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
|
MONTHYEARML13333A4221979-10-22022 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
ML13322A6191979-11-15015 November 1979
Summary of 791108 Telcon W/Util Re Unacceptable Schedule for Implementing Lessons Learned Task Force Items
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
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
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
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
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
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
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
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
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
ML13330A0521980-05-22022 May 1980
Discusses Open Items Re Implementation of Category a Lessons Learned Task Force Requirements Per NRC 800502 Request.Open Items Involve Instrumentation for Inadequate Core Cooling, post-accident Sampling & Reactor Cooling Sys Venting
Project stage: Other
ML13330A0621980-06-13013 June 1980
Discusses Completed Review of NRC Forwarding Five Addl Items Resulting from post-TMI Reviews.Forwards Commitments to Meet Implementation Requirements for Items 1-5
Project stage: Other
ML13319A2131980-07-0909 July 1980
Forwards Post-Accident Sampling Sys,Capabilities & Description, & Drawings,In Response to Open Item Identified in NRC Re Implementation of TMI Lessons Learned Requirements.Drawings Available in Central Files Only
Project stage: Other
IR 05000206/19800201980-07-0909 July 1980
IE Insp Rept 50-206/80-20 on 800616-19.No Noncompliance Noted.Major Areas Inspected:Major Maint,Major Surveillance, IE Bulletin & Circular Followup & Independent Insp Effort
Project stage: Request
ML13322A7711980-07-0909 July 1980
Post-Accident Sampling Sys,Capabilities & Description
Project stage: Other
ML13302A4691980-09-12012 September 1980
Forwards Amend 20 to Fsar.Amend Contains Responses to NUREG- 0660 & NUREG-0694, TMI-Related Requirements for New Ols
Project stage: Request
ML13322A9461980-09-12012 September 1980
Notifies That Actions Required in NRC Re License Amend Application Concerning Implementation of TMI Lessons Learned Requirements Cannot Be Accomplished by 800912. License Amend Application Will Be Submitted by 810116
Project stage: Other
ML13330A1321980-10-0909 October 1980
Notifies That Date for Submittal of Info Re Design Details for Reactor Coolant Vents & Addl Info for Main Steam Line Piping Integrity Evaluation Will Be Submitted 801101 & 1201,respectively
Project stage: Other
ML13330A1351980-10-15015 October 1980
Provides Plans,Schedules & Commitments to Meet Interim Criteria for Shift Staffing & Administrative Controls,In Response to NRC 800731 Request.Full Compliance W/Criteria Will Be Achieved No Later than 820701
Project stage: Other
ML13316A5161980-10-31031 October 1980
Environ Qualification of Electrical Equipment
Project stage: Request
ML13330A1581980-12-23023 December 1980
Advises That Response to NRC Requesting Confirmation for Implementation Dates of TMI-related Items Will Be Submitted by 810105
Project stage: Other
ML13308B8211980-12-30030 December 1980
Submits Addl Info Re Description of Shift Technical Advisor Training Program & Plans for Requalification Training Per 791031 Request
Project stage: Other
ML13330A1661981-01-0707 January 1981
Notifies That License Amend Application to Incorporate Applicable Tech Specs for Implementing TMI-2 Lessons Learned Category a Items Will Be Submitted by 810401
Project stage: Request
ML13308A6711981-01-13013 January 1981
Advises That Licensee Inadvertently Omitted Info from Re Plans for Implementation of Action Item II.K.3.25 in NUREG-0737 Re Effect of Loss of Ac Power on Pump Seals. Evaluation Will Be Submitted by 820101
Project stage: Other
ML13330A1911981-01-14014 January 1981
Informs That Radiochemical & Chemical Analysis Mods Promised in Util No Longer Necessary.Due to Other TMI Recommendations,Samples Can Be Analyzed Outside Lab.Cart Mounted Iodine Sampler W/Single Channel Analyzer to Be Used
