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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20154L9861998-10-13013 October 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $500,000.Violation Noted:As of 980227,licensee Had Not Provided Instructions Appropriate to Circumstances for Activity Affecting Quality ML20211J5281987-02-18018 February 1987 Notice of Violation from Insp on 861216-870126 ML20214F8181986-11-18018 November 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Violations Noted:Wire Lifted at Same Time & Crossed in Power Range Nuclear Instrument Channel NI-41 Without Use of Lifted Wire Form ML20206N4901986-08-21021 August 1986 Notice of Violation from Insp on 860707-11 ML20154R5591986-03-26026 March 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violations Noted:Unit 1 Vents,Drains & Valves Improperly Aligned & Unit 1 Procedure 1 Thp 4030 STP .202 Did Not Require Tagging Valves IR 05000521/20060241985-07-23023 July 1985 Notice of Violation from Insp on 850521-0624 IR 05000316/20050101985-06-26026 June 1985 Notice of Violation from Insp on 850316-0510 ML20058F2301982-07-15015 July 1982 Notice of Violation from Insp on 820501-0615 ML20055A6551982-06-30030 June 1982 Notice of Violation from Insp on 820315-26 ML20054L5581982-06-23023 June 1982 Notice of Violation from Insp on 820314-0430 1998-10-13
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000315/19990271999-10-15015 October 1999 Partially Deleted Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24 (Ref 10CFR73.21).Noncited Violation Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of Plant Facility. 15 IR 05000315/19980241998-12-14014 December 1998 Partially Withheld Insp Repts 50-315/98-24 & 50-316/98-24 on 981112-19 (Ref 10CFR73.71).Violations Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of DC Cook Facility ML20154L9861998-10-13013 October 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $500,000.Violation Noted:As of 980227,licensee Had Not Provided Instructions Appropriate to Circumstances for Activity Affecting Quality IR 05000315/19980111998-06-0202 June 1998 Partially Withheld Insp Repts 50-315/98-11 & 50-316/98-11 on 980504-08 (Ref 10CFR73.21(c)(2)).No Violations Noted.Major Areas Inspected:Security Program Plans,Security Program Procedures,Security Organization & Administration IR 05000315/19970191997-11-24024 November 1997 Partially Withheld Insp Repts 50-315/97-19 & 50-316/97-19 on 970929-1003 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Security Staff Knowledge & Performance,Training & Qualification Program & Organization & Administration IR 05000315/19970071997-04-25025 April 1997 Partially Withheld Insp Repts 50-315/97-07 & 50-316/97-07 on 970324-28 (Ref 10CFR73.21).No Violations.Major Areas Inspected:Review of Physical Security Program IR 05000315/19960081996-10-25025 October 1996 Insp Repts 50-315/96-08 & 50-316/96-08 on 960909-13.No Violations Noted.Major Areas Inspected:Licensee Assessment of Performance in Area of Physical Security PNO-III-94-006, on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup1994-01-25025 January 1994 PNO-III-94-006:on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup IR 05000315/19930231993-12-0202 December 1993 Partially Withheld Insp Repts 50-315/93-23 & 50-316/93-23 on 931117-19 & 22-24 (Ref 10CFR73.21).No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Physical Barriers IR 05000315/19930021993-02-0505 February 1993 Partially Withheld Insp Repts 50-315/93-02 & 50-316/93-02 on 930119-22.No Violations Noted.Major Areas Inspected:Mgt Support,Protected & Vital Area Physical Barriers,Detection Sys & Detection Aid & Protected & Vital Area Access Control PNO-III-92-045, on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor1992-09-0909 September 1992 PNO-III-92-045:on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor IR 05000315/19910111991-06-27027 June 1991 Insp Repts 50-315/91-11 & 50-316/91-11 on 910501-0614.No Violations Noted.Major Areas Inspected:Plant Operations, Reactor Trip,Maint & Surveillance,Engineering & Technical Support & Actions on Previously