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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility ML20210S0391997-08-27027 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000.Violation Noted:Between 970501-02,w/ Fuel in Oconee Unit 3 Core & RCS Temp Greater than 350 F, Licensee Failed to Maintain HPI Sys Operable as Required ML20134D2581991-06-0404 June 1991 Notice of Violation from Insp on 910312-15.Violations Noted:Station Was Not Maintained According to Main Procedure MP/0/A/1800/105,Section 6.5,which Clearly Identified That Flange Was to Be Installed on Valve 3LP19 ML20207T5431987-03-12012 March 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Noncompliance Noted:Measures Not Established to Assure That Regulatory Requirements & Design Bases Correctly Translated Into Specs,Drawings & Procedures ML20211A4991987-02-11011 February 1987 Notice of Violation from Insps on 870112-16 ML20210U3211987-02-0505 February 1987 Notice of Violation from Insp on 861015-1110.Violation Noted:For Periods in 1978,1981 & 1986 When Lake Keowee Elevation Less than 792 Ft,Emergency Condenser Cooling Water Sys Inoperable & Unable to Provide Sustained Siphon Flow ML20211A0871987-02-0303 February 1987 Notice of Violation from Insp on 870105-08 ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 ML20199H4661986-03-27027 March 1986 Notice of Violation from Insp on 860224-28 ML20210H3741986-03-21021 March 1986 Notice of Violation from Insp on 860114-0210 ML20214D7201986-02-19019 February 1986 Notice of Violation from Insp on 851216-20 ML20137U5261986-02-12012 February 1986 Notice of Violation from Insp on 851210-860113 ML20137E3821985-11-22022 November 1985 Notice of Violation from Insp on 851008-1111 ML20133C7351985-10-0101 October 1985 Notice of Violation from Insp on 850903-06 IR 05000813/20090091985-09-16016 September 1985 Notice of Violation from Insp on 850813-0909 ML20132C1851985-09-13013 September 1985 Notice of Violation from Insp on 850729-0802 ML20135D5841985-08-28028 August 1985 Notice of Violation from Insp on 850709-0812 ML20125B5471985-06-0606 June 1985 Notice of Violation from Insp on 850211-0310 IR 05000411/20050131985-06-0303 June 1985 Notice of Violation from Insp on 850411-0513 ML20127N7301985-05-20020 May 1985 Notice of Violation from Insp on 850422-26 ML20127F1021985-04-0909 April 1985 Notice of Violation from Insp on 850318-21 ML20132B0651985-01-23023 January 1985 Notice of Violation from Insp on 841126-30 ML20129H3211984-11-23023 November 1984 Notice of Violation from Insp on 840910-14 ML20024F6531983-07-27027 July 1983 Notice of Violation from Insp on 830628-0701 ML20024A7401983-06-0202 June 1983 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $180,000.Noncompliance Noted:Inadequate Procedures to Ensure That Air Lock Sys Restored to Operability After Maint ML20058H5731982-06-16016 June 1982 Notice of Violation from Insp on 820510-14 ML20054K3371982-05-0303 May 1982 Notice of Violation from Insp on 820310-0410 ML20053E2571982-04-0202 April 1982 Notice of Violation from Insp on 820210-0310 ML20050H8151982-03-0505 March 1982 Notice of Violation from Insp on 820110-0210 ML19347F5441981-04-0303 April 1981 Notice of Violation from Insp on 810311-13 ML19345G6641981-02-24024 February 1981 Notice of Violation from Insp on 810102-31 ML19350C0031981-02-11011 February 1981 Notice of Violation from Insp on 801201-31 ML19350C0451981-02-10010 February 1981 Notice of Violation from Insp on 801215-18 & 810105-08 ML20003D8251981-02-0909 February 1981 Notice of Violation from Insp on 810106-09 ML19341D6671981-02-0505 February 1981 Notice of Violation from Insp on 801208-12 ML20008F3331981-01-0808 January 1981 Notice of Violation from Health Physics Appraisal on 800908-19 ML20003A6061980-11-26026 November 1980 Notice of Violation from Insp on 801001-31 ML19339B0051980-09-0404 September 1980 Notice of Violation from Insp on 800701-31 ML19337A8851980-07-28028 July 1980 Notice of Violation from Insp on 800602-30 ML19337A9761980-06-20020 June 1980 Notice of Violation from Insp on 800501-30 ML19332A1291980-05-23023 May 1980 Notice of Violation from Insp on 800401-30 ML19332A6391980-05-15015 May 1980 Notice of Violation from Insp on 800415-17 & 21-23 ML19323E2281980-04-0202 April 1980 Notice of Violation from Insp on 800201-29 ML19305B1301980-01-30030 January 1980 Notice of Violation from Insp on 791218 ML19322E3531980-01-28028 January 1980 Notice of Violation from Insp on 791127-30 ML19305E2771980-01-11011 January 1980 Notice of Violation from Insp on 791203-10 ML19344D3751979-11-21021 November 1979 Notice of Violation from Insp on 791009-12 ML19257D6491979-10-24024 October 1979 Notice of Violation from Insp on 790904-28 ML19250A7101979-09-10010 September 1979 Notice of Violation from Insp on 790806-10 ML19250C4601979-07-13013 July 1979 Notice of Violation from Insp on 790627-29 1997-09-26