Project stage: Other
ML14135A0051981-01-23023 January 1981
High Radiation Sampling Station General Piping Arrangement Plan
Project stage: Other
ML13330A1931981-02-0202 February 1981
Forwards Application for Amend 96 of License DPR-13
Project stage: Request
IR 05000206/19810041981-02-25025 February 1981
IE Insp Rept 50-206/81-04 on 801229-810130.No Noncompliance Noted.Major Areas Inspected:Followup on Systematic Appraisal of Licensee Performance & Allegation by Contractor Employee
Project stage: Request
ML13330A2411981-03-0606 March 1981
Responds to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Sys Automatic Initiation Will Occur on Low Steam Generator Level W/Setpoint at 5% of Narrow Range Instrument
Project stage: Other
ML13330A2661981-03-17017 March 1981
Forwards Listing Containing Brief Description of Design Changes Completed During 1980 Per 10CFR50.59b & Rept on Challenges to Relief & Safety Valves Per NUREG-0578
Project stage: Other
ML13330A2671981-03-18018 March 1981
Advises That post-accident Sampling Sys,Described in Licensee ,Will Not Include Capability to Perform Chloride Analysis,Per NUREG-0737 & NUREG-0578.Chloride Analyses Using Dilute Samples Are Inaccurate
Project stage: Other
ML13330A2911981-04-13013 April 1981
Responds to NRC 801031 Request for Clarification of NUREG-0737 Requirements & Confirmation of Implementation Date.Rept by NUS Corp, Control Room Habitability Evaluation San Onofre Generating Station,Unit 1 Encl
Project stage: Request
ML13302B0341981-04-13013 April 1981
Summary of 810310 Meeting W/Utils in Bethesda,Md Re Explosion Hazards.Attendance List & Applicant Handouts Encl
Project stage: Request
ML13331A0741981-04-17017 April 1981
Requests That NRC Finish Review of Util Compliance W/Ie Bulletin 79-06C, Nuclear Incident at TMI - Suppl. Review Completion Needed for Util to Complete Design Change to Assure Automatic Tripping of Reactor Coolant Pumps
Project stage: Other
ML13330A2991981-04-20020 April 1981
Forwards Response to NUREG-0737,Item II.K.3.17 Re ECCS Equipment Outages.Also Forwards Analysis of Probability of Toxic Gas Hazard for San Onofre Nuclear Generating Station as Result of Truck Accidents Near Plant
Project stage: Other
ML13317A6101981-05-0707 May 1981
Forwards Addl Info Re SEP Topic XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment, Per 801215 & 810319 Requests
Project stage: Request
ML13317A6161981-05-12012 May 1981
Advises That TMI Action Plan Item II.K.3.9 Was Not Completed by 810101.Facility Has Been Shut Down Since Apr 1980.Item Will Be Completed Prior to Restart.Also Lists Completion Schedules for Items II.D.3,II.E.4.2.,II.G.1 & III.D.3.3
Project stage: Other
ML13317A6271981-06-0808 June 1981
Submits Results of Evaluation of Containment post-accident Pressure Reanalysis on Operational Limits,In Response to TMI Action Plan Item II.E.4.2(5).Peak post-accident Pressure & Temp in 770119 Analysis Is Still Applicable
Project stage: Other
ML20196A6141981-06-15015 June 1981
IE Review & Evaluation of Licensee Implementation of TMI Action Plan Requirement 1.C.5, `Procedures for Feedback of Operating Experience to Plant Staff
Project stage: Other
ML20196A6061981-06-15015 June 1981
IE Review & Evaluation of Licensee Conformance W/Tmi Action Plan Requirements 1.A.1.3, `Shift Manning Part 1,Limit Overtime
Project stage: Other
ML13317A6371981-06-17017 June 1981
Advises That Effluent Monitoring Sys,Per NUREG-0737,Item II.F.1 Will Not Be Completed Prior to Startup,As Remote Readout Gm Detector Has Been Removed.Interim Requirements of NUREG-0578 Will Be Met Per
Project stage: Other
1980-04-11
[Table View] |
Text
PEGULATURY INFORMATION DISTRIBUTION SYSJ i (RIDS)
ACCESSION N3R:8107130280 DUC.DATE: 81/07/01 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre: Nuclear Station, Unit 1, Southern Californ 05000206 50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre,tuclear Station, Unit 3, Southern Caliform
-3 AUTH.NAME AUTHOR AFFILIATION BASKINF.P.
