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 March 19 1981 TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Fire Protection Program Review San Onofre Nuclear Generating Station Unit 1 The new Fire Protection regulations, 10 CFR 50.48, which became effective on February 17, 1981, require that information regarding our plans and schedules for complying with these regulations be submitted by March 19, 1981.
The purpose of this letter is to provide the required information.
Paragraph (c)(5) of 10 CFR 50.48 requires Licensees to "submit plans and schedules for meeting the provisions of paragraphs (c)(2), (c)(3), and (c)(4) within 30 days after the effective date of this section and Appendix R to this part."
In accordance with Supplement No. 1 to the Fire Protection Safety Evaluation Report (FPSER) for San Onofre Unit'1 which was received by NRC letter dated February 4, 1981, the following items are to be implemented as indicated in paragraphs (c)(2), (c)(3), and (c)(4) of 10 CFR 50.48:
- 1.
Install Smoke Detectors in various locations per Section III.F of Appendix R to 10 CFR 50. This includes items 3.1.1(2), (3), (4),
(6), (9), (10) and (11) of Table 3.1 of the FPSER. The completion date for installation as specified in 10 CFR 50.48(c), is November 17, 1981 for modifications not requiring a plant outage and for modifications requiring plant outage, the installation is required to be completed on the following schedule commencing after August 16, 1981; a 60 day planned outage, a 120 day unplanned outage, or the next refueling outage.
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D.
March 19, 1981
- 2.
Install Emergency Lighting in various locations per Section III.J of Appendix R to 10 CFR 50. This includes item 3.1.17 of Table 3.1 of the FPSER. The completion date for installation, as specified in 10 CFR 50.48(c), is November 17, 1981 for modifications not requiring a plant outage. For modifications requiring a plant outage, the installation is required to be completed on the following schedule commencing after August 16, 1981; a 60 day planned outage, a 120 day unplanned outage, or the next refueling outage.
- 3.
Install a Reactor Coolant Pump Lube Oil Collection System per Section III.0 of Appendix R to 10 CFR 50. This includes item 3.1.15(5) of Table 3.1 of the FPSER. The completion date for installation, as specified in 10 CFR 50.48(c), is on the following schedule commencing after August 16, 1981; a 60 day planned outage, a 120 day unplanned outage, or the next refueling outage.
- 4. Provide a Safe Shutdown capability per Section III.G of Appendix R to 10 CFR 50.
This includes item 3.1.11(e) of Table 3.1, and items 1, 4, and 5 of Table 3.2 of the FPSER. The completion date for installation, as specified in 10 CFR 50.48(c), is 30 months after NRC approval for Dedicated Shutdown modifications, 6 months after NRC approval for Alternate Shutdown modifications not requiring a plant outage.
For Alternate Shutdown modifications requiring a plant outage, the instalation is required to be completed on the following schedule commencing 6 months after NRC approval; a 60 day planned outage, a 120 day unplanned outage, or the next refueling outage.
Items 1, 2, and 3 above have been reviewed, and based on conceptual engineering performed to date, it appears probable that each of the items can be completed on the required schedules. Accordingly, design and engineering activities associated with these items have been initiated. As these activities progress, we will be in a better position to assess our ability to complete the items as required based on detailed quantities, procurement lead times and construction unit rates. In addition, unforeseen schedular problems such as the need to reallocate resources (i.e., manpower), strikes, accessibility constraints, etc., may also impact our ability to complete these items as required. If we determine that items 1, 2 and 3 above cannot be completed as required, we will request an exemption from the schedular requirements for these items at that time.
Item 4 above has also been reviewed. An extensive effort has been completed to determine the impact of the requirements in this area. Based on conceptual engineering, we have determined that extensive modifications are necessary to comply with the requirements of Sections III.G of Appendix R. In addition, revised operating procedures will be required to address the use of redundant equipment to achieve safe shutdown following a fire in a specified area.