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-II-97-065, on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG1997-12-29029 December 1997 PNO-II-97-065:on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility ML20210S0391997-08-27027 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000.Violation Noted:Between 970501-02,w/ Fuel in Oconee Unit 3 Core & RCS Temp Greater than 350 F, Licensee Failed to Maintain HPI Sys Operable as Required PNO-II-97-034, on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities1997-06-13013 June 1997 PNO-II-97-034:on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts PNO-II-93-039, on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified1993-08-24024 August 1993 PNO-II-93-039:on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified IR 05000269/19930181993-06-13013 June 1993 Insp Repts 50-269/93-18,50-270/93-18 & 50-287/93-18 on 930614-17.No Violations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000269/19930101993-04-16016 April 1993 Insp Repts 50-269/93-10,50-270/93-10 & 50-287/93-10 on 930315-19.No Violations or Deviations Noted.Major Areas Inspected:Radiological Effluents,Process & Effluent Radiation Monitoring Instrumentation & Water Chemistry IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19933001993-02-23023 February 1993 Initial Exam Rept 50-269/93-300 Administered During Wk of 930125.Exam Results:Seven Senior Reactor Operators Passed Both Written Exams & Operating Tests ML20034E9571993-02-19019 February 1993 Insp Repts 50-269/93-03,50-270/93-03 & 50-287/93-03 on 930103-30.Violations Noted.Major Areas Inspected:Plant Operations,Surveillance Testing,Maint Activities,Keowee Issues & Insp of Open Items IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld PNO-II-92-070A, on 921019,AIT Dispatched to Facility Following Reactor Trip Due to Loss of Ac Power Followed by Degraded Emergency Power Supply.Following Implementation of Corrective Actions,Facility Restarted on 9210261992-10-28028 October 1992 PNO-II-92-070A:on 921019,AIT Dispatched to Facility Following Reactor Trip Due to Loss of Ac Power Followed by Degraded Emergency Power Supply.Following Implementation of Corrective Actions,Facility Restarted on 921026 PNO-II-92-070, on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed1992-10-20020 October 1992 PNO-II-92-070:on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed PNO-II-91-074B, on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell1991-11-26026 November 1991 PNO-II-91-074B:on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell ML20134D2581991-06-0404 June 1991 Notice of Violation from Insp on 910312-15.Violations Noted:Station Was Not Maintained According to Main Procedure MP/0/A/1800/105,Section 6.5,which Clearly Identified That Flange Was to Be Installed on Valve 3LP19 IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt PNO-II-91-006A, on 910308,augmented Insp Team Dispatched to Followup on Loss of Decay Heat Capability Event.Team Will Arrive on-site & Begin Insp on 9103121991-03-11011 March 1991 PNO-II-91-006A:on 910308,augmented Insp Team Dispatched to Followup on Loss of Decay Heat Capability Event.Team Will Arrive on-site & Begin Insp on 910312 PNO-II-91-006, on 910308,during Draining of RCS & Borated Water Storage Tank,Loss of DHR Occurred.Caused by Securing LPI Pump 3A Due to Pump Cavitation.Suction Valves from Borated Water Tank Opened to Recover Rx Vessel Level1991-03-0808 March 1991 PNO-II-91-006:on 910308,during Draining of RCS & Borated Water Storage Tank,Loss of DHR Occurred.Caused by Securing LPI Pump 3A Due to Pump Cavitation.Suction Valves from Borated Water