|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20151T2571985-12-20020 December 1985 Mechanical Maint Technical Rept, Unit 3 Containment Bldg Tendon Surveillance, Jul 1977 - Jul 1980 ML20135G5891985-09-0303 September 1985 Rev 0 to B&W Owners Group Emergency Operating Procedures Technical Bases Document. W/Three Oversize Drawings ML20151K2671984-03-31031 March 1984 Final Rept:Failure Modes & Effects Analysis of Integrated Control Sys/Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Vol 1 - Main Rept & Vol 2 - App a ML20151K2491984-03-29029 March 1984 Draft Oconee-1 AC Electrical Distribution Control & Protection Design Features ML20151K2761983-10-28028 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys ML20080E0101983-10-0303 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys, Preliminary Draft ML20080E6061983-08-26026 August 1983 Failure Modes & Effects Analysis of Integrated Control Sys/ Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Interim Rept ML20072B7961983-02-15015 February 1983 Control Room Review Plan for Oconee,Mcguire & Catawba Nuclear Stations,Duke Power Co ML20117J3641983-01-31031 January 1983 Evaluation of Oconee Nuclear Station,Duke Power Co ML20117J3571981-07-31031 July 1981 Evaluation of Oconee Nuclear Power Station ML19323A1621980-03-26026 March 1980 TMI-Plus One:Toward a Safer Nuclear Power Program. ML19249D8631979-09-30030 September 1979 Description of Proposed Mod to Radiological Effluent Treatment Facility, Preliminary Rept.Oversize Drawings Encl ML19308A7471979-09-27027 September 1979 Jocassee Development Rept on 790825 Earthquake & Effects on Jocassee Structures. ML19322B8741979-08-24024 August 1979 Addl Info to 790824 Response to IE Bulletin 79-05C Nuclear Incident at TMI Including Supplemental Small Break Analysis ML19312C1281979-08-16016 August 1979 Mgt & Technical Resources:Experience & Qualifications of Steam Production Dept General Office Staff. ML19312C7981979-07-30030 July 1979 Response to IE Bulletin 79-05C, Nuclear Incident at Tmi. ML19259C4821979-05-0909 May 1979 Effect of Closing Oconee Nuclear Plants on Ability to Meet Summer Peak Demands. ML19312C5841978-07-14014 July 1978 Proposed Mod of Hpis. ML19316A1201978-07-14014 July 1978 Rept on Seismic Activity at Lake Jocassee,780301-0531. ML19316A1351978-04-0404 April 1978 Rept on Seismic Activity at Lake Jocassee,771201-780228 ML19319A7261978-03-0101 March 1978 Info & Evaluation Re Fracture Toughness of Steam Generator & Reactor Coolant Pumps Support Matls. ML19354C2851978-02-28028 February 1978 Possible Geologic/Seismicity Relationships in Vicinity of Facility from Available Data & Repts. Oversize Maps Encl ML19354C2861978-01-19019 January 1978 Rept on Preliminary Investigation of Seismicity Near Lake Keowee,Oconee County,SC,771230-780115. ML19317E6991978-01-16016 January 1978 Fire Protection Program Comparison to NRC Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls & Qa. ML19316A1231977-11-30030 November 1977 Rept on Seismic Activity at Lake Jocassee,770901-1130. Oversize Earthquake Charts Encl ML19317E7261977-10-14014 October 1977 Fuel Assembly 1D40. ML19312C5811977-09-24024 September 1977 Generator Tube Leak Status Rept. ML19316A1301977-09-0202 September 1977 Jocassee Dam Northwestern Sc:Estimate of Existing Strain & Cracking Potential from Hypothetical Foundation Displacements. ML19319A7301977-08-31031 August 1977 Safety Assessment of Steam Generator Tube Leakage. ML19316A1361977-08-31031 August 1977 Rept on Seismic Activity at Lake Jocassee,770601-0831. Oversize Map Encl ML19316A1291977-08-26026 August 1977 Steam Generator Tube Leak Status Rept. ML19308A8381977-07-18018 July 1977 Requalification Program for NRC Licensed Personnel, 731211.Revised on 740703,750107,0221,760930 & 770718 ML19316A3121977-04-21021 April 1977 Evaluation of Potential for Turbine Bldg Flooding. ML19312C3611977-03-30030 March 1977 Qualification of Power Distribution Connector for Use in 15kV Rated Medium Voltage Electrical Penetrations. ML19312C1251977-03-22022 March 1977 Rept on Seismic Activity at Lake Jocassee Between 760601 & 770228. ML19316A1131976-12-31031 December 1976 Response to App a to Branch Technical Position Apcsb 9.5.1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to 760710. ML19317D7041976-10-14014 October 1976 Evaluation of Potential Reactor Vessel Overpressurization. ML19308B2771976-10-0101 October 