NRC-85-3049, Forwards Listed Nonproprietary Documents Requested by NRC During 850517 & 0626 Audits & Application for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790: Difference between revisions

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s Westinghouse             Water Reactor                             Q 3l5 ,p 3 ,, m 3ag333 Electric Corporation     Divisions July 15, 1985 NS-NRC-85-3049 8
s Westinghouse Water Reactor Q 3l5,p 3,, m 3ag333 Electric Corporation Divisions July 15, 1985 NS-NRC-85-3049 8
Mr. Harold R. Denton, Director                                         d Office of Nuclear Reactor Regulation                           I* , 9 U.S. Ncclear Regulatory Commission Washington, D.C.       20055 Attention:     P. Kadambi Transmittal of Westinghouse Documents Requested by the USNRC at the South Texas Mechanical Engineering Branch Audits on May 17. 1985 and June 26. 1985 Enclosed is one copy of each of the subject documents which are listed below.
d Mr. Harold R. Denton, Director I*, 9 Office of Nuclear Reactor Regulation U.S. Ncclear Regulatory Commission Washington, D.C.
20055 Attention:
P. Kadambi Transmittal of Westinghouse Documents Requested by the USNRC at the South Texas Mechanical Engineering Branch Audits on May 17. 1985 and June 26. 1985 Enclosed is one copy of each of the subject documents which are listed below.
These documents contain information which is non-proprietary to Westinghouse.
These documents contain information which is non-proprietary to Westinghouse.
In order not to delay submittal of proprietary information requested by the Comission, Westinghouse transmitted the proprietary versions of these same documents to the Comission in Westinghouse letter No. NS-NRC-85-3038, Rahe to Denton, dated May 30, 1985 and Westinghouse letter No. NS-NRC-85-3044, Rahe to Denton, dated July 3, 1985, for the purpose of expediting review.
In order not to delay submittal of proprietary information requested by the Comission, Westinghouse transmitted the proprietary versions of these same documents to the Comission in Westinghouse letter No. NS-NRC-85-3038, Rahe to Denton, dated May 30, 1985 and Westinghouse letter No. NS-NRC-85-3044, Rahe to Denton, dated July 3, 1985, for the purpose of expediting review.
Also enclosed are:
Also enclosed are:
(1)     One (1) copy of Application for Withholding, AW-85-040, (Non-proprietary)
(1)
(2)     One (1) copy of Affidavit (Non-proprietary)
One (1) copy of Application for Withholding, AW-85-040, (Non-proprietary)
Document Number         Document Type _                   Title G-952342 Rev. 2         Equipment             General Specification Reactor with interim           Specification         Coolant Pump Model 100 60 Hertz revisions 1 & 2                               & Model 100 50 Hertz 952721 Rev. 4           Equipment             South Texas Reactor Coolant Pump           -
(2)
Specification 8507260543 8507157 PDR A
One (1) copy of Affidavit (Non-proprietary)
ADOCK 05000498 pop.
Document Number Document Type _
Title G-952342 Rev. 2 Equipment General Specification Reactor with interim Specification Coolant Pump Model 100 60 Hertz revisions 1 & 2
& Model 100 50 Hertz 952721 Rev. 4 Equipment South Texas Reactor Coolant Pump Specification 8507260543 8507157 PDR ADOCK 05000498 A
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f Mr. Harold R. Denton                               July 15, 1985 NS-NRC-85-3049 Document Number   Document Tvoe                 Tyge WEMD E.M. 5351   Engineering       South Texas Project Unit No. 1 Memorandum         Model 100 Reactor Coolant Pump Pressure Boundary Summary Report WEMD E.M. 4932,   Engineering       Model 100 Reactor Coolant Pump -
f Mr. Harold R. Denton July 15, 1985 NS-NRC-85-3049 Document Number Document Tvoe Tyge WEMD E.M. 5351 Engineering South Texas Project Unit No. 1 Memorandum Model 100 Reactor Coolant Pump Pressure Boundary Summary Report WEMD E.M. 4932, Engineering Model 100 Reactor Coolant Pump -
Rev. 1, Volume 1 Memorandum         Pressure Boundary Stress Report
Rev. 1, Volume 1 Memorandum Pressure Boundary Stress Report
        & Volume 2 WEMO E.M. 5003,   Engineering       Model 100 Reactor Coolant Pump -
& Volume 2 WEMO E.M. 5003, Engineering Model 100 Reactor Coolant Pump -
Rev. 1           Memorandum         Casing Nozzle Design Loads G-952850, Rev. 0 Equipment         Motor Operated Gate Valves -
Rev. 1 Memorandum Casing Nozzle Design Loads G-952850, Rev. 0 Equipment Motor Operated Gate Valves -
with interim     Specification     ASME Boiler and Pressure Vessel revision 1                           Code Section III - Class 1, 2, &
with interim Specification ASME Boiler and Pressure Vessel revision 1 Code Section III - Class 1, 2, &
3 952874, Rev. 4   Design             South Texas Project Units Specification       Number 1 and 2 Motor Operated Gate Valves - ASME Boiler and Pressure Vessel Code Section III WEMD E.M. 5158   Engineering       Stress Report for Westinghouse Volumes I & II   Memorandum         Class I Nuclear Valves 6 inch and larger Gate Valves for Westinghouse PWRSD 8373D81, Rev. 3   Engineering       Motor Op Gate Valve Drawing           Mod, 08000GM84FEB0D0 8-316 ASME Cl 1 GPO Assy 953385, Rev. 0   Equipment         Piping Design Specification ASME Specification     III Code Class 1, for Houston Lighting and Power Co. - South Texas Project Nuclear Power Plants Units 1 and 2 953385, Rev. 1   Design             Piping Design Specification Specification     ASME III Code Class 1, for H ouston Lighting & Power Co. -
3 952874, Rev. 4 Design South Texas Project Units Specification Number 1 and 2 Motor Operated Gate Valves - ASME Boiler and Pressure Vessel Code Section III WEMD E.M. 5158 Engineering Stress Report for Westinghouse Volumes I & II Memorandum Class I Nuclear Valves 6 inch and larger Gate Valves for Westinghouse PWRSD 8373D81, Rev. 3 Engineering Motor Op Gate Valve Drawing Mod, 08000GM84FEB0D0 8-316 ASME Cl 1 GPO Assy 953385, Rev. 0 Equipment Piping Design Specification ASME Specification III Code Class 1, for Houston Lighting and Power Co. - South Texas Project Nuclear Power Plants Units 1 and 2 953385, Rev. 1 Design Piping Design Specification Specification ASME III Code Class 1, for H ouston Lighting & Power Co. -
South Texas Project Nuclear Power Plant Units 1 and 2 WCAP-9135         Westinghouse       Structural Analysis of Reactor Report             Coolant Loop for the South Texas Project Units 1 & 2 - Volume 1 -
South Texas Project Nuclear Power Plant Units 1 and 2 WCAP-9135 Westinghouse Structural Analysis of Reactor Report Coolant Loop for the South Texas Project Units 1 & 2 - Volume 1 -
Analysis of the Reactor Coolant Loop Piping
Analysis of the Reactor Coolant Loop Piping


