ML20101B075

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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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< n:l a ix cma s 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

/

A PDR

'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.

Sun e3nce testing on RPT Periodic Testing 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 er channels redundant controller channels redundant contro!!er channels t

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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