Tank Opened to Recover Rx Vessel Level PNO-II-90-070, on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a1990-11-0808 November 1990 PNO-II-90-070:on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900241990-10-0202 October 1990 SALP Repts 50-269/90-24,50-270/90-24,50-287/90-24 & 72-0004/90-24 for Feb 1989 - Jul 1990 IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control PNO-II-90-024, on 900517,plant Operators in Unit 1 & 2 Control Room Break Area Noted Water Coming Down Wall.Water Being Pumped to Spent Fuel Pool Due to Out of Sequence Valve Alignment Which Caused Overfilling.No Personnel Injured1990-05-18018 May 1990 PNO-II-90-024:on 900517,plant Operators in Unit 1 & 2 Control Room Break Area Noted Water Coming Down Wall.Water Being Pumped to Spent Fuel Pool Due to Out of Sequence Valve Alignment Which Caused Overfilling.No Personnel Injured IR 05000269/19900061990-03-19019 March 1990 Partially Withheld Insp Repts 50-269/90-06 & 50-270/90-06 & 50-287/90-06 on 900212-16 (Ref 10CFR2.790(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors,Specifically Mgt & Barriers IR 05000269/19890391990-02-22022 February 1990 Insp Repts 50-269/89-39,50-270/89-39 & 50-287/89-39 on 891212-15 & 18-20.No Violations or Deviations Noted.Major Areas inspected:post-refueling Startup Tests of Unit 3 & Core Performance Surveillances on Units 1 & 2 IR 05000269/19890321989-11-20020 November 1989 Partially Withheld Insp Repts 50-269/89-32,50-270/89-32 & 50-287/89-32 on 891002-04 (Ref 10CFR2.790 & 73.21).Major Areas Inspected:Physical Security Program for Power Reactors IR 05000269/19890331989-11-15015 November 1989 Insp Repts 50-269/89-33,50-270/89-33 & 50-287/89-33 on 890930.No Violations or Deviations Noted.Major Areas Inspected:Physical Protection of Shipment of Irradiated Reactor Fuel IR 05000269/19890301989-11-0707 November 1989 Partially Withheld Insp Repts 50-269/89-30,50-270/89-30 & 50-287/89-30 on 890918-22 (Ref 10CFR2.790 & 73.21).One non- Cited Violation Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Mgt Effectiveness IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes PNO-II-88-013, on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination1988-02-12012 February 1988 PNO-II-88-013:on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination ML20237B2261987-12-15015 December 1987 EN-87-017A:informs That 870309 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Withdrawn Due to Determination That Violation Did Not Occur. Violation Based on Failure of Emergency Feedwater Pumps ML20235T5821987-09-18018 September 1987 Exam Rept 50-269/OL-87-02 on 870713-23.Exam Results:Seven of Ten Reactor Operator (RO) & Eight of Nine Senior Reactor Operator (SRO) Candidates Passed Written Exam.All RO & SRO Candidates Passed Operating Exam ML20238F7081987-09-0909 September 1987 Exam Rept 50-269/OL-87-01 for Units 1,2 & 3 on 870713-17. Exam results:7 of 10 Reactor Operators & 3 of 6 Senior Reactor Operators Passed ML20236E5111987-07-14014 July 1987 EN-86-056:on 870717,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Licensee.Action Based on Failure to Properly Implement Startup Procedure Causing Trains to Fail IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 ML20207T5431987-03-12012 March 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Noncompliance Noted:Measures Not Established to Assure That Regulatory Requirements & Design Bases Correctly Translated Into Specs,Drawings & Procedures ML20207R4851987-03-0909 March 1987 EN-87-017:on 870312,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Util Based on Failure to Provide Adequate Design Control to Ensure Emergency Feedwater Pump Operability IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress ML20211A4991987-02-11011 February 1987 Notice of Violation from Insps on 870112-16 IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards 1997-09-26
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y NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTIES Duke Power Company Docket Nos. 50-269 & 50-287 Oconee Units 1 and 3 License Nos. DPR-38 & DPR-55 EA 83-41 On March 17, 1983, the licensee initiated a periodic test procedure to perform the quarterly surveillance of the Unit 3 reactor building emergency air lock.
