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, 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
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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
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 April 21, 1983 Director, Office of Nuclear Reactor Regulation Attention:
Mr. D. G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Supplement 1 to NUREG-0737 Requirements for Emergency Response Capability San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter, D. G. Eisenhut, NRC, to All Licensees of Operating Reactors, Supplement 1 to NUREG-0737 - Requirements for Emergency Response Capability (Generic Letter No. 82-33),
December 17, 1982
- 2. Letter, K. P. Baskin, SCE to D. G. Eisenhut, NRC, Requirements for Emergency Response Capability and Inadequate Core Cooling Instrumentation System, February 10, 1983 Reference 1 provided us with Supplement 1 to NUREG-0737 to which we responded with Reference 2. Discussions with members of your staff have indicated a desire to be informed of the current level of compliance with Supplement 1 at San Onofre Unit 1. Responsive to that desire we have prepared the enclosed document "Current Status of Emergency Response Capability Implementation, San Onofre Nuclear Generating Station, Unit 1, April 15, 1983."
This should provide an adequate assessment of the current situation at San Onofre Unit 1. For those items for which no action has yet been initiated we will not begin work until resolution of the startup issue as described in Reference 2.
.8304250096 830421 PDR ADOCK 05000206
_F
- PDR'
Mr. D.
April 21, 1983 If you have any questions or desire additional information regarding the implementation status of the Supplement 1 initiatives at San Onofre Unit 1, please let me know.
Subscribed on this p day of
, 1983.
Respectfully submitted, SOUTHERN CALIFORNIA EDISON COMPANY By:
Krieger Supervising Engineer San Onofre Unit 1 Licensing Subscribed and sworn t before me this
,f/
day yof f
Notary ublic in and for the County of Los A geles, State of California My Commission Expires:
4
'f f OFFICIAL SEAL AGNES CRABTREE NOTARY PUBLIC -
CALIFORNIA PRINCIPAL OFFICE IN LOS ANGELES COUNTY My Commission Expires Aug. 27, 1986
CURRENT STATUS OF EMERGENCY RESPONSE CAPABILITY IMPLEMENTATION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 APRIL 15, 1983
INTRODUCTION The NRC provided Supplement 1 to NUREG-0737 as an attachment to a letter from D. G. Eisenhut to All Licensees of Operating Reactors, dated December 17, 1982.
Supplement 1 defined the requirements for emergency response capability that, when implemented, would provide a consistent level of capability among all licensees. The NUREG's and Regulatory Guides that Supplement 1 references are intended to be utilized as "guidance" in meeting the initiatives of Supplement 1.
It is the purpose of this status report to provide a complete assessment of the current implementation level of the Supplement 1 initiatives at San Onofre Unit 1. The report is organized to correspond to the categories of Supplement 1 and a list of the references is provided as an Appendix.
CURRENT STATUS OF SUPPLEMENT 1 TO NUREG-0737 AT SAN ONOFRE UNIT 1
- 1. Safety Parameter Display System (SPDS) - Our letter of October 17, 1979 (Reference 1) contained our response to NUREG-0578 item 2.2.2.b, Onsite Technical Support Center,in which we stated that we would install a Technical Data Display and Transmit System in the Technical Support Center (TSC). Our letter of July 1, 1981 (Reference 2) provided the NRC with the design description of the above mentioned system and indicated that it contains the capability to transmit the data, via modems, to the offsite Emergency Operations Facility (EOF).
This data display and.
transmission system, currently installed, is not an SPDS and currently there are no plans to initiate any work on the SPDS initiative per Supplement 1 until resolution of the startup issue as described in Reference 3.
- 2.
Detailed Control Room Design Review - This requirement was initially set forth in NUREG-0737 as Item I.D.1.
However, the NRC deferred implementation until NUREG-0700, "Guidelines for Control Room Design Reviews" could be finalized. NUREG-0700 was published in September 1981.
Despite the issuance of NUREG-0700, the NRC had not yet taken action to require licensees to perform a control room design review until the issuance of Supplement 1. There are no plans to perform a control room design review for San Onofre Unit 1 until resolution of the startup issue as described in Reference 3.
- 3. Regulatory Guide 1.97 (Revision 2) - This Regulatory Guide was issued in December, 1980 and has been implemented at San Onofre Unit 1 only where appropriate as a design criteria in response to NUREG-0737 requirements.
The balance of the accident monitoring capabilities described in Regulatory Guide 1.97 have not been committed for San Onofre Unit 1.