Identified Items IR 05000315/19900231990-11-29029 November 1990 Insp Repts 50-315/90-23 & 50-316/90-23 on 901010-901113.No Violations Noted.Major Areas Inspected:Plant Operations & Maintenance & Surveillance PNO-III-90-049, on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated1990-07-13013 July 1990 PNO-III-90-049:on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated PNO-III-90-033, on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62%1990-05-24024 May 1990 PNO-III-90-033:on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62% IR 05000315/19880181988-08-19019 August 1988 Partially Withheld Insp Repts 50-315/88-18 & 50-316/88-21 on 880705-21 (Ref 10CFR73.21).Noncompliances Noted.Major Areas Inspected:Mgt Effectiveness,Records & Repts,Testing & Maint, Power Supply,Lighting,Compensatory Measures & Vital Areas IR 05000315/19870421987-12-30030 December 1987 Partially Withheld Insp Repts 50-315/87-42 & 50-316/87-42 on 871207-10 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Personnel Training & Qualifications,Safeguards Contingency Plan & Compensatory Measures ML20235W2421987-10-0909 October 1987 Exam Repts 50-315/OL-87-02 & 50-316/OL-87-02 on 870804-07. Exam results:3 of 5 Senior Reactor Operator Candidates & 10 of 11 Reactor Operator Candidates Passed Exams ML20235E2681987-09-16016 September 1987 Exam Rept 50-315/OL-87-01 for Units 1 & 2 on 870622-24.Exam Results:Seven Senior Reactor Operators & Two Reactor Operators Failed PNO-III-87-113A, updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing1987-09-0303 September 1987 PNO-III-87-113A:updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing IR 05000206/19870141987-08-31031 August 1987 Insp Repts 50-206/87-14,50-361/87-13 & 50-362/87-15 on 870524-0704.Violations Noted.Major Areas Inspected: Operational Safety Verification,Evaluation of Plant Trips & Events,Monthly Surveillance Activities & Maint Activities PNO-III-87-100, on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination1987-07-24024 July 1987 PNO-III-87-100:on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination PNO-III-87-098, on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys1987-07-15015 July 1987 PNO-III-87-098:on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys PNO-III-87-081, on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants1987-06-11011 June 1987 PNO-III-87-081:on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants IR 05000315/19870041987-03-17017 March 1987 Safety Insp Repts 50-315/87-04 & 50-316/87-04 on 870127-0223.No Violations or Deviations Noted in Five of Six Areas Inspected.Violation Re Visitor Escort Deficiency Addressed in Insp Repts 50-315/87-08 & 50-316/87-08 IR 05000315/19870081987-03-16016 March 1987 Partially Withheld Insp Repts 50-315/87-08 & 50-316/87-08 on 870127-0223 (Ref 10CFR73.21).Violation Noted:Visitor Escort Deficiency ML20207R3701987-03-0909 March 1987 EN-87-015:on 870312,notice of Violation & Proposed Imposition of Civil Penalties in Amount of $50,000 Will Be Issued for License.Action Based on Violation of Tech Spec Re ECCS Subsystems PNO-III-87-032, on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented1987-03-0404 March 1987 PNO-III-87-032:on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented IR 05000315/19860381987-03-0303 March 1987 Addendum to Insp Repts 50-315/86-38 & 50-316/86-38,providing Criteria for Comparing Results of Capability Tests & Verification Measurements IR 05000315/19870061987-02-26026 February 1987 Insp Repts 50-315/87-06 & 50-316/87-06 on 870209-11.No Violations,Deficiencies or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise.Exercise Weakness Noted in Area of Protective Action Recommendations IR 05000315/19870051987-02-20020 February 1987 Insp Repts 50-315/87-05 & 50-316/87-05 on 870211-12.No Violations or Deviations Noted.Major Areas Inspected:Insp, Testing & Seal Replacement Program for Large Bore Steam Generator Snubbers ML20211J5281987-02-18018 February 1987 Notice of Violation from Insp on 861216-870126 IR 05000315/19870031987-02-18018 February 1987 Insp Repts 50-315/87-03 & 50-316/87-03 