Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML13302A354, ML13302A367, ML13311A220, ML13311B020, ML13311B023, ML13311B024, ML13311B025, ML13311B028, ML13316A522, ML13316A524, ML13316A713, ML13316B729, ML13316B742, ML13316B758, ML13316B810, ML13317A151, ML13317A158, ML13317A160, ML13317A256, ML13317A368, ML13317A479, ML13317A535, ML13317A553, ML13317A700, ML13317A778, ML13317A851, ML13317B031, ML13317B095, ML13317B109, ML13319A212, ML13319A216, ML13322A697, ML13324A846, ML13324A913, ML13326A720, ML13329A100, ML13330A038, ML13330A130, ML13330A153, ML13330A184, ML13330A214, ML13330A241, ML13330A283, ML13331B423, ML13333A455, ML13333A465, ML13333A468, ML13333A473, ML13333A475, ML13333A498... further results
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MONTHYEARML19261E3241979-05-13013 May 1979 Requests Time & Distance Parameters for Emergency Planning Project stage: Request IR 05000361/19790151979-06-25025 June 1979 IE Insp Rept 50-361/79-15 & 50-362/79-15 on 790529-0601.No Noncompliance Noted.Major Areas Inspected:Const Activities Involving License Actions on Previous Insp Findings, Preservice Insp,Instrumentation & safety-related Pipe Welds Project stage: Request ML13304A5631979-06-29029 June 1979 Notifies That NRC Will Not Respond to Applicant 790619 Response & Objections to Document Requests from Intervenors Friends of the Earth.Matter Relates Solely to Discovery Between Intervenors & Applicants Project stage: Request ML13333A5521979-10-17017 October 1979 Forwards Responses to NRC Requirements Established to Date Following TMI Accident, in Response to NRC 790913 Request. Includes Commitments to Actions Set Forth in NUREG-0578 Project stage: Other ML13329A1001979-10-31031 October 1979 Responses to NRC Requirements Established to Date Following TMI Accident Project stage: Other ML13308A6511979-10-31031 October 1979 Nuclear Power Reactors in Us Project stage: Request IR 05000361/19790271979-11-15015 November 1979 IE Insp Repts 50-361/79-27 & 50-362/79-25 on 791001-05.No Noncompliance Noted.Major Areas Inspected:Allegation Re Factory Splices in GE Class IE Electrical Cable Installed at Facilities Project stage: Request ML13333A4551979-11-15015 November 1979 Forwards NRC Generic & plant-specific Requirements for Auxiliary Feedwater Sys.Designs & Procedures of Facility Should Be Evaluated Against Requirements to Determine Degree of Conformity Project stage: Other ML13319A2121979-11-21021 November 1979 Submits Addl Info in Support of 791017 Responses to NUREG-0578 Requirements.Forwards Two Oversize Drawings, Available in Central Files Only Project stage: Other ML13333A4561979-12-14014 December 1979 Responds to NRC Re Operation of Containment Purge & Vent Valves Pending Resolution of Isolation Valve Operability.Purge Valves Closed During Reactor Operation Until Operability Under Design Basis LOCA Is Proven Project stage: Request IR 05000206/19790011979-12-21021 December 1979 IE Insp Rept 50-206/79-01 on 790205-16.Noncompliance Noted: Failure to Issue Procedures,Failure of Offsite Committee to Perform Required Audits & Failure to Issue Corrective Action Request Project stage: Request ML13333A4651980-01-0202 January 1980 Notifies of Intent to Respond to NRC by 800110, Requesting Addl Info Re Auxiliary Feedwater Sys.Response to May Require Six to Eight Months.Util Is Consulting W/Westinghouse Project stage: Other ML13333A4681980-01-14014 January 1980 Responds to NRC 800102 Show Cause Order Re NUREG-0578 & 800104 Request Re Power Reliability.Seeks Aid in Preparing Response.Forwards Analysis of Reliability Impacts Resulting from Facility TMI Backfit Outage. W/O Encl Project stage: Other ML13333A4731980-01-16016 