Similar Documents at Ginna |
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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20217L9861997-08-15015 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Vehicle Barriers Deployed Outside Outer Isolation Zone Would Not Prevent Malicious Use of Vehicle to Gain Entry to Protected Areas ML20132H0791996-12-13013 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Prior to 960803, Measures Not Established to Assure That Certain Conditions Adverse to Quality Not Promptly Identified & Corrected ML20246E2561989-04-28028 April 1989 Notice of Violation from Insp on 890313-17.Violation Noted: Design Criteria & Safety Analysis for PORV Block Valve Replacement,To Be Performed During 1989 Outage,Did Not Address Operability Qualification of Replacement Valves ML20054K9011982-06-16016 June 1982 Notice of Violation from Insp on 820501-31 1997-08-15
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000244/19990071999-09-20020 September 1999 Insp Rept 50-244/99-07 on 990719-23 & 0802-06.NCVs Noted. Major Areas Inspected:Maint & Engineering ML20217L9861997-08-15015 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Vehicle Barriers Deployed Outside Outer Isolation Zone Would Not Prevent Malicious Use of Vehicle to Gain Entry to Protected Areas IR 05000244/19970081997-07-16016 July 1997 Insp Rept 50-244/97-08 on 970527-30.Apparent Violations Being Considered for Escalated Ea.Major Areas Inspected: Conduct of Security & Safeguards Activities,Status of Security Facilities & PA Barriers & Vehicles Barrier Sys ML20132H0791996-12-13013 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Prior to 960803, Measures Not Established to Assure That Certain Conditions Adverse to Quality Not Promptly Identified & Corrected IR 05000244/19900211990-10-24024 October 1990 Physical Security Insp Rept 50-244/90-21 on 900910-14. No Violations Noted.Major Areas Inspected:Onsite follow-up of Previously Indentified Items,Mgt Support & Security Program Plans & Audits ML20246E2561989-04-28028 April 1989 Notice of Violation from Insp on 890313-17.Violation Noted: Design Criteria & Safety Analysis for PORV Block Valve Replacement,To Be Performed During 1989 Outage,Did Not Address Operability Qualification of Replacement Valves PNO-I-88-057A, identified Radioactive Contamination on Contractor Exiting Facility Protected Area.Contamination Also Identified in Individual Home & co-worker Car.Caused by Inadequate Monitoring Before Leaving Restricted Area1988-06-22022 June 1988 PNO-I-88-057A:identified Radioactive Contamination on Contractor Exiting Facility Protected Area.Contamination Also Identified in Individual Home & co-worker Car.Caused by Inadequate Monitoring Before Leaving Restricted Area IR 05000244/19870281988-01-25025 January 1988 Partially Withheld Physical Security Insp Rept 50-244/87-28 on 871116-20 (Ref 10CFR2.790 & 73.21).No Violations Noted. Major Areas Inspected:Plan & Implementing Procedures, Organization,Program Audits & Records & Repts IR 05000244/19870221987-11-24024 November 1987 Exam Rept 50-244/87-22OL During Week of 871005.Exam Results: Six Senior Reactor Operators & Four Reactor Operators Passed All Exams & One Reactor Operator Failed Written Exam IR 05000244/19870211987-09-29029 September 1987 Insp Rept 50-244/87-21 on 870831-0904.No Violations Noted. Major Areas Inspected:Review of Licensee Action on Previously NRC Identified Concerns,Followup of Generic Ltr 83-28,Item 4.1 & Qa/Qc Interfaces IR 05000244/19870191987-08-28028 August 1987 Insp Rept 50-244/87-19 on 870727-31.Violation Noted.Major Areas Inspected:Occupational Radiation Protection Program, Including Status of Previously Identified Items,Organization & Mgt Controls,Audits & External Exposure Control ML20212R5131987-04-20020 April 1987 PNS-i-87-006:on 870420,bomb Threat Received by Monroe County Police Emergency Notification Dispatcher.Security Personnel Posted on Plant Access Roads to Verify Id Prior to Access to Plant.State & Local Police Patrolled Area IR 05000244/19870061987-03-24024 March 1987 Insp Rept 50-244/87-06 on 870224-27.No Violations Noted. Major Areas Inspected:Activities Associated W/Steam Generator Exams & Maint,Inservice Insp & Licensee Actions on Previous Insp Findings IR 05000244/19870051987-03-24024 March 1987 Insp Rept 50-244/87-05 on 870224-27.No Violations Noted. Major Areas Inspected:Status of Previously Identified Items, Organization & Mgt Controls,Training & Qualification of New Personnel,External & Internal Exposure Control & ALARA IR 05000244/19870021987-02-18018 February 1987 Insp Rept 50-244/87-02 on 870104-0207.