ML20101B075

Forwards Response to Agenda Item 11 Discussed During Ge/Nrc Reactor Sys Branch 911120-21 Meeting Re Credit for nonsafety-grade Equipment

ML20101B075
Person / Time
Site:	05200001
Issue date:	04/30/1992
From:	Stirn R GENERAL ELECTRIC CO.
To:	Pierson R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
EEN-9262, NUDOCS 9205050247
Download: ML20101B075 (3)

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< i S C, a A.: , t Sa >.Aco (4 9Wr April 30,1992 MFN No.103-92 Docket No. STN 52-001 EEN-9262 Document Control Desk.

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 -

Attention: Robert C. Pierson, Director Standardization and Non-Power Reactor Project Directorate

Subject:

GE Response to Agenda item 11 Discus ed During the GE/NRC Reactor Systems Branch Meeting on November 20-21,1991 Enclosed are thirty four (34) copies of the GE response to the subject discu.;sion item pertaining to credit for non safety grade equipment.

Sincerely, R. C. Stirn, Acting Manager

.. Regulatory and Analysis Services M/C 444, (408) 925-6948 cc: F. A. Ross ' _ _ (DOE)

N. D. Fletcher . (DOE)

C. Poslusny, Jr. (NRC)

G. Thomas (NRC)

R. C. Berglund. (GE)

J. F. Quirk (GE) s p/D i 9205050247 920430 PDR ADOCK-05200001 -

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'6 NON-SAFETY HELATED TRANSIENT MITIGATION FUNCTIONS EQUIPMENT ATTRIBUTES TO ENSURE OPERABILITY KEY EQUIFMENT RECIRCULATION PUMP STEAM BYPA5d LEVEL 8 ATTR!BUTES TRIP FijNOTION ' FUNCTION TRIP FUNCTtON Setsmic -

Seismic Qual.bcation is not -

Seismic Qualification is not -

Seismic Qua::lication is not required. This is consistent with required requereo requirements for other non-safety related equipment which Equipment enclosures and -

Equipment enclosures and perform mitigation tunctions anchoring 9:all be designed to anchoring shall be designed to (refer to Table A-1 of NEDE- maintain integrity during an maintain integrity during an 31096-P-A, " Anticipated .OBE to preciude damage to OBE to preciude damage to Transients without Scram, safaty-related equipment. safety related equipment.

Response to NRC ATWS Rule, 10CFR50.62-). -

Steam bypar,s eQJipment and

• Turbine stop valves, power control components have supply equipment, and Level

- Equipment enclosures and been shown through 8 trip instrumentation have anchoring shall be designed to operating experience to been shown through maintain integrity during an remain operable fo!!owing an 4 operating experience to OBE to preclude damage to OBE. remain operable folicwing an safety-related equipment. OBE.

Power supply equipment and control components have been shown through operating experience to remain operable following an OBE.

Periodic Testing - Sun e3nce testing on RPT -

Surveillance testing on bypass -

Surveillance testing on Level instrunwGalion required by valve opening response time 8 trip instrumentation required Tech Spc.'s required by Tech Specs by Tech Specs Quality Assurance -

OA program shallcomply with -

OA program shall comply with -

QA program sha'l comply wth the guidanco provided in the guidance provided in the guidance provided in Generic NRC Letter 85-06. Generic NRC Letter 85-06 Generic NRC Letter 85-06

'Ouality Assurance Guidance for ATWS Equipment that is not Safety-Related*

e NON-SAFETY RELATED TRANSIENT MITIGATION FUNCTIONS , j EQUIPMENT ATTRIBUTES TO ENSURE OPERABILITY KEY EQUIPMENT RECinCULATION PUMP STEAM BYPASS LEVEL 8 ATTRIBUTES TRIP FUNCTION FUNCTION TRIP FUNCTION Redundancy - Tripfcated ontroller and - Triplicated contro!!er and -

Triplicated level controller and communice-i ns communications communications for generating trip command Four output demand signal -

Three steam bypass valves voters (ona for each RIP - -

Triplicated turbine tripped) -

Three fast-open solenoid Electrohydraulic Control (EHC) valves (one for each bypass and four turbine stop valves Four RIP adjustable speed valve) for r :ain turbine trip flaiction drives (one for each RIP tripped) -

Three reactor feedpumps adjustable speed drives for feedwater trip function isolation -

Communication between -

Communication between -

Communication between redundant controt t er channels redundant controller channels redundant contro!!er channels through fioer optic links through fiber optic links through fiber optic links Environmental - Equipment shall meet the - Equipment shall meet the 1 -

Equipment shall meet the environmental conditions environmental conditions environmenta; conditions associated with Plant Normal associat?d with Plant Normal associated with Plant Normal Operating Conditioris (i.e., not Operating Conditions, as Operanng Conditions, as Design basis Accident specil:ed in Appendix 31 specified in Appendix 31 conditions) as specified in Appendix 31of the ABWR SSAR f

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