Mr. Harold R. Denton                                                 July 15, 1985                                   ,
Mr. Harold R. Denton July 15, 1985 NS-NRC-85-3049 DE ument Number Document Type Type G-952744, Rev. 0 Equipment Reactor Coolant System Equipment Specification Supports Design Specification, ASME III Code Class 1 (for Steam Generator, Reactor Coolant Pump, j
,                                                                              NS-NRC-85-3049 l
Reactor Pressure Vessel,'and Pressurizer) 953533, Rev. 0 Equipment South Texas Project Units 1 & 2 Specification Reactor Coolant System Equipment Supports Design Specification, ASME Ill Code Class 1 (for Steam 4
DE ument Number     Document Type                               Type G-952744, Rev. 0   Equipment                     Reactor Coolant System Equipment Specification                 Supports Design Specification,
Generator, Reactor Coolant Pump, f-Reactor Pressure Vessel, and Pressurizer)
.                                                              ASME III Code Class 1 (for Steam Generator, Reactor Coolant Pump, j                                                             Reactor Pressure Vessel,'and Pressurizer)
G-952628, Rev. 1 Equipment Fabrication Requirements for the Specification Reactor Coolant System Component Supports SSDC 1.3, Rev. 2 Systems Standard Systems Standard Design Criteria-Design Criteria Nuclear Steam Supply System -
:            953533, Rev. 0     Equipment                     South Texas Project Units 1 & 2 Specification                 Reactor Coolant System Equipment Supports Design Specification, ASME Ill Code Class 1 (for Steam 4                                                             Generator, Reactor Coolant Pump, f-                                                             Reactor Pressure Vessel, and Pressurizer)
Design Transients SSDC 1.3, App. A Systems Standard Fluid Systems Design Transients Rev. O Design Criteria 3XL and 4XL (South Texas) Plants CENC-1332 Analytical Report Addendum 1 to Analytical Report for South Texas Project No. 1 -
G-952628, Rev. 1   Equipment                     Fabrication Requirements for the Specification                 Reactor Coolant System Component Supports SSDC 1.3, Rev. 2   Systems Standard             Systems Standard Design Criteria-Design Criteria               Nuclear Steam Supply System -
Design Transients SSDC 1.3, App. A   Systems Standard             Fluid Systems Design Transients Rev. O             Design Criteria               3XL and 4XL (South Texas) Plants CENC-1332           Analytical Report             Addendum 1 to Analytical Report for South Texas Project No. 1 -
Houston Lighting and Power Co.
Houston Lighting and Power Co.
WCAP-8447           Westinghouse                 Roto-Lok Closure System Report                       Development CENC-1302           Analytical                   Analytical Report for South Texas Report                       Project No. 1 Houston Lighting and Power Company The letters referenced in AW-85-040 transmitted proprietary information of Westinghouse Electric Corporation. In conformance with the requirements of 10CFR Section 2.790, as amended, of the Commission's regulations, we are enclosing with this submittal an application for withholding from public disclosure and an affidavit. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission.
WCAP-8447 Westinghouse Roto-Lok Closure System Report Development CENC-1302 Analytical Analytical Report for South Texas Report Project No. 1 Houston Lighting and Power Company The letters referenced in AW-85-040 transmitted proprietary information of Westinghouse Electric Corporation.
In conformance with the requirements of 10CFR Section 2.790, as amended, of the Commission's regulations, we are enclosing with this submittal an application for withholding from public disclosure and an affidavit.
The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission.