January 1980 Submits Addl Info Requested by NRC Re Auxiliary Feedwater Sys Flow Requirements.Provides Completion Schedule of Six to Eight Months for Requested Info Project stage: Other ML13311B0321980-01-16016 January 1980 Forwards Lists of CA Resident Petitions Re Seismic Conditions at Facility.Petitioners Have Received Fr Notice Re Receipt of Petition Under 10CFR2.206 Project stage: Request ML13311A2201980-01-17017 January 1980 Forwards Addl Info in Response to TMI Lessons Learned Task Force short-term Requirements Re Emergency Power Supply for Pressurizer Heaters & Relief & Block Valves.Seven Regular Size Drawings & 32 Oversize Drawings Encl Project stage: Other ML13311B0231980-01-18018 January 1980 Answer to NRC 800102 Order to Show Cause Why Licensee Should Not Implement Category a TMI Lessons Learned Task Force short-term Requirements by 800131.Requests Relief Due to Difficulty in Obtaining Equipment.W/Certificate of Svc Project stage: Other ML13311B0251980-01-18018 January 1980 Affidavit Attesting That Shutdown of Facility During Feb 1980 Will Adversely Impact Reliability in State of Ca. Analysis of Reliability Impacts Resulting from TMI Backfit Outage Encl Project stage: Other ML13311B0241980-01-18018 January 1980 Affidavit Attesting to Inability to Complete Implementation of Mods to Provide Capability for Individual Valve Operability After Containment Isolation Signal Reset &/Or Override Project stage: Other ML13311B0281980-01-18018 January 1980 Affidavit Attesting That Delay Until After 800601 in Implementation of long-term Mods to Provide Reset/Override Ability for All Automaticaly Isolated Valves Does Not Cause Undue Risk to Public Health & Safety Project stage: Other ML13311B0201980-01-20020 January 1980 Forwards Response to NRC 800102 Order to Show Cause Why Licensee Should Not Implement Category a TMI Lessons Learned Task Force short-term Requirements by 800131 Project stage: Other ML13333A4751980-01-23023 January 1980 Forwards Response to short-term & long-term Recommendations in Encl 1 of NRC Re Evaluation of Auxiliary Feedwater Sys.Five Drawings in Central Files Only Project stage: Other ML13322A6971980-01-31031 January 1980 Reload Safety Evaluation,Unit 1,Cycle 8 Project stage: Other ML13322A6911980-02-0808 February 1980 Forwards Amend 88 to Ol,Consisting of Proposed Changes 86, 87,88 & 90 to Tech Specs.Nrc Review of Proposed Change 88, Supporting Documentation Requested Prior to Resumption of Power Operation & Fee Encl Project stage: Request ML19296C2141980-02-0808 February 1980 Forwards IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. No Written Response Required Project stage: Other ML13333A4981980-02-0808 February 1980 Submits Addl Info Re Commitment Schedule for short-term Lessons Learned Task Force Requirements.Circuitry to Close Auxiliary Feedwater Motor Operated Discharge Valve Will Be Installed During Apr 1980 Refueling Outage Project stage: Other ML13322A6961980-02-0808 February 1980 Proposed Changes 86,87,88 & 90 to App a Tech Specs Re Auxiliary Feedwater Sys,Control Group Insertion Limits & Containment Integrity & App B Tech Specs Re Plankton Studies Project stage: Request ML13322A6931980-02-0808 February 1980 Amend 88 to Ol,Consisting of Proposed Changes 86,87,88 & 90 to Tech Specs.Certificate of Svc Encl Project stage: Request ML13333A5071980-02-14014 February 1980 Forwards Addl Info Re Conditions & Results of Endurance Testing Performed on Auxiliary Feedwater Sys Pumps in Support of Responses to NRC Lessons Learned Task Force Requirements Project stage: Other IR 05000206/19800051980-04-18018 April 1980 IE Insp Rept 50-206/80-05 on 800310-13.No Noncompliance Noted.Major Areas