Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: 05000206/LER-1978-003-01, /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired, ML13308A644, ML13308A646, ML13317A193, ML13317A236, ML13317A408, ML13317A411, ML13317A726, ML13317A797, ML13322A549, ML13326A530, ML13326A551, ML13326A553, ML13330A121, ML13330A157, ML13330A207, ML13330A251, ML13330A253, ML13333A308, ML13333A315, ML13333A322, ML13333A323, ML13333A326, ML13333A338, ML13333A348, ML13333A367, ML13333A406, ML13333A423, ML13333A476, ML13333A524, ML13333A762, ML14100A289, ML14119A353, ML19282B877, ML19318H957, ML19318H978, ML19318H981, ML19340D243, ML20136H076
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MONTHYEAR05000206/LER-1978-003-01, /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired1978-03-28028 March 1978 /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired Project stage: Other ML19318H9571978-05-19019 May 1978 Submits Results of Review of Fire Protection Program for Conformance W/Nrc Guidelines, Nuclear Plant Fire Protection Functional Responsibilities, Admin Controls & QA, Per 770819 Request Project stage: Other ML19318H9781978-07-0303 July 1978 Discusses V Stello Forwarding Manpower Requirements for Operating Reactors. Util Still Maintains That Min Fire Brigade of Three Persons Sufficient.Basis for Position Included in Util Project stage: Other ML19318H9811978-07-0808 July 1978 Forwards Suppl 1 to Fire Protection Program Review..., Providing Addl Info Requested in Encl 1 to NRC & Responses to NRC Positions Identified in Same Ltr Project stage: Other ML13309A5711978-10-18018 October 1978 Forwards Amend 12 to Fsar. Amend Contains Responses to NRC 780726 & 0818 Questions & Includes Corrections & Additions to FSAR Info Project stage: Request ML13333A3081978-10-18018 October 1978 Forwards Info Re Mod to 4,160-volt Switchgear Room for Fire Zone 8 & Mod to Lube Oil Reservoir & Conditioner Area in Fire Zone 9A as Part of Fire Protection Program Project stage: Other ML13333A3141978-10-30030 October 1978 Repts Insertion of Containment Spray Sys Nozzle Insp Requirement in Section 4.2 of Tech Specs, Safety Injection & Containment Spray Sys Periodic Testing Project stage: Request ML13333A3151978-10-30030 October 1978 Advises That Casualty Procedure Re Air Supply for Lube Oil Reservoir & Conditioner Area & Station walk-through Will Be Performed in Response to NRC 781018 Request Re Fire Protection Project stage: Other IR 05000361/19780161978-11-17017 November 1978 IE Inspec Rept 50-361/78-16 on 781030-1103 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Incl:Reactor Internals & Miscellaneous Open Items from Previous Inspecs Project stage: Request ML13333A3221978-11-22022 November 1978 Submits Proposed Mods to Air Supply Sys of Subj Facil.Mods Will Ensure Availability of Air Supply to Req Equip After Loss of Main Air Header Due to Fire in Lube Oil Reservoir & Conditioner Area Project stage: Other ML13333A3231978-11-28028 November 1978 States Util Is Unable to Submit Response to Fire Protec Review Questions by 781127.Will Submit by 781201 Project stage: Other ML13333A3261978-12-0101 December 1978 Responds to NRC Staff Positions Forwarded in 781117 NRC Ltr Re Fire Protec Prog Review.Staff Positions Responded to incl:PF-27A,Cable Spreading Area & PF-51,Containment Project stage: Other ML13333A3381979-01-15015 January 1979 Forwards Conceptual Plan for Safe Unit Shutdown Following Fire in 4160v Switchgear Room or Lube Oil Reserve Area.Also Forwards Related Plant Mod Plan & Implementation Schedule Project stage: Other ML19282B8771979-01-31031 January 1979 Fire Protection in Operating Nuclear Power Stations Project stage: Other ML13326A5301979-01-31031 January 1979 Suggests Mods to Fire Protection Plan,Re Electrical Valve Supervision & Portable Smoke Venting Equipment