1976 Engineering Geology of Keowee-Toxaway Project. ML19260C1781976-09-30030 September 1976 Jocassee Hydro-Station Seismic Studies Summary Rept. Cover Ltr & Oversize Drawings Encl ML19312C1591976-08-0606 August 1976 Evaluation of Post-LOCA Boric Acid Concentration Control Sys for Facility Reactors. ML19340A1241976-04-16016 April 1976 Criticality Evaluation for Dry Storage of Fresh Fuel Assemblies in Oconee Unit 3 Spent Fuel Pool. ML19316A1171976-04-13013 April 1976 Attachment A:Structural Analysis of Worn Surveillance Specimen Holder Tubes. ML19340A1571976-04-12012 April 1976 Surveillance Holder Tube Rept. ML19322B6161975-12-18018 December 1975 Methods to Prevent Boron Precipation in Long-Term Following Postulated Loca. ML19322B6121975-11-14014 November 1975 Reactor Vessel Support Evaluation for LOCA Loadings. ML19312C8231975-08-12012 August 1975 Safety Evaluation Supporting Util Application to Amend License DPR-55 for Mod of Spent Fuel Storage Facility ML19317E5061975-08-0101 August 1975 Partial Loop ECCS Analysis. 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134N7121997-02-20020 February 1997 Safety Evaluation Accepting Relief Request 96-04 for Plant ML20138L2151997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 ML20138L2281996-12-31031 December 1996 Revised Monthly Operating Repts for Dec 1996 for Oconee Nuclear Station,Units 1,2 & 3 ML20133C1231996-12-23023 December 1996 Informs Commission of Staff Review of Request for License Amends from DPC to Perform Emergency Power Engineered Safeguards Functional Test on Three Oconee Nuclear Units ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20086M0851995-06-29029 June 1995 DPC TR QA Program ML20077R3631994-12-31031 December 1994 Monthly Operating Repts for Dec 1994 for Bfnpp ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20064L2001994-01-31031 January 1994 Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station ML20062K7481993-12-0101 December 1993 ISI Rept for Unit 2 McGuire 1993 Refueling Outage 8 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20046C1291993-08-0202 August 1993 LER 93-007-00:on 930701,determined That Unit 1 Ssf Rc Makeup Sys Inoperable in Past Due to Design Deficiency.Operations Procedures Revised to Reflect Newly Calculated Operating Limits for Rc Makeup Pump,Rcps & RCS.W/930802 Ltr ML20056G0131993-07-27027 July 1993 Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20097G0421992-05-31031 May 1992 Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19332D5391989-10-31031 October 1989 Core Thermal-Hydraulic Methodology Using VIPRE-01. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20239A6991987-11-30030 November 1987 Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20236Q9491987-10-31031 October 1987 Monthly Operating Repts for Oct 1987 ML20235W9611987-09-30030 September 1987 Monthly Operating Repts for Sept 1987 ML20234B1861987-08-31031 August 1987 Monthly Operating Repts for Aug 1987 ML20237K4761987-07-31031 July 1987 Monthly Operating Repts for Jul 1987 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20235S6311987-06-30030 June 1987 Monthly Operating Repts for June 1987 1999-01-05
[Table view] |
Text
, _. _ _ _ _ _--..... ._
- n. ^ s
/ j o-i-
OCONEE NUCLEAR STATION FIRE PROTECTION PROGRM COMPARISON TO T9E NUCLEAR REGULATORY COMMISSION'S
" NUCLEAR PLANT FIRE PROTECTION FUNCTIONAL RESPONSIBILITIES, ADMINISTRATIVE CONTROLS AND QUALITY ASSURANCE"
?
I k
4 January 16, 1978 i
(
l i
s k
. 991sisogyg
'"' i er m- q+ g +c--@ w 9%> p g P --.c
- 7 -Iy -- '-t- -g a er4-- s- .* w+4 -
tr. 'd e e e1--T"
m ,
[, . ... j ATTACHMENT #1
~7 IRE PROTECTION ORGANIZATION RESPONSE TO 1.0 a & b The offsite management positions responsible for implementation of the fire protection program are outlined in Section A.1 of Duke Power Company's Response to Appendix A to Branch Technical Position APSCB 9.5-1, " Guide-lines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1,1976," which was transmitted by our letter of December 31, 1976.
Organizational charts relating positions and jurisdiction statements outlining division and group responsibilities are being amended to include fire protection responsibilities.
In addition to these management positions Technical Specifications have have been proposed which require the Nuclear Safety Review Board (NSRB) to audit the fire protection program and implementing procedures annually.
