage area (Rm. WB508) I and the hose connections are located in the vaste test tank and l recovery test tank pump room (WB316). The hoses are routed from )

WB316 up through a pipe chase, over monorail WS-CR-8, and through a sleeve WB-025-WB507-2011 to the skid in WB508. The hoses are  ;

routed and supported such that there will be no hazard to J personnel or equipment, and no interference with WS-CR-8 )

operation. Booster pump power will be supply from a 480-VAC welding outlet and routed through the same sleeve. j l l Penna..ent floor drains are available in the area of the hose J connection, the vendor skid and in areas where the hoses are ,

wuted. These floor drains go directly to the floor drains tanks l for processing. Absorbent and temporary curbing may also be used I for spill control. l 1

Return flow from the skid is discharged at a point upstream of the process radiation monitor, 1-RM-RE-6514 maintaining its I operation as described in FSAR section 11.2.2._.c.

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o4 o APPENDIX F (continued)

Continued use of the domineraliser skid will be evaluated at the end of the first refueling outage.

This temporary modification changes the facility as shown by Figure 11.2-3 in the FSAR. It allws for the domineraluation M radioactive liquid effluent to be performed by a qualified vendor (Chem-Nuclear) System operation described in the FSAR, Section 11.2.1.la discusses the transfer of liquid from the floor drains tanks to various locations for_ process / discharge. The temporary modification allows for the transfer of liquid from the floor drains tanks to vendor's skid for processing and return to the waste test tank for direct discharge via the intake and discharge transition etructure if quality and radioactivity levels are within design limits. Radiation levels are monitored by 1-RM-RE-6514 prior to returning flow to the waste test tanks.

This modification does not affect any procedural requirements or ccurnitmente contained in the FSAR and does not constitute a test or experiment not described in the FSAR. The portion of the waste liquid system being modified is not nuclear safety related and is non-seismic category I. Liquid effluent concentrations are maintained below the limits specified in Technical Specification bases 3.11.1.

The probability or consequences of an accident, as discussed in FSAR section 11.2 and 15.7, will not be increased by this temporary modification. A failure of this modification would not increase the inventory of liquid used as the accident basis. The accident analysis in the FSAR is based on an uncontrolled release of radioactive liquids that are stored in or transferred to a liquid containing tank. All liquid containing tanks outside containment have been considered, including the floor drains tanks. The conclusion of this accident would not result in any uncontrolled surface release. The modification does not affect the final effluent concentrations as the original control and monitoring provisions remain in effect prior to discharge into the circulating water tunnels.

The waste liquid system is non-safety related and non-seismic category I. The vendor skid and booster pump are located in the solid waste storage area where no safety related equipaent is installed. Based on the design and layout of the equipnent important to safety cannot be physically damaged by the loss of structural integrity in any portion of the temporary modification. The probability or consequences of a malfunction of equipnent important to safety is not increased by this modification.

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  • O APPENDIX F fcontinued1

( l The possibility of an accident or malfun<: tion of a different type than any previously analyzed in the FSAR is not created by this  !

modification. The hoses and skid mounted equipment have been o hydrostatically tested to 225 psig based on the system operating pressure of 150 psig. The modification meets the design l standards required for the waste liquid system.  !

The avxlification does not reduce the margin of safety as defined in the technical specifications. The modification does not i interface with any safety-related equipnent. The Technical

( Specification bases 3.11.1, Liquid Effluents, is not affected.

Predicted releases of radioactive material in liquid effluents as j a result of this modification are maintained below those l previously predicted. The domineralization skid has a design  !

decontamination factor of 1000 based on new resin. The estimated l 3

additional spent resin generated from this source is 360 ft /yr.

The expected offsite exposure as a result of this modification remains below the maximum exposures previously estimated in the  ;

License application and amendments thereto.

The present data base for liquid effluent releases reflects very j limited system operation and release levels, therefore comparison '

of predicted released with actual data from the period prior to implanentation of the change does not reflect the full  ;

effectiveness of the modification. Operation of the l demineralizer skid was fully implemented in the 4th quarter of )

1989. As indicated in Table 2A, the low levels recorded during the 3rd quarter were reduced below detectable levels.

The exposure to plant operating psrsonnel as a result of this modification is estimated to be <5 man-rem / year.

This revision to the temporary modification was approved for implementation by SORC in meeting no. 90-4 on January 5,1990.

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APPENDIX G ]

Unclanned Releases  :

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Reauirement: Technical Specification 6.8.1.4 requires a list and description of unplanned releases from the site to UNRESTRICTED AREAS of

  • radioactive materials in gaseous and'11guid effluents made during the reporting period.  !-

Responses No unplanned releases to unrestricted areas were made during the  !

reporting period.

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