Project stage: Other IR 05000361/19790011979-01-31031 January 1979 IE Insp Repts 50-361/79-01 & 50-362/79-01 on 790108-11. Noncompliance Noted:Discrepancies Noted in Governing Record Used as Calibr Control Project stage: Request ML13333A3481979-03-0101 March 1979 Requests Extension to 790330 in Which to Submit Evaluation, Originally Due 790215,re Effects of Fire in H-seal Unit on Structured Steel of Turbine Bldg Project stage: Other ML13322A5491979-04-13013 April 1979 Requests Licensee Provide Design Mods Which Will Assure Safe Shutdown Can Be Achieved & Maintained Using Onsite Power Source Project stage: Other ML13333A3671979-05-15015 May 1979 Updates Status of Commitments Re Operating Functions & Plant Mods of Fire Protection Program.Discusses Safe Shutdown Casualty Procedure,Spurious Valve Actuation & Hydrogen Seal Oil Area Fire Project stage: Other ML13326A5511979-07-19019 July 1979 Amend 44 to License DPR-13,incorporating Tech Spec Changes Re Fire Protection Sys Operability & Surveillance & Fire Protection Program Responsibility Project stage: Other ML13326A5531979-07-19019 July 1979 Notice of Issuance & Availability of Amend 44 to License DPR-13 Project stage: Other ML13326A5491979-07-19019 July 1979 Forwards Amend 44 to License DPR-13,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML13326A5521979-07-19019 July 1979 Safety Evaluation Supporting Amend 44 to License DPR-13 Project stage: Approval ML13333A4061979-08-10010 August 1979 Urges Util to Improve Schedules for Completion of Fire Protection Mods Prior to Oct 1980.Requests That Any Outstanding Info Re Open Items & Required Design Details Be Submitted on Expedited Basis Project stage: Other ML13333A4131979-08-27027 August 1979 Forwards 790413 Request for Addl Info Re Safe Shutdown of Facility Project stage: RAI ML14100A2891979-09-14014 September 1979 NRC Position on Safe Shutdown Capability Project stage: Other ML13333A4181979-09-14014 September 1979 Forwards NRC Position on Safe Shutdown Capability,To Help Licensee Prepare Response to Safety Evaluation for Fire Protection.Requests Schedule for Submittal of Revised Safe Shutdown Plan within 30 Days Project stage: Approval ML13333A4231979-10-23023 October 1979 Forwards Addl Design Info Re Fire Protection Program Review in Response to NRC .Revised Plan for Safe Shutdown Following Fire Deferred Pending Completion of Integrated Assessment of SEP Mods Project stage: Other ML13333A4591979-12-26026 December 1979 Forwards Rept Re Analysis Methods to Determine That Fire in Hydrogen Seal Oil Unit Would Not Substantially Impact Structural Integrity of Steel in South End of Turbine Bldg Project stage: Request ML13333A4761980-01-23023 January 1980 Forwards Addl Design Info & Drawings Re Fire Protection Mods to Be Implemented During Next Refueling Outage.Drawings Available in Central Files Only Project stage: Other ML13311B0361980-01-23023 January 1980 Requests Denial of Petitions Under 10CFR2.206.Petitions Fail to Particularize Factual Basis for Conclusions,Fail to Raise Unreviewed Health or Safety Issues & Fail to Seek Proper Reconsideration of Resolved Issues Project stage: Request ML13333A5241980-03-0606 March 1980 Informs NRC That in Situ Testing of Fire Detection Sys Will Be Deferred Until Acceptable Method Is Developed to Ensure That Station Will Not Be Adversely Affected.Util Will Proceed W/Inplace Sensitivity & Loop Voltage Tests Project stage: Other IR 05000206/19800091980-04-16016 April 1980 IE Insp Rept 50-206/80-09 on 800301-0404.Noncompliance Noted:Failure to Follow Emergency Procedure & Operation Outside Limiting Condition for Operation Project stage: Request ML13308A6441980-04-16016 April 1980 Forwards Revision to BNL Re Items 3.1.1(5),3.1.2 (b),3.1.5(d),3.1.6,3.1.7(a),3.1.7(b),3.1.15(b) & 3.2.3. for Fire Protection Review