The Director of the NSRB reports the results of the audit directly to the Vice President, Steam Production. Reports of the audit are also transmitted to the Senior Vice President, Production and Transmission, and to the management positions responsible for the areas audited.
An independent fire protection and loss prevention inspection and audit to be performed annually by qualified off-site personnel and an inspection and audit by a qualified fire consultant to be performed at intervals of no greater than three years is also provided for by the proposed Technical Specifications.
RESPONSE TO 1.0c The Station Manager is responsible for overall administration of plant operations and emergency plans. The organization chart in Enclosure 1 shows the organization as it applies to fire protection with brief des-cription of responsibilities.
RESPONSE TO 1.0d (1) To minimize the amount of conbustibles in safety-related areas and determine the effectiveness of housekeeping practices, the station group superintendents perform monthly inspections of assigned areas to assure that housekeeping and storage practices are according to station directives and procedures. The Safety Supervisor (Fire Pro-tection Supervisor) performs frequent inspections to also insure proper housekeeping and storage.
The availability and acceptable condition of all fire protection systems and equipment are assured by the procedures and practices of the Maintenance, Operations and Techniaal Services Groups.
Emergency breathing apparatus is maintainei by the Technical Services Group. Communications' equipment is maintained by the Maintenance Group. Emergency lighting equipment is maintained by the Operations Group. Fire stops and penetrations seals are maintained by the Maintenance Group and periodically inspected by the
' n
. [ -
Administrative Services Group. Procedures and Station Directives are used by Maintenance, Operations and Technical Services to assure that prompt and effective corrective actions are taken to correct conditions adverse to fire protection and preclude their recurrence.
.(2) Fire fighting training is the responsibility of the Administrative Services Group. The design and selection of equipment is the res-ponsibility of the Design Engineering Department, Periodic inspections and tests are performed on various equipment by Operations, Mainte-nance and Technical Services as described in (1) above.
(3) The Administrative Services Group is responsible for conducting and critiquing fire drills.
(4) The supervisor in charge of a work activity is responsible for identifying transient fire loads and maintaining them within the guidelines of Station Directive 3.11.5.
(5) The Superintendent of the group for which contractor personnel are working is responsible for assuring that such personnel are properly indoctrinated.
(6) The Administrative Services Group is responsible for instructing personnel in the handling of events that affect fire protection.
RESPONSE TO 1.0e The Quality Assurance Organization assures the effective implementation of the fire protection program by planned inspections and audits. Results are reported to appropriate personnel.
RESPONSE TO 1.Of The plant fire brigade positions and responsibilities are defined (1)3 (2) 'in Station Directive 5.3.1. This directive outlines the authority and duties of each brigade position.
(3)g All available fire brigade members respond to fire emergencies. l (4) To assure sufficient response all operations shift and guard force personnel receive fire brigade training. They are available in numbers such that sufficient brigade members can respond without j being in conflict with other requirements.
(5) The guidance incorporated in NFPA No. 27 " Private Fire Brigades" has been utilized in the establishment of the Oconee fire brigade to the extent practical.
RESPONSE TO 2.0a As-stared in our December 31, 1976 letter referred to in Response to 1.0 a & b, {
a registered fire protection engineer with twenty-five years of experience in the field of industrial fire protection has been engaged on a consulting basis.
A. copy of the consultant's resume is included in that report.
I i
RESPONSE 'IO 2.0b The Fire Brigade members receive physical examinations and training as described in the response to the positions in Attachment #2.
RESPONSE TO 2.0c Employees performing maintenance and testing are qualified in accordance with ANSI 18.1-1971.
RESPONSE TO 2.0d Personnel responsible for Fire Brigade are qualified by experience and/or training.
l l
^
g
~
FIRE BRIGADE TRAINING RESPONSE TO 1.0 All items under this section are covered in classroom instruction with the following exception:
- d. In lieu of regular planned meetings, quarterly written critiques of monthly fire drills are read and signed by each Brigade member and requalification training is conducted every two years.
RESPONSE TO 2.0 Practice sessions are conducted every two years in initial and requalifica-tion training. During these sessions Brigade members extinguish actual fires using the type of equipment available in the plant.
Respiratory training will be given in accordance with NUREG-0041 wnich is required by Regulatory Guide 8.15.
RESPONSE TO 3.0 Fire drills are conducted in accordance with items in this section with the following exceptiens:
(1) Each fire brigade participates in at least two drills per year.
(2) Written critiques of these drills are read and initialed by each brigade member.
RESPONSE TO 4.0 Records are maintained as described in Item 4.0.
