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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20217K5821998-04-0202 April 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 971017,shift Supervisor Failed to Ensure That Equipment Could Be Removed from Svc,By Failing to Ensure That TS Requirements Were Met ML20132F8881996-10-18018 October 1996 Notice of Violation from Insp on 960727-0906.Violation Noted:On 960820,electrical Maint Technician Operated Supply Ventilation Fan to EDG 1-2 Room W/O Proper Authorization of Shift Supervisor ML20059C1281993-12-23023 December 1993 Notice of Violation from Insp on 931018-1103.Violation noted:930917 Primary Coolant Sys Temp Between 170 Degrees & 250 Degrees F,Average Cooldown Was Approx 48 Degrees F Per Hour ML20059G2071993-10-25025 October 1993 Notice of Violation from Insp on 930819-0929.Violation Noted:Licensee Cycle 10 Radiochemistry Testing Did Not Positively Identify Failed I-series Fuel ML20149D3601993-09-14014 September 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Shift Supervisor Failed to Explain Plans,Procedures & Safety Precautions to Auxiliary Operators Assigned to Perform CRDM mock-up ML20127M7821993-01-21021 January 1993 Notice of Violation from Insp on 921207-18.Violation Noted: Inservice Test Procedure QO-8B Contained Inadequate Acceptance Criteria to Verify That Listed Check Valves Exercised Full Open Position ML20212P8351987-03-0909 March 1987 Notice of Violation from Insp on 860724-1231 ML20214W1891986-09-26026 September 1986 Notice of Violation from Insp on 860723-0908 ML20206T5401986-07-0101 July 1986 Notice of Violation & Proposed Impostion of Civil Penalty in Amount of $50,000.Violation Noted:Inadequate Review & Corrective Action for Containment Isolation Valve Leakage Event Noted in May & Aug 1985 ML20205M3121986-04-11011 April 1986 Notice of Violation from Insp on 860119-0313 ML20154Q0381986-03-14014 March 1986 Notice of Violation from Insp on 860107-0228 ML20141N2321986-02-26026 February 1986 Notice of Violation from Insp on 860127-0207 ML20153E8281986-02-20020 February 1986 Notice of Violation from Insp on 860106-08 ML20151U9481986-02-0606 February 1986 Notice of Violation from Insp on 860113-21 ML20137H8581986-01-16016 January 1986 Notice of Violation from Insp on 851119-1223 ML20141H5731986-01-0909 January 1986 Notice of Violation from Insp on 851203-20 IR 05000919/20110181985-12-23023 December 1985 Notice of Violation from Insp on 850919-1118 ML20137H4681985-11-24024 November 1985 Notice of Violation from Insp on 850930-1004 IR 05000709/20080121985-09-13013 September 1985 Notice of Violation from Insp on 850709-0812 IR 05000710/20090041985-09-0505 September 1985 Notice of Violation from Insp on 850710-0904 IR 05000409/20050061985-06-0303 June 1985 Notice of Violation from Insp on 850409-0506 ML20128M2731985-05-21021 May 1985 Notice of Violation from Insp on 850423-26 & 0501-02 ML20055C1451982-07-22022 July 1982 Notice of Violation from Insp on 820601-30 1998-04-02
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-II-99-043, on 991013,Palisades Nuclear Plant Located Near South Haven,Mi Notified NRC That Package Received from Licensee Exceeded External Radiation Limits of 200 Mrem Per H Authorized by Regulations.Shipper & Carrier Notified1999-10-14014 October 1999 PNO-II-99-043:on 991013,Palisades Nuclear Plant Located Near South Haven,Mi Notified NRC That Package Received from Licensee Exceeded External Radiation Limits of 200 Mrem Per H Authorized by Regulations.Shipper & Carrier Notified IR 05000255/19980081998-05-28028 May 1998 Partially Withheld Insp Rept 50-255/98-08 on 980504-08 (Ref 10CFR73.71).No Violations Noted.Major Areas Inspected: Effectiveness of Access Control Functions & Testing & Maint Activities Related to Security Equipment ML20217K5821998-04-0202 April 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 971017,shift Supervisor Failed to Ensure That Equipment Could Be Removed from Svc,By Failing to Ensure That TS Requirements Were Met IR 05000255/19970071997-06-0505 June 1997 Partially Deleted Insp Rept 50-255/97-07 on 