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
[Table View] |
Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, June 30, 1982 (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 By letter dated May 10, 1982, you granted our request for an exemption from the schedule for submittal of information specified in 10 CFR 50.48(c).
The exemption deferred to July 1, 1982 the schedule for submittal of plans and schedules to achieve compliance with the Fire Protection Safe Shutdown requirements of Section III.G.2 of Appendix R to 10 CFR 50. A similar exemption was granted for submittal of design descriptions for alternative or dedicated shutdown systems, if applicable' to comply with the requirements of Section III.G.3 of Appendix R. If alternative or dedicated shutdown systems are employed, the information requested in the NRC Generic Letter 81-12 as clarified in your May 10, 1982 letter is to be provided for these systems. This letter supplies these plans, schedules and design descriptions. to this letter provides the results of our evaluation of the design of San Onofre Unit 1 regarding compliance with Section III.G.2 of Appendix R. Due to the original design of San Onofre Unit 1, a large number of areas were identified where the plant systems require modification.
Compliance with Section III.G.3 was examined for those areas not in compliance with<III.G.2. Existing equipment which could be used as alternative shutdown
.systems is very limited so that the use of this option would have resulted in plant changes very similar to those which would be required to comply with Section III.G.2, but the installation could be non-safety related with appropriate isolation devices. The installation of a dedicated shutdown system in accordance with Section III.G.3 would involve the addition of all of the pumps, valves, piping, power supply and controls equipment for one train S8207060120 820630
(';PDR ADOCK 05000206 j
PDR
Mr. D.
June 30, 1982 of non-safety related shutdown equipment which would be used only for post-fire shutdown. This would also involve a large set of modifications similar to those required to comply with Section III.G.2, without the commensurate increase in safety provided by a set of safety related modifications. It was decided that the best approach for San Onofre Unit 1 would be to modify the plant to comply with Section III.G.2 of Appendix R, in order to provide a safety related system that will serve broad safety goals.
Accordingly, extensive plant system changes as identified in Enclosure 1 to this letter are proposed for installation at San Onofre Unit 1.
As a result of recent discussions with representatives of the Regulatory staff during the week of June 14, 1982, we have been informed that they consider use of the Remote Shutdown Panel (RSP), even assuming that the RSP is safety related and part of the normal shutdown systems, as an alternative shutdown system. As described in Enclosure 1 to this letter, we are using the RSP to achieve safe shutdown following a fire in the control room. Accordingly, the information requested in the NRC Generic Letter 81-12 as clarified by your letter of May 10, 1982, related to the Remote Shutdown Panel is provided in Enclosure 2 to this letter. Additionally, Enclosure 2 to this letter as supplemented by Enclosure 3 to this letter also provides our evaluation of high-low pressure interfaces as required in the NRC Generic Letter 81-12. to this letter lists two sets of system configuration changes defined in separate categories. These two identified categories represent the intrinsic nature of the changes and are labeled Modifications and Additions. The Modifications involve installation of fire barriers, reconnection of equipment to a different but existing power supply and minor equipment relocation. The Additions involve substantial additional new equipment or systems and new equipment to accommodate substantial component relocation activities. As demonstrated in Enclosure 1 to this letter, since the plant changes all involve existing safety systems, both Modification and Addition changes require a plant outage for installation.
As discussed above, our evaluation has determined that:
(1) the best means of compliance with Appendix R is to modify existing systems to meet the requirements of Section III.G.2, and (2) the Regulatory staff has defined one alternate shutdown system; namely, the RSP. Under the original schedule contained in 10 CFR 50.48(c) all Modifications and Additions, except for those involving the RSP, were to have been implemented during the first outage meeting certain requirements beginning at least 150 days after plans and schedules were filed. However, since the May, 1982 exemption addressed only the deadline for filing plans and schedules, and did not provide a corresponding deferral in the implementation schedule, 10 CFR 50.48(c) would require that these modifications be implemented during the current outage, without the time for implementation initially contemplated by NRC.