Project stage: Other ML13308A6461980-05-13013 May 1980 Forwards Fire Protection Review Responding to Items 3,7 & 10 & Licensee .Automatic Power Backup Should Be Supplied for Fire Alarm Sys Project stage: Other ML13330A1211980-09-26026 September 1980 Forwards Response to Comments & Recommendations Re BNL Review of Fire Protection Program.Response Includes New Design Change Commitments.Oversize Drawings,Hydraulic Design Info & Calculation Sheets Available in Central Files Project stage: Other IR 05000206/19800251980-09-26026 September 1980 IE Insp Rept 50-206/80-25 on 800811-29.No Noncompliance Noted.Major Areas Inspected:Plant Operations During long-term Outage,Monthly Maint & Surveillance Observations & Review of LERs Project stage: Request ML13330A1571980-11-0606 November 1980 Informs of Recently Approved Revised 10CFR50.48 Containing Schedules for Completion of All Fire Protection Mods.No Present Implementation Required as Necessary Addl Info Has Not Yet Been Approved Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility Encl Project stage: Other ML13302A8701980-11-24024 November 1980 Summary of 801020 Meeting W/Fema in Los Angeles,Ca Re Emergency Planning Project stage: Request ML20136H0761981-02-0404 February 1981 Marked-up Sser 1 Supporting Fire Protection Project stage: Other ML13302A1651981-02-0404 February 1981 LOCA, Emergency Operating Instruction Project stage: Request ML13330A2191981-02-0404 February 1981 Forwards Suppl 1 to 790719 Fire Protection Safety Evaluation Rept.Items Reviewed:Control Room Fire Detection Sys,Smoke Detectors in Lube Oil Area,Fire Pump Test Features & Turbine Bldg Structure Project stage: Approval ML13330A2071981-02-10010 February 1981 Requests Extension to 811117 for Completion of Fire Protection Features Re Water Suppression Sys,Fire Barriers, Fire Dampers,Fire Barrier Penetrations & Water Damage Protection Project stage: Other ML13330A2531981-02-13013 February 1981 Notice of Extension of Completion Dates of Fire Protection Mods from 800719 to 811117 Project stage: Other ML13330A2511981-02-13013 February 1981 Forwards Fr Notice Re Extension of Time for Completion of Fire Protection Mods from 800719 to 811117.Description of Mods Encl Project stage: Other ML14119A3531981-03-19019 March 1981 Provides Info Required by New Fire Protection Regulations 10CFR50.48.Installation of Smoke Detectors,Emergency Lighting,Reactor Coolant Pump Lube Oil Collection Sys & Provision of Safe Shutdown Capability Discussed Project stage: Other ML13330A9081981-11-0404 November 1981 Application for Exemption from Deadline to Install Certain Fire Safety Measures Project stage: Request ML13330A9121981-11-0404 November 1981 Affidavit Re Support of Application for Exemption from Deadline to Submit Fire Safety Plans & Schedules.Proof of Svc by Mail Encl Project stage: Request ML13330A9101981-11-0505 November 1981 Affidavit Re Support of Application for Exemption from Deadline to Install Certain Fire Safety Measures.Proof of Svc by Mail Encl Project stage: Request 1979-05-15
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Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN January 15, 1979 TELEPHONE MANAGER.
GENERATION ENGINEERING 213-572-1401 Director, Office of Nuclear Reactor Regulation Attention:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Provisional Operating License No. DPR-13 Fire Protection Program Review San Onofre Nuclear Generating Station Unit 1 In accordance with the commitment made in our letter dated October 18, 1978, this letter forwards as Enclosure 1, a conceptual plan for providing the capability to establish a safe shutdown of San Onofre Unit 1 following a fire in the 4160 volt switchgear room or the lube oil reservoir area,which is not dependent on the Chemical and Volume Control System test pump.