970428-0513. Violations Noted.Major Areas Inspected:Mgt Support,Plant Support,Detection Equipment & Evaluation of Security Communication Activities IR 05000255/19960011997-01-24024 January 1997 SALP Rept 50-255/96-01 for Period from 950528-961123 ML20132F8881996-10-18018 October 1996 Notice of Violation from Insp on 960727-0906.Violation Noted:On 960820,electrical Maint Technician Operated Supply Ventilation Fan to EDG 1-2 Room W/O Proper Authorization of Shift Supervisor ML20059C1281993-12-23023 December 1993 Notice of Violation from Insp on 931018-1103.Violation noted:930917 Primary Coolant Sys Temp Between 170 Degrees & 250 Degrees F,Average Cooldown Was Approx 48 Degrees F Per Hour IR 05000255/19930301993-12-21021 December 1993 Insp Rept 50-255/93-30 on 931203.Violations Noted.Major Areas Inspected:Previous Violations Were Reviewed IR 05000255/19930011993-12-0101 December 1993 SALP 12 Rept 50-255/93-01 for 920401-931030 IR 05000255/19930281993-11-19019 November 1993 Insp Rept 50-255/93-28 on 931018-1103.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Excessive Cooldown Following Identification of Nonisolable thru-wall Leak on Primary Coolant Sys IR 05000255/19930271993-11-16016 November 1993 Insp Rept 50-255/93-27 on 931025-28.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise ML20059G2071993-10-25025 October 1993 Notice of Violation from Insp on 930819-0929.Violation Noted:Licensee Cycle 10 Radiochemistry Testing Did Not Positively Identify Failed I-series Fuel IR 05000255/19930201993-10-25025 October 1993 Insp Rept 50-255/93-20 on 930819-0929.Violations Noted.Major Areas Inspected:Licensee Activities Re Summer 1993 Refueling Outage Problems & Plant Restart Preparations IR 05000255/19930251993-10-21021 October 1993 Insp Rept 50-255/93-25 on 931005 & 06.No Violations of NRC fitness-for-duty Noted.Major Areas Inspected:Review of fitness-for-duty Concern Relating to Implementation of Testing for-cause & follow-up of Random Testing Program PNO-III-93-055, on 930917,indications of Leak Found in Pipe Connecting Top of Pressurizer to Two PORVs During Insp of Reactor Sys Piping.Issues Related to Cracked Pipe Being Reviewed by Region III & NRR & Repairs Underway1993-09-24024 September 1993 PNO-III-93-055:on 930917,indications of Leak Found in Pipe Connecting Top of Pressurizer to Two PORVs During Insp of Reactor Sys Piping.Issues Related to Cracked Pipe Being Reviewed by Region III & NRR & Repairs Underway ML20057B8581993-09-16016 September 1993 Exam Rept 50-255/OL-93-02 on 930914.Exam Results: Requalification Written Retake Exam Was Administered to One RO ML20149D3601993-09-14014 September 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Shift Supervisor Failed to Explain Plans,Procedures & Safety Precautions to Auxiliary Operators Assigned to Perform CRDM mock-up ML20057A1731993-09-0707 September 1993 Insp Rept 50-255/93-05 on 930614-17 & 29,0701 & 20-21 & 0803-04.No Violations or Deviations Noted.Major Areas Inspected:Isi Activities Including Review of Program, Procedures & Observation of Work Activities PNO-III-93-049A, provides Update on Degraded Neutron Absorbing Plates in Spent Fuel Pool at Plant.Licensee Determined That Sufficient Subcritical Margin Maintained in Spent Fuel Pool.State of Mi Informed1993-08-31031 August 1993 PNO-III-93-049A:provides Update on Degraded Neutron Absorbing Plates in Spent Fuel Pool at Plant.Licensee Determined That Sufficient Subcritical Margin Maintained in Spent Fuel Pool.State of Mi Informed IR 05000255/19930181993-08-31031 August 1993 Augmented Insp Team Rept 50-255/93-18 on 930708-20.No Violations Noted.Major Areas Inspected:Review of Validation of Sequence of Events & Licensee Corrective Actions IR 05000255/19930051993-07-30030 July 1993 Insp Rept 50-255/93-05 on Stated Date.No Violations Noted. Major Areas Inspected:Independent NDE of Components & Welds in Order to Ascertain Accuracy of NDE Performed by Licensee PNO-III-93-038, on 930701,licensee Discovered Highly Radioactive Object on Floor of upender-tilt Pit in Refueling Area of Containment.There Have Been No Radiation Overexposures