ML20035G131

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Forwards SSAR Markup Addressing Draft,Final Ser,Confirmatory Item 7.6.1.3-1 Re Instrumentation & Controls for Process Radiation Monitoring Sys & High Pressure/Low Pressure Sys Interlock Protection Functions
ML20035G131
Person / Time
Site: 05200001
Issue date: 04/14/1993
From: Fox J
GENERAL ELECTRIC CO.
To: Poslusny C
Office of Nuclear Reactor Regulation
References
NUDOCS 9304260199
Download: ML20035G131 (3)


Text

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GE Nuclear Energy cevs temc com;wy iib cG!! Del AVCHUB. kN JDSR cA 55II5 April 14,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and Ucense Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Review Schedule - DFSER-Confirmatory Item 7.6.13-1

Dear Chet:

Enclosed is a SSAR markup addressing DFSER Confirmatory Item 7.6.13-1.

Please provide a copy of this transmittal to im Stewart.

Sincerely, Y

Jack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)

Mike Song (GE)

BillTaft (GE) g7 ns90

nnnno, 9304260199 930414' DR ADOCK 05200001 PDR.

o ABWR CI ' 6 I 3-I St'andard Plant

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REV A tekting feature similar to that described 7.6.1.3 High Pressure / Low Pressure Systems for SSLC is also provided (see Subsection Interlock Protection Functions i

7.1.2.1.6).

(1) Function Identification l

(8) Emironmental Considerations l

The low pressure modes of the RHR which All APRM equipment is operated in the connect to the reactor coolant pressure environments described in Section 3.11. The boundary and the instrumentation which APRM is capable of functioning during and protects them from overpressurization are after the design basis events in which discussed in this section. Such high continued APRM operation is required (see pressure / low pressure interfaces with the Sections 3.10 and 3.11).

reactor vessel are exclusive to the RHR system for the ABWR. The RHR P&ID may be

}

7.6.1.2 Process Radiation Monitoring System -

found on Figure 5.4-10. The RHR IBD may be Instmmentation and Controls found on Figure 7.3-4 l

A number of radiation monitoring functions are (2) Power Sources l

provided on process lines, HVAC ducts, and vents I

that may serve as discharge routes for radio-The power for the interlocks is provided active materials. These include the following:

from the essential power supplies used for the RHR system and its various modes of (1) Main steam line tunnel radiation monitoring operation.

(2) Reactor building ventilation system radia-(3) Equipment Design tion monitoring (including fuel exchange area)

Refer to Table 7.6-3 for a list of high pressure / low pressure interfaces and the (3) Liquid radiation monitoring rationale for valve interlock equipment.

(4) Off-gas radiation monitoring (4) Circuit Descripti NO 9

(5) Gland steam condenser and mechanical.acuum At least two valves are provide in series pump off-gas radiation monitoring in each of these lines. The RH shutdown FOIL cooling supply valves (Ell-and Ell-(6) Stack radiation monitaring

' FOi3) have independent sets of interlocks to prevent the valves from being opened j

(7) Off-gas system area exhaust radiation moni.

when the primary system pressure is above toring the subsystem design pressure or when reac-l tor water level is below Level 3. These (8) Standby gas treatment ventilation system ra-valves also receive a signal to close when diation monitoring reactor pressure is above system pressure < (*g

  • or reactor water level is +beved.evel 3.

(9) Drywell drain radiation monitoring An additional interlock is RHR equipment area ambient temperature (not shown on The process radiation subsyste.ms are shown in Table 7.6-3).

the system design IED (Figure 7.6-5). Subsys-tems A and B, above, are classified nuclear The RHR shutdown cooling /LPFL injection safety-related whili subsystems C through I are valve E11-FO47 is interlocked to prevent classified as nonsafety-related. System descrip-valve opening whenever the reactor pressure tions and requirements are described in detailin is above the subsystem design pressure, and Section 11.5.

automatically closes whenever the reactor Amendment 2 744

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