Prior to the issuance of Supplement 1, we initiated a survey of our compliance to Regulatory Guide 1.97. This survey is under contract to Westinghouse and the current completion schedule for the survey is July 1, 1983.
No further action on Regulatory Guide 1.97 will be considered until resolution of the startup issue as described in.
Reference 3.
- 4. Upgrade Emergency Operating Procedures (EOP's) - This requirement was initiated by NUREG-0737, Item I.C.1.
Our previous position, as defined in our letter of August 6, 1981 (Reference 4), has been that the Westinghouse Owners Group had addressed this item adequately. In response to an NRC request for upgrades to particular EOP's for San Onofre Unit 1, we provided, by letter dated September 13, 1982 (Reference 5), the final versions of the requested procedures.
-2 Since that date we have initiated the long-term procedure upgrade effort, scheduled to be completed in June, 1983. During a meeting in Bethesda, Maryland, on October 7, 1982, we informed the NRC of our final implementation schedule for the completion of the training and implementation for the EOP upgrade effort. This schedule was updated to the Fall, 1983 by letter dated February 16, 1983 (Reference 6).
The required procedures generation package had been planned to be submitted by April 1, 1983, but final review constraints have pushed the schedule to July 1, 1983.
- 5. Emergency Response Facilities - The Emergency Response Facilities consist of the TSC, OSC, and EOF as detailed below:
- a. Technical Support Center (TSC) - The requirements for the TSC were initiated by item 2.2.2.b of NUREG-0578, and later revised in NUREG-0737 and NUREG-0696.
We committed to the implementation of an onsite technical support center in our letter of October 17, 1979 (Reference 1).
We updated this commitment in our letter of January 17, 1980 (Reference 6), which provided the NRC with details of what technical data would be available in the TSC via the technical data display system. We informed the NRC in our letter of July 1, 1981 (Reference 2) that the TSC would be completed by October 1, 1982.
The TSC, as a facility, meets the requirements of Supplement 1 with the exception of the HVAC system which is to be upgraded on the schedule in your Order Confirming Commitments dated March 14, 1983.
The technical data display and acquisition capability, as installed, meets the committments in Reference 2, but it does not meet the guidance in NUREG-0696. Currently there are no plans to upgrade this system as previously discussed in item 1.
- b. Operational Support Center (OSC) - The requirements for the OSC were initiated by item 2.2.2.c of NUREG-0578 and later revised in NUREG-0737 and NUREG-0696. We committed to implementing an OSC in our letter of October 17, 1979 (Reference 1) and informed the NRC that our OSC was operational in our letter of July 1, 1981 (Reference 2).
The OSC meets the criteria of Supplement 1.
- c. Emergency Operations Facility (EOF) - The requirements for the EOF were initiated by NUREG-0660 and later revised by NRC letter dated February 18, 1981 (Reference 8).
The functional criteria for the EOF is contained in NUREG-0696. We informed the NRC in our letter dated July 1, 1981 (Reference 2), of our conceptual design and scheduled implementation date of October 1, 1982.
The EOF, as a facility, meets the criteria of Supplement 1, with the exception of the distance to the backup EOF previously discussed in Reference 9.
The technical data display and acquisition capability, as installed, meets what was committed to in Reference 2, but it does not meet the guidance in NUREG-0696. Currently there are no plans to consider upgrade to this system as previously discussed in item 1.
LAB:7870
APPENDIX REFERENCES
- 1. Letter, J. H. Drake, SCE, to D. G. Eisenhut, NRC, Responses to NRC Requirements Related to the Three Mile Island Accident, October 17, 1979
- 2. Letter, K. P. Baskin, SCE, to D. G. Eisenhut, NRC, San Onofre Nuclear Generating Station, Units 1, 2, and 3, July 1, 1981
- 3. Letter, K. P. Baskin, SCE, to D. G. Eisenhut, NRC, Requirements for Emergency Response Capability and Inadequate Core Cooling Instrumentation System, February 10, 1983
- 4.
Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, Response to Order Confirming Commitments for TMI Related Requirements, August 6, 1981
- 5.
Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, San Onofre Nuclear Generating Station, Unit 1, September 13, 1982
- 6.
Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, Post-TMI Requirements, February 16, 1983
- 7. Letter, K. P. Baskin, SCE, to D. G. Eisenhut, NRC, Additional Information in Support of Responses to NRC TMI Requirements, January 17, 1980.
- 8. Letter, D. G. Eisenhut, NRC, to All Licensees of Operating Plants, Post-TMI Requirements for the Emergency Operations Facility (Generic Letter 81-10), February 18, 1981.
- 9. Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, Emergency Response Facilities, December 7, 1982 7870
