|
---|
Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20237D1381998-08-19019 August 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 971024 & 980528,licensee Failed to Assure That Design Change in Oct 1997 Subject to Design Control Measures ML20236M6011998-07-0606 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:On 970808,double Verifications of Steps 3.4.1 & 3.5.2 of PT-W1,which Involved Checks of DG Compressor,Not Performed,But Records Created ML20217H3531997-10-0707 October 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:Con Edison Did Not Operate within Restrictions of TS Figure 3.1.A-3,in That Pressurizer Level Was Greater than 30% ML20217R3361997-08-19019 August 1997 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Measures Were Not Established to Assure That Applicable Regulatory Requirements & Design Basis,Were Correctly Translated Into EOPs ML20247A1051989-05-0909 May 1989 Notice of Violation from Insp on 890228-0417.Violation Noted:Technicians Failed to Secure Pump When Vibration Level Observed on Pump Motor Exceeded Procedural Limit of 3.5 Mils ML20247A0681989-05-0505 May 1989 Notice of Violation from Insp on 890314-25.Violation Noted: Workers Allowed to Enter High Radiation Areas W/O Being Provided or Accompanied by Individual Authorized in Radiation Protection Procedures ML20154Q7231988-09-21021 September 1988 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violations Noted:Qualification of Containment high-range Radiation Monitors Cable Connector Assembly Deficient ML20207S3401987-03-11011 March 1987 Notice of Violation from Insp on 870127-29 ML20212J3921987-03-0202 March 1987 Notice of Violation from Insp on 870106-0202 ML20210V6021987-02-10010 February 1987 Notice of Violation from Insp on 861215-19 ML20213A4821987-01-22022 January 1987 Notice of Violation from Insp on 861116-870105 ML20212K3521987-01-20020 January 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Based on 860811-0922 Insp.Violation Noted:Reactor Heated Up Above 200 F W/Both Recirculation & Containment Spray Pumps Inoperable ML20207N1691987-01-0505 January 1987 Notice of Violation from Insp on 861014-1121 ML20203D7841986-04-16016 April 1986 Notice of Violation from Insp on 860106-10 ML20055B6381982-07-0202 July 1982 Notice of Violation from Insp on 820601-04 ML20055B5681982-07-0202 July 1982 Notice of Violation from Insp on 820524-28 ML20058B8581982-06-29029 June 1982 Notice of Violation from Insp on 820516-0615 ML20054L0451982-06-16016 June 1982 Notice of Violation from Insp on 820501-31 1998-08-19
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000003/19980191999-03-0909 March 1999 Insp Rept 50-003/98-19 on 981130-990222.No Violation Noted. Major Areas Inspected:Review of Facility Mgt & Control ML20237D1381998-08-19019 August 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 971024 & 980528,licensee Failed to Assure That Design Change in Oct 1997 Subject to Design Control Measures ML20236M6011998-07-0606 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:On 970808,double Verifications of Steps 3.4.1 & 3.5.2 of PT-W1,which Involved Checks of DG Compressor,Not Performed,But Records Created ML20154Q1951998-01-22022 January 1998 Partially Deleted Investigation Rept 1-97-038.Noncompliance Noted.Major Areas Investigated:Falsification of Surveillance Test Records by Nuclear Production Technician ML20217H3531997-10-0707 October 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:Con Edison Did Not Operate within Restrictions of TS Figure 3.1.A-3,in That Pressurizer Level Was Greater than 30% PNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997 PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR ML20217R3361997-08-19019 August 1997 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Measures Were Not Established to Assure That Applicable Regulatory Requirements & Design Basis,Were Correctly Translated Into EOPs IR 05000247/19930261993-11-23023 November 1993 Insp Rept 50-247/93-26 on 931108-12.No Violations Noted. Major Areas Inspected:Mgt Support Plans,Protected & Vital Area Physical Barriers,Detection & Assessment Aids,Protected & Vital Area Access Control of Personnel IR 05000286/19930161993-10-19019 October 1993 Insp Rept 50-286/93-16 on 930802-06 & 0920-24.No Violations Noted.Major Areas Inspected:Isi Program,Procedures,Scope of ISI Work for Outage,Current Insp Plan & Testing Procedures IR 05000286/19930211993-09-17017 September 1993 Insp Rept 50-286/93-21 on 930830-0902.No Violations Noted. Major Areas Inspected:Mgt Support & Audits,Protected & Vital Area Physical Barriers,Detection & Assessment Aids & Protected Vital Area Access Control of Personnel PNO-I-90-094, on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured1990-10-17017 October 1990 PNO-I-90-094:on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured PNO-I-90-077, on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed1990-09-0707 September 1990 PNO-I-90-077:on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed PNO-I-90-065, on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days1990-08-15015 August 1990 PNO-I-90-065:on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days PNO-I-90-063, on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced1990-08-0909 August 1990 PNO-I-90-063:on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced ML20247K5281989-09-14014 September 1989 EN-89-086:on 890919,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued to Licensee Based on Security Violations Re Access Control & Illumination in Protected Area ML20247B9531989-08-24024 August 1989 Enforcement Conference Rept 50-286/89-15 on 890808.Major Areas Discussed:Security Program During Spring 1989 Plant Outage IR 05000286/19890151989-07-24024 July 1989 Partially Withheld Physical Security Insp Rept 50-286/89-15 on 890605-07 (Ref 10CFR73.21).Violations Noted Re Physical Barriers,Vital Areas & Access Controls.Major Areas Inspected:Detection & Assessment Aids & Alarm Stations ML20245G2181989-06-21021 June 1989 PNS-I-89-010:on 890621,Dept of Investigation in New York City Received Call Threatening Destruction of Plant & Ref 1977 Incident Where Damage Inflicted on Plant.Bomb Threat Contingency Procedures Implemented & Security Maintained IR 05000286/19890031989-06-13013 June 1989 Enforcement Conference Rept 50-286/89-03 on 890428 in King of Prussia,Pa Re Findings of Insp Repts 50-286/89-03 & 50-286/88-22.Violations Noted.Areas Discussed:Security Program During Current Outage ML20247A1051989-05-0909 May 1989 Notice of Violation from Insp on 890228-0417.Violation Noted:Technicians Failed to Secure Pump When Vibration Level Observed on Pump Motor Exceeded Procedural Limit of 3.5 Mils ML20247A0681989-05-0505 May 1989 Notice of Violation from Insp on 890314-25.Violation Noted: Workers Allowed to Enter High Radiation Areas W/O Being Provided or Accompanied by Individual Authorized in Radiation Protection Procedures IR 05000286/19890051989-04-11011 April 1989 Partially Withheld Physical Security Insp Rept 50-286/89-05 on 890227-0303 (Ref 10CFR73.21).Violations & Noncompliances Noted.Major Areas inspected:non-routine Event,Mgt Support, Security Program Plans & Audits & Physical Barriers ML20154Q7231988-09-21021 September 1988 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violations Noted:Qualification of Containment high-range Radiation Monitors Cable Connector Assembly Deficient PNO-I-88-065, on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals1988-06-20020 June 1988 PNO-I-88-065:on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals IR 05000247/19880121988-05-24024 May 1988 Physical Security Insp Rept 50-247/88-12 on 880407.No Noncompliance Noted.Major Areas Inspected:Program for Protection of Safeguards Info,Per 10CFR73.21,including Use of Required Storage Repositories & Handling Procedures IR 05000286/19880061988-05-19019 May 1988 Physical Security Insp Rept 50-286/88-06 on 880412-14.No Noncompliance Noted.Major Areas Inspected:Plan & Implementing Procedures,Organization,Program Audits,Testing & Maint,Physical Barriers & Security Sys Power Supply PNO-I-88-003, on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 8801051988-01-0707 January 1988 PNO-I-88-003:on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 880105 IR 05000286/19870131987-08-21021 August 1987 Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714. Rept Describes Activities & Findings Associated W/First Portion of Team Insp Re Outage Design Insp IR 05000247/19870141987-06-0808 June 1987 Emergency Preparedness Insp Rept 50-247/87-14 on 870512-14. No Violations Identified.Major Areas Inspected:Licensee Annual Emergency Exercise Performed on 870513 IR 05000286/19870111987-05-14014 May 1987 Insp Rept 50-286/87-11 on 870420-24.No Violations Noted. Major Areas Inspected:Radiological Effluents Control Program,Mgt Controls,Air Cleaning Sys,Program Implementation & Previously Identified Items IR 05000286/19870091987-05-11011 May 1987 Insp Rept 50-286/87-09 on 870402-03.No Violations Noted. Major Areas Inspected:Nuclear Matl Control & Accounting, Including Organization & Operating,Shipping & Receiving, Storage & Internal Control & Records & Repts PNO-I-87-039, on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays1987-05-0101 May 1987 PNO-I-87-039:on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays IR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions PNO-I-87-025, on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days1987-03-26026 March 1987 PNO-I-87-025:on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days IR 05000286/19870021987-03-18018 March 1987 Insp Rept 50-286/87-02 on 870127-29.No Violations Noted. Major Areas Inspected:Dosimetry Staffing & Training, Facilities & Equipment Procedures,Dose Assessment QA & Documentation & Recordkeeping IR 05000247/19870041987-03-16016 March 1987 Insp Rept 50-247/87-04 on 870203-0302.No Violations Noted. Major Areas Inspected:Routine Daily Insps,As Well as Unscheduled Backshift Insps of Onsite Activities,Operations, Maint,Surveillance & Review of Periodic & Special Repts ML20207S3401987-03-11011 March 1987 Notice of Violation from Insp on 870127-29 IR 05000247/19870021987-03-10010 March 1987 Insp Rept 50-247/87-02 on 870127-29.Violation Noted:Failure to Include Acceptance Limits for Battery Electrolyte Temp & Failure to Ensure Battery Room Temp within Normal Bounds ML20207R1791987-03-0606 March 1987 PNS-I-87-003:on 870306,security Officer at Offsite Training Ctr in Toddville,Ny Received Bomb Threat by Telephone.Search of Site Produced Negative Results.Local Law Enforcement Agencies Responded.Security Measures Heightened IR 05000286/19870011987-03-0505 March 1987 Insp Rept 50-286/87-01 on 870106-0217.Major Areas Inspected: Plant Operations Including Shift Logs & Records,Reactor Trips/Engineered Safeguards Actuation,Surveillance,Maint & Followup to Generic Ltr 83-28 & TMI Action Items ML20212J3921987-03-0202 March 1987 Notice of Violation from Insp on 870106-0202 IR 05000247/19870011987-02-26026 February 1987 Insp Rept 50-247/87-01 on 870106-0202.Violation Noted:No post-maint (Mod) Test Performed After Changing Location of Emergency Diesel Generator Svc Water Flow Indication & Control Instruments PNO-I-87-010, on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown1987-02-12012 February 1987 PNO-I-87-010:on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown ML20210V6021987-02-10010 February 1987 Notice of Violation from Insp on 861215-19 IR 05000286/19860241987-02-0909 February 1987 Insp Rept 50-286/86-24 on 861215-19.Violation Noted:Raychem Splices Identified W/Less than Required 2-inch Overlap & Bending Radii Less than Allowed IR 05000247/19860331987-01-27027 January 1987 Radiation Protection Insp Rept 50-247/86-33 on 861215-19.No Violations Noted.Major Areas Inspected:Alara,Internal Exposure Control & External Exposure Control ML20213A4821987-01-22022 January 1987 Notice of Violation from Insp on 861116-870105 IR 05000247/19861361987-01-21021 January 1987 Meeting Rept 50-247/86-136 on 861209.Major Items Discussed: Plans for Integrated Assessment of Auxiliary Feedwater Sys. Mods Being Considered Include Providing Direct Indication of Overspeed Trip Mechanism Status in Control Room ML20212K3521987-01-20020 January 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Based on 860811-0922 Insp.Violation Noted:Reactor Heated Up Above 200 F W/Both Recirculation & Containment Spray Pumps Inoperable IR 05000286/19860231987-01-15015 January 1987 Onsite Regular & Backshift Insp Rept 50-286/86-23 on 861118- 870105.Violation Noted:Failure to Follow Administrative Procedures AP-6 & AP-25-3 Re Work Requests & Matl Substitutions,Respectively 1999-03-09
[Table view] |
Text
- - - ---- - - -- - - - --
ENCLOSURE NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF civil PENALTY New York Power Authority Docket No. 50 286 Indian Point Unit 3 License No. DPR-64 EA 97 294
/
During an NRC inspection conducted between April 7 and May 1,1997, for which exit meetings were held on May 1,1997, and June 10,1997, a violation of NRC requirements was identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the Nuclear Regulatory Commission proposes to impose a civil penalty pursuant to Section 234 of the Atomic Energy Act of 1954, as amended (Act),
42 U.S.C. 2282, and 10 CFR 2.205. The particular violation and associated civil penalty are set forth below:
10 CFR Part 50, Appendix B, Criterion lil, requires that measures shall be established to assure that applicable regulatory requirements and the design basis, are correctly translated into specifications, drawings, procedure , and instructions.
