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
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Southern California Edison Company P. 0. BOX 800 2244WALNUTGROVEAVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER, NUCLEAR ENGINEERING February 14, 1980 (213) 572-1401 AND LICENSING Director, Office of Nuclear Reactor Regulation Attention:
Mr. D. G. Eisenhut, Acting Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlmen:
Subject:
Docket No. 50-206 Additional Information in Support of Responses to NRC Requirements Related to the Three Mile Island Accident San Onofre Nuclear Generating Station Unit 1 By letter dated November 15, 1979 you provided NRC recommendations for the Auxiliary Feedwater (AFW) System at San Onofre Unit 1. Our response to these recommendations was provided by letter dated January 23, 1980.
One of the recommendations (Section X.13.3.2.2) required the performance of endurance testing of the AFW pumps. Based on the guidelines provided in the recommendation, the endurance testing was completed by January 25, 1980.
During recent telephone discussions with members of your Staff, subsequent to the completion of the endurance testing, we were advised that the guidelines under which the endurance testing should be conducted had been revised, and that a summary of the conditions and results of the endurance testing would have to be submitted to the NRC. The revised guidelines and a specific request for submittal of information obtained from the endurance testing was received by telecopy on January 25, 1980.
Submitted herewith as Enclosure 1 to this letter is the requested information obtained from the endurance testing. Where the information obtained from the endurance testing deviates from that requested by the revised guidelines, a basis for the deviation is also provided in Enclosure 1.
If you have any questions, or require additional information concerning the enclosure to this letter, please contact me.
Very truly yours,
'00 to Letter Dated February 14, 1980 from K. P. Baskin to D. G. Eisenhut A revision to guidelines for endurance testing of the AFW pumps, as described in Section X.13.3.2.2 of your letter, November 15, 1979, was telecopied to us on January 25, 1980.
The revised guidelines included requirements for a summary report of the endurance testing. The report requirements and our responses are provided below:
- 1)
Include a brief description of the test method (including flow schematic diagram) and how the test was instrumented (i.e., where and how bearing temperatures were measured).
Response
Special Operating Procedure #11, "Auxiliary Feedwater Pumps Endurance Run Test," was developed to establish test acceptance criteria for bearing temperatures and vibration.
The acceptance criteria were derived from the pump and pump driver manufacturer instruction manuals and pump head curves, or from similar test criteria which have been developed for the In-Service Pump Testing Program performed in compliance with ASME Boiler and Pressure Vessel Code,Section XI requirements.
Bearing temperatures were measured with a Wall Model Platinum 392 surface pyrometer held on the outside surface of the top of the bearing caps. Bearing vibration readings were measured with an IRD Model 306 vibration meter held on the outside surface of the bearing caps.
Each pump was tested individually using the flow path from the normal water source (Condensate Storage Tank) to all three steam generators via the emergency flow path as shown on Figure 1.
Each pump was operated for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This duration complied with that recommended in your November 15, 1979 letter and exceeded the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> duration recommended in your revised guidelines.
At the conclusion of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> endurance tests, each pump was shut down and allowed to cool down for four hours. The pumps were then restarted and operated at design rated conditions for at least one hour. This cooldown and retest was consistent with that recommended in your November 15, 1979 letter (specific cooldown limits were not provided), but did not comply with specified cooldown limits recommended in your revised guidelines. Specifically, (1) we did not verify that the pumps cooled down until pump temperatures were reduced to within 20oF of their values at the start of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> endurance test, and (2) we did not allow the pumps to cool down for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. However, the AFW pumps at San Onofre Unit 1 are relatively small (300 gpm -
steam and 240 gpm -
electric).
Thus, the pumps cool down more quickly than larger pumps and we consider the four hour cooldown period used for our endurance testing to meet the intent of the Staff recommendations. In addition, normal surveillance testing was successfuly completed from ambient conditions 15 days and 3 days following completion of the endurance testing for the electric and steam driven pumps, respectively.
-2
- 2)
Include a discussion of how the test conditions (pump flow, head, speed and steam temperature) compare to design operating conditions.
Response
Both pumps were operated at design rated discharge pressure and flow using pressure indications and the pump head curves. The steam driven pump was operated at design rated speed during normal plant operation with steam supplied from the steam generators at normal temperature (greater than 500 0F) and pressure.
- 3)
Include plots of bearing/bearing oil temperature versus time for each bearing of each AFW pump/driver demonstrating that temperature design limits were not exceeded.
Response
Pump and driver bearing temperatures were recorded at least every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> throughout the endurance tests. Plots of bearing temperatures (pump and driver) versus time for the electric and steam driven AFW pumps are shown on Figures 2 and 3, respectively. All bearing temperature readings remained within the acceptance criteria during the endurance tests.
- 4)
Include a plot of pump room ambient temperature and humidity versus time demonstrating that the pump room ambient conditions do not exceed environmental qualification limits for safety-related equipment in the room.
Response
The AFW pumps are located in an open area under the west feedwater heater deck.
The exhaust from the steam-driven AFW pump is piped to a remote outside location. Therefore, ambient conditions (temperature, humidity) are not substantially affected by AFW pump operation. Actual temperature and humidity conditions were not measured during the endurance testing.
- 5)
Include a statement confirming that the pump vibration did not exceed allowable limits during tests.
Response
Pump and driver bearing vibration readings were recorded at least every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> throughout the endurance tests. All vibration readings remained within the acceptance criteria.
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