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Findings, Review of Plant Operations,Operational Safety Verification, Surveillance Testing,Plant Maint & LERs IR 05000244/19870011987-02-0404 February 1987 Insp Rept 50-244/87-01 on 870105-09.No Violations Noted. Major Areas Inspected:External Exposure Control,Internal Exposure Control,Control of Radioactive Matl & Contamination & Surveys & Monitoring ML20212M1901987-01-16016 January 1987 Safety Insp Rept 50-244/86-22 on 861215-19.No Violations or Deviations Noted.Major Areas Inspected:Licensee Response to Previous Insp Findings & Effectiveness of Licensee Correction Action Program IR 05000244/19860211987-01-12012 January 1987 Insp Rept 50-244/86-21 on 861109-870103.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Findings, Review of Plant Operations,Operational Safety Verification, Surveillance Testing & Plant Maint IR 05000244/19860121986-10-0909 October 1986 Emergency Preparedness Insp Rept 50-244/86-12 on 860826-29. Violation Noted Re Ability to Fully Staff & Augment Emergency Response Organization in Timely Manner IR 05000244/19860131986-10-0202 October 1986 Insp Rept 50-244/86-13 on 860909-11.No Violation Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise Performed on 860910 PNO-I-86-058, on 860729,reactor Manually Tripped from 100% Power Due to Break in Drain Line from Main Steam Reheater 2A to Feedwater Heater 5A.Cause Under Investigation.Licensee Actions Under Review1986-07-29029 July 1986 PNO-I-86-058:on 860729,reactor Manually Tripped from 100% Power Due to Break in Drain Line from Main Steam Reheater 2A to Feedwater Heater 5A.Cause Under Investigation.Licensee Actions Under Review ML20140B0401986-01-0808 January 1986 Exam Rept 50-244/OL-85-23 on 851111-15.Exam Results:All Candidates Passed Both Written & Oral Portions of Exam PNO-I-85-085A, on 851106,licensee Secured from Unusual Event Declared Due to Automatic Actuation of Cable Tunnel Deluge Sys.Caused by Faulty Printed Circuit Card.Ground on Nonvital Bus Damaged by Deluge Sys Corrected1985-11-0707 November 1985 PNO-I-85-085A:on 851106,licensee Secured from Unusual Event Declared Due to Automatic Actuation of Cable Tunnel Deluge Sys.Caused by Faulty Printed Circuit Card.Ground on Nonvital Bus Damaged by Deluge Sys Corrected PNO-I-85-085, on 851106,fire Protection Deluge Sys in Cable Tunnel Automatically Actuated.Smoke Smelled at Scene.Sys Isolated After 10 Minutes of Operation.Visual Insp of Cable Tunnel Revealed No Apparent Damage1985-11-0606 November 1985 PNO-I-85-085:on 851106,fire Protection Deluge Sys in Cable Tunnel Automatically Actuated.Smoke Smelled at Scene.Sys Isolated After 10 Minutes of Operation.Visual Insp of Cable Tunnel Revealed No Apparent Damage IR 05000244/19850201985-10-22022 October 1985 Insp Rept 50-244/85-20 on 850925-27.No Violation Noted.Major Areas Inspected:Emergency Preparedness & Annual Emergency Exercise Performed on 850926 ML20128L0521985-07-18018 July 1985 PNS-I-85-010:on 850718,safeguards Contingency Plan Drill Will Be Held.Exercise Will Test Command/Control, Communications & Response Force Mobilization Developed by State of Ny Emergency Mgt Agency IR 05000244/19850111985-07-11011 July 1985 Exam Rept 50-244/85-11 on 850624.Exam Results:All Candidates Passed.No Generic Deficiencies Noted IR 05000244/19820131982-07-20020 July 1982 IE Insp Rept 50-244/82-13 on 820628-0701.No Noncompliance Noted.Major Areas Inspected:Followup on IE Circular 80-21, Verification of