ML20058Q297

Proposed Tech Specs Section 5.0,Paragraphs 5.7.2.4 Re Primary Coolant Sources Outside Containment & 5.7.2.13 Re Explosive Gas & Storage Tank Radioactivity Monitoring Program

ML20058Q297
Person / Time
Site:	05200001
Issue date:	10/20/1993
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20058Q293	List: ML20058Q290 ML20058Q297
References
NUDOCS 9310260136
Download: ML20058Q297 (4)

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{{#Wiki_filter:on 21 s 10: Z 14 ; P. 3 Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.3 Offsite Dose Calculation Manual (ODCM) (continued) c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCN was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.. month and year) the change was implemented. 5.7.2.4 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Low Pressure Core Flooder, High Pressure Core Flooder, Residual Heat Removal, Reactor Core Isolation Cooling, Hydrogen Recombiner, Post Accident Sampling, Standby Gas Treatment, Suppression Pool Cleanup, Reactor Water Cleanup, Fuel Pool Cooling and Cleanup, Process Sampling, Containment Atmospheric Monitoring, and Fission Product Monitor. The program shall include the following: a. Preventive maintenance and periodic visual inspection requirements; and b. Integrated leak test requirements for each system at refueling cycle intervals or less. 5.7.2.5 In Plant Radiation Monitoring This program provides controls to ensure the capability to accurately determine the airborne it, dine concentration in vital areas under accident conditions. Ttis program shall include the following: a. Training of personnel; b. Procedures for monitoring; and c. Provisions for maintenance of sampling and analysis equipment. (continued) ABWR TS 5.0-19 10/21/93 9310260136 931020 ~ PDR ADDCK 05200001 A PDR a

O *T, 2 ] '93: lO 21Hl'l P,.4 Procedures, Progrces, and Manuals ~ 5.7 5. 7' Procedures, Programs, and Manuals 5.7.2.12 Ventilation Filter Testing Program (VFTP) (continued) Reviewer's Note: Allowable penetration - [100% - methyl iodide efficiency for charcoal credited in staff safety evaluation)/ (safety factor). Safety factor - [5] for systems with heaters. d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below (i 10%): ESF Ventilation System Delta P Flowrate Control Room Habitability System Standby Gas Treatment System e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [t 10%) when tested in accordance with ASME N510-1989: ESF Ventilation System Wattage Control Room Habitability System Standby Gas Treatment System The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies. 5.7.2.13 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas l mixtures contained in the Offgas Systent-{-the ge:ntity :f r:di;::tivity contained-ir,-ga: :t:r:g: tank: cr-fed int th: effg: tre:trent cy: tem, end the qu:ntity :f radic ethity cent:ined in unpretected cutdeer liquid : tor:g: t:nk:}. The gaseous radioactivity quantities shall be determined following the (continued) ABWR TS 5.0-26 10/21/93

.WT 21 '93 10:2241 P.5 Procedures, Programs, and Manuals 5.7 . 5.7 Procedures, Programs, and Manuals 5.7.2.13 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) methodology in Branch Technical Position (BTP) ETSB 11-5, " Postulated Radioactive Release due to Waste Gas System Leak or Failure". 4: 'iquid redwate qu;nt4tia: chal' be determined in l ee< erd:nt: with [ Standard Review Pl:n, Sccticr 15.'.0, "Pc:teleted Radic: 44ve-Rcknt due to T:nk F;ilurcs"). The program shall include: i a. The limits for concentrations of hydrogen and oxygen in the Offgas System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); b. A surveillance program to ensure that the quantity of radioactivity ccatained in-[c Ch g:3-ter:g: t:r.k :nd-ded 'nte th: cffg;; tre:.te:nt Oy; tem] is less than the amount that would result in a whole body exposure of 2 0.5 rem to any individual in an unrestricted area, in the event of ten uneentrclled relet:0 cf the t:nk:' tentert:]; and inadvertent bypass of the Offgas Systems charcoal beds as analyzed in SSAR Section 15.7.1. c. A surveill:nce progr:m to on:ure tMt the qu;ntity of r:dic :tivity contained in :11 Outdc0r liquid r:dw;ste t;nks het are not -surrcunded by-liners,- dikes, cr w 112, -:-apable Of h0lding the tank:' s tents :nd th:t d0 n0t have t nk ov rf1:ws and ;;rr:unding :r:: d ra i r.: :enn::ted t; the [ Liquid R:dwaste Treatment System) i: less th:n the Om0unt th:t w:uld rc; ult in :Oncentret{::: 1::: th:r the -it: Of 10 CFR 20. Appendix B. T ble !!, 00le= 2,----:t th; ne:r:M pet +ble-weter Supply :nd th; nc;rc:t :urf :: :ter : pply in

r unr::t-ict d cre, " tF: cvent of an un:cntnMed rel:::: Of th: 1:nk;' ::ntert;.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies. (continued) ABWR TS 5.0-27 10/21/93

eX T 21 '93. 10:2CW1 P.1 a o O GENuclewEnergy gll} ABWW -~ a[e __10-21-93 l Fax No. To cuti postusn us n.n3 nRc This page plus 4 _ page(s) From acx rox Mail code ,o, 175 Curtner Avenue San Jose, CA 95125 Phone (408) 925-4874 -_ FAX (408) 925-1193 or (408) 925-1687 Subject _ suemitte, support 4na acce,eretes Aswa nev4ew schedule - Section 5.0 of the Technical Specifications Message 4 1 6

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