The study was based on the criteria which was received from the NRC staff during the site visit (and containment inspection) of October 19, 1978, and which was included as Enclosure 2 to our letter dated December 1, 1978. Also, included as Enclosure 2 is a conceptual implementation schedule for the plant modifi cations associated with the conceptual plan.
The proposed plan of Enclosure 1 meets all the criteria of Enclosure 2 of our December 1, 1978 letter with the exception that the proposed means of shutdown utilizes either one of two separate and independent sources of offsite power regardless of fire related damage in the 4160 volt switchgear room rather than utilizing either onsite or offsite power.
It is our understanding that the basis for requesting the utilization of either onsite or offsite power is the concern that a fire in the fire zones of concern could affect the availability of offsite power. A review of the proposed alternate source of offsite power, as described in Enclosure 1, confirmed that its availa bility would be unaffected by a forced outage of San Onofre Unit 1 such as an outage due to a fire.
It has also been determined that the alternate source of offsite power can be made electrically independent and physically separate from the existing offsite power source except for their intertie to the San Diego 7901 230213
(
-2 Gas & Electric Company's 138 kV system. Dependence on the San Diego Gas & Electric Company's 138 kV system is considered acceptable inasmuch as the guidance provided in Appendix A to Branch Technical Position APCSB 9.5-1, "Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976," indicates that postulated fires or fire protection failures need not be con sidered concurrent with other plant accidents or the most severe natural phenomena (e.g., events leading to a loss of offsite power).
In view of the facts that:
(1) the 4160 volt switchgear room and lube oil reservoir area are being provided with the fire detection and suppression systems as described in our letter dated October 18, 1978 and these systems are designed to limit fire damage in those areas such that plant shutdown can be accomplished using either of the existing onsite or offsite power sources and (2) we are now proposing the addition of an electrically independent and physically separate alternate source of offsite power for plant shutdown presuming the loss of the existing power sources due to fire in the 4160 volt switchgear room or lube oil reservoir area, we conclude that there is adequate assurance that San Onofre Unit 1 can be safely shutdown following fire related damage as is required to be postulated by the NRC Regulatory Staff.
As has been suggested by the NRC Staff position included as Enclosure 2 to our December 1, 1978 letter, the conceptual plan described in Enclosure 1 could be significantly impacted by the review of selected topics in the course of the Systematic Evaluation Program (SEP).
For that reason, we do not propose to proceed with the detailed engineering of the conceptual plan described in Enclosure 1 until such time as:
(1) the Regulatory Staff concurs with the conceptual plan and (2) related SEP topics are assessed by the Regulatory Staff and the integrated assessment of any necessary backfit modifications has begun.
A conceptual implementation schedule following (1) and (2) above is provided as Enclosure 2. Detailed engineering and material procurement quotations will necessarily have an effect on any final implementation schedule. Pending implementation of the conceptual plan, interim modifications as described in our letters dated October 18, 1978, and November 22, 1978 provide adequate assurance that San Onofre Unit 1 can be safely shutdown in the event of a fire in the 4160 volt switchgear room or the lube oil reservoir area.
If you have any questions or desire further information please contact me.
Very truly yours, Enclosures CONCEPTUAL PLAN FOR SAFE SHUTDOWN.
In response to the recent NRC position regarding safe shutdown without reliance on the CVCS test pump following a fire in the 4160V switchgear room or the lube oil reservoir area (fire zone 9A), the following conceptual design changes have beeh developed for San Onofre Nuclear Generating Station Unit 1.
Alternate 4160V power will be provided for a charging pump using the San Onofre Units 2 and 3 12 kV construction power line from San Diego Gas & Electric's Japanese Mesa Substation as an independent offsite power source feeding a 4160V transformer. The line would also feed a 480V transformer to power the 480V switchgear No. 2 bus (see attached drawing).