Southern California Edison Co.
RECIP.1NAME REClPINV AFFILIATION EISENHUTD.G.
Division of Licensing
SUBJECT:
Forwards info in response to TMI Action Plan Item I.A.1,3 re irplementation scneuule for licensed,operators & shift technical advisorsFhree oversize drawings encl.Aperture cards will oe in PDH.
DISTRIBUTION CODE: A045S COPIES RECEIVED:LTR -L ENCL L SIZE:
TITLE: Emerqency Plan Intormation/NURG 0696 Comments NOTES:1 cy each:SEP Section Leader & J Hanchett (Region V) o5000206 Sand all FSAR & ER amends to L Chandler, 05000361 1 cy:J Hanchett (Region V),D Scalettis cy of all envir info Send all FSAR & ER amends to L Chandler, 05000362 1 cy:J Hanchett (Region V),D ScalettiI cy of all envir info RECIPIENT COPIES RECIPIENT COPIES I) CODE/NAMEt LTTR ENCL ID CODE/NAME LTTR ENCL ACTION:
OR3 #5 BC 1
1 LIC BR #3 BC 1
1 NO4ICKIrS, 04 1
1 ROOD,H, 04 1
1 INTERNAL: DIR,EMER PL PRO 1
0 EMER PREP DEV12 1
.1 EMER PREP LICO6 4
4 I&E 10 2
2 A1 1
RAD ASMT BR 1
1 FIr 01 1
1 EXTERNAL: INPO,J.STARNES 1
1 LPDR 03 1
1 NSIC 05 1
NTIS 1
I P R 02 1
1 TOTAL vU4ER OF COPIES R~EUIREO: LTTR ENCL
Southern California Edison Company P. 0. BOX BOO 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING.
(213) 572-1401 SAFETY. AND LICENSING July 1, 9
Director, Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director 454 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos.
50-206, 50-361 and 50-362 San Onofre Nuclear Generating Station Units 1, 2 and 3 Reference is made to your letter dated February 18, 1981, in which you requested confirmation that the implementation dates for upgrading emergency support facilities, indicated in Enclosure 1 to your letter, would be met.
This letter is provided to submit the requested commitment or alternate schedule.
This letter has been dela-yed as discussed in our letter to you, dated April 8, 1981, and further as a result of continued efforts in site selection and preliminary engineering of the Emergency Operations Facility (EOF) for San Onofre Units 1, 2 and 3.
The clarification statement enclosed with your letter identifies October 1, 1982, as the required operational date for the upgraded emergency response facilities and June 1, 1981, for submittal of facility conceptual design descriptions.
Information in response to your letter is provided in the following paragraphs.
Staffing Levels for Emergency Situations to your February 18, 1981 letter, references Task Action Item I.A.1.3 as establishing the implementation schedule for licensed operators and shift technical advisors on shift. also establishes September 1, 1981 as the required implementation schedule for other staffing requirements identified in Table III.A.1.2-1 (Table B-1 to NUREG-0654, Rev.
- 1) and July 1, 1982 as the deadline for removal of any deficiencies.
The above noted shift manning requirements can be met in all cases with operators meeting the requirements on July 1, 1982.
This compliance is predicated on using the Health Physics Technician and Nuclear Chemical Technician to meet the 2.HP Technician requirement for Protective Actions (in-plant).
8107130280 810701 A
PDR ADOCK 05000206 V
PDR P
Mr. Darrell G. Eisenhut, Director July 1, 1981 We must take exception to the 30-minute augmentation manning.
