Letter Sequence Approval |
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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
Eq,0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
58 TO LICENSE NO.
DPR-13 SOUTHERN.CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY SAN ONOFRE UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION AND BACKGROUND
1.1 Introduction By letter dated May 7, 1981, Southern California Edison Company.and San Diego Gas and Electric Company (the licensees) proposed changes to the San Onofre Nuclear Generating Station (SONGS) Unit No. 1, Technical Specifications and addition of Licensing Conditions.
This proposal superseeds a similar request proposed in a letter dated February 8, 1980. The staff has not completed its review of all the proposed changes submitted by this application but this Safety Evaluation documents the results of the reviews that have been com pleted. The amendment incorporates certain Three Mile Island (TMI)-2 Lessons Learned Category "A" requirements.
The licensee's request is in.
direct response to the NRC staff's letter dated July 2, 1980.
1.2 Background
By our letter dated September 13, 1979, we issued to all operating nuclear power plants requirements established as a result of our review 6f.the TMI-2 accident. Certain of these requirements, designated Lessons Learned Category "A" requirements, were to have been completed by the licensee prior to any operation subsequent to January 1, 1980.. Our evaluation of the licensee's compliance with these Category "A" items was attached to our letter-to SCECO dated May 2, 1980.
SONGS 1 was in.an extended maintenance outage from March, 1980 through May of 1981 and their submittal,reflects some of the modifications completed during this.period.
In order to provide reasonable assurance that operating reactor facilities are maintained within the limits determined acceptable following the implementation of the TMI-2 Lessons Learned Category "A" items, we requested that licensees amend their TS to incorporate additional Limiting Conditions for Operation and Surveillance Requirements, as appropriate. This request was transmitted to all 8111300185 811106 PDR ADOCK 05000206 PDR
licensees on<July 2, 1980.
Included therein were model specifications that we had determined to be acceptable.
Each of the issues identified by the NRC staff and the licaisee's response is discussed in the evaluation-below; except auxiliary feedwater automatic-initiation, which -will be resolved in a-separate-issuance.
2.0 EVALUATION 2.1.1 Emergency Power Supply Requirements The press'urizer water.level indicators, pressurizer relief and block valves, and pressurizer heaters are important in a post-accident situation. Adequate emergency power supplies add assurance of post accident functioning of these components. The facility's design has the requisite emergency power supplies. We find the TSs provide appropriate surveillance and actions in the event of component inoperability and are thus acceptable.
2.1.3.a Direct Valve Indication..
The licensee has installed stem mounted limit switches with CONAX con ductor seal module assemblies at each switch connector on the PORVs, their associated block valves and the safety valves.
Each limit switch has a position indicator in the control room. Alarms are provided-in
-the control room to indicate 'i'f either of the.PORVs or safety valves are open. The stem mounted limit switches are. powered from vital buses.
The licensee has submitted TSs that provide for 31-day channel check and 18-month.channel calibration requirements.
'These TSs are acceptable as they meet our July 2, 1980 model TS criteria.
2.1 3.b Instrumentation for-Inadequate Core Cooling.
The licensee has installed an instrument system to detect the effects of inadequate core cooling. This instrument system, a subcooling meter, receives and pro.cesses date from existing plant instrumentation.
The licensee has agreed-to TS with a monthly'channel check and a refueling interval channel calibration requirement and appropriate actions to be taken in the event of component inoperability.. We conclude the TS are acceptable as they provide adequate surveillance and meet our July 2, 1980 model TS criteria.
2'.1.4 Containment Isolation The licensee's June 25, 1979 and January 17, 1980 submittals identified the essential and non-essential systems and the bases for the essential system' classification.
The isolation control system was modified to provide diverse containment isolation signals.
Non-essential systems are isolated automatically.upon receipt of a safety injection sigal or a containment high pressure signal.
-3 Containment siolation system relay panels have been installed to multiply the containment isolation actuation signal for individual vslve control-.--- Each-valve cht6trol circuit consists of a latching relay control and override control in addition to.the valve position indication circuit. The latching control scheme prevents automatic reopening of the isolation valve on containment isolation actuation signal reset.
The licensee has made the additional isolation control modifications described in their March 25, 1980 submittal.
These modifications preclude.group reopening of the isolation valves., so that reopening is accomplished on a valve-by-valve or penetration basis. The surveillance requirements for the containment purge supply and exhaust valves is currently under review by the licensee and NRC staff. The instrumentation requirements for these valves is under active review in SEP. The submitted TS's are therefore acceptable until the reviews are complete.
2.1.5 Dedicated Penetrations for External Recombiners or Post-Accident External Purge System The NRC's position is that dedicated containment isolation systems should be used for the external recombiners or purge systems that meet redundancy and single failure requirements.
The licensee would utilize a purge system for post-accident hydrogen.
control.
Those systems that could be used are described in the licensees March 25, 1980 submittal.. The submittal also includes a single failure analysis of the system for the hydrogen control function, and the containment integrity function.
2.1.6.a Integrity of Systems Outside Containment Our request indicated that licensees should be required to periodically conduct a System Integiryt Measurements Program to prevent the release of significant.amounts of radioactivity to the environment via leakage from engineered safety systems and auxiliary, systems which are located outside reactor containment. The licensee's program includes provisional for a preventive-maintenance program and periodic visual :inspections.
The program also includes system leak test measurements at frequencies not to exceed refueling cycle intervals.
Based on our review we find that inclusion of this requirement.as a license condition satisfies our-requirement and is acceptable.
-A
-4 2.l.7b Auxiliary Feed Flow Indication Control grade auxiliary feediflow indication has been provided for each steam generator. Diverse backup indication is provided by steai generator level indicators in the control room. The power to the.
auxiliary feedwater flow indication is from a vital bus.
The accuracy of the auxiliary feed flow is within the requirement of +10%.
The licensee has submitted TSs with a monthly channel check and a refueling outage. calibration-requirement; thus the TSs are acceptable and they meet out July 2, 1980 model TS criteria.
2.T.8.c Iodine Monitoring We requested that the-licensees implement a program which will ensure the capability to determine the airborne iodine concentration in areas requiring personnel access under accident conditions. The licensee's program includes.training of personnel, procedures for monitoring and provisions for maintenance of sampling and analysis equipment.
Based on our review we find that-inclusion of this requirement as a, license condition satisfies our requirement and is acceptable.
2.2.1.b Shift Technical Advisor Our request indicated that the TS related to minimum shift manning should be revised to-reflect the augmentation of Shift Technical Advisor. The licensee'.s application would add one Shift Technical Advisor to each shift to perform the function of accident assessment during reactor operation. The individual performing this function will have at least a bachelor's degree or equivalent in-a scientific or engineering discipline with special training in plant design, and response and analysis of the plant for-transients and accidents.
Part of the Shift Technical Advisor duties are related to operating experience review function. Based on our review, we find the licensee's submittal satisfies our requirement and is, therefore, acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
We have determined that the amendment does not authorize a change in effluent types or total amounts not an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact.
and, pursuant to 10 CFR §51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance-of this amendment.
-5
4.0 CONCLUSION
We have concluded, based on the consideration discussed above, that:
(1) because the amendment doesnot involve. a significant7 ilthc'iase fin the pro bability or consequences of'accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation int he proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to. the common defense and security or to the health and safety of the public.
Date:
November 6, 1981