During a pre-surveillance radiation survey, an alert Radiation Protection Technician detected an odor he recognized as typical of the inside of the reactor building.
Subsequently, it was discovered that the source of the odor was a 3/4-inch test line on which the isolation valve was found to be open. This. valve, in conjunction with a leaking inner hatch equalizing valve, provided a flowpath from the containment to the outside atmosphere. The valve had apparently been open since the leak rate surveillance had last been performed on December 17, 1982.
The shift supervisor promptly closed the valve when informed of the improper condition.
On March 21, 1983, oncoming shift control room personnel noticed an "open" indicator light was on for the inner hatch of the Unit 1 emergency air lock. This condition was visually checked at the hatch and the inner door was found to be partly open, and was promptly closed.
Subsequent investigation indicated that it had been left cracked open after the performance of a surveillance procedure on March 17, 1983. No pathway existed to the environment in this second event.
Both of these violations of NRC requirements can be attributed to inadequate procedures to ensure that systems were restored to operability after maintenance or other activities affecting the system were performed.
In the first case, on Unit 3, the procedure ended without the instructions for aligning system valves to the proper position.
In the event involving the Unit 1 emergency air lock, inadequate instructions were provided to personnel perftrming the work. The operation of the door mechanism was not clearly understood by those manipulating it and the significance of the indicating light, both at the door itself and at the remote indicator in the control room, was not understood.
The need for independent verification has been brought to the attention of Duke Power Company (DPC) by the NRC in NUREG-0585 and NUREG-0737, issued in November 1979 and November 1980, respectively, as a result of lessons learned from the Three Mile Island accident.
Both recommended that licensee's procedures "be reviewed and revised, as necessary, to assure an effective system of verifying the correct performance of operating activities is provided as a means of reducing human errors." Both documents specifically referred to " human verifi-cation of operations and maintenance independent of the people performing the activity" (emphasis added).
8306220175 830S02 PDR ADOCK 05000269 G
PDR i
4 Notice of Violation 2
4 These provisions have been the subject of extensive NRC/ licensee correspondence over the past.two and one-half years and of' a Confirmatory Order issued on July 10,1981.
On October 12, 1982, the NRC issued an order imposing a civil penalty of Forty--
Four Thousand Dollars for a similar event involving a breach of containment integrity. The attention of DPC was directed at that time to a review of procedures to ensure safe operation and restoration of operability after the performance of maintenance.
The NRC inspection, conducted by the Resident Inspectors on March 17-28, 1983, confirmed the violations in items A and B below.
The;< violations show that the
- licensee, despite prior notice and previous similar violations, has failed to provide an effective means of verification of operability of important safety systems as required.
To~ emphasize the need for significant improvements with respect to the adequacy of procedures and verification of safety system operability, the Nuclear Regula-tory Commission proposes to impose civil penalties in the cumulative amount of
- One Hundred and Eighty Thousand Dollars for this matter.
In accordance with the
~ NRC Enforcement Policy, 47 FR 9987 (10 CFR Part 2, Appendix C) (March 9, 1982),
and pursuant to Section 234 of the Atomic Energy Act of-1954, as amended ("Act"),
42 U.S.C. 2282, PL 96-295, and 10 CFR 2.205, the particular violations and associated civil penalties are set forth below:
A.
Technical-Specification 3.6.1 requires that containment integrity be main-tained whenever reactor coolant system (RCS) pressure is greater than 300 psig and temperature is greater than 200 F.