as Result of Event1993-07-0101 July 1993 PNO-III-93-038:on 930701,licensee Discovered Highly Radioactive Object on Floor of upender-tilt Pit in Refueling Area of Containment.There Have Been No Radiation Overexposures as Result of Event PNO-III-93-027, on 930504,listed Individuals Filed Suit Against NRC on Dry Cask Storage Sys at Plant.Util Planning to Begin Movement of Sf Into Storage Casks on 9305071993-05-0404 May 1993 PNO-III-93-027:on 930504,listed Individuals Filed Suit Against NRC on Dry Cask Storage Sys at Plant.Util Planning to Begin Movement of Sf Into Storage Casks on 930507 IR 05000255/19930021993-02-17017 February 1993 Insp Rept 50-255/93-02 on 921229-930208.No Violations Noted. Major Areas Inspected:Previously Identified Items, Operational Safety Verification,Maint,Surveillance & Design Changes ML20127M7821993-01-21021 January 1993 Notice of Violation from Insp on 921207-18.Violation Noted: Inservice Test Procedure QO-8B Contained Inadequate Acceptance Criteria to Verify That Listed Check Valves Exercised Full Open Position IR 05000255/19920281993-01-21021 January 1993 Insp Rept 50-255/92-28 on 921207-18.Violations Noted.Major Areas Inspected:Licensee Program on Check Valves,Self Assessment & Incorporation of GL 89-04, Guidance on Developing Acceptable Inservice Test Programs IR 05000255/19920271993-01-13013 January 1993 Insp Rept 50-255/92-27 on 921117-1228.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Engineering & Technical Support,Maintenance,Surveillance & Quality Control Activities IR 05000255/19920231992-11-25025 November 1992 Insp Rept 50-255/92-23 on 921006-1116.Noncited Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Reactor Trip,Maint Surveillance,Quarterly Mgt Meeting & Dry Cask Storage Project Insps IR 05000155/19900201990-11-0707 November 1990 Insp Repts 50-155/90-20 & 50-255/90-27 on 900925-28 & 1015-19.Violations Noted.Major Areas inspected:fitness-for- Duty & Corrective Actions for Audit Findings IR 05000255/19900161990-07-0606 July 1990 Insp Rept 50-255/90-16 on 900618-22 & 25.No Violations Noted.Major Areas Inspected:Mgt Support,Protected & Vital Areas,Detection & Assessment Aids,Package & Vehicle Access, Compensatory Measures & Training & Qualification IR 05000255/19890111989-05-0101 May 1989 Partially Withheld Physical Security Insp Rept 50-255/89-11 on 890410-14 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Mgt Support,Protected & Vital Area Barriers & Access Control,Including Personnel,Packages & Vehicles PNO-III-89-007, on 890130 Unit Taken off-line to Repair Primary to Secondary Tube Leak in B Sg.Caused by Leakage Increase Since 890124 & Reaching Licensee Administrative Limit of 0.1 Gpm.Plans Include Preventive Plugging of Tubes1989-02-0101 February 1989 PNO-III-89-007:on 890130 Unit Taken off-line to Repair Primary to Secondary Tube Leak in B Sg.Caused by Leakage Increase Since 890124 & Reaching Licensee Administrative Limit of 0.1 Gpm.Plans Include Preventive Plugging of Tubes IR 05000255/19880131988-05-24024 May 1988 Partially Withheld Insp Rept 50-255/88-13 on 880502-05 (Ref 10CFR73.21).Major Areas Inspected:Security Plan/ Implementing Procedures,Mgt Effectiveness,Security Organization,Testing & Maint & Security Sys Power Supply IR 05000255/19880091988-04-27027 April 1988 Insp Rept 50-255/88-09 on 880411-15.No Violations or Deviations Noted.Major Areas Inspected:Activation of Emergency Plan,Licensee Action on Previously Identified Items & Changes to Emergency Preparedness Program PNO-III-87-140, on 871111,oiler on Feedwater Block Valve Exploded in Turbine Bldg,Injuring Two Workers.One Individual Taken to Local Hosp & Later Transferred to Kalamazoo,Mi Hosp for Surgery & Second Worker Treated at Plant1987-11-12012 November 1987 PNO-III-87-140:on 871111,oiler on Feedwater Block Valve Exploded in Turbine Bldg,Injuring Two Workers.One Individual Taken to Local Hosp & Later Transferred to Kalamazoo,Mi Hosp for Surgery & Second Worker Treated at Plant PNO-III-87-134, on 871015,w/unit Cold Shutdown for Maint, Operators Tripped Operating Shutdown Coolant Pump in Response to Alarms & