ML20210T119

Forwards Effluent Treatment Sys Branch Revised Release Point Data,Based on Amends 25 & 26 to Psar.New Release Point Locations Noted on Encl Plot Plan

ML20210T119
Person / Time
Site:	Satsop
Issue date:	12/18/1975
From:	Burke W Office of Nuclear Reactor Regulation
To:	Markee E Office of Nuclear Reactor Regulation
References
CON-WNP-1663 NUDOCS 8605290739
Download: ML20210T119 (4)

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DEC 181975 Docket Nos. h 509 E. Markas, Leader, Meteorology Section, Site Analysis Branch, TR REVISIONS TO WPPSS IINITS 3 AND 5 EFFLUENT BRLRASE POINT DATA On November 6,1975, we provided information on WPPSS Units 3 and 5 release point data, based on information submitted by the applicant in a letter dated October 17, 1975. In PSAR A-ndments 25 and 26, submitted subsequent to that date, changes were made which affected the release point data. We have determined that the revised data given in Enclosure A is appropriate for use in your analysis. New release point locations are also noted on the attached plot plan.

Questions concerning these data should be addressed to P. Stoddart, cognizant en;;ineer assigned to this facility.

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k'. C. Burke Leader, Application Section Effluent Treatment Systems Branch Division of Technical Review

Enclosures:

1. Release Point Data

2. Site Plot Plan

, cc: J. Collins f W. Ga:nmill l

P. Stoddart

[ Docket Files 50-508-509 Distribution:

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ENCLOSURE A RELEASE POINT DATA FOR WNP 3/5 The release points listed below are keyed to the attached plant diagrams.

Elevations are above finished grade.

- 1. Fuel Handiing Building and Shield Building Ventilation Vents

. Vent Dimensions 8.5' i.d.

Flow Rate (avg) 42,100 cfm Effluent Velocity (avg) 740 fpm Temperature (avg) 104'F Elevation 90' Height Above Roof 37-1/2' Release Frequency Continuous from FHB Diffusers None Number of Vents 1 per unit

3. Turbine Building Roof Ventilation Vent l

Vent Dimensions 10.5' i.d.

Flow Rate (avg) 256,000 cfm Effluent Velocity (avg) 2,960 fpm i Temperature (avg) 104*F

) Elevation 145' ,

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Height Above Roof , 5' Release Frequency Continuous Diffusers None Number of Vents 1 per unit

6. Mechanical Vacuum Pump Discharge Vent

. Vent Dimensions 1.3' i.d.

Flow Rate (avg) 60 cfm Effluent Velocity (avg) 15 fpm Temperature (avg) 80*F Elevation 140' Height Above Roof 11' Release Frequency Continuous

. ' Diffusers None

• Number of Vents 1 per unit D

s 9, 10. Containment Purge Discharge Vent Vent Dimensions 3.5' i.d.

Flow Rate (avg) 30,000 cfm Effluent Velocity (avg) 3,100 fpm Temperature (avg) 90'F Elevation 70' Height Above Roof 3' f

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Release Frequency 24 purges per year Diffusers None Number of Vents 2 per unit 11, 12, 13, Auxiliary Building Ventilation Vents 14, 15, 16.

Vent Dimensions 3.5' i.d.

Flow Rate (avg) 26,900 cfm Effluent Velocity (avg) 2,800 fpm Temperature (avg) 104*F Elevation 70' Height Above Roof 3' Release Frequency Continuous Diffusers None Number of Vents 6 per unit

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• a 1 e DEC 17 1975 D. R. Muller, Assistant Director, for Environmental Projects, RL REVIEW OF APPLICANT'S RESPONSE TO APPENDIX I QUESTIONS - METEOROLOGY PLANT NAME: WPPSS Nuclear Projects Nos. 3 6 5 LICENSING STAGE:

DOCKET NUMBER: 50-50 50-509 MILESTONE NO. : NA RESPONSIBLE BRANCH: EP-4 The Meteorology Section, Site Analysis Branch has reviewed the applicant's response to the kequested Information for Appendix I Compliance Demonstration provided in Supplement No. 6 to the WPPSS 3 & 5 Environmental Report dated October 17, 1975.

Of the 16 separate items identified in the five requests for additional meteorological information, the applicant has provided complete responses to only eight. Inco.1:plete responses were provided for two items, while no information was provided for six items. The missing information included data on regional (within 50 miles of the plant) meteorological conditions characterizing expected atmos-pheric transport processes, as well as the applicant's calculated deposition (D/Q) values for radioiodines and particulates.

Because of the inadequate response of the applicant to these requests, it will be necessary (as stated in the third paragraph of the letter from the Constission to the applicant requesting the information) to l use a less complex meteorological calculational procedure, comparable in conservatism to that used in the past to demonstrate compliance with Appendix I guidelines.

This review was prepared by R. Kornasiewicz, Site Analysis Branch, TR.

! r i.wal Signed by n GL H. R. Benten Harold R. Denton," Assistant Director ,

for Site Safety Division of Technical Review Office of Nuclear Reactor Regulation -

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Form AEC 318 (Rev. 9 53) AICM C240 W u. s. oovanmusNT Pnimi s OFFicat te74 sas-tes

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D. R. ullar, Assistant Director, for vironmental Projects, RL REVIEW OF PLICANT'S RESPONSE TO APPENDII I QUESTIONf3 - METEOROLOGY PLANT NAME: PSS Nuclear Projects Nos. 3 & 5 LICENSING STAGE. CP DOCKET NUMBER: 508 & 50-509 MILESTONE No.: N/

RESPONSIBLE ERANCH: P-4 the MeteoroloSy Section. Site Arialygig Branch has reviewed th.e applicsut's response to t Requested Information for Appendix I Cesplitance Demonstration p vided in Supplement No. b to the WPPSS 3 & 5 Environrental Re rt caced October 17, 1971.

Of "the 16 seperate items reques d in the five tsquests for additiocol meteorological infotuation, the plicant has provided complete responses to only eight. Incompie reepenses sete prcvided for two items while no informaticq was ovided for six Stese. The missing information included data on agional (within 50 r.iles of the plant) meteorological conditicu c tracterizing espected atmos-phoric transport processes, ao vell as se applicant's calculated deposition (D/Q) values for rr.dioindines nd perticulateS.

Because of the inadequate response of the a alicant to these requests, it will be necessary (as stated in the third aragraph cf the letter from tne Comission to the applicant requesti the infortsatien) to use a less complex meteorological calculationa# rocedure, cowarable in conservatism to that used in the pact to deao trate compliange with Appendix ! guidelines.

This review was; prapared by R. Rornssiewice, Si",e ysie $ ranch, TR.

i Harold R. Denton, Aspistant Di ctor for Site Safety Division of Technical Review Office of Nucleat lient. tor Regulatio err.c a >

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DEC 17 571 D. R. Huller '

cc R. Ecyd W. Mcdonald J. Fansarella

8. Hannuar R. Reineman R. Denton Re C. DaToung L. Crutchfis1d SS Branch ChisJa W. Regan O. Parr J. Norris A. Bournia 7.. Kornasiewicz J. Coll R. Klecker D. Eisenhut ,

M. Williams S. Varga DISTRIBUTION:

DOCKET FILES NRR RDG SAB RDG orr cs, TR:SAB Q AK TR:SA , .

TR: /SS RKornasiewica :km EMarH e HDen 12/ 4 /75 12//f,/75 12/ ( 7 /75 12/ 75 Form AEC 318 (Rev. 9 SM AECM 0240 W u. e. sovammusht Paintene orncas sove.ase.see