Core load,post-refueling Startup Testing & Control Rod Worth Measurements & Predications IR 05000244/19820111982-06-18018 June 1982 IE Insp Rept 50-244/82-11 on 820517-19.No Noncompliance Noted.Major Areas Inspected:Environ Monitoring Programs for Operation Including Mgt Controls & QC of Analytical Measurements ML20054K9011982-06-16016 June 1982 Notice of Violation from Insp on 820501-31 IR 05000244/19820101982-06-15015 June 1982 IE Insp Rept 50-244/82-10 on 820501-31.Noncompliance Noted: Failure to Properly Implement & Track QA Surveillance Repts ML20236L5201979-10-24024 October 1979 PNS-I-79-005:on 791023,unidentified Male Called Rochester Gas & Electric Corp Switchboard in New York,Stating That Bomb Planted in Ginna Plant in Retaliation for Attempted Murder on Highway 490 ML20249A0931978-01-25025 January 1978 PNO-78-013:on 770125,unit Was Shutdown from 100% Power Due to Leak in One Steam Generator.Licensee Made Decision to Shutdown for Repairs,Although Leak Rate Did Not Exceed TS Limit.State of Ny Informed ML20207G5861977-11-17017 November 1977 PNO-77-201:on 771116,urgent Failure Alarm Occurred on Rod Control Sys,Indicating Logic Problem in CRD Sys.Reactor Shutdown from 100 Percent Power to Cold Shutdown Condition commenced.In-motion of Control Rods Determined Operable ML20236E9101977-08-18018 August 1977 PNS-77-032:on 770816,canoe Capsized W/Two Men Aboard About 100 Feet Offshore Near Plant Discharge Canal to Lake Ontario.One Man Swam Ashore & Climbed Over Security Fence & Called for Help Over Loudspeaker.Other Man Was Rescued ML20151X7111977-07-0606 July 1977 PNO-77-121:on 770705,unit Was Shutdown from 100% Power,Due to Identified Tube Leakage from RCS to Secondary Sys in One of Two Sgs.Outage Duration Expected to Be Two Weeks.Media Interest Expected ML20249B0281976-01-29029 January 1976 PNO-76-018:on 760129,reactor Shutdown Due to Increase Vibration on Two Low Pressure Turbine Bearings.Extent of Problem Not Known.Exam of Bearings Will Be Accomplished During Weekend After Turbine Disassembly ML20236W7901975-12-30030 December 1975 PN-75-157:on 751230,unscheduled Shutdown Completed Due to Increasing Tube Leakage from B Sg.Load Reduction Initiated.Duration of Shutdown Expected to Be Approximately Six Days.State of New York Kept Informed ML20236U2371975-06-18018 June 1975 PN75-037:on 750617,turbine Was Manually Tripped as Result of Excessive Feedwater Piping Vibration.Visual Insp Revealed No Apparent Damage to Pipe Restraints or Containment Penetrations.Some Instrument Sensing Lines Inoperable 1999-09-20
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NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF civil PENALTY Rochester Gas and Electric Cnrporation Docket No. 50-244 Ginna Nuclear Power Station License No. DPR-18. .
Rochester, New York EA 96-282 During an NRC inspection conducted from July 22-26,1996, and August 6-9,1996, for which exit meetings were conducted on August 9,1996, and October 4,1996, violations of NRC requirements were 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 particu-lar violations and associated civil penalty are set forth below:
A. 10 CFR Part 50, Appendix B, Criterion ill, " Design Control," requires, in part, that measures ahall be established to assure that applicable regulatory requirements and design basis are correctly translated into specifications, drawings, procedures, and instructions, and shall provide for verifying and checking the adequacy of design, such as by the performance of design reviews, by alternate or simplified calculational methods, or by performance of a suitable testing program.
RG&E Engineering Procedure 3-P-121, Design Criteria, Revision 0, dated November 2,1994, states, in part, in Section 3.2, that "... design inputs shall be specified and approved on a timely basis and to the level of detail necessary to permit the design activity to be carried out in a correct manner and to provide a consistent basis for making design decisions, accomplishing design verification measures, and evaluating design changes."