Technical Specification 1.7.a defines' containment integrity, as related to the emergency hatch, to exist only when both doors are closed and sealed except during. refueling or personnel passage through the hatch.
1.
-Contrary.to the above, on March 17, 1983, a test valve was open on Unit 3 emergency hatch,-effectively defeating the closing and seal of the outer hatch door. The unit was operating with. reactor coolant pressure at greater than 500 psig and temperature greater than 200*F.
This is a Severity Level III violation (Supplement I)
(Civil-Penalty - 560,000) 2.
Contrary to the above, on March 21,11933, the inner door on Unit 1 emergency hatch was open. The unit was operating with reactor coolant system pressure greater'than 300 psig and temperature' greater,than 200 F.
This is a Severity Level III violation (Supplement I)
(Civil Penalty.- '560,000).
il
4 B.
The licensee was issued an immediately effective order confirming licensee commitments on post-TMI related issues dated July 10, 1981. This Order
- stated, "It is hereby ordered effective immediately that the licensee shall comply with the following conditions:
The licensee shall satisfy the specific requirements described in the attachment to this order (as appropriate to the licensee's facilities) as early as practicable but. no later than 30 days after the effective date of the Order."
The Order referred to and incorporated the licensee's submittal dated December 15, 1980, which committed to complete each of the actions specified in the Attachment to the Order. Attachment Item I.C.6, Correct Performance of Operating Activities, states that procedures would be reviewed and revised to verify correct performance of operating activities by January 1, 1981.
Contrary to the above, after January 1,1981, procedures had not been reviewed and revised to assure the correct performance of operating activities as evidenced by the violations of required containment integrity on Oconee Units 1 and 3 as described in Item A of this notice.
This.is a Severity Level III Violation (Supplement I)
(Civil Penalty - 560,000).
Pursuant to the provisions of 1C CFR 2.201, Duke Power Company is hereby required to submit to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and a copy to the Regional
~
Administrator, U.S. Nuclear Regulatory Commission, Region II, within 30 days of the date of this Notice, a written statement or explanation including for each alleged violation:
(1) admission or denial of the alleged violation; (2) the
,~
reasons for the violation, if admitted; (3) the corrective steps which have been taken and the results achieved; (4) the corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved.
Consideration may be given to extending the response-time for good cause shown.
Under the authority of Section 182 of the Act, 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
Within the same time as provided for the response required above under 10 CFR 2.201, Duke Power Company may pay the civil penalties in the cumulative amount of
$180,000 or may protest imposition of the c1vil penalties in whole.or in part by a writt en answer.
Should Duke Power Company fail to answer within the time specified, the Director,- Office of Inspection and Enforcement, will issue an Order imposing the civil penalties proposed above.
Should Duke Power Company elect to file an answer in accordance with 10 CFR 2.205 protesting
- Notice, in the civil penalties, such answer may:
(1) deny the violations. listed in the
JUN 021983 Notice of Violation 4
whole or in part; (2) demonstrate extenuating circumstances; (3) show error in this Notice; or (4) show other reasons why the penalties should not be imposed. In addition to protesting the civil penalties, in whole or in part, such answer may request remission or mitigation of the penalites. In requesting mitigation of the proposed penalties, the five factors contained in Section IV(B) of 10 CFR Part 2, Appendix C should be addressed. Any written answer in accordance with 10 CFR 2.205 should be set forth separately from the statement or explanation in reply pursuant to 10 CFR 2.201, but may incorporate statements or expianations by specific reference (e.g., citing page and paragraph numbers) to avoid repetition. Duke Power Company's attention is directed to the other provisions of 10 CFR 2.205, regarding the procedures for imposing a civil penalty.
Upon failure to pay any civil penaity due, which has been subsequently determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attorney General, and the penalty unless compromised, remitted, or mitigated, may be collected by civil action pursuant to Section 234c of the Act, 42 U.S.C. 2282.
FOR THE NUCLEAR REGULATORY COMMISSION James P. O'Reilly Regional Administrator Dated in Atlanta, Georgia this[{dayofJune1983
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