D.
March 19, 1981 The modifications required include the addition of a new building to house new equipment, redundant 4 kV switchgear, a 480V/208V-120V transformer, a charging pump, an auxiliary feedwater train, approximately 12 motor operated valves and an instrument air compressor and receiver. In addition, approximately 10 motor operated valves and five instruments will need to be relocated. There will be approximately 580 circuits which will require relocation and approximately 300 circuits/raceways to be added to supply the redundant equipment described above.
Numerous isolation devices will be required for associated circuits not yet identified.
In addition, fire barriers will be required between some redundant equipment. The remote shutdown panel will need to be modified to add hot shutdown equipment and the required cold shutdown equipment controls and instrumentation. In order to meet the requirement to assume loss of offsite power, a tie-in to one of the existing emergency diesel generators will be necessary to provide an onsite power source to the new switchgear described above.
Although many of the modifications identified above are associated with alternate shutdown capability (existing equipment), such as the great number of circuit reroutings which would be required, the safe shutdown capability as defined in Appendix R would not be available until the dedicated shutdown capability (new equipment) has been installed. This means that the safe shutdown capability is not required to be in place until 30 months after NRC approval of the proposed modifications.
A schedule based on 30 months for implementation of the safe shutdown capability (following NRC approval) is not incompatible with a schedule which would result from the implementation of similar modifications upon completion of the Systematic Evaluation Program (SEP) Integrated Assessment. Based upon existing NRC schedules, it is estimated that the SEP review will be complete and a Safety Evaluation Report issued in April, 1982.
If the requirements of Appendix R were applied to the plant configuration resulting from potential modifications identified in the SEP review, we have determined that the extensive nature of the Fire Protection modifications described above could be reduced or integrated into potential modifications which result from the SEP Integrated Assessment. This determination is based on the fact that review topics included as part of SEP involve electrical and physical separation of safe shutdown components, electrical and physical separation of power sources required to operate safe shutdown equipment, and seismic qualification of structures and components required for safe shutdown.
Based on a value-impact assessment, the commitment to proceed with the extensive modifications to comply with the safe shutdown capability of Appendix R on the schedule required by 10 CFR 50.48(c) cannot be justified for San Onofre Unit 1. It has been estimated that the cost of implementing these modifications is approximately $40,000,000 without including differential fuel costs associated with replacement power during outage times. In addition, the schedule for completion of the SEP Integrated Assessment and that specified in 10 CFR 50.48(c) for safe shutdown capability, will coincide in approximately one year. The expenditure of the significant resources associated with
D.
March 19, 1981 complying with the safe shutdown capability of Appendix R at the present time is justified only if compliance significantly improves the protection of the health and safety of the public. The increase in the protection of the health and safety of the public provided by the safe shutdown modifications described above is not commensurate with the expenditure of resources required for implementation of these modifications. Adequate protection, in the interim (approximately one year), is provided as discussed below.
As indicated in Table 3.1 of the FPSER Supplement No. 1, a large number of fire protection modifications have already been implemented. In accordance with NRC guidance and previously approved schedules, we are proceeding with additional Fire Protection modifications. In addition, as indicated in the original FPSER dated July 19, 1979, several measures have already been taken to provide alternate shutdown capability in the interim by the installation of an additional source of offsite power, modifications to the station air system, provisions for isolation capability of affected control systems, and development of station procedures.
Based on the information presented above, Southern California Edison Company, in the near future, will be formally requesting an exemption under 10 CFR 50.12(a) from the schedular requirements of 10 CFR 50.48(c) for the modifications required by Section III.G of Appendix R to 10 CFR 50.
Pending resolution of this exemption application, compliance with Section III.G of Appendix R to 10 CFR 50 will be evaluated as part of the fire protection of the safe shutdown capability resulting from modifications associated with SEP.
If you have any questions or desire additional information, please contact me.
Very truly yours, Enclosure