Mr. Harold R. Denton             ~-                        July 15, 1985 NS-NRC-85-3049 Correspondence with respect to the affidavit or application for withholding should reference AW-85-040 and should be addressed to R. A. Wiesenann, Manager of Licensing Programs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pa. 15230.
Mr. Harold R. Denton July 15, 1985
Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION OW E   P. Rahe, Jr. , Manager
~-
                                              .uclear Safety Department
NS-NRC-85-3049 Correspondence with respect to the affidavit or application for withholding should reference AW-85-040 and should be addressed to R. A. Wiesenann, Manager of Licensing Programs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pa. 15230.
  /wh Enclosure cc:   E. C. Shomaker, Esq.
Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION OW E
P. Rahe, Jr., Manager
.uclear Safety Department
/wh Enclosure cc:
E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC}}
Office of the Executive Legal Director, NRC}}

Latest revision as of 12:38, 12 December 2024

Forwards Listed Nonproprietary Documents Requested by NRC During 850517 & 0626 Audits & Application for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790
ML20128P954
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 07/15/1985
From: Rahe E
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Harold Denton, Kadambi P
Office of Nuclear Reactor Regulation
Shared Package
ML20128P958 List:
References
NS-NRC-85-3049, NUDOCS 8507260543
Download: ML20128P954 (4)
v • d • e


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s Westinghouse Water Reactor Q 3l5,p 3,, m 3ag333 Electric Corporation Divisions July 15, 1985 NS-NRC-85-3049 8

d Mr. Harold R. Denton, Director I*, 9 Office of Nuclear Reactor Regulation U.S. Ncclear Regulatory Commission Washington, D.C.

20055 Attention:

P. Kadambi Transmittal of Westinghouse Documents Requested by the USNRC at the South Texas Mechanical Engineering Branch Audits on May 17. 1985 and June 26. 1985 Enclosed is one copy of each of the subject documents which are listed below.

These documents contain information which is non-proprietary to Westinghouse.

In order not to delay submittal of proprietary information requested by the Comission, Westinghouse transmitted the proprietary versions of these same documents to the Comission in Westinghouse letter No. NS-NRC-85-3038, Rahe to Denton, dated May 30, 1985 and Westinghouse letter No. NS-NRC-85-3044, Rahe to Denton, dated July 3, 1985, for the purpose of expediting review.

