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
ENCLOSURE 1 4.1.9 Auxiliary Feedwater Pumps and Valves Applicability: Applies to the motor driven auxiliary feedwater pump, the turbine driven auxiliary feedwater pump, and auxiliary feedwater valves for MODES 1, 2 and 3.
Objective:
To ensure the reliability of the auxiliary feedwater system.
Specification:
A. Each auxiliary feedwater pump shall be demonstrated OPERABLE by testing each pump in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i).
B. At least once per 31 days when the auxiliary feedwater system is required to be operable, an inspection shall be made to verify that normally open manual valves in the auxiliary feedwater system suction piping and the I
emergency path from the auxiliary feedwater pumps to the steam generators that could interrupt all AFW flow are locked open.
C. Each auxiliary feedwater pump shall be demonstrated OPERABLE at least once per 18 months during shutdown by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.
- 2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.
D. At least once per 18 months, all normally closed manual valves in the alternate auxiliary feedwater system suction line shall be demonstrated operable.
E. When the reactor coolant system pressure remains less than 500 psig for a period longer than thirty (30) days, a flow test shall be performed to verify the emergency flow path from the condensate storage tank to each steam generator, using the motor driven auxiliary feedwater pump prior to increasing reactor coolant system pressure above 500 psig. The flow test shall be conducted with the auxiliary feedwater system valves in their emergency alignment.
As soon as steam becomes available, the steam driven auxiliary feedwater pump shall be similarly tested.
e203120334 820310 PDR ADOCK 05000206
-2 Basis:
The OPERABILITY of the auxiliary feedwater. system ensures that the Reactor Coolant System can be cooled down to less than 350oF from normal operating conditions in the event of a total loss of offsite power.
The electric driven auxiliary feedwater pump and the steam driven auxiliary feedwater pump are both capable of delivering a total feedwater flow of 165 gpm at a pressure of 1015 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350oF when the residual Heat Removal System may be placed into operation.
References:
(1) NRC letter dated July 2, 1980 from D. G. Eisenhut to all pressurized water reactor licensees.
ENCLOSURE 3 AUXILIARY FEEDWATER FLOW INDICATION SAN ONOFRE UNIT 1 SYSTEM DESCRIPTION San Onofre Nuclear Generating Station Unit 1 is provided with two means of verifying auxiliary feedwater flow.
Steam Generator Wide Range Level Indication A wide range level indicator for each steam generator permits observation of level over essentially the full height of the steam generator shell.
The wide-range level indicator channels are independent of the control range level channels.
Each steam generator is provided with a wide range level transnitter (LT-450, 451, 452) with instrument taps on the steam generators located at elevations 20'-3 9/16" and 46'-10 5/16" providing a measurement range of 318 3/4 inches.
This provides the capability to monitor the level from 252 5/8 inches below to 65 7/8 inches above the steam generator feedwater inlet centerline. Control room level indicators (LI-450A, 451A, 452A) have a scale range of 400 inches.
Auxiliary Feedwater Flow Indication Each steam generator is capable of being independently fed auxiliary feedwater.
A high and low range flow transmitter (FTH-3453, 3454, 3455 and FTL-3453, 3454, 3455) monitor flow to each steam generator and provide control room flow indication (FI-3453, 3454, 3455).
Each of the three flow indicators has the capability to monitor a range of 0 to 300 gpm. The combined maximum capacity of the two auxiliary feedwater purrps at expected steam generator pressure is 440 gpm with each steam generator auxiliary feedwater control valve set to supply less than 150 gpm which corresponds to the midrange position of the flow indicator.
SYSTEM SEPARATION Electrical Separation The steam generator wide range level indication system is powered from steam generator auxiliary rack R-10 which receives power from Vital Bus Number 1 which receives power from Battery Bank Number 1.
The auxiliary feedwater flow indication system is powered from Vital Bus Number 5 which receives power from Battery Bank Number 2.
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-2 Physical Separation The steam generator wide range level indication system power and instrumentation cables are routed in cable trays outside the containment sphere. The cables assoiated with LT-450 are routed separately from the cables associated with LT-451 and LT-452 which are routed in the same tray system. These trays, starting at the containment penetraton, cross the space between the sphere and the turbine building at about elevation 29 feet.
Inside the turbine building the cable tray system associated with LT-450 enters the switchgear and cable spreading room along side the cable tray system associated with LT-451 and LT-452.
The auxiliary feedwater flow indication system power and instrumentation cables are routed entirely in conduit.
The cables associated with all the flow transmitters share the same conduit routing system.
The flow transmitters are located to the west of the fuel storage building with the entire conduit system located outside the containment sphere.
The conduit runs to the west of the ventilation equipment building and turns east to enter the contol building after passing between the containment sphere and turbine building space at about elevation 40 feet.
SUMMARY
The ultimate power supplies for the wide range steam generator level indication system and the auxiliary feedwater flow indication system are Battery Bank Number 1 and Battery Bank Number 2 respectively which are electrically independent.
The routing of the power and indication cables for the wide range steam generator level indication system and the auxiliary feedwater flow indication system are physically independent in all areas.