Contrary to the above, from June 28,1995 (the date by which that the licenses committed to complete its Generic Letter 89-10 program), until August 3,1996, design inputs for the Residual Heat Removal (RHR) Core Deluge Motor Operated Valves (MOVs) 852A and 852B were not adequately specified and approved to the level of detail necessary to permit the design activity for these valves to be carried out in a correct manner, and to provide a consistent basis for making design decisions and accomplishing design verification measures. The thrust requirements for the RHR core deluge valves, used to evaluate the performance of the MOVs, were not adequately validated; specifically, an outdated and unjustified 0.3 valve factor was assumed. This valve factor was unjustified because it was lower than valve factors issued for similar MOVs at Ginna and in the industry. As a result, the licensee did not adequately assure that the valves would operate under design basis conditions.
9612270131 961213 PDR ADOCK 05000244 G PDR l
l Notice of Violation B. 10 CFR Part 50, Appendix B, Criterion XVI, " Corrective Action," requires that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment.
and nonconformances are promptly identified and corrected, in the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition. The identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management.
Contrary to the above, prior to August 3,1996, measures were not established to assure that certain conditions adverse to quality were promptly identified and corrected. Specifically,
- 1. During an NRC inspection in March-April 1995, prior to the licensee's completion of its Generic Letter 89-10 program, the NRC informed the licensee that the design inputs for core deluge valves 852A and 8528 needed to be justified because the assumed valve factor of 0.3 was unusually low and had no recognized technical basis when compared to similar valves in the industry and at Ginna. Although the use of this valve factor constituted a significant condition adverse to quality, the licensee had I not taken measures to assure, prior to the time of its shutdown of the i
reactor in August 1996, that the 0.3 valve factor accurately predicted l performance of the valves.
- 2. When statically retesting the core deluge valves after maintenance during the Spring 1996 refuel outage, the licensee identified that the valves may not open when subject to degraded voltage, at 69% and 70% of nominal bus ;
voltage respectively. Although the licensee had previously determined that I the more limiting case (MOV 852A) would require 20,943 lbs of thrust to open, assuming a valve factor of 0.30, the licensee estimated that MOV 852A would develop only 11,845 lbs of thrust and documented these findings in its Action Reports (ARs) 96-0320 and 96-0338. However, despite this discrepancy, the licensee did not take appropriate corrective action; rather the licensee considered both RHR core deluge valves to be operable based on a single 1993 " stall test" performed on MOV 852A at 100% voltage. The stall test did not provide adequate assurance that the RHR core deluge valves could perform their safety function.
shese violations are categorized in the aggregate as a Severity Level lli problem (Supplement 1).
Civil Penalty - $100,000 Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation (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 should
e Notice of Violation be clearly marked as a " Reply to a Notice of Violation" and should include for each alleged violation: (1) admission or denial of the alleged violation, (2) the reasons for the violation if admitted, and if denied, the reasons why, (3) the corrective steps that have been taken and the results 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 penalty 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 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 fail 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 (s) 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 mitigation of the penalty.
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 2.205 should be set forth separately from the statement or explanation in reply pursuant to _10 CFR 2.201, but may incorporate parts of the 10 CFR 2.201 reply by specific reference (e.g., citing page and paragraph numbers) to avoid repetition. The attention of the Licensee is directed to the other provisions of 10 CFR 2.205, regarding the procedure for imposing a civil penalty.
Upon failure to pay any civil penalty due that 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 234c of the Act,42 U.S.C. 2282c.
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: James Lieberman, Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, One White Flint North,11555 Rockville Pike, Rockville, MD 20852-2738, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region I, and a copy to the NRC Senior Resident inspector at the facility that is the subject of this Notice.
. i Notice of Violation 4 ,
i Because your response will be placed in the NRC Public Document Room (PDR), to the l extent possible, it should not include any personal privacy, proprietary, or safeguards ;
information so that it can be placed in the PDR. If redactions are required, a proprietary !
version containing brackets placed around the proprietary, privacy, and/or safeguards information should be submitted. In addition, a non-proprietary version with the .
information in the brackets redacted should be submitted to be placed in the PDR.
Dated at King of Prussia, Pennsylvania :
this/J" day of December 1996 l, I
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