The charging pump would normally be fed from 4 kV bus 2C; in case of fire in the 4160V room or adjacent fire zone 9A, a transfer will be made to the 12 kV alternate offsite power source provided from the SDG&E system, which is independent of the San Onofre Unit 1.switchyard. The transfer will be effected by operating a two position selector switch.
The alternate offsite source will be electrically independent and physically separate from the San Onofre Unit 1 switchyard except for their intertie to the SDG&E power distribution system. There are no direct connections between the San Onofre Unit 1 switchyard and SDG&E's Japanese Mesa Substation. SDG&E's Japanese Mesa Substation is supplied by two independent 138 kV sources from the SDG&E power distribution system.
If, as a result of a fire, the San Onofre Unit 1 generation supply to the SDG&E power distribution system is lost, the system will remain functional since that power source amounts to less than 10% of the total generating capacity and the system's load follow capability can accom modate the change in demand placed upon it.
A fire will therefore not affect the alternate source of offsite power due to the loss of San Onofre Unit 1 generation to the SDG&E power distribution system.
The possibility that a line fault created by a fire in the fire zones of concern would backfeed to the San Onofre Unit 1 switchyard, which supplies a normal source of offsite power to the station, has also been investigated. A fault in the line which connects the 4160V switchgear in the 4160V switchgear room through auxiliary transformer C to the switchyard, will be interrupted by the line breakers in the switchyard.
In the highly unlikely event that the breakers do not perform their isolation function, the fault will be
-2 interrupted by the Local Breaker Failure Backup Protection System, which is not interconnected to any electrical system at San Onofre Unit 1, so it will not be affected by a fire in the fire zones of concern.
Therefore, a line fault created by a fire will not impact the SDG&E power distribution system and.the availability of the alternate source of offsite power is unaffected.
In view of the independence of the 12 kV power source from San Onofre Unit 1 power generation and fault propagation, it is concluded that the alternate source of offsite power is electrically independent of the normal cffsite source.
The electrical independence and physical senaktLon of the normal and alternate sources o-ofrsite cower result in the conclusion that a fire will not impact tle availability of offsite power to othe station.
In order to provide adequate controls for hot and cold shutdown, it is proposed that a centralized control location be constructed near the auxiliary control panel for remote manual operation of essential equipment.
The control panel will incorporate controls for test pump G-42, charging pump C-8B and controls for the essential valves necessary to ensure correct valve alignment for CVCS flow injection to the reactor coolant system. The panel will also incorporate local instruments to indicate VCT level and seal injection flow for each RCP.
To avoid possible spurious actuation of necessary equipment, essential power and control cables will be rerouted from the 4160V room and area 9A fire zones.
In addition, control switches will be provided in the control room-to-control normally open power disconnect switches for MOV356, MOV357 and MOV358 on the charging lines to ensure that these valves will not spuriously actuate and divert the charging flow from the reactor coolant pump seal injection paths.
To ensure that an adequate water supply is available for the auxiliary feedwater pump with minimum operator action, a permanent piping connection will be installed between the service water system and the condensate storage tank.
This connection would be locally controlled with a normally closed manual valve.
Since the compressed air system instrument air header passes
.- through fire zone 9A, the northern portion of the header and its associated lines will be relocated outside of the fire zone to eliminate the possibility of fire damage to the system. The instrument air system will be provided with compressed air from the existing diesel driven portable air compressor.
-3 The above described conceptual design changes will provide assurance that, in the event of a fire in the 4160V room or fire zone 9A, it will be possible to bring the plant to a safe shutdown condition without relying on the CVCS test pump.
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ITLEMENTATION SCHEDULE The following tentative schedule is based on only conceptual designs and may alter after preliminary detailed design engineering is completed.
Engineering & Design Procuremert D'Construction 0
8 52 86 104 Time (weeks)