Contrary to the above, prior to May 20,1997, measures were not established to assure that applicable regulatory requirements and the dulgn basis, were correctly translated into Emergency Operating Procedures (EOPs), as evidenced by the following examples:
- 1. Design basis information for the component cooling water heat exchangers' service water outlet valve position was not correctly translated into EOP ES 1.3, Revision 10, Transfer to Cold Leg Recirculation. The EOP did not provide instruction for operators to re-position these valves (from their normally throttled position) at the beginning of the recirculation phase of a postulated design basis accident. Under certain conditions, failure to re position the valves, may have caused the loss of function of the component cooling water and other supported systems.
- 2. Design basis information for protection of the recirculation pumps from runout was not correctly translated into EOP ES-1.3, Revision 10, Step 18(b). The EOP did not provide appropriate instructions to reduce flow to less than 3000 gpm to assure that net positive suction head requirements are satisfied when only one recirculation pump is operating.
- 3. Design basis information for isolating nonsafety-related equipment was not correctly translated into EOP ES-1.3, Revision 10, Step 60(a), which directed operators to isolate component cooling water flow to the non-regenerative heat exchanger using air operated temperature control valve AC-TCV-130. This procedura step wasinadequate because valve AC TCV-130 could f ailopen, due to a non safety-related source of supply air, and divert cooling water flow from other safety-related components. (01013) 9709050070 970eg9 DR ADOCK 05000286 PDR l
Enclosure 2 This violation is classified at Severity Level 111. (Supplement 1).
Civil Penalty - $55,000.
Pursuant to the provisions of 10 CFR 2.201, New York Power Authority (Licensee) is hereby required to submit a written statement or explanation to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, within 30 days of the date of this Notice of Violation and Proposed imposition of Civil Penalty (Notice). This reply sho6 v i clearly marked as a
" Reply to a Notice of Violation" and should include for each alleget g :ation: (1) admission or derial of the alleged violation, (2) the reasons for the violation if Mmitted, and if denied, the reasons why, (3) the corrective steps that have been taken and the mults achieved, (4) the corrective steps that will be taken to avoid further violations, and (5) the date when full compliance will be achieved. if an adequate reply is not received within the time specified in this Notice, an Order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. 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, the Licensee may pay the civil penasty by letter addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, with a check, draft, money order, or electronic transfer payable to the Treasurer of the United States in the amount of the civil penalty proposed above, or the cumulative amount of the civil penalties if more than one civil penalty is proposed, or may protest imposition of the civil penalty, in whole or in part, by a written answer addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission. Should the Licensee f all to answer within the time specified, an order imposing the civil penalty will be issued. Should the Licensee elect to file an answer in accordance with 10 CFR 2.205 protesting the civil penalty, in whole or in part, such answer should be clearly marked as an " Answer to a Notice of Violation" and may: (1) deny the violation listed in this Notice, in whole or in part, (2) demonstrate extenuating circumstances, (3) show error in this Notice, or (4) show other reasons why the penalty should not be imposed. in addition to protesting the civil penalty, in whole or in part, such answer may request remission or j mitigation of the penalty.
l- In requesting mitigation of the proposed penalty, the factors addressed in Section VI.B.2 of the Enforcement Policy should be addressed. Any written answer in accordance with 10 CFR l 2.205 should be set forth separately from the statement or explanation in reply pursuant to l
10 CFR 2.201, but may incorporate parts of the 10 CFR 2.201 reply by specific reference l to.g., citing page and paragraph numbers) to avoid repetition. The attention of the Licensee l is directed to the other provisions cf 10 CFR 2.205, regarding the procedure for imposing a j civil penalty.
Upon failure to pay any civil penalty due which subsequently has been 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 234(c) of the Act,42 U.S.C. 2282c.
l
Enclosure 3 The response noted above (Reply to Notice of Violation, letter with payment of civil penalty, and Answer to a Notice of Violation) should be addressed to: Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555 with_ a copy to the Director, Special Projects Office, NRR, U.S. Nuclear Regulatory Commission, and a copy to the NRC Resident inspector at the facility tSt is the subject of this Notice.
Because your response will be placed in the NRC Public Document Room (PDP), to the extent possible, it should not include any persor.al privacy, proprlutary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed
., copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request. withholding of such material, you muti specifically identify the portions of your response that you seek to have
. withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information), if safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at King of Prussia, PA this 19th day of August 1997 4
t l
w ..-.e