Letter Sequence Request |
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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 GROV.E AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN TELEPHONE
- MANAGER, GENERATION ENGINEERING December 26, 1979 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 Fire Protection Program Review San Onofre Nuclear Generating Station Unit 1 During the review of the Fire Protection Program at San Onofre Unit 1, the NRC staff identified a concern regarding the effect on the structural steel of the south end of the turbine building, which would result from a fire in the hydrogen seal oil unit.
By letter dated May 15, 1979, we indicated that the result of our analysis determined that the conservatively assumed unmitigated fire will not'affect the structural integ rity of the turbine pedestal nor any of the individual structural systems surrounding it.
Subsequent to that submittal, we were requested to provide a report on the methods used to perform the analysis and this is provided as the enclosure to this letter.
The calculation determines the peak temperature for the hottest column to be 604 F. Based on Figure 6-7B, Section 6, Chapter 7 of the Fire Protection Handbook, 14th Edition, it is estimated that the compressive strength of the steel columns will be reduced by 20%.
Therefore, the loading capacity will be reduced from approximately 460 kips to approximately 370 kips, which is considerably greater than the maximum credible load of 150 kips for each column.
of&
FT
Mr. D. L. Ziemann
-2 It is concluded that the peak temperatures reached in the steel columns of the south turbine deck extension are not high enough to substantially impact the structural integrity of these supports.
These temperatures were recalculated and verified for submittal to your staff for review.
If you have any questions or desire additional infor mation, please contact me.
Very truly yours, encl.
ENCLOSURE AREA 9E FIRE STUDY ANALYSIS METHODS PURPOSE The purpose of this enclosure is to set forth the principal assumptions, methods, and conclusions of the calculation to determine the peak temperatures expected to occur at the steel support columns of the south turbine deck extension due to a fire in the hydrogen seal oil area (Area 9E).
ASSUMPTIONS The following assumptions were used in the calculation:
- 1. Maximum oil volume -
12,300 gal (Ref. 4).
- 2.
Air properties obtained from Reference 3.
- 3. Oil specific gravity - 0.85 (Spec.
2L-4140).
- 4. Heat load to steel columns is primarily due to radiation; heat load from conduction and convection is neglected.
- 5.
Heat loss from columns is convective and conductive; radiation is neglected.
- 6.
Flame temperature is assumed to be 2300 0F Most hydrocarbon fuels produce flame temperatures in the range of 25000-40000 F (Ref.
2, page 4-76) under ideal conditions. Choosing 23000 F compensates to some extent for temperature reductions due to uneven combustion, off-stoichiometric conditions & smoke.
- 7.
Emissivity for painted steel columns is E 12 0.90 (Ref.
1, Pg. 385).
- 8.
Small obstructions (pipes, conduits, etc.) are ignored in calculating configuration factors for radiation.
- 9. Air flow is assumed to be toward fire, past columns, @ 2 ft/sec.
- 10.
Air temperature is assumed to be 100 0 F @ Col. P, 150 0F @ Col. N and 200 0 F 0 Col. M.
- 11.
Columns @ Col. line P are least affected by the fire and will not be analyzed.
- 12. Pairs of columns are equally affected.
Only one column
@ each column line will be analyzed.
- 13. Since fire duration >> 8 brs, assume columns reach thermal equilibrium (Ref. 5,6).
- 14.
Assume conduction to the slab only, not to turbine deck.
-2 METHOD In order to calculate the peak temperatures, a heat balance is performed between the heat load on the columns due to radiation from the fire and the heat losses from the column due to conduction and convection. The.methodology and the associated references utilized in the calculation are listed below.
- 1. The heat load to the columns is primarily due to radiation. The radiation heat flux with associated shape factors was determined using the methods of Reference 1.
The heat loads from conduction and convection are neglected since the geometry of the area is such that air flow would be towards the north and away from the columns.
- 2. The heat loss fr3m the columns is convective and conductive.
Conduction losses are calculated by assuming each column to be a rectangular solid embedded in a semi-infinite medium with an isothermal surface at 100 0 F and using the methods of Reference 1 (See Ref. 1, Table 7-1, pg. 53).
The convective losses are determined assuming an air flow at 2 ft per sec, calculating appropriate dimensionless parameters from Reference 3, and determining the convective heat transfer coefficients as described in Reference 2.
- 3. Since it is assumed that the columns reach thermal equilibrium, a heat balance is performed using the previously obtained expressions for the heat loads input and the heat losses to determine the final equilibrium temperature.
CONCLUSION The peak temperature reached in any of the columns is determined to be 6040 F.
REFERENCES
- 1.
Holman, J.
P., Heat Transfer; 2nd Ed., McGraw Hill, 1968
- 2.
Baumeister, T., Marks' Handbook for Mechanical Engineers; 7th Ed.,
McGraw Hill, 1967
- 3.
Crane Technical Paper 410, Flow of Flids, 11th Ed.,
1970
- 4.
Dwg.
No. 567870
- 5.
Fire Study, Response to BTP APCSB 9.5-1, Docket 50-206 License DPR-13
- 6.
ASTiM Spec. E-119