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
UNITED-STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 2056 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 44 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The facility will operate in conformity with the license amendment, the provisions of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission; B. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; C. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and D. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2 Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by changing paragraph 3.B and adding paragraph 3.H to Provisional Operating License No. DPR-13 to read as follows:
790817009i 1
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
H. Fire Protection The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.17 of the NRC's Fire Protection Safety Evaluation (SE),
dated July 19, 1979 for the facility. These modifications will be completed in accordance with the schedule in Table 3.1 of the SE and supplements thereto.
In addition, the licensee shall submit the additional information identified in Table 3.2 of this SE in accordance with the schedule contained therein. In the event these dates for submittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.
The licensee is required to implement the administrative controls identified in Section 6 of the SE. The administrative controls shall be in effect within 90 days from the date of issuance of this amendment.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance.
7/19/79
ATTACHMENT TO LICENSE AMENDMENT NO. 44 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 39i 39i 39j 39j 60L 60L 60m 60m 72 72
3 Fire Protection Systems Ooerability 3.14 e
s-- S Apolicability:
Applies to the operating status of the fire detection and etinguishing systems and equipment at all times.
Objective:
To ensure availability of fire protection systems.
Soecifications:
A. As a minimum, the following fire detection and extinguishing systems and equipment shall be operable:
(1)
The Fire Suppression Water System, with:
- a. Any two of the following four pumps operable each with a capacity o.
1000 gallons per minute with their discharge aligned to the fire main:
- 1. San Onofre Unit 1 fire water pumps (2)
- 2. San Onofre Units 2 and 3 motor driven fire water pumps (2) b; With San Onofre Unit 1 fire water pumps satisfying the pump requirement, the San Onofre Unit 1 service water reservoir supply available containing a minimum of 300,000 gallons reserved for fire fighting.
- c. With San Onofre Units 2 and 3 fire pumps satisfying the pump requirement, the San Onofre Units 2 and 3 service and fire water storage tanks available with 300,000 gallons reserved for fire fighting.
- d. With a combination of thefour pumps satisfying the pump requirement, the separate water supplies for each pump(s) available as indicated in A(1)b, and A(l)c above.
Amendment No. 3J, 44
-60L 4.15 Fire Protection System Surveillance Applicability:
Applies to the-surveillance of fire detection and extinguishing systems and equipment.
Objective:
To ensure the operability of fire detection and extinguishing systems and equipment.
Specifications:
A. The Fire Suppression Water System shall be demonstrated to be operable.
(1) With the San Onofre Unit 1 fire water pumps satisfying the pump requirements of Technical Specification 3.14.A(l), at least once per seven days by verifying the water supply volume in the San Onofre Unit 1 Service Water Reservoir. With the San Onofre Units 2 and 3 fire water pumps satisfying the pump requirements of Technical Sepcification 3.14.A(l), by initially verifying the water supply volume in the San Onofre Units 2 and 3 service and firewater storage tanks and at least once per seven days thereafter.
(2) At least once per 31 days on a staggered test basis by starting each pump satisying the pump requirements of Technical Specification 3.14.A(l) and operating it for at least fifteen minutes.
(3) At least once per thirty one days by verifying that each valve (manual, power operated or automatic is in its correct position. For valves located inside the containment sphere, verifi cation shall be made consistent with the 31-day requirement when possible during available plant outages or during containment entrances for other reasons.
(4) At least once per 12 months by cycling each testable valve through one complete cycle of full travel.
(5) At least once per 18 months by performing a system functional test which includes simulated actuation of the system, and:
- a. Verifying that each valve in the flow path is in its correct position,
- b. Verifying that each pump develops at least 90'j of the flow.and head at somn point on the manufacturer's pump performance curves.
Amendment No. 3J, 3, 44
60-M
- c. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and d..
Verifying that each pump starts to supply the fire suppression water system at >50 psia.
(6) At least once per 36 months by performing flow tests of the system in accordance with Chapter 5, Section 11 of Fire Protection Handbook, 14th Edition, published by National Fire Protection Association.
B. The Spray and/or Sprinkler Systems indicated in Technical Specification 3.14.A(2) shall be demonstrated to be operable:
(1) At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of.full travel.
For the valves located in the containment sphere, testing shall be performing consistent with the 12-month requirement when possible during available plant outages.
(2) At least once per 18 months:
a.. By performing a system functional test which includes simulated automatic actuation of the system, and:
- 1. Verifying that the automatic valves in the flow path actuate to their correct positions on a smoke and infrared test signal, and
- 2. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
- b. By inspection of the spray headers to verify their integrity, and (3) By inspection of each nozzle at least once every refueling outage to verify no blockage.
(4) At least once every second refueling outage by performing an air flow test through each accessible spray/sprinkler header and verifying that the spray/sprinkler nozzles are unobstructed.
C. Each Fire Hose Station indicated in Table 3.14.1 shall be verified to be operable:
Amendment No. 3J. 44
72 A
- b. At least one licensed Operator shall be at the controls when fuel is in the reactor.*
During refueling operations this operator is permitted to step outside the red line to update the refuel.ing status board.
- c. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips."
One of the two licensed Operators is permitted to be present in the Chemical Laboratory or the area around and behind the vertical instrumentation boards for short periods of time for the purpose of checking necessary instrumentation.
- d. An individual qualified in radiation protection supervision shall be on site when fuel is in the reactor.
- e. All core alterations after the initial fuel loading shall be directly supervised by a licensed Senior Reactor Operator.
- f.
A Fire Brigade of at least five members shall be maintained on site at all times. This excludes members of the minimum shift crew necessary for safe shutdown of Unit 1 and any personnel required for other essential functions during a fire emergency.
6.2.3 Fire Protection Oroanizations The responsibility for the operational Fire Protection Program at the San Onofre Nuclear Generating Station Unit 1 is vested in the Vice President of the Power Supply Department. The imple mentation of this program is delegated to staff and.line organizations within the Power Supply Department as shown in Figure 6.2. 3.1
- At the controls" means within the area bounded by the three vertical instrumentation boards and the red line on the floor of the control room.
- Reactor startup, reactor shutdown and recovery from reactor trips means operations between keff = 0.99 and the attainment of E5%
indicated thermal power.
Amendment No. 37. 44