ML20090L591: Difference between revisions
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| number = ML20090L591 | | number = ML20090L591 | ||
| issue date = 03/13/1992 | | issue date = 03/13/1992 | ||
| title = Forwards Nonproprietary Amend 20 to Advanced BWR | | title = Forwards Nonproprietary Amend 20 to Advanced BWR SSAR | ||
| author name = Marriott P | | author name = Marriott P | ||
| author affiliation = GENERAL ELECTRIC CO. | | author affiliation = GENERAL ELECTRIC CO. | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:e | {{#Wiki_filter:e GE Nucicar Energy h1 arch 13,1992 h1FN No. 065 92 Docket No. STN 50 605 EEN-9239 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: | ||
GE Nucicar Energy h1 arch 13,1992 h1FN No. 065 92 Docket No. STN 50 605 EEN-9239 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | Robert C. Pierson, Director Standardization and Non-Power Reactor Project Directorate | ||
Attention: | |||
==Subject:== | ==Subject:== | ||
| Line 25: | Line 24: | ||
==Reference:== | ==Reference:== | ||
Submittal of Amendment 20, Proprietary Information, to GE's ABWR SSAR, MFN-066-92, dated h1 arch 13,1992 O | Submittal of Amendment 20, Proprietary Information, to GE's ABWR SSAR, MFN-066-92, dated h1 arch 13,1992 O | ||
==Dear Mr. hiil!er:== | ==Dear Mr. hiil!er:== | ||
Enclosed are thirty-four copies of selected sections of Chapter 1, Introduction and General 0 | |||
Enclosed are thirty-four copies of selected sections of Chapter 1, Introduction and General | Description of Plant, Chapter 2 Site Chamcteristics, Chaptcc 3, Design of Structures, components, Equipment, and Systems, Chapter 4, Reactor, Ch pter 5. Reactor Coolant System and Connet ted Systems, Chapter 6, Engineered Safey Features. Chepter 7, Instnunentation and Control Systems,, | ||
Chapter 9, Auxiliary Systems, Chapter 10, Steam and Power Conversion System, Chapter 1I, Radioactive Waste Management, Chapter 12, Radiation Protection, Chapter 14, initial Test Program, Chapter 15, Accident Anaysis, Chapter 16 Technical Specifications, Chapter 18, iluman Factors Engineering, Chapter 19, Response to Severe Accident Policy Statement, Chapter 20, Question and Response Guide, of the Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor (ABWR). | Chapter 9, Auxiliary Systems, Chapter 10, Steam and Power Conversion System, Chapter 1I, Radioactive Waste Management, Chapter 12, Radiation Protection, Chapter 14, initial Test Program, Chapter 15, Accident Anaysis, Chapter 16 Technical Specifications, Chapter 18, iluman Factors Engineering, Chapter 19, Response to Severe Accident Policy Statement, Chapter 20, Question and Response Guide, of the Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor (ABWR). | ||
This submittalinciades changes to include the entire ABWR Standard Plant product structure in Section 1/2 and Table 3.2-1, analysis procedure for nonseismic structures, control building flooding revision, reactor building rebar, revised te ctor building fire hazard analysis, update of radiation protection and update of P&lDs and FCss. | This submittalinciades changes to include the entire ABWR Standard Plant product structure in Section 1/2 and Table 3.2-1, analysis procedure for nonseismic structures, control building flooding revision, reactor building rebar, revised te ctor building fire hazard analysis, update of radiation protection and update of P&lDs and FCss. | ||
Changes to the vririous sections of the SSAR which are identified on the attached page change | Changes to the vririous sections of the SSAR which are identified on the attached page change | ||
[" | [" | ||
instruction sheet. As noted on the page change instruction sheet, the 11 x 17 inch drawings will be sent under a separate cover in the first week of April. | |||