Inspected:Document Control & Records Programs Project stage: Request ML14107A2611980-04-18018 April 1980 Provides Preliminary Info Re Impact of Auxiliary Feedwater Sys Automation on Main Steam Line Break Safety Analysis,In Response to NRC 791221 Request.Revised Scoping Studies Will Be Completed by 800516 Project stage: Other ML13330A0381980-04-29029 April 1980 Responds to NRC Re Item 2.1.7.a,NUREG-0578, Automatic Initiation of Auxiliary Feedwater Sys. Commits to Installation of safety-grade Sys During Outage on or After 810101 Project stage: Other ML13302A3541980-05-12012 May 1980 Forwards Amend to OL Application,Consisting of Amend 18 to FSAR & Amend 3 to Fire Protection Plan Project stage: Other ML13316B7421980-05-12012 May 1980 Responds to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Scoping Studies Will Be Completed by 800513.Studies Include Effect of Auxiliary Feedwater Runout & Impact of Other Energy Sources Project stage: Other ML13303A7821980-05-19019 May 1980 Notification of 800520 Meeting W/Usgs & Util in Bethesda,Md to Discuss Need for Addl Offshore Seismic Profiles Near Site Project stage: Request ML13316B7291980-05-19019 May 1980 Provides Addl Info to 800512 Responses to IE Bulletin 80-04. Evaluation of Scoping Studies Will Be Completed by Approx 800523 W/Full Response to Item 1 Provided by 801001.Review of Westinghouse Input Re Item 2 to Be Completed by 800701 Project stage: Other 05000206/LER-1980-026-01, /01T-0:on 800609,preliminary Results of Main Steam Line Break Accident Scenarios to Determine Containment Response Required Corrective Actions to Reduce Calculated Peak Containment Pressures.Rept Re 800513 Meeting Encl1980-06-0909 June 1980 /01T-0:on 800609,preliminary Results of Main Steam Line Break Accident Scenarios to Determine Containment Response Required Corrective Actions to Reduce Calculated Peak Containment Pressures.Rept Re 800513 Meeting Encl Project stage: Meeting 05000206/LER-1980-026, Forwards LER 80-026/01T-0 & Rept Re Automatic Initiation of Auxiliary Feedwater Sys,Per 800513 Meeting W/Nrc1980-06-10010 June 1980 Forwards LER 80-026/01T-0 & Rept Re Automatic Initiation of Auxiliary Feedwater Sys,Per 800513 Meeting W/Nrc Project stage: Meeting ML13316B7581980-07-16016 July 1980 Reschedules Response to Item 2 of IE Bulletin 80-04, Analysis of PWR Main Stream Line Break W/Continued Feedwater Addition. Response Will Be Forwarded by 800801, Pending MSLB Core Response Reanalysis Project stage: Other ML13331B4231980-08-0404 August 1980 Provides Response to IE Bulletin 80-04,Item 2,per 800716 Commitment.Westinghouse Reviewed Previous Analysis of Core Response Following Main Steam Line Break.Results Indicated No Main or Auxiliary Feedwater Assumed in Previous Analysis Project stage: Other ML13302A3671980-08-13013 August 1980 Forwards Amend to OL Application,Consisting of Amend 19 to Fsar.Amend Provides Open Item Responses Requested by NRC & Miscellaneous Corrections,Clarifications & Additions. Repts & Oversize Drawings Available in Central Files Only Project stage: Other ML13330A1301980-10-0606 October 1980 Notifies That Date for Submittal of Info Re Analyses of Main Steam Line or Feedwater Line Break Assuming Early Initiation of Auxiliary Feedwater Flow Has Been Rescheduled for 801201.Ltr Re TMI Lessons Learned Requirement Mods Encl Project stage: Other ML13302A4711980-10-0606 October 1980 Forwards Responses to NRC Questions & Revised FSAR Sections Re Preservice & Inservice Insp & Testing Project stage: Request ML13302A8501980-10-16016 October 1980 Summary of 800923 Meeting W/Consultants,Usgs,Util & CA Div of Mines & Geology in Menlo Park,Ca Re Plant Seismology & Geology.Attendee List,Agenda & Util Conclusions Encl Project stage: Request ML13319A2161980-10-16016 October 1980 Forwards Design Details for Automated Auxiliary Feedwater Sys & RCS to Be Installed Per TMI Lessons Learned Requirements.Info Provided Supersedes Info in . Drawings in Central Files.Aperture Cards in PDR Project stage: Other ML13316A5241980-10-31031 October 1980 Fatigue Crack Growth Evaluation for San Onofre Unit 1 Main Steam Line Pipe Project stage: Other ML13316A5221980-11-30030 November 1980 Mechanistic Fracture Evaluation of San Onofre Unit 1 Main Steam Line Pipe Containing Postulated Through-Wall Crack Project stage: Other ML13330A1531980-12-0505 December 1980 Requests Extension Until 810201 to Evaluate Impact of Automating Auxiliary Feedwater Sys on Existing Safety Analysis & Extension Until 810115 to Provide Info Re Main Steam Line Piping Integrity Evaluation Project stage: Other ML13316B8101981-01-0505 January 1981 Confirms Implementation Dates for Approved TMI-related Items Contained in NUREG-0737 W/Exceptions Listed.Procurement or Const Activities Will Not Be Initiated Until NRC Review & Concurrence.Mods Targeted for Completion 830101 Project stage: Other ML13330A1841981-01-14014 January 1981 Forwards Westinghouse WCAP-9832 & WCAP-9808 Re Main Steam Line Integrity Evaluation.Crack Appearing Instantaneously Would Be Stable Both Globally & Locally.Initial Circumferential Flaw Would Show Negligible Growth Project stage: Other 1980-10-16
[Table View] |
Text
APR 20 9 Docket Nos:
50-361 and 50-362 APPLICANTS:
Southern California Edison Company, (SCE)
San Diego Gas and Electric Company City of Anaheim, California City of Riverside, California FACILITY:
San Onofre Nuclear Generating Station, Units 2 and 3
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS FINAL REPORT ON GA INDEPENDENT DESIGN REVIEW PROGRAM On April 12, 1982, members of the NRC staff met with representatives of the General Atomic Company, (GA) and SCE to discuss the GA final report entitled, "Independent Verification of San Onofre Nuclear Generating Station Units 2 and 3 Seismic Design and Quality Assurance Program Effectiveness,4 dated April 5, 1982. Attendees at the meeting are given in Enclosure 1.
At the meeting, SCE outlined the basis for their confidence in the design and the design process and GA summarized the results of their report. Slides presented at the meeting are given in Enclosure 2. At the meeting, SCE representatives indicated that, although the program called for corrective action plans (CAP's) to be instituted only for "findings," SCE had also issued CAP's for all "observations."
origira Harry Rood, Project Manager Licensing Branch No. 3 Division of Licensing
Enclosure:
As stated cc w/enclosures:
See next page 82 0 50aag OFFICE SURNAME)
HRood:ph ia DATEO 4/94) 2 4/
/82 NRC FORM 31810 8o0) NcM 0240 OFFICIAL RECORD COPY
Mr. Robert Dietch
- 2 Mr. D. W. Gilman cc:
Mr. P. Dragolovich Bechtel Power Corporation P. 0. Box 60860, Terminal Annex Los Angeles, California 90060 Mr. Mark Medford Southern California Edison Company 2244 Walnut Grove Avenue P. 0. Box 800 Rosemead, California 91770 Henry Peters San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Ms. Lyn Harris Hicks Advocate for GUARD 3908 Calle Ariana San Clemente, California 92672 Richard J. Wharton, Esq.
University of San Diego School of Law Environmental Law Clinic San Diego, California 92110 Phyllis M. Gallagher, Esq.
Suite 222 1695 West Crescent Avenue Anaheim, California 92701 Mr. A. S. Carstens 2071 Caminito Circulo Norte Mt. La Jolla, California 92037 Resident Inspector, San Onofre/NPS c/o U. S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92672 Charles E. McClung, Jr., Esq.
