Letter Sequence Other |
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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
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, October 6 1980 (213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Automatic Initiation of Auxiliary Feedwater System San Onofre Nuclear Generating Station Unit 1
References:
(1) D. G. Eisenhut letter to J. H. Drake dated November 15, 1979.
(2) D. L. Ziemann letter to J. H. Drake dated December 21, 1979.
(3) K. P. Baskin letter to D. G. Eisenhut dated January 16, 1980.
(4) K. P. Baskin letter to D. L. Ziemann dated April 29, 1980.
(5) IE Bulletin No. 80-04 dated February 8, 1980.
(6) H. L. Ottoson letter to R. H. Engelken dated May 19, 1980.
(7) J. G. Haynes letter to D. M. Crutchfield dated August 8, 1980. of Reference (1) provided an NRC staff request for information regarding the auxiliary feedwater system (AFWS) flow requirements at San Onofre Unit 1. Reference (2) provides an NRC staff request for information regarding the applicability of current analyses of a main steam line break or main feedwater line break assuming early initiation of auxiliary feedwater flow. In Reference (3) it was indicated that in order to supply the requested information, a complete re-analysis of the applicable transients and accidents would have to be performed and it was estimated that the information could be submitted by October 1, 1980. This same schedule was reiterated in Reference (4), and it was indicated that the design details for the automation of the AFWS would be submitted for NRC staff review by October 15, 1980.
Reference (5) was a request from the NRC Office of Inspection and Enforcement for information similar to that requested by Reference (2).
In Reference (6) it was indicated that the information requested in Reference (5) would be supplied by October 1, 1980 in conjunction with our submittal to the NRC staff of the results of the main steam line break re-analysis.
0140 I4
D. M. Crutchfield, Chief October 6, 1980 In Reference (7), the NRC staff was provided with information regarding the impact of the failure of the salt water cooling system on the design basis loss of coolant accident and the main steam line break accident. Included in Reference (7) was a committment to advise the NRC staff if the above discussed re-analyses, due October 1, 1980, would impact the information supplied in Reference (7).
The purpose.of this letter is to reschedule the date for submittal of the above discussed information which was to be supplied by October 1, 1980. A delay has resulted due to the repair work which is being done on the steam generators at San Onofre Unit 1. As a part of the analytical effort associated with the steam generator repairs, it was determined that the Reload Safety Evaluation for Cycle 8 would be impacted and it was necessary to perform re-analyses of the affected events. Therefore, it is expected that the requested information can be submitted by December 1, 1980. The design details for the automated auxiliary feedwater system will be provided by October 15, 1980 as indicated in Reference (4).
If you have any questions or desire additional information, please contact me.
Very truly yours, cc: R. H. Engelken (NRC Office of Inspection and Enforcement, Region V)
Division of Reactor Operations Inspection (NRC Office of Inspection and Enforcement, Washington, D.C.)
-A.*
October 6, 1980 TI MR. 0. K., NELSON.
SUB83ECT:
ACitional WI1 Infurmation Requirements San Onofre Nuclear Generating Station.
unit I The NRC staff hais requtesteo several items of informattion'regardi,, 1 the' modificat ions -which have resulted from the T.hI Lessons: Leaerned. tequir n-s, As previous~ly discussed with U. F.' Martinbyhoeth sitc oth Engineern icpines Is needed in order to respond to-the NRC by tho' committed Cajte.
&ach of the three Items of inforn jation is' d.isLussed; belw AUXILIARY FEWATER SYSTEM DESIGN DETAILS 8y letter, datedApril 29, 1980, It was indi-cated that th~e design dtailoof the. eutomatically initiated auxiliary feedw; Ter iystem (AFWS)v to be inistall~e.0 in Jariuax y,.1981l, would be priovici"d to thi4 NRG staff' by Optcber i5, 198 These design details shoulcsinclud6 the latest dirawings (CCN's icue)na funt onu q )scription. of trte system.
PJi~tse provide the requested Information by October '10, l9 4q, to Su POTV?
.50r~tts to the NRC by cAtober 15, 1980.
REA(.TOR COOLANT SY$TEM VENTING. DESIGN DETAILS
~
8y letter dated May 22, 1980 it~ was Indicated that the design details of the reac t or cuolant system vents would be provided to the NRC staff. by October 1 1980.
The NRC st-,ff has-teen Contacted and submittal'O this information has
- been deferred to Octob-,er 15, 1980.'* Tha desigo ciatails shouilu inciuati the latist dxa~winV4 (CCN's included) pnd a functional description of the systemn.
P1j~se provide the requested inforg~ation byOctober.10, 19W to su pprt suibmittal to the NRC by Otbe 5 1980.
AUXILIARY FEEDWAT EE SYSTEM FLOW ANAL-Y5S The letter -from -R. Hi. Verbeck dated September 12 198P provided 'Flow
.capabill.Uelot'f th~e autq1ittd Auiliary Fpedwa,tr System (q.FWS)
- t& Le
!:n6stelleO inh Janujary, 1981 unider counditions f of fmanfaedwater it~
"System)., I n o.Cder for, West inat ous!e.o conmplete ana-.ys is to metNRi.
Wnotration", requests, we need to provici AFWS flow, capabilities unde'r 1t"iof main *teamlire break (M$b) or main 'feeo~ebek(L)
AccordWn~ly, we, havte dentified he following pdoitlonal MAFWS flow analysis:
Oct. 6, 1980 I.
Case 1I MSLB outside containment.
Determine total flow to WGs
- assunp, i tor-driven auxiliary feecwater purip feeding 3 SG s throuvgh 4 ICVs at '0 psig SU pressure.
2.,
Case, 2 -MSLb inside cc'ntainatent.
Determine t otJ tifow'to 3.SGIS througt! 4 FCV's at 50 pSig SG pressifre for:
-a. nmotor-driven pump only
- b.
steaff-driven pup only
- c.
both pumps ope rat ing.
- 3.
Cast 3 M FLB outsiae containment. Determine total fiow to ~
'"suqing motor-Oriven auxiliary feedwater pup feeding 2 "G!s St ps ig SG pressure and I euxllidry feedwat 4r line spiling' to atmo phere at 0 psig 4ssming. the 4 FCs eaifuy open.,,.
ea assuming auxiliary feedwater it isolated fromtc ra (operator, action to close 2 FCsi plig.uiiry feedwater line)
Thb onitnt with the NRC coanitteu submittal dt e (Decemb~er 1, i980) n Westinhouse need dates, please Provide the inf'ormation by October 150., 1960.
If-you have any questions or desire additional. information, please contqct me.
W*".MOODY RO/ WGVF;wvo Q0., F. Mar~tln E.
. Dnovn/. G. Flournoy R. V. Krieger/R. Ornelas U..'hendrikar 1A. 1. Kaneko R. H~. Vtirbeck K. M. Evans E Files
