Letter Sequence Other |
|---|
|
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, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: 05000206/LER-1981-013, Forwards LER 81-013/99X-0.Detailed Event Analysis Submitted, 05000206/LER-1981-013-99, /99X-0:on 810618,power Operated Relief Valve Controller Opened Twice During Normal Pressure Transient Following Reactor Trip.Caused by Setting Time Constant to Off to Satisfy NUREG-0737,Item II.K.3.9, L-81-029, Forwards Proposed Licensing Exam Schedule for 1981-82 for Reactor & Senior Operator Candidates,Per 810807 Request, L-82-002, Informs That Necessary Procedures Per NUREG-0737,Item I.A.1.3 Re Use of Overtime Required by Generic Ltr 82-12 Will Be Implemented by 821001.Tech Spec Will Not Be Submitted for Review Pending Receipt of Model Tech Specs, ML13308A671, ML13308B064, ML13308B821, ML13308B925, ML13310A775, ML13310A777, ML13310A778, ML13310A826, ML13310A828, ML13310A923, ML13310A926, ML13310B078, ML13310B081, ML13310B120, ML13310B280, ML13310B546, ML13310B619, ML13311B030, ML13316B714, ML13317A133, ML13317A134, ML13317A166, ML13317A190, ML13317A263, ML13317A267, ML13317A289, ML13317A367, ML13317A369, ML13317A377, ML13317A391, ML13317A427, ML13317A450, ML13317A454, ML13317A468, ML13317A478, ML13317A479, ML13317A484, ML13317A488, ML13317A490, ML13317A507, ML13317A512, ML13317A519, ML13317A553, ML13317A567, ML13317A581, ML13317A616... further results
|
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
ML13333A4221979-10-22022 October 1979
Forwards Responses to NRC post-TMI Requirements Re Design & Analysis,Operations,Rcs High Point Vents,Emergency Preparedness & Instrumentation to Monitor Containment Conditions
Project stage: Other
ML13303A7381979-10-30030 October 1979
Summary of 790927 Meeting W/Utils in San Clemente,Ca Re Emergency Plan Review
Project stage: Request
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
ML13322A6191979-11-15015 November 1979
Summary of 791108 Telcon W/Util Re Unacceptable Schedule for Implementing Lessons Learned Task Force Items
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
ML13333A4571979-12-14014 December 1979
Forwards Revisions to Util 790913 Commitments Re Compliance w/short-term TMI Lessons Learned Task Force Requirements Per NUREG-0578
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
IR 05000206/19790161980-01-0404 January 1980
IE Insp Rept 50-206/79-16 on 791101-02 & 26.No Noncompliance Noted.Major Areas Inspected:Scope & Methods of Field Insp for IE Bulletin 79-14,repair of Shorted Electrical Buswork & Licensee Design Change Proposal
Project stage: Request
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
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
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
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
ML13311B0301980-01-21021 January 1980
Discusses Response to NRC 800102 Order to Show Cause Re Implementation of NUREG-0578 Category a Requirements.Will Continue Operation Until 800315.Shutdown on 800131 Would Severely Impact Power Reliability in Pacific Northwest
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
ML13333A4781980-01-23023 January 1980
Advises That Responses to NRC Requesting Info Re Small Break LOCA Guidelines Will Be Submitted by 800228. Bulletin Response Will Be Sent by 800228
Project stage: Other
ML13333A4811980-01-24024 January 1980
Forwards Corrected Page 3 of App 10 to Enclosure a of Re Power Reliability Info.Omitted Info Sent to R Weiner of DOE on 800118
Project stage: Other
ML13333A4831980-01-29029 January 1980
Confirms 800124 & 25 Telcons Re Facility 800126 Shutdown for Implementation of Lessons Learned Task Force Category a short-term Requirements Re Reopening of Containment Isolation Valves
Project stage: Other
ML13308B0641980-01-30030 January 1980
Concludes That Inadequate Justification Exists to Extend Util 800131 Deadline to 800315 for Response to 800102 Order to Show Cause Why All Category a Lessons Learned Requirements Should Not Be Implemented
Project stage: Other
ML13322A6971980-01-31031 January 1980
Reload Safety Evaluation,Unit 1,Cycle 8
Project stage: Other
ML19290E8091980-02-0101 February 1980
Denies Request for Shutdown Extension Until 800315 to Complete Category a Requirements W/Available Equipment. Reopening of Containment Isolation Valves Until Further Mods Completed Acceptable
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
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
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
ML13333A5031980-02-13013 February 1980
Forwards Justification for RCS Subcooling Setpoint,In Response to NRC 791227 Request.Addl Info Will Be Forwarded in Response to IE Bulletin 79-27 by 800228
Project stage: Other
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
ML13316B7141980-03-0707 March 1980
Advises NRC of Delay in Responding to Item 4 of as Part of Response to IE Bulletin 79-27.Submittal Rescheduled from 800228 to 800701
Project stage: Other
ML13330A0251980-03-25025 March 1980
Forwards Addl Info for Implementation of TMI short-term Lessons Learned Task Force Requirements.Describes Mods to Backup Nitrogen Pneumatic Supply & Valve Position Indication.Drawing Available in Central Files Only
Project stage: Other
ML13330A0271980-03-28028 March 1980
Responds to NRC 800117 Request for Review of Draft Evaluation of SEP Topic XV-20, Radiological Consequences of Fuel Damaging Accidents,(Inside & Outside Containment). Review Confirms Facts as Correct
Project stage: Request
ML13330A0321980-04-11011 April 1980
Confirms 800410 Telcons W/Regulatory Personnel Re Implementation of Several Category a TMI Lessons Learned Task Force Requirements Described in
Project stage: Other
IR 05000206/19800041980-04-11011 April 1980
IE Insp Rept 50-206/80-04 on 800128-0229.Noncompliance Noted:Failure to Rept Reactor Protection Sys Setpoints Less Conservative than Those Established by Tech Specs & Use of Nonstandard Fitting
Project stage: Request