on 861216-870126. Violations Noted:Untimely Return to Svc Testing & Inappropriate Surveillance Test Acceptance Criteria IR 05000315/19860411987-01-16016 January 1987 Insp Repts 50-315/86-41 & 50-316/86-41 on 861104-1215. Apparent Violation Noted:Failure to Perform Timely post- Maint Operability Test on Valve & Subsequent Performance of Opposite Train Maint Being Tracked as Unresolved Issue ML20207P5111987-01-0606 January 1987 Exam Rept 50-315/OL-86-03 on 861202-04.Exam Results:Two Senior Reactor Operators & Two Retake Reactor Operators Passed IR 05000315/19860391986-12-0101 December 1986 Partially Withheld Physical Protection Insp Repts 50-315/86-39 & 50-316/86-39 on 861103-06 (Ref 10CFR73.21). No Violations Noted.Licensee Identified Concerns Re Personnel Access Control Program & Contingency Personnel IR 05000315/19860401986-11-28028 November 1986 Insp Repts 50-315/86-40 & 50-316/86-40 on 861103-07.No Violations,Deficiencies or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program ML20214F8181986-11-18018 November 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Violations Noted:Wire Lifted at Same Time & Crossed in Power Range Nuclear Instrument Channel NI-41 Without Use of Lifted Wire Form ML20214A3261986-11-13013 November 1986 EN-86-085:on 861118,notice of Violation & Proposed Imposition of Civil Penalties in Amount of $25,000 Issued Based on Failure of Personnel to Follow Procedures,Rendering Two of Four power-range ex-cores Inoperable PNO-III-86-130, on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization1986-11-0606 November 1986 PNO-III-86-130:on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization IR 05000315/19860321986-10-17017 October 1986 Partially Withheld Reactive Physical Security Insp Repts 50-315/86-32 & 50-316/86-32 on 860818-22 & 0908-11 (Ref 10CFR73.21).No Noncompliance Noted.Major Areas Inspected: Inadequate Maint of Safety Equipment.Details Withheld IR 05000315/19860361986-10-0101 October 1986 Insp Repts 50-315/86-36 & 50-316/86-36 on 860922-23.No Violations,Weaknesses or Deviations Noted.Major Areas Inspected:Emergency Preparedness Drill Involving Observations of Key Functions & Locations PNO-III-86-096, on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified1986-09-12012 September 1986 PNO-III-86-096:on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified PNO-III-86-094, on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 19821986-09-10010 September 1986 PNO-III-86-094:on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 1982 ML20206N4901986-08-21021 August 1986 Notice of Violation from Insp on 860707-11 IR 05000315/19860271986-08-20020 August 1986 Insp Repts 50-315/86-27 & 50-316/86-27 on 860707-11. Violation Noted:Failure to Adequately Test ESF Response Time in Unit 1 Steam Generator Water Level hi-hi Level Turbine Trip Reactor Trip Test PNO-III-86-072, on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances1986-07-23023 July 1986 PNO-III-86-072:on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances ML20206R9231986-06-30030 June 1986 Exam Rept 50-315/OLS-86-02 on 860519-22.Results of Exam:All Senior Reactor Operator Candidates & Seven Reactor Operator Candidates Passed IR 05000315/19860161986-06-25025 June 1986 Insp Repts 50-315/86-16 & 50-316/86-16 on 860609-11.No Noncompliance,Deviation or Deficiency Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000315/19860241986-06-20020 June 1986 Partially Withheld Physical Security Insp Repts 50-315/86-24 & 50-316/86-24 on 860604-05 (Ref 10CFR73.21).Noncompliance Noted:Items Not Searched or Secured as Required by Security Plan 1999-10-15
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j Appendix 1
NOTICE OF VIOLATION
- American Electric Power Service Docket No. 50-315
{ Corporation Docket No. 50-316 As a result of the inspection conducted on March 14 through April 30, 1982, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following violations were identified:
- 1. 10 CFR 50.72 requires notification of the NRC Operations Center within one hour of any accidental, unplanned, or uncontrolled radioactive release.