1
-s ,
. 1 ATTACHMENT #3
' -d /
CONTROL OF COMBUST,IBLES RESPONSE TO ATTACHMENT 3 The following Station Directives provide administrative controls of com-bustibles in areas containing safety-related equipment:
3.11.1 Procedure to Control Combustible Materials and Ignition Sources In Cable Spreading Rooms and Equipment Rooms 3.11.4 Cleanness Levels in Safety Related Areas 3.11.5 Permanent and Transient Storage of Combustible Material 5.1.4 Welding and Burning Safety Procedure 5.1.8 Storage of Material In Safety Related Structures or Systems 5.1.9 Wood Control In The Protected Area It is felt that these Station Directives assure that the items mentioned in Attachment 3 are controlled such that a high degree of protection from fire is afforded.
4
- c. .
s mTACHMENT #4 CONTROL OF IGNITION SOURCES.
' RESPONSE TO 1.0 The following Station Directives provide administrative controls of ignition sources in areas containing safety-related . equipment:
3.11.1 Procedure to Control Combustible Materials and Ignition Sources In Cable Spreading Rooms and Equipment Rooms 3.11.5 Permanent and Transient Storage of Combustible Materials 5.1.4 Welding and Burning Safety Procedure 5.1.8 Storage of Material In Safety Related Structures or Systems RESPONSE TO 2.0 All items in this section are controlled under Station Directives listed abree with the exception of:
b'4) Oxyacetylene equipment leak testing.
- c. Signature concurrence of a second party when a fire watch is not required.
These two items will be added to appropriate directives by April 1,1978.
RESPONSE TO 3.0 Leak testing is performed using consercially available aerosol or bubble techniques under procedures approved by group heads. The only areas in which candles or open flames are permitted are in the search for secondary system condenser vacuum leaks. In this case candles are considered accep-table since the areas are sufficiently removed from safety related equip-ment and ignition hazards are minimized.
RESPONSE TO 4.0 Areas containing flammable or potentially explosive atmospheres have been posted to restrict smoking, burning, or welding. Areas containing safety.
~
related equipment have been. administrative 1y designated and will be
. physically marked..
} e.
^
3
, , j sATTACHMENT #5
~
FIRE FIGHTING PROCEDURES RESPONSE TO ATTACHMENT 5 Station Directive 5.3.1 Fire Brigade Organization and Training describes the fire brigade organization, lists qualified fira brigade members, basically outlines the training they will be given and gives the procedure to be followed before conducting a fire drill. This procedure also do.s-cribes the actions to be taken by personnel who discover a fire and the control room operator actions after a fire has been reported. Additionally, general station personnel are given yearly training on reporting fires, the use of portable extinguishers, and other actions they are expected to take if they discover a fire.
It is our policy that offsite fire departments will not be called except for those fires which may occur outside the protected area fence such as woods and grass fires. However, the Keowee-Ebenezer Fire Department volunteers are trained yearly in basic radiation principles.
In lieu of the fire fighting procedures described in Section d, general arrangement drawings of all levels within the station and yard areas have been marked showing the location of fire protection equipment and the location of some combustibles. These drawings are located in each control room and in the Safety Supervisor's office. We intend to expand the information on these drawings to indicate additional combustibles Fazards and ventilation systems supplying each location. It is our opinion that this method makes necessary information available in a broader and much more readily retrievable manner than the use of plans for individual areas or zones.
^ s
']
~
A.tACIDENT # 6 QUALITY ASSURANCE RESPONSE TO ATTACHMENT 6 The quality assurance program identified in Section 17.2 of Topical Report DUKE-1-A, " Quality Assurance Protection", for nuclear safety-related structures, systems and components was implemented for the fire protection program as of January 1,1978.
I l
l i
L1
OCONEE NUCLEAR STATION FIRE PROTECTION RESPONSIBILITIES STATION MANAGER O-
~
MAINTENANCE TECHNICAL SERVICES OPERATIONS ADMINISTRATIVE SERVICES SUPERINTENDENT SUPERINTENDENT SUPCRINTENDENT SUPERINTENDENT Repair and perform Provide llealth Physics Responsible for all Develop and implement periodic tests on coverage for fires with plant conditions fire protection poli-various equipment radiological involvement cies and procedures Perform operational tests Identify activities Performs Performance on various equipment Audit compliance with that will violate Testing various procedures, per-fire stops or create formance of tests, and transient fire loads availability of systems Proper storage of Provide Fire Brigade combustibles Training and documenta-Procurement and use of fire retardant lumber Conduct and critique fire drills Total preventive maintenance program Responsible for general housekeeping
- Provide approx. 4 Fire Provide approx. 7 Fire Provide approx. 100 Fire Provide approx. 50 Fire
, Brigade Members Brigade Members Brigade Members from Brigade Members from
- operating shifts Guard Force
. 9 b
. ,