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
ML13311A2341979-05-31031 May 1979
Analysis of Capsule F,Reactor Vessel Radiation Surveillance Program
Project stage: Other
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
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
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
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
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
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
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
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
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
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
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
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
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
ML13330A0341980-04-24024 April 1980
Forwards Analysis of Capsule F,Reactor Vessel Radiation Surveillance Program, & Tech Specs 3.1.3 for Combined Heatup,Cooldown & Pressure Limitations.Proposed Change to Tech Specs Will Be Submitted by 801231
Project stage: Request
ML13330A0351980-04-24024 April 1980
Tech Spec 3.1.3 for Combined Heatup,Cooldown & Pressure Limitations,Figures 3.1.3a-3.1.3d & Table 3.1.3.1 for Reactor Vessel Toughness Data (Unirradiated)
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
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
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
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
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
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
1980-01-23
[Table View] |
Text
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON
)
COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY )
for a Class 104(b) License to Acquire,
)DOCKET NO. 50-206 Possess, and Use a Utilization Facility as
)
Part of Unit No. 1 of the San Onofre Nuclear )Amendment Application No. 118 Generating Station
)
SOUTHERN CALIFORNIA EDISON COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY, pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 118.
This amendment application consists of Proposed Change Nos. 127, 137 and 138 to Provisional Operating License No. DPR-13. Proposed Change No. 138 revises Provisional Operating License No. DPR-13, Section 3, "Contents and Conditions," and Proposed Change Nos. 127 and 137 modify the Technical Specifications incorporated into Provisional Operating License No. DPR-13 as Appendices A and B.
Proposed Change No. 127 is a request to revise the Appendix A Technical Specifications, to include revised limiting conditions for operation and surveillance requirements for the Auxiliary Feedwater System (AFWS) at San Onofre Unit 1. These revisions are required in response to NRC review of TMI Action Plan Items II.E.1.1 and II.E.1.2 regarding the AFWS and due to seismic modifications being implemented at San Onofre Unit 1 during the current outage.
PDR ADOCK 05000206 PDR
-2 Proposed Change No. 137 is a request to revise Appendix A Technical Specification 3.1.3, "Combined Heatup, Cooldown, and Pressure Limitations,' to update the curves, extend applicability to 16 EFPY of operation, and incorporate the additional information on reactor vessel material determined by analysis of Capsule F. The curves are revised based on Appendix G to 10 CFR 50 which involves changes to the calculational techniques used in the analysis. These changes have resulted in small modifications to the wording in the new specification. The.new curves also include a requirement to review the Overpressure Mitigation System setpoint for continued applicability should the curves require change in the future.
Proposed Change No. 138 is a request to revise Provisional Operating License No. DPR-13, Section 3, "Contents and Conditions", Condition 3.E, Steam Generator Inspections to allow 6 Equivalent Full Power Months (EFPM) of operation until the next required steam generator inspection. This revision is made at the request of the NRC in their letter dated February 7, 1984.
In the event of conflict, the information in Amendment Application No. 118 supersedes the information previously submitted.
-3 Based on the safety analysis provided in the Description of Proposed Change and Safety Analysis, it is concluded that (1) these proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59, nor do they present significant hazards considerations not described or implicit in the Final Safety Analysis, and (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change.
Pursuant to 10 CFR 170.22, the Proposed Changes contained in Amendment Application No. 118 have each been determined to constitute the amendment class defined below:
Proposed Change No. 127 is determined to constitute a Class III amendment. The basis for the determination is that the Proposed Change involves a single safety issue regarding the limiting conditions for operation and surveillance requirements of. the AFWS. The fee of $4,000.00 corresponding to this determination is herewith remitted as required by 10 CFR 170.22.
Proposed Change No. 137 is determined to constitute a Class.III amendment. The basis for the determination is that the Proposed Change involves a single safety issue regarding the reactor vessel integrity. The fee of $4,000.00 corresponding to this determination is herewith remitted as required by 10 CFR 170.22.
-4 Proposed Change No. 138 is determined to be exempt from fee. The basis for this determination is that the revision is necessary to comply with an NRC request for a revision to License Condition 3.E. Accordingly, no fee is provided.
The total fee of $8,000.00 corresponding to the above determinations is.
herewith remitted as required by 10 CFR 170.22.
-5 Subscribed on this,/_
day of
/
Respectfully submitted, SOUTHERN CALIFORNIA EDISON COMPANY Kenneth P. Baskin Vice President Subscribed and sworn to before me this day of
/9/ffY OFFICIAL SEAL AGNES CRABTREE NOTARY PUBLIC -
CALIFORNIA PRINCIPAL OFFICE IN LOS ANGELES COUNTY My Commission Expires Aug. 27, 1986 Notary yblic in and for the County of Los Angeles, State of California My Commission Expires: d/',7 IM61 Charles R. Kocher James A. Beoletto Attorneys for Southern California Edison Company By Ja s 4A.
eo t
-6 Subscribed on this day of 4
/
Respectfully submitted, SAN DIEGO GAS & ELECTRIC COMPANY By J. C. Holcombe Vice President Subscribed and sworn to before me this day of 4
OFFICIAL SEAL SLORAINE E. GRAY NOTARY PUBLIC -CALIFORNIA 10-ter PRINCIPAL OFFICE IN SAN DIEGO COUNTY o ary Public in and f the County of MY commission Exp. April 1986 San Diego, State of California My Commission Expires:
6 David R. Pigott Samuel B. Casey Orrick, Herrington & Sutcliffe Attorneys for San Diego Gas & Electric Company By David R. Pigott U
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of SOUTHERN
)
CALIFORNIA EDISON COMPANY
)
and SAN DIEGO GAS & ELECTRIC
)Docket No. 50-206 COMPANY (San Onofre Nuclear
)
Generating Station Unit No. 1 CERTIFICATE OF SERVICE I hereby certify that a copy of Amendment No. 118 was served on the following by deposit in the United States Mail, postage prepaid, on the 17th day of May 1984.
Henry 3. McGurren, Esq.
Staff Counsel U.S. Nuclear Regulatory Commission Washington, D.C. 20545 David R. Pigott, Esq.
Samuel B. Casey, Esq.
Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 John V. Morowski Bechtel Power Corporation P.O. Box 60860, Terminal Annex Los Angeles, California 90060 Michael L. Mellor, Esq.
Thelen, Marrin, Johnson & Bridges Two Embarcadero Center San Francisco, California 94111 Huey Johnson Secretary for Resources State of California 1416 Ninth Street Sacramento, California 95814 Janice E. Kerr, General Counsel California Public Utilities Commission 5066 State Building San Francisco, California 94102
-2 J. Rengel Atomic Power Division Westinghouse Electric Corporation Box 355 Pittsburgh, Pennsylvania 15230 A. I. Gaede P.O. Box 373 San Clemente, California 92672 Frederick E. John, Executive Director California Public Utilities Commission 5050 State Building San Francisco, California 94102 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 James f.Eeoletto Assist tCounsel Souther alifornia Edison Company