Contrary to the above, an unplanned, uncontrolled release occurred l on April 2, 1982, resulting in the evacuation of the Auxiliary l Building at 0723 EST. Notification of the NRC Operations Center l was not made until 1040 on April 2, 1982.
This is a Severity Level V violation (Supplement I).
i 2. Technical Specification 6.5.1.6 states in part: "The PNSRC shall be responsible for:... Review of all proposed tests and experiments that
- affect nuclear safety.,..."
I 10 CFR 50.59 states in part:(a) (1) The holder of a license authorizing i
operation of a production or utilization facility may (i) make changes in the facility as described in the safety analysis report, (ii) make j changes in the procedures as described in the safety analysis report, and (iii) conduct tests or experiments not described in the safety 4
analysis report, without prior commission approval, unless the pro-posed change, test or experiment involves a change in the technical e specifications incorporated in the license or an unreviewed safety question.
(2) A proposed change, test, or experiment shall be deemed to involve
, an unreviewed safety question (1) if the probability of occurrence or l consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be in-creased; or (ii) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or (iii) if the margin of safety as defined in the basis for any technical specification is reduced.
(b) The licensee shall also maintain records of tests and experiments carried out pursuant to paragraph (a) of this section. These records shall include a written safety evaluation which provides the bases for the determination that the change, test or experiment does not involve an unreviewed safety question, i
k 8207080238 820623 i PDR ADOCK 05000315 G PDR ,
{
Appendix 2 Contrary to the above, the licensee conducted tests and/or experiments on the Unit 2 CVCS Boron .nake up system from on or about April 19, 1982 through April 22, :932 when attempting to locate a recirculation flow blockage. These efforts were conducted without written procedures and without a written safety evaluation while the unit operated at 100*. power.
This is a Severity Level IV violation (Supplement I).
- 3. Technical Specification 6.8.1 states in part: " Written procedures shall be established, implemented and maintained...".
Contrary to the above, while Unit 2 was operated at 100*4 power:
- a. Surveillance required by Technical Specification 4.5.4.la was not accomplished according to procedure 2-OHP4030.STP.030.
The boron injection tank (BIT) sample drawn on April 15, 1982, was not in accordance with normal sampling practices (no recir-culation flow) and this had the potential of degrading the operability of the BIT.
- b. Chemical addition was made on April 22, 1982, without knowledge of the actual concentration of the BIT utilizing a higher concen-tration of boron than specified in procedure 12-OHP4021.007.001.
- c. No written or approved procedures were utilized to control the maintenance testing and experimentation conducted on the BIT recirculation system nor were appropriate records of this activity maintained.
This is a Severity Level V violation (Supplement I).
- 4. Technical Specification 6.8.1 states in part: " Written procedures shall be established, implemented and maintained covering the activi-ties referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
Donald C. Cook's procedures for equipment control, PMI 2110 " Clear-ance Permit System" states in part: "When any Technical Specification identified equipment is to be removed from service or returned to service we will require independent verification of correct tagging )
and isolating or clearing... ;
1 Contrary to the above, the Unit 2 East Centrifugal Charging Pump was !
inoperable (breaker open, valved out) from April 2 through April 5, 1982, without the appropriate equipment controls. l This is a Severity Level V violation (Supplement I). .
1
Appendix 3 Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each item of noncom-pliance: (1) corrective action taken and the results achieved; (2) cor-rective action to be taken to avoid further noncompliance; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.
'% - 21 1992.
Qmes-2 A h =^bn yhted G. KeppleV U egional Administrator I
f 4