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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20153G9561998-09-25025 September 1998 Nonproprietary Figure 1-3 of PCS-T2R-050, Large-Scale Test Data Evaluation ML20236F6911998-05-29029 May 1998 Rev 6 to AP600 Emergency Response Guidelines, Including Guidelines SDG-1,SDG-2,SDG-3 & Change Pages for Background Documents AE-1,SDF-0.1,SDG-1,SDG-2 & SDG-3 ML20198S7471997-10-31031 October 1997 Rev 5 to AP600 Emergency Response Guidelines ML20212A9081997-10-16016 October 1997 Proposed Tech Specs 3.7.9 Re Fuel Storage Pool Makeup Water Sources ML20198S8741997-08-31031 August 1997 Proposed Tech Specs,Incorporating NRC Comments Resolved During 971027 Telcon ML20202B4411997-08-31031 August 1997 Proposed Tech Specs 3.3.1 & 3.3.2 Re Changes to Reflect Ssar Chapter 15 Analyses Setpoints ML20216C2581997-08-31031 August 1997 Proposed Tech Specs 3.4.10 Re RCS Leakage Detection Instrumentation ML20211M9021997-08-31031 August 1997 Proposed Tech Specs 3.7.2 Re MSIVs ML20216D2331997-08-29029 August 1997 Proposed Tech Specs,Providing Draft RCS PIV Integrity TS ML20216D2511997-08-28028 August 1997 Proposed Tech Specs,Modifying SR 3.6.9.4 & SR 3.6.9.2, Consistent W/Nrc Example Provided in Question 68 & Consistent w/NUREG-1432 ML20198G5641997-08-27027 August 1997 Proposed Tech Specs Pages 5.0-15,5.0-21 & IV to Reporting Requirements 5.6.1 to Be Incorporated in Rev 7 of AP600 TS to Be Transmitted to NRC on 970902 ML20198G5951997-08-27027 August 1997 Proposed Tech Specs Re Response to NRC Reactor Sys Branch RAI Re AP600 TS ML20210P2921997-08-19019 August 1997 Proposed Tech Specs,Reflecting Responses to Comments on AP600 TS Containment Sys ML20210P4181997-08-19019 August 1997 Proposed Tech Specs 3.8.1 & 3.8.5,documenting Changes Agreed Upon W/Nrc Re Electrical Power Sys ML20210Q0581997-08-19019 August 1997 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & Engineered Safety Features Actuation ML20149H5111997-07-0101 July 1997 Rev 4 to GW-GJR-100, AP600 Emergency Response Guidelines ML20140C4571997-06-0606 June 1997 Proposed Tech Specs Providing Explanation for AP600 TS Completion Times & Surveillance Frequencies Which Are Not Identical to Standardized TS Completion Times & Surveillance Frequencies ML20141B6551997-05-31031 May 1997 to AP600 Emergency Response Guidelines ML20141H1501997-05-16016 May 1997 Rev 3 to DE-AC03-90SF18495, Simplified Passive Advanced LWR Plant Program,AP600 Certified Design Matl ML20141C6961997-05-0909 May 1997 Proposed Tech Specs LCO 3.0.2 & 3.0.3,reflecting Compliance W/Nrc Staff Position of Ltr ML20137C6781997-03-19019 March 1997 Proposed Tech Specs Rev Re LCO 3.0.3,Key Licensing Issue 19 Deleting Exemption for Entry ML20134A5621997-01-15015 January 1997 Rev 2 to Design Reviews ML20141B1351996-08-31031 August 1996 Proposed Tech Specs Re Advance Markup of AP600 ML20141K2571996-08-31031 August 1996 Proposed Tech Specs 3.7.6 Re Main Room Habitability Sys ML20117J1071996-08-30030 August 1996 Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to EA-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2 ML20116A4421996-07-31031 July 1996 Westinghouse AP600 Chapter 14,Initial Test Program ML20116J8331996-07-31031 July 1996 Rev 2 to SDG-6, AP600 Response to Unexpected RCS Temp Changes During Shutdown ML20116J8231996-07-31031 July 1996 Rev 2 to SDG-5, AP600 Response to Cold Overpressure During Shutdown ML20116J8151996-07-31031 July 1996 Rev 2 to SDG-4, AP600 Response to Increasing Nuclear Flux During Shutdown ML20116J8101996-07-31031 July 1996 Rev 2 to SDF-3, AP600 Response to High Containment Radiation During Shutdown ML20116J7941996-07-31031 July 1996 Rev 2 to SDF-0.1, AP600 Shutdown Safety Status Tree During Shutdown ML20116J8031996-07-31031 July 1996 Rev 2 to SDG-2, AP600 Response to Loss of Rns During Shutdown ML20116J8001996-07-31031 July 1996 Rev 2 to SDF-1, AP600 Response to Loss of RCS Inventory During Shutdown ML20111B0501996-05-0101 May 1996 Proposed Tech Specs 5.1,5.2 & 5.3 ML20107C7421996-04-0808 April 1996 Non-proprietary Man-In-The-Loop Test