Also enclosed are:

(1)

One (1) copy of Application for Withholding, AW-85-040, (Non-proprietary)

(2)

One (1) copy of Affidavit (Non-proprietary)

Document Number Document Type _

Title G-952342 Rev. 2 Equipment General Specification Reactor with interim Specification Coolant Pump Model 100 60 Hertz revisions 1 & 2

& Model 100 50 Hertz 952721 Rev. 4 Equipment South Texas Reactor Coolant Pump Specification 8507260543 8507157 PDR ADOCK 05000498 A

pop.

BooI

'IL

f Mr. Harold R. Denton July 15, 1985 NS-NRC-85-3049 Document Number Document Tvoe Tyge WEMD E.M. 5351 Engineering South Texas Project Unit No. 1 Memorandum Model 100 Reactor Coolant Pump Pressure Boundary Summary Report WEMD E.M. 4932, Engineering Model 100 Reactor Coolant Pump -

Rev. 1, Volume 1 Memorandum Pressure Boundary Stress Report

& Volume 2 WEMO E.M. 5003, Engineering Model 100 Reactor Coolant Pump -

Rev. 1 Memorandum Casing Nozzle Design Loads G-952850, Rev. 0 Equipment Motor Operated Gate Valves -

with interim Specification ASME Boiler and Pressure Vessel revision 1 Code Section III - Class 1, 2, &

3 952874, Rev. 4 Design South Texas Project Units Specification Number 1 and 2 Motor Operated Gate Valves - ASME Boiler and Pressure Vessel Code Section III WEMD E.M. 5158 Engineering Stress Report for Westinghouse Volumes I & II Memorandum Class I Nuclear Valves 6 inch and larger Gate Valves for Westinghouse PWRSD 8373D81, Rev. 3 Engineering Motor Op Gate Valve Drawing Mod, 08000GM84FEB0D0 8-316 ASME Cl 1 GPO Assy 953385, Rev. 0 Equipment Piping Design Specification ASME Specification III Code Class 1, for Houston Lighting and Power Co. - South Texas Project Nuclear Power Plants Units 1 and 2 953385, Rev. 1 Design Piping Design Specification Specification ASME III Code Class 1, for H ouston Lighting & Power Co. -

South Texas Project Nuclear Power Plant Units 1 and 2 WCAP-9135 Westinghouse Structural Analysis of Reactor Report Coolant Loop for the South Texas Project Units 1 & 2 - Volume 1 -

Analysis of the Reactor Coolant Loop Piping

Mr. Harold R. Denton July 15, 1985 NS-NRC-85-3049 DE ument Number Document Type Type G-952744, Rev. 0 Equipment Reactor Coolant System Equipment Specification Supports Design Specification, ASME III Code Class 1 (for Steam Generator, Reactor Coolant Pump, j

Reactor Pressure Vessel,'and Pressurizer) 953533, Rev. 0 Equipment South Texas Project Units 1 & 2 Specification Reactor Coolant System Equipment Supports Design Specification, ASME Ill Code Class 1 (for Steam 4

Generator, Reactor Coolant Pump, f-Reactor Pressure Vessel, and Pressurizer)

G-952628, Rev. 1 Equipment Fabrication Requirements for the Specification Reactor Coolant System Component Supports SSDC 1.3, Rev. 2 Systems Standard Systems Standard Design Criteria-Design Criteria Nuclear Steam Supply System -

Design Transients SSDC 1.3, App. A Systems Standard Fluid Systems Design Transients Rev. O Design Criteria 3XL and 4XL (South Texas) Plants CENC-1332 Analytical Report Addendum 1 to Analytical Report for South Texas Project No. 1 -

Houston Lighting and Power Co.

WCAP-8447 Westinghouse Roto-Lok Closure System Report Development CENC-1302 Analytical Analytical Report for South Texas Report Project No. 1 Houston Lighting and Power Company The letters referenced in AW-85-040 transmitted proprietary information of Westinghouse Electric Corporation.

In conformance with the requirements of 10CFR Section 2.790, as amended, of the Commission's regulations, we are enclosing with this submittal an application for withholding from public disclosure and an affidavit.

The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission.

Mr. Harold R. Denton July 15, 1985

~-

NS-NRC-85-3049 Correspondence with respect to the affidavit or application for withholding should reference AW-85-040 and should be addressed to R. A. Wiesenann, Manager of Licensing Programs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pa. 15230.

Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION OW E

P. Rahe, Jr., Manager

.uclear Safety Department

/wh Enclosure cc:

E. C. Shomaker, Esq.

Office of the Executive Legal Director, NRC

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