ML20065L305

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Forwards Amend 15 to Advanced BWR Ssar
ML20065L305
Person / Time
Site: 05000605
Issue date: 11/30/1990
From: Marriott P
GENERAL ELECTRIC CO.
To: Chris Miller
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20065L307 List:
References
MFN-145-90, NUDOCS 9012060038
Download: ML20065L305 (2)


Text

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"i 175 Curtner A.enue Se Jose CA 95125 November 30,1990 MFN No.143 90 Docket No. STN 50-605 EEN.9073 l

Document Control Desk U.S. Nuclear Regulatory Commission Washington,D.C. 20555 l

! Attention: Charles L Miller, Director Standardization and Non Power Reactor Project Directorate l

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Subject:

Submittal of Amendment 15 to GE's ABWR SSAR

Reference:

1. Submittal of Amendment 15, Proprietary Information, to GE's ABWR SSAR, MFN No.146-90, dated November 30,- 1990

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2. Submittal of Amendment 15 to GE,s ABWR SSAR, Chapter 13, Conduct of Operations, MFN No.147 90, dated November 30, 1990

Dear Mr. Miller:

l Enclosed are thirty four copies of selected sections of Chapter 1, Introduction and General Description of Plant, Chapter 2, Site Chamcteristics, Chapter 3, Design of Stmetures, Components, Equipment, and Systems, Chapter 4, Reactor, Chapter 5, Reactor Coolant System and Connected

' Systerru, C1, apter 6, Engineered Safety Features, Chapter 7, Instrumentation and Control Systems, Chapter 9, Auxillary Systems, Chapter 10, Steam and Power Conversion System, Chaptc r 11, P"Mve Waste Management, Chapter 13, Canduct of Opemtioru, Chapter 15, Accident Analysis,

' Chapter 18, Human Factors Engineering, Chapter 19, Resporue to Severe Accident Policy Statement, Chapter 20, Question and Responte Guide, of the Standard Safety Analysis Report (SSAR) for the

- Advanced Boiling Water Reactor (ABWR).

This submittai includes the addition of the following information: reactor internal pump probability analysis, pressure regulator downscale failure probability analysis and ATWS l

L performance analysis to Chapter 15; ABWR shutdown risk to Chapter 19; Chapters 1,4,5,6,9 & 15 l to include update of fuel related sections; site suitability for design basis and PRA to Chap:er 2; response to Chapter 3 open items; update of Chapters 5 & 15 including conversion to metric

-liniu; insider sabotage risk design considerations to Chapter 19; responses to Request for AdditionalInformation dated August 15,1990 to Chapter 13 and Chapter 20.

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Document Control Desk Docket No. STN 50 605 U.S. Nuclear Regulatory Commission MFN No.145 90 November 30,1990 Page 2 i

In addition there are other changes to various sections of the SSAR which are identified, along  :

I with the above changes, on the page change instruction sheet. Also, enclosed is a set of revised pages for the Page Status listing.

Please note that all or parts of the following sections cont:in information that is designated as General Electric Company proprietary information: 2A,4.3,4B,4C,6.3,11.2,11.3,15C, ISD, 19B,19E,19L & 20.3. This information is being submitted under separate cover (Reference 1).  !

Safeguards Information, included in Sections 13.6 and 20.3, is being submitted under separate cover per 10 CFR 73.21 (Reference 2).

Sincerely, y

P.W.Narriott, Manager el '

Regulatory and Analysis Services 1

L ' cc: D. R. Wilkins (GE) l T. E. Murley (NRC) l - D. M. D.utchfiald (NRC) >

l D. J. McGoff L OE) '

F. J. Mimglia, Jr. (NRC)

' D. C. Sea.etti (NRC)

- K. E. Stahlkopf (EPRI)

F. A. Ross '(DOE) -

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