ML20070C993

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Forwards Amend 16 to Advanced BWR SSAR
ML20070C993
Person / Time
Site: 05000605
Issue date: 02/22/1991
From: Marriott P
GENERAL ELECTRIC CO.
To: Chris Miller
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20070C995 List:
References
EEN-9111, MFN-018-91, MFN-18-91, NUDOCS 9102280031
Download: ML20070C993 (2)


Text

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'T'N February 22,1991 MFN No. 018 91 Docket No. STN 50-605 EEN 9111 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:

Charles L MiUer, Director Standardization and Non Power Reactor Project Directorate i.

Subject:

Submittal of Amendment 16 to GE's ABWR SSAR Submittal of Amendment 16, Proprietary Information, to GE's

Reference:

ABWR SSAR, MFN No. 019 91, dated February 22,1991

Dear Mr. Miller:

. 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 Structures, Components, Equipment, and Systemr, Chapter 4 Reactor, Chapter 5, Reactor Coolant System and Co Systems, Chapter 6, Engineered Safety Features, Chapter 8, Electric Power, Chapter 9, A

. Systems, Chapter 10, Steam and Power Conversion System, Chapter 11, Radioac:ive Wast Management, Chapter 13, Conduct of Operations, Chapter 15, Accident Analysis, Chapter 1 Respome to Severe Accident Policy Statement, and Chzpter 20, Question and Response (ABWR).

. Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor This submittal includes the addition of the following information: control building fire hazards analysis; control building seismic and structural design; turbine building HVAC; and respo Request for Additional Information dated May 4,1990, July 27,1990, August September 19,1990 to Chapter 20.

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5 Document Control Desk Docket No. STN $0-605 U.S. Nuclear Regulatory Commission MFN No. 018 91 February 22,1991 Page 2 In addition there are other changes to various sections of the SSAR which are identified, along with the above changes, on the page change instruction sheet. As noted on the page change instruction sheet, the 11 x 17 drawings will be sent under a separate cover. That submittal will also include a set of revised pages for the Page Status listing.

Please note that all or parts of the following sections contain information that is designated as General Electric Company proprietary information: 13,4B,63,9.2,93,9.4,9.5,9A.2,9A3,9A.4, 9A.5,9A.6,11.2,113, ISB, & 203. This information is being submitted under separate cover (See Reference).

Sincerely, W

P.W. h rriott, Manager Regulatory and Analysis Senices cc:

D. R. Wilkins (GE)

T. E. Murley (NRC)

D. M. Crutchfield (NRC)

D.J. McGoff (DOE)

F. J. Miraglia, Jr. (NRC)

D. C. Scaletti (NRC)

K. E. Stahlkopf (EPRI)

F. A. Ross (DOE) l t.

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February 22,1991 MFN No. 018 91 Docket No STN 50-605 EEN 9111 Document Control Desk U.S. Nuclear Regulatog Commission Washington, D.C. 20555 Attention:

Charles L Miller, Director Standardization and Non Power Reactor Project Directorate

Subject:

Submittal of Amendment 16 to GE's ABWR SSAR

Reference:

Submittal of Amendment 16, Pro ictary Information, to GE's ABWR SSAR, MFN No. 019 91, dated February 22,1991

Dear Mr. Miller:

Enclosed are thirty four copies of selected sections of Chapter 1, Introduction and General Description of Plant, Chapter 2, Site Characteristics, Chapter 3, Design of Structures, Cornponents, Equipment, and Systenu, Chapter 4, Reactor, Chapter 5, Reactor Coolant System and Connected Systems, Chapter 6, Engineered Safety Features, Chapter 8, Electric Power, Chapter 9,hatiliary

. Systems, Chapter 10, Steam and Power Conversion System, Chapter 11, Radioactive Waste

-Management, Chapter 13, Conduct of Operations, Chapter 15, Accident Analysis, Chapter 19,

' Resporue to Severe Acciden: Policy Statement, and Chapter 20, Question and Resporue Guide, of the Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor (ABWR).

This submittal lacludes the addition of the following information: control building fire hazards analysis; control building seismic and structural design; turbine building HVAC; and responses to Request for Additional Information dated May 4,1990, July 27,1990, August 15,1990 and September 19,1990 to Chapter 20.

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Document Control Desk Docket No. STN 50-605 U.S. Nuclear Regulatory Commission hiFN No.018 91 February 22,1991 Page 2 In addition there are other changes to various sections of the SSAR which are identified, along with the above changes, on the page change instruction sheet. As noted on t!.e page change instruction sheet, the 11 x 17 drawtngs will be sent under a separate cover. That submittal will also include a set of revised pages for the Page Status listing.

Please note that all or parts of the following sections contain information that is designated as General Electric Company proprietary intormation: 1.3, 4 B, 6.3, 9.2, 9.3, 9.4, 9.5, 9A.2, 9A.3, 9A.4, 9A.5,9A.6,11.2,11.3,15B, & 20.3. This information is being submitted under separate cover (See Reference).

Sincerely, P.W. h rriott, hianager Regulatory and Analysis Services cc:

D. R. Wilkins (GE)

T. E. Murley (NRC)

D. hi. Crutchfield (NRC)

D.J. hicGoff (DOE)

F. J. hiiraglia, Jr. (NRC)

D, C. Scaletti (NRC)

K. E. Stahlkopf (EPRI)

F. A. Ross (DOE) l I--

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