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Document Control Desk | ~-. - -... -. - | ||
Sincerely, 1 | Document Control Desk Docket No. STN 50 605 U.S. Nuclear Regulatory Commission htFN No. 065-92 hiarch 13,1992 Page 2 Please note that all or parts of the following sections contain information that is designated as General Electric Company proprietary information: 4B. 7.3. 7A. 9.3. 9.4,9.5. 9A,11.2,11.3,11.4, 158,19H and 19ht. This information is being submitted under separate cover. | ||
Sincerely, 1 | |||
/ | |||
/hhgwd C | |||
P.W. hiatriott, i<f anager Regulatory and Analysis Services ec: | |||
R. C. Berglund (GE) | |||
T. E. hiurley (NRC) | |||
/ | |||
) | |||
D. hl. Crutchfield (NRC) | |||
D. J. hicGoff (DOE) | D. J. hicGoff (DOE) | ||
F. J. hiiraglia, Jr. (NRC) | F. J. hiiraglia, Jr. (NRC) | ||
Latest revision as of 12:54, 13 December 2024
| ML20090L591 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 03/13/1992 |
| From: | Marriott P GENERAL ELECTRIC CO. |
| To: | Miller, Pierson R NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20090L593 | List: |
| References | |
| EEN-9239, NUDOCS 9203200337 | |
| Download: ML20090L591 (2) | |
Text
e GE Nucicar Energy h1 arch 13,1992 h1FN No. 065 92 Docket No. STN 50 605 EEN-9239 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:
Submittal of Amendment 20 to GE's ABWit SSAlt
Reference:
Submittal of Amendment 20, Proprietary Information, to GE's ABWR SSAR, MFN-066-92, dated h1 arch 13,1992 O
Dear Mr. hiil!er:
Enclosed are thirty-four copies of selected sections of Chapter 1, Introduction and General 0
Description of Plant, Chapter 2 Site Chamcteristics, Chaptcc 3, Design of Structures, components, Equipment, and Systems, Chapter 4, Reactor, Ch pter 5. Reactor Coolant System and Connet ted Systems, Chapter 6, Engineered Safey Features. Chepter 7, Instnunentation and Control Systems,,
Chapter 9, Auxiliary Systems, Chapter 10, Steam and Power Conversion System, Chapter 1I, Radioactive Waste Management, Chapter 12, Radiation Protection, Chapter 14, initial Test Program, Chapter 15, Accident Anaysis, Chapter 16 Technical Specifications, Chapter 18, iluman Factors Engineering, Chapter 19, Response to Severe Accident Policy Statement, Chapter 20, Question and Response Guide, of the Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor (ABWR).
This submittalinciades changes to include the entire ABWR Standard Plant product structure in Section 1/2 and Table 3.2-1, analysis procedure for nonseismic structures, control building flooding revision, reactor building rebar, revised te ctor building fire hazard analysis, update of radiation protection and update of P&lDs and FCss.
Changes to the vririous sections of the SSAR which are identified on the attached page change
["
instruction sheet. As noted on the page change instruction sheet, the 11 x 17 inch drawings will be sent under a separate cover in the first week of April.
(,
\\
s h#
eA s,, m e
~d2032OO337 920313 fm DDR ADOCK 05000605 A
s
. _. -.. - - ~.
~-. - -... -. -
Document Control Desk Docket No. STN 50 605 U.S. Nuclear Regulatory Commission htFN No. 065-92 hiarch 13,1992 Page 2 Please note that all or parts of the following sections contain information that is designated as General Electric Company proprietary information: 4B. 7.3. 7A. 9.3. 9.4,9.5. 9A,11.2,11.3,11.4, 158,19H and 19ht. This information is being submitted under separate cover.
Sincerely, 1
/
/hhgwd C
P.W. hiatriott, i<f anager Regulatory and Analysis Services ec:
R. C. Berglund (GE)
T. E. hiurley (NRC)
/
)
D. hl. Crutchfield (NRC)
D. J. hicGoff (DOE)
F. J. hiiraglia, Jr. (NRC)
C. Poslusny, Jr. (NRC)
K. E. Stahlkopf (EPRI)
F. A. Ross (DOE)
N. D. Fletcher (DOE)