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
REGULATORYTNFORMATION DISTRIBUTION SYTEM (RIDS)
ACCESSION NBR:8005220512 DOCDATE: 80/05/13 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTH,NAME AUTHOR AFFILIATION
- HAILRE, Brookhaven National Laboratory RECIP.NAME RECIPIENT AFFILIATION FERGUSONfR,L, Assistant Director for Plant Systems
SUBJECT:
Forwards fire protection review responding to Items 3,7 & 10
& licensee 800123 Itr,Automatic power backup should be supplied for fire alarm sys, DISTRIBUTION CODE: A006S COPIES RECEIVED:LTR I ENCL j SIZE:.
TITLE: Fire Protection Information (After Issuance of OP, Lic,)
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION:
05 BC Ot W..,
4 4
INTERNAL: 0 1
1 02 NRC PDR I
1 09 I&
2 2
12 AUXIL SYS BR 2
2 14 PLANT SYS BR 5
5 19 WAMBACH 1
1 20 MURANAKAR 1
1 OELD 1
0 EXTERNAL: 03 LPDR 1
1 04 NSIC 1
1 22 ACRS 16 16 MAY 23 1980
- 31.
TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL
ULD f1~ UBROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton, New York 11973 Department of Nuclear Energy (516) 345-2144 May 13, 1980 Mr. Robert L. Ferguson Chemical Engineering U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RE:
San Onofre, Fire Protection Review
Dear Bob:
The attached evaluation has been made at the request of Leo Derderian.
It involves our response to items 3, 7 and 10 and the licensee's letter of January 23, 1980.
Respectfully yours, Robert E. Hall, Group Leader Reactor Engineering Analysis REH:EAM:bf attachment cc.: W. Benaroya wo/att.
W. Kato M. Levine E. MacDougall 8005220 31.&
San Onofre Fire Protection Review Item 3 The fire suppression system power supplies should be automatically transferred to the on-site diesel generators upon loss of offsite power.
Response
The present design of the electric system at San Onofre, Unit 1 is such that upon loss of normal offsite power, manual actions are required to return power to the station (4i e., energization of the 4 kV buses) from either the alternate source of offsite power, or the onsite diesel generators. The time required to perform all manual actions, and verify the automatic actions, is approximately two minutes. If the main generator disconnect switch DC drive motor fails, the switch must be opened manually increasing the total time to seven minutes.
Once the 4 kV buses are energized, no additional manual actions are required to return the fire protection systems to service. Since under normal circumstances the fire protection system would only be out of service for approximately two minutes (seven minutes for worst case) and since no additional manual actions are required to restore the systems to service, the existing design is consider ed acceptable for supplying power to the fire protection systems following loss of normal pffsite power for the following reasons:
- a. The fire water system at San Onofre Unit 1 will be interconnected to the Units 2 & 3 fire water system. Since the Units 2 & 3 diesel driven fire pump will automatically start on a low pressure demand signal regardless of the availability of offsite power, fire water pumping capabilitisfor Unit 1 will be available without performing any manual actions.
- b. In the lube oil reservoir and conditioner area, the 480 volt room walls, the north wall of the turbine building, and the general area coverage is protected by a fusible link wet-pipe sprinkler system, in addition to the other systems in the area. As specified in a) above, fire pumping capabil ity is available so that given a complete loss of offsite power and a fire in this area, the sprinkler system would be available for fire protection even during the 2-7 minutes it would take to restore power to Unit 1.
- c. For the areas where the combustible material is cable insulation (switch gear rooms and vital bus cabinet) the 2-7 minute outage of the fire pro tection systems is considered acceptable based on the fact that these areas involve slow burning, smoldering fires which would not cause a significant amount of damage during the short time period.
- d. The area of the Station Service Transformers 2 & 3 involves a fire hazard associated with 2308 lb. of cable insulation and 534 gal. of oil.
The postulated fire is ignition and spillage of transformer oil from one of
.the two transformers (267 gal.)
The fire suppression system is intended
to protect surrounding cables and other equipment in the vicinity of the transformers. Since this is an open area, it has been determined that the unmitigated fire occurring for a short duration (7 minutes) is not expected to damage these cables and equipment. It has also been shown that the loss of the area will not prevent a safe shutdown of the station. For these reasons, the 7 minute outage is determined to be acceptable for this area's fire detection and suppression systems.
The manual switchover to emergency power for the fire alarm system is unaccept able. Since the plant safety systems have to be manually switched to emergency power it is assumed that the diesel generators are not of §ufficient size to pick up the entire electrical load of the plant.
If the diesels had this capability automatic transfer switches would be provided for the safety systems. Since the fire alarm systems are not necessary for a plant operations, the system may not be manually transferred to emergency power in a situation of critical power requirements.
The fire alarm system protects highly critical areas of the plant required for safe shutdown. A time delay of from 2 to 7 minutes does not comply with our interpretation of the rule 10CFR Part 50 - II F "Automatic Fire Detection where "prompt modification and alarm" is required. We recommend that automatic power back-up be supplied for the fire alarm system; this can be a battery or diesel generator system where no manual transfer is required.
This recommendation is applicable to the items in 3.1.1 of the SER, but it is not by itself an asterisked item of the SER.
Item 7 Provide the basis for using a temperature alarm setpoint of 2800F for the line type heat detection system of the Cable Tray Fire Detection System in the Lube Oil Reservoir and Conditioner Area.
Response
The cable trays in this area contain power and control cables with ratings up to 266 F. Hot spots and cab e fires are only expected to occur at or near the rated value. A setpoint of 280 F provides sufficient margin to minimize the likelihood of spurious action yet is adequate to protect the cables from a fire both in ternal and external to the cable trays.
The 2800F temperature alarm setpoint for the Cable Tray Fire Detection System in the Lube Oil Reservoir and Conditioner Area is acceptable but we recommend that final acceptance of 3.1.5(B) be withheld until the recommendations-intBNL letter dated April 16, 1980 are complied with.
Item 10 Provide design drawings and detailed description of the Reactor Coolant Pump Lube Oil Drain Pans and Spray Shields. Will the system completely enclose all-
pressurized portions of lube oil piping associated with the RCP's? Where will the oil be drained to? Can the drains handle the entire inventory of 1 RCP?
Response
Enclosed drawings (5154154, 5154155) are provided for your review. The pressur ized portions of the lube oil piping will be completely enclosed. Thessphere sump pump will convey spilled oil to the decontaminationddrain tank (D-26).
This tank has a capacity of 350 cubic feet (approximately 2700 gals.).
Since each reactor coolant pump has lubricating oil inventory of less than 250 gallons, the radioactive waste system can easily accommodate a spill from any one pump.
The above referenced drawings were reviewed and found acceptable except for the collection point. The licensee wants to use a containment sump instead of a vented closed container. We recommend that the licensee modify their design to include the vented closed container. Based upon-the above review and recommenda tion, the first part of 3.1.15h Oil Collection System is acceptable.