Plan Description ML20107C7401996-04-0808 April 1996 Non-proprietary Programmatic Level Description of AP600 Human Factors Verification & Validation Plan ML20101N8341996-03-31031 March 1996 Non-proprietary Version of AP600 Reactor Internals Flow-Induced Vibration Assessment Program ML20096F1261996-01-15015 January 1996 Revised Pages 1-3 & 1-4 of Rev 1 to AP600 SPES-2 Test Analysis Rept ML20095E6721995-12-0808 December 1995 Plan to Resolve AP600 PRA MAAP4 Success Criteria Issues ML20091M3831995-07-31031 July 1995 SPES-2 Hot Preoperational Test H-06 Inadvertent ADS Stage 1 Actuation (with No ADS Stage 4) ML20134A5501995-06-0101 June 1995 Rev 2 to AP600 Sys Specification Documents ML20134A6001995-06-0101 June 1995 Rev 1 to Control of Subcontractor Submittals ML20083R3451995-05-31031 May 1995 Nonproprietary Large-Scale Test Data Evaluation ML20085E4261995-05-31031 May 1995 AP600 Emergency Response Guidelines ML20083B8901995-02-28028 February 1995 Rev 3 to Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment ML20073C9101994-08-26026 August 1994 Rev 2 to WCAP-13234, Test Spec for Long-Term Cooling Test ML20065M2971994-05-31031 May 1994 Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992 ML20069A3761994-05-0606 May 1994 Rev 6 to AP600 Design Certification Test Program Overview NRC-94-4120, Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93)1994-04-27027 April 1994 Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93) NRC-94-4116, Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test1994-04-21021 April 1994 Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test 1998-09-25
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20236F6911998-05-29029 May 1998 Rev 6 to AP600 Emergency Response Guidelines, Including Guidelines SDG-1,SDG-2,SDG-3 & Change Pages for Background Documents AE-1,SDF-0.1,SDG-1,SDG-2 & SDG-3 ML20198S7471997-10-31031 October 1997 Rev 5 to AP600 Emergency Response Guidelines ML20149H5111997-07-0101 July 1997 Rev 4 to GW-GJR-100, AP600 Emergency Response Guidelines ML20141B6551997-05-31031 May 1997 to AP600 Emergency Response Guidelines ML20141H1501997-05-16016 May 1997 Rev 3 to DE-AC03-90SF18495, Simplified Passive Advanced LWR Plant Program,AP600 Certified Design Matl ML20134A5621997-01-15015 January 1997 Rev 2 to Design Reviews ML20117J1071996-08-30030 August 1996 Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to EA-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2 ML20116J8101996-07-31031 July 1996 Rev 2 to SDF-3, AP600 Response to High Containment Radiation During Shutdown ML20116A4421996-07-31031 July 1996 Westinghouse AP600 Chapter 14,Initial Test Program ML20116J7941996-07-31031 July 1996 Rev 2 to SDF-0.1, AP600 Shutdown Safety Status Tree During Shutdown ML20116J8001996-07-31031 July 1996 Rev 2 to SDF-1, AP600 Response to Loss of RCS Inventory During Shutdown ML20116J8031996-07-31031 July 1996 Rev 2 to SDG-2, AP600 Response to Loss of Rns During Shutdown ML20116J8151996-07-31031 July 1996 Rev 2 to SDG-4, AP600 Response to Increasing Nuclear Flux During Shutdown ML20116J8231996-07-31031 July 1996 Rev 2 to SDG-5, AP600 Response to Cold Overpressure During Shutdown ML20116J8331996-07-31031 July 1996 Rev 2 to SDG-6, AP600 Response to Unexpected RCS Temp Changes During Shutdown ML20107C7401996-04-0808 April 1996 Non-proprietary Programmatic Level Description of AP600 Human Factors Verification & Validation Plan ML20107C7421996-04-0808 April 1996 Non-proprietary Man-In-The-Loop Test Plan Description ML20101N8341996-03-31031 March 1996 Non-proprietary Version of AP600 Reactor Internals Flow-Induced Vibration Assessment Program ML20095E6721995-12-0808 December 1995 Plan to Resolve AP600 PRA MAAP4 Success Criteria Issues ML20134A6001995-06-0101 June 1995 Rev 1 to Control of Subcontractor Submittals ML20134A5501995-06-0101 June 1995 Rev 2 to AP600 Sys Specification Documents ML20085E4261995-05-31031 May 1995 AP600 Emergency Response Guidelines ML20083B8901995-02-28028 February 1995 Rev 3 to Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment ML20073C9101994-08-26026 