Attorney at Law 24012 Calle de la Plata Suite 330 Laguna Hills, California 92653
ENCLOSURE 1 ATTENDEES MARCH 12, 1982 MEETING INDEPENDENT DESIGN VERIFICATION PROGRAM SAN ONOFRE 2 AND 3 NAME ORGANIZATION H. Rood NRC-DL W. Haass NRC-DE-OAB R. Bosnak NRC-DE-MEB F. Cherny NRC-DE-MEB R. E. Lipinski NRC-DE-SEB David Jeng NRC-DE-SEB K. P. Baskin SCE G. L. Wessman TPT/GAC J. Jack Adrian SCE R. H. Vollmer NRC-DE J. P. Knight NRC-DE F. Schauer NRC-DE-SEB
ENCLOSURE 2 QUALIFICATIONS OF SOUTHERN CALIFORNIA EDISON COMPANY (SCE)
Headquarters engineering staff over 400 Station engineering staff of approximately 100 and total station staff of over 800 o
10 CFR 50 Appendix B Quality Assurance Program in place since issuance of Appendix B Fourteen years of Unit 1 experience Deliberate and methodical pace of corporate nuclear activities Industry leadership by SCE senior management
SOUTHERN CALIFORNIA EDISON COMPANY QUALITY ASSURANCE ORGANIZATION 0
Compliance of Quality Assurance Program with 10 CFR 50 Appendix B 4
Tenure of Quality Assurance Program 0
Staff of approximately 70 personnel Independence from engineering, construction and operations activities Additional level of review of Bechtel and Combustion Engineering Quality Assurance and design activities Augmentation of Quality Assurance organization by separate records management organization
SEISMIC DESIGN BASIS Suspension of project design pending resolution of seismic design basis Uniformity of design basis Severity of project design basis Depth of review of project design basis
CONSERVATISM OF STRUCTURAL DESIGN CRITERIA Number of Structural Design Reviews Sources of Additional Margin 9
Utilization of Enveloped In-Structure Response Spectra
QUALIFICATIONS OF ENGINEER-CONSTRUCTOR 0
Three decades of nuclear power plant design and con struction experience Design and/or construction of 84 nuclear projects Largest nuclear engineer-construction staff in U.S.
10 CFR 50 Appendix B Quality Assurance Program in place since issuance of Appendix B Selection of Bechtel to complete projects initiated by other organizations
QUALIFICATIONS OF GENERAL ATOMIC COMPANY Business Experience Active in nuclear power industry since 1958 Full range of NSSS and supplier capabilities to the nuclear industry Breadth of Technical Capabilities All major engineering disciplines Verified and state-of-the-art computer codes ASME certifications Applied experience Depth of Capabilities Total staff of 1920 916 degreed professionals, including 485 with ad vanced degrees Required Infrastructure First NRC accepted Quality Assurance Program (1974)
Document control capabilities (since 1970)
INDEPENDENCE OF GENERAL ATOMIC COMPANY Financial Less than 1 % revenue from Southern California Edison Company related contracts Corporate Integrity Company completely independent of Southern California Edison (SCE) and San Diego Gas and Electric (SDG&E) Companies Maintain corporate image of parent companies No substantive conflict of interest of personnel No past work experience for key personnel in design, construction or quality assurance at SONGS 2 & 3 No immediate family employed by SCE or SDG&E No significant ownership or creditor interest in SCE or SDG&E Compliance assured through Security Question naires
SCOPE OF REVIEW Program was structured to give a discerning basis on which to make a definitive evaluation.
SCOPE OF REVIEW BASIC PROGRAM STRUCTURE DESIGN ONSTRUCTION U
U U
U U
U I
SIS SCE QA&&
a SCE QA ENGINEERING aQ AUDITS AUDITS TS U
U U
U U
DESIGNSTUTN DESIGN U\\1SYSTEM
)
DESTMIGNCOPLTE I BASIS j I OR DSG R
~
ETR TASK G PR CS KAST S
K U
U U
U U
TAK
SC 0 P F 0 F RE VIE W PURPOSE EFFORT DOCUMENTS ISSUES (Manmonchs)*
REVIEWED RAISED To DETERMINE IF THE DESIGN PROCESS USED BY SCE, BPC AND C-E SATISFIED COMMITMENTS IN:
35 MANUALS 2 OBSERVATIONS TASK A o
APPENDIX A OF PSAR AND o C-E QA TOPICAL REPORT TO DETERMINE-IF THE DESIGN CONTROL PROCEDURES 21 1280 35 OBSERVATIONS TASK B IDENTIFIED IN TASK A WERE IMPLEMENTED IN THE 33,000 INDIVIDUAL 1 FINDING DESIGN DOCUMENTS.
CHECKS TO REVIEW THE SEISMIC DESIGN OF SELECTED SAFETY RELATED STRUCTURES, COMPONENTS AND SYSTEMS 111 500 41 OBSERVATIONS (FEATURES) FOR COMPLIANCE WITH DESIGN BASIS AND 22 FEATURES 1 FINDING METHODOLOGY IN FSAR SECTIONS 3.7 AND 5.8.