The Additions involving the RSP are required to be installed at the first planned or unplanned outage of 60 days or 120 days respectively, or the first refueling outage, which occurs 180 days after NRC approval of design details.
This would result in installation of the RSP Additions by no later than the
Mr. D.
June 30, 1982 next refueling outage. Implementation of the Modifications and Additions on the existing 10 CFR 50.48(c) schedules is not practical because of the nature and extent of the proposed modifications and because the conceptual engineering has only now been completed as provided in the exemption dated May 10, 1982. A detailed evaluation of engineering, procurement and installation requirements for the Modifications and Additions has determined that the following implementation schedules can be met:
- 1. The Modifications can be completed prior to startup from the next refueling outage which is currently expected in late 1983,
- 2. The Additions can be completed prior to startup from the second refueling outage from the date of this letter which is currently expected in mid 1985.
Since these schedules are similar to those applicable to utilities proposing alternative and dedicated shutdown systems of a scope similar to that faced at San Onofre Unit 1 in complying with Section III.G.2, and because the NRC granted an exemption to July 1, 1982 for submittal of plans, schedules and design descriptions, it is appropriate that an extension of the existing implementation schedules should be granted to those schedules identified above.
In addition, installation of Modifications and Additions in accordance with either of the two sets of schedules for implementation discussed above would result in a very large set of plant system configuration changes that could be affected by or conflict with those expected to be identified as part of the SEP Integrated Assessment, as was explained in our exemption request of March 17, 1981 as supplemented on November 9, 1981.
Implementation of these changes independent of SEP can result in wasted effort since SEP may determine that additional modifications to a system are necessary to comply with another specific NRC concern.
In developing the proposed Modifications and Additions we have endeavored to minimize the risk of wasteful system changes by incorporating, where possible, the changes which can now be predicted to be forthcoming from SEP and other NRC review programs. The fact remains that this risk can not be eliminated unless the resolution of concerns is integrated into a common effort which is the purpose of SEP Integrated Assessment. Integration of the effort will result in the optimum design and maximum safety benefits.
Accordingly, we request NRC action regarding compliance with 10 CFR 50.48(c) as follows:
- 1. An exemption from the schedular implementation requirements of 10 CFR 50.48(c)(3).is hereby requested for the Modifications and Additions identified in Enclosure 1 and 2 to this letter, with the exception of the RSP Additions, to be implemented as part of any modifications identified during SEP Integrated Assessment, no earlier than the schedule indicated on page 2 above.
Mr. D.
June 30, 1982=
- 2. An exemption from the schedular implementation requirements of 10 CFR 50.48(c)(4) is hereby requested for the RSP Additions identified in Enclosure 1 to this letter, to be implemented as part of any modifications identified during SEP Integrated Assessment, no earlier than the schedule indicated on page 2 above.
- 3. Commission reconsideration of its May, 1982 exemption decision is hereby requested with respect to the submittal of plans, schedules, and design descriptions in accordance with 10 CFR 50.48(c)(5) as originally requested by our submittals of March 19, 1981 and November 9, 1981, to allow subsequent modification of the attached plans to conform with SEP as it develops. Reconsideration is warranted based on the likelihood that new information derived from SEP Integrated Assessment may result in the identification of other plant configuration changes.
Fully documented formal submittals for these three requests will be provided as soon as practicable but no later than July 31, 1982.
It should also be noted that in spite of the above mentioned exemption requests, it is our intent to commence the efforts necessary to comply with the existing requirements on the schedules previously identified above on page 2 as those which can be met. In order to avoid costly and wasteful effort, however, we have requested these exemptions and our formal exemption submittals will provide what we believe is sufficient basis to justify the schedular extensions. In order to resolve any concerns which may result from review of Enclosure 1 to this letter, we are presently available to meet with the Regulatory Staff.
If you have any questions or desire additional information, please contact me.
Very truly yours, Enclosures