A 30-minute response from most people working at San Onofre cannot reasonably be achieved due to their physical living location. Personnel could be called, proceed to the plant and arrive within 30-minutes; however, we cannot assure that all will, in fact, arrive in 30-minutes. We intend to initiate call outs immediately and expect that some personnel will arrive within 30 minutes and all required personnel would be present in 60-minutes.
Emergency Response Facilities (ERFs) - Conceptual Design to your letter establishes that the upgraded ERFs conceptual design shall be submitted by June 1, 1981. Conceptual design information for the ERFs is hereby submitted as follows:
0 Onsite Operations Support Center, Unit 1 (OOSC-1)
The Onsite Operations Support Center is located in the Control and Administration Building Conference Room and provides protection of personnel under postulated accident conditions with no airborne releases.
The OOSC-1 has communication capability with the control room and will also have access to the station documents and records available to the onsite technical support center.
o Onsite Operational Support Center, Units 2&3 (OOSC-2&3)
An Onsite Operational Support Center has been established in the lunch room of the administration, warehouse, and shop (AWS) building at San Onofre. The OOSC 2&3 will serve as a "holding area" outside of the control rooms for shift support personnel (other than those in the control rooms) to report and to receive assignments.
The OOSC 2&3 has communication capability with the control room and will also have access to the station documents and records available to the onsite technical support center. This facility is being established with due consideration given to the functional criteria stated in NUREG-0696. In addition, the San Onofre Emergency Plan has been revised to reflect existence and function of the center.
o Technical Support Center, Unit 1 (TSC-1)
The general design criteria for the San Onofre Unit 1 Technical Support Center (TSC-1) was previously transmitted to the Commission in letters dated October 17, 1979 (Mr. J. H. Drake to Mr. D. G. Eisenhut),
January 17, 1980 (Mr. K. P. Baskin to Mr. D. G. Eisenhut), and March 25, 1980 (Mr. J. G. Haynes to Mr. U. G. Eisenhut). In summary, the conceptual designs associated with the installation of data acquisition systems in the onsite TSC will consider, as a minimum, the following:
1.,
The system will interface with the existing critical station parameters with some being displayed in the Onsite Technical Support Center by means of a CRT and printer.
Mr. Darrell G. Eisenhut, Director
-3 July 1, 1981
- 2. The system will be actuated automatically in the event of an accident or manually for acquisition of desired data for the evaluation of station status.
- 3. The critical station parameters to be monitored will be consistent with those recommended by the Westinghouse Owner's Group.
The conceptual design for the TSC-1 computer is described in Enclosure A to this letter.
o Technical Support Center, Units 2&3 (TSC-2&3)
The design criteria and data displayed for San Onofre, Units 2 and 3 Technical Support Center (TSC-2&3) are described in SCE's response to NUREG-0737, Item III.A.1.2, transmitted to the Commission in a letter dated February 2, 1981, from K. P. Baskin to Mr. F. Miraglia. The pertinent portion of this response is provided in Enclosure B to this letter.
A data system for SONGS 2&3 that will meet all of the data system requirements for NUREG-0696 is presently under evaluation. It is expected that the existing Critical Function Monitoring System (CFMS) will comprise an integral part of this instrumentation. The conceptual design for this data system will be forthcoming by August, 1981.
o Emergency Operations Facility, Units 1, 2 and 3 (EOF)
The conceptual design for the Emergency Operations Facility (EOF) is described in Enclosure C to this letter.
Emergency Response Facilities (ERFs) - Operational Date o
OOSC-1 The OOSC for Unit 1 is operational at present.
o OOSC-2&3 The OOSC for Units 2&3 will be operational by fuel load.
o TSC-1 The TSC for Unit 1 will be operational by October 1, 1982.
o TSC-2&3 The TSC for Units 2&3 as described in Enclosure B will be operational by fuel load.
Data systems to meet NUREG-0696 criteria are expected to be partially operational by October 1, 1982 and fully operational by mid-1983.
Mr. Darrell G. Eisenhut, Director July 1, 1981 o
EOF The EOF for San Onofre is expected to be operational by October 1, 1982.
Please let me know if you have any questions or need additional information.
Very truly yours,