To PERFORM INDEPENDENT CALCULATIONS USING TASK H1 ALTERNATE ANALYTICAL TECHNIQUES ON SELECTED 3
2 SETS OF 1 OBSERVATION FEATURES REVIEWED IN TASK C, CALCULATIONS l0 DETERMINE IF SCE AND BPC PERFORMED AUDITS AT THE SITE AND FABRICATOR'S SHCPS IN AREA OF IMPLEMENTA-8 AUDIT PLANS &
5 OBSERVATIONS TASK D TION OF SEISMIC DESIGN DOCUMENTS AND TO EVALUATE SCHEDULES 2 FINDINGS EFFECTIVENESS AND RESULTS OF SUCH AUDITS.
279 AUDIT REPORTS TO REVIEW BY VISUAL EXAMINATION THE TASK 6 (AS-BUILT) INSTALLATION OF A SEGMENT 1
41 DRAWINGS 2 OBSERVATIONS OF PIPE.
- INCLUDES REVIEW AND PROCESSING OF POTENTIAL FINDING REPORTS.
VOLUMES I & It OF THE REPORT SPECIFY REVIEW EFFORT ONLY.
REVIEW PROCESS o
Established selection criteria e
Areas selected Procedures written Review performed Questions raised (PFRs)
Resolution of questions Observations -
Valid deviation that could not create a safety hazard Findings -
Valid deviation that could create a safety hazard Corrective Action Plan (CAP) -
The set of steps planned by SCE to meliorate the affect of a finding a
Review documented
REVIEW PROCESS (continued)
Comprehensiveness of review -
A five-tier process Independent Reviewer Task Leader Original Design Organization Findings Review Committee 0
Project Manager
SAN ONOFRE UNITS 2 AND 3 13 POTENTIAL FINDING REVIEW FLOWCHART CAPS 66 REVIEWERS 3 TASK LEADERS 7 F D I N G S D E S I G N ADEQUACY 86 OBSERVATIONS 2041 170 FINDINGS PROJECT DOCUMENTS QUESTIONS REVIEW MANAGER AND RAISED COMMITTEE ORIGINAL DESIGN ORGANIZATION INPUT 77 NOT VALID 000 RESPONSE
PROGRAM CONCLUSIONS Design Review Procedure Review -
Task A Two Observations No discernible impact Three Findings Lack of formal procedures for C-E Project Manage ment coordination and design review functions Resolved by CAP and Task B, C and H review Conclusion The design process Meets commitments Expected to produce an adequate design
PROGR AM CONCLUSIONS (continued)
Design Procedure Implementation Review -
Task B Thirty-five observations No discernible impact One finding SCE lack of strict compliance with procedures Resolved by CAP and review of all SCE design work Conclusion Implementation of the design system is satisfac tory
PROGR AM CONCLUSION (continued)
Seismic Design Technical Review -
Task C and Independent Calculations -
Task H Forty-two Observations.
No discernible impact One Finding Design of concrete anchor inserts for cable tray supports Resolved by CAP when implemented Conclusion
-The design of the twenty-two features is adequate
4 0 PROGRAM CONCLUSION (continued)
Design area -
Tasks A, B, C & H The seismic design of San Onofre Units 2 and 3 is judged adequate
PROGR AM CONCLUSION (continued)
Construction Area Audit Plan Review -
Task D Five Observations No discernible impact 4
Two Findings Lack of SCE procedure for auditing of effectiveness Lack of maintenance of permanent records.
Resolved by two CAPs Conclusion The audit program is adequate Construction -
Pipe Segment Walkdown -
Task G 0
Two Observations Installation shown acceptable No Findings Conclusion The installation of the pipe segment is adequate
PROGRAM CONCLUSION (continued)
Unit 2 vs Unit 3 0
Concentrated on Unit 2 0
Significant unique features of Unit 3 reviewed Conclusion The conclusions of the program are applicable to Unit 2 and Unit 3 Overall QA Program Procedures reviewed using QA program documents and PSAR commitments as source documents Requirements interpreted in light of 10CFR50, Appen dix B and ANSI N45.2 Conclusion QA program, in general, responsive to 10CFR50, Appendix B No deficiencies found
Ae 6
PROGRAM CONCLUSION (continued)
Overall The seismic aspects of the San Onofre Units 2 and 3 project are judged adequate and supports issuance of the full power license for Units 2 and 3.