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
ML13331B3711980-05-0707 May 1980
Ro:On 800506,during Refueling Operations,After Lowering of Reactor Internal Instrumentation Package,Incore Instrumentation Package for Thimble Location D-7 Found Bent Outward.Caused by No Provision for Thimble Passage to Core
Project stage: Request
1980-01-21
[Table View] |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER, NUCLEAR ENGINEERING February 8, 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 Gentlemen:
Subject:
Docket No. 50-206 Additional Information in Support of Responses to NRC Requirements Related to the Three Nile Island Accident San Onofre Nuclear Generating Station Unit 1 This letter confirms telephone discussions with members of your staff on January 4 and January 7, 1980 in which we indicated our inability to meet several commitments regarding TMI modifications during the current outage. Specifically:
- 1. We will be unable to complete the installation of circuitry to automatically close the new auxiliary feedwater (AFW) motor operated discharge valve upon initiation of Safety Inspection as discussed in Enclosure 1 to our letter dated January 23, 1980.
The circuitry is required for single failure protection in con junction with the automation of the AFW System. Until the cir cuitry is installed, the motive power to the new valve will be disconnected by means of a disconnect switch in the locked open position and the valve hand wheel will be locked in the closed position (local manual operation of the valve will not be jeopardized) whenever the Safety Injection System is required to be operable. This configuration is consistent with the existing manual operation of the AFW System and the NRC letter dated December 21, 1979 which requires that we not automate the AFW System until the NRC has reviewed and approved the steamline and feedwater line break analyses being performed in accordance with that letter.
It is expected that the circuitry will be installed during the refueling outage currently scheduled to commence in April, 1980.
At that time, the ability will exist to operate the new AFW motor operated discharge valve remote manually from the control room.
8OO219o5,67
Mr. D. G. Eisenhut, NRC February 8, 1980
- 2. We may be unable to provide new AFW flow measurement devices for the existing emergency manual AFW flow path as discussed in to our letter dated November 21, 1979.
The flow devices failed during testing and new devices may not be available prior to resumption of power operation currently scheduled for February 11, 1980. New flow measurement devices have been ordered to replace the failed devices and are expected to be delivered and installed prior to resumption of power operation. If fabri cation and/or delivery problems prevent installation prior to :
resumption of power operation, the new flow measurement devices will be installed within thirty days of their receipt, but in no case, later than June 1, 1980.
As discussed in our November 21, 1979 letter, the emergency manual AFW flow path and the associated new AFW flow measurement devices would be utilized in the event the normal AFW flow path, which is being automated, is not operable. The normal AFW flow path has been provided with AFW flow measurement devices and the emergency manual AFW flow path has existing steam generator water level indicators located at the manual isolation valves.
The steam generator water level indicators are supplied power from the vital buses and would be utilized by the operator stationed at the manual isolation valves to maintain the proper steam generator water inventory. In addition, the operator stationed at the manual isolation valves has appropriate communication with the control room operator who also has access to steam generator water level indicators.
- 3. The proposed testing and surveillance specifications for the AFW System cannot be fully implemented as discussed in Enclosure 1 to our January 23, 1980 letter until the remote manual and auto matic actuation of the AFW System is completed. The following items cannot be implemented at this time:
- a. As discussed in Item 1 above, the new AFW pump motor operated discharge valve must remain closed until the circuitry to automatically close the valve on a Safety Injection signal has been installed whenever the Safety Injection System is required to be operable. Accordingly, the new valve will be treated (and tested) as a closed manual valve which cannot be locked open. All other manual valves in the AFW System pump suction piping and the normal AFW flow path from the AFW pumps to the steam generators will be locked open and inspectalmonthly to assure proper system alignment.
Mr. D. G. Eisenhut, NRC February 8, 1980
- b. As discussed in Item 1 above, remote manual operation capability cannot be implemented until the circuitry to auto matically close the new AFW pump motor operated discharge valve has been installed. In addition, the automatic-start system will not be activated and the manual-start system will not be adversely affected until the NRC has completed their review and issued an approval of the information concerning the applicability of current analyses of a main steamline break or main feedwater line break assuming early initiation of auxiliary feedwater flow with a failure to limit flow to the affected steam generator as requested by the NRC letter dated December 21, 1979.
Accordingly, the remote manual and automatic-start circuitry for the AFW System cannot be tested periodically. As dis cussed in Item 1 above, the circuitry to automatically close the new AFW pump motor operated discharge valve will be installed during the refueling outage currently scheduled to commence in April, 1980. As indicated in our January 16, 1980 letter, the information requested by the NRC letter dated December 21, 1979 will be submitted by October 1, 1980.
If you have any questions concerning the above information, please contact me.
Very truly yours,