August 1994 Rev 2 to WCAP-13234, Test Spec for Long-Term Cooling Test ML20065M2971994-05-31031 May 1994 Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992 ML20065A4731994-03-22022 March 1994 AP600 Design Certification Test Program Overview, Rev 5.W/ Ten Oversize Drawings ML20134A5801994-03-11011 March 1994 Rev 2 to AP600 Design Criteria Documents ML20134A5901991-10-31031 October 1991 Rev 0 to AP600 Engineering Data Base Access & Control ML20134A6061991-10-31031 October 1991 Rev 0 to AP600 Plant Instrumentation & Control Sys ML20134A5851991-02-0808 February 1991 Rev 0 to Interface Control Document ET-NRC-92-3779, Nonproprietary AP600 Preliminary Refueling Outage Plan Description of Pert Chart Activities1988-05-25025 May 1988 Nonproprietary AP600 Preliminary Refueling Outage Plan Description of Pert Chart Activities 1998-05-29
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AP 3.6 2 .
W Westinghouse Electric Corporation
" Advanced Technology Business Area AP600 Design Criteria Documents AP600 OW ygu n . . - ~ , .
H. . BruscN. General Manager 03-11 94 Program Operating Procedure goy,nc e 7,cnnoiogy go,,n,,, 4,,,
- AUTHOR / COGNIZANT Contact Manager, AP600 Plant Engineering, on questions FUNCTION conceming this procedure.
PURPOSE This procedure establishes requirements for the preparation, review, approval and revision of Design Criteria Documents for the AP600.
SCOPE This procedure applies to all AP600 Design Criteria Documents prepared by Westinghouse. AP600 contractors will prepare Design Criteria Documents in accordance with their own procedures using a format similar to that defined in this '
procedure.
DEFINITIONS Desian Criteria Document - A document defining requirements for n design of specific aspects of the AP600. Typically these 4
(d' documents cover a single discipline or subdiscipline.
Desian Criteria Manual - A Manual that incorporates the top level Design Criteria Documents.
Responsible Manaaer - The individual who identifies the need for a Design Criteria Document and is responsible for its preparation in accordance with this procedure.
Responsible Enoineer - The engineer who is assigned to develop 4
the Design Criteria Document.
PROCEDURE General A. A Design Criteria Document is prepared to define criteria for use in subsequent design activities. It translates safety,
, licensing and contractual requirements into detail design requirements in order to assure a uniform design basis within all engineering activities.
B. Design Criteria Documents are intended to provide mandatory ;
requiremeris for subsequent design activities. The I documer.ts can be supplemented as required by design l guides if guidance rather than mandatory requirements are to I be defined. i l
te2so.wptio(cusT)-os1484 Page 1 of 5 ooos.FRM 9701290003 970115 PDR ADOCK 05200003 A PDR
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WESTINGHOUSE PROPRIETARY OLASS 2 I AP 3.6 2 C. The iniSal issue and all subsequent revisions shall be precared in accordance with the detailed procedure described below.
D. A Design Criteria Manual will be compiled consisting of top level Design Criteria Documents. It willinclude documents 1 prepared by Westinghouse under this procedure as well as documents, prepared by other AP600 contractors, reviewed and approved for project use by Westinghouse. ,
l E. J.Thabetic revision symbols shall be used prior to placement of the criteria dccument under configuration control.
Thereafter, numeric revision symbols shall be used.
Revisions require change approval in accordance with the i change control procedure (AP 3.2). The design change l number shall be identified on the cover cheet. All technical l changes shall be listed on the Record of Changes Sheet and i shall be identified by a verticalline in the margin. The I complete document will be reissued for each revision.
F. Plant Engineering coordinates preparation and completion of I the Design Criteria, coordinates AP600 Contractor preparation and review of Design Criteria Documents and assists in l integration, review and approval cycles.
Responsibility Action Responsible Manager 1. Identifies need for a Design Criteria Document within his area of responsibility and define the scope of the document.
- 2. Assigns responsibility for the preparation of the Design Criteria Document.
- 3. Identifies interfacing organizations that will provide input, review and/or approve the Design Criteria Document.
Responsible Engineer 4. Prepares the Design Criteria Document utilizing the format and content guidelines identified in Appendix A.
- 5. Obtains a document number in accordance with the standard AP600 numbering system (GW GMP 005).
- 6. Ensures that all design inputs used in the preparation of the document are protected in accordance with the applicable records flow schedule.
- 7. Distributes copies of the draft document to reviewers and others, as required.
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WESTINGHOUSE PROPRIETARY CLASS 2 AP-3.6 2 y~\
V( Responsible Manager 8. Assigns an independent verifier to verify the document.
Independent Verifier 9. Reviews document for adequacy, correctness and completeness.
Interfacing Groups 10. Review and comment on the draft document.
Responsible Engineer 11. Resolves comments on the document generated during the review process.
- 12. Obtains required approval signatures on the cover and intemal review sheet, j Responsible Manager 13. Ensures that the Responsible Engineer has resolved l comments with the verifier and mandatory reviewers and has obtained approval signatures on the sign-off sheet.
- 14. Reviews, approves and signs-off the Design Criteria Document.
Responsible Engineer 15. Relesses the Design Criteria Document to Program Control and Contract Administration.
O Program Control and 16. Distributes the Design Criteria Document as specified h Contract Administration by the responsible engineer. Incorporates document in AP600 records.
Plant Engineering 17. Identifies the top level criteria documents to be included in the Design Criteria Manual and identifies the distribution list for !
the Design Criteria Manual.
Program Control and 18. Distributes the Design Criteria Documents selected for Centract Administration inclusion in the Design criteria Manual to the controlled distribution.
REFERENCES 1
A. AP-3.2, Design Configuration Change Control for AP600 Program, Phase 2 !
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- l B. GW GMP 005, AP600 Document Numbering '
FORMS / EXHIBITS AP600 Document Cover Sheet Exhibit 10 AP600 Standard Intemal Review Sheet - Exhibit 17 AP600 Record of changes - Exhibit 16 V
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- WESTINGHOUSE PROPRIETARY CLASS 2 APPENDICES Appendix A Design Criteria Format and Content 1
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. WESTINGHOUSE PROPRIETARY CLASS 2 4
AP.3.6 2 APPENDIX A j DESIGN CRITERIA FORMAT AND CONTENT
. The Design Criteria Document shall be prepared using the following forms: 1 I
4 AP600 Document Cover Sheet -in accordance with Exhibit 10 !
4 AP600 Standard Intemal Review Sheet - in accordance with Exhibit 17
- AP600 Record of Changes - in accordance with Exhibit 16 2
- Subsequent pages shall include "AP600 Design Cnteria Westinghouse Proprietary Class 2" in the header and the AP600 document number, revision number, page number and date in the footer.
- The Design Criteria Document shall include a Table of Contents with the following sections
i Section 1.0 Introduction
1.1 Purpose and Scope
1.2 Background
1.3 Definitions and Acronyms '
Section 2.0 Codes and Standards Section 3.0 and subsequent section numbers may be selected by the author Section References shall be the last section Appendices The Design Criteria Document shall define the criteria in sufficient detail that design of the plant in accordance with the criteria will meet all technical and licensing requirements. The '
document shall consider the following design inputs:
a) Regulatory requirements. If the design criteria include any exceptions from Regulatory Guides, Standard Review Plans or other licensing documents, such exceptions shall also be documented in the 'AP600 Compliance with SRP Acceptance Criteria" (GW GL 001).
b) ALWR Utility Requirements. If the design criteria include any exceptions from the Utility Requirements Document, such exceptions shall also be documented in the " Comparison of AP600 Design with the Utilities Requirements Document".
Section 2.0 identifies the Codes and Standards imposed on the user of the criteria document, and is distinct from references which are provided in the last section to describe where requirements come from or to provide assistance to the user in understanding the criteria. In 1 general, Regulatory Guides, Standard Review Plan sections and ALWR sections should be !
identified in the references and not in Section 2.0. AP600 requirements implementing the position should be incorporated in the body of the criteria document. Thus, any interpretation !
of the Regulatory or URD requirements is done by the Responsible Engineer for the Design l Criteria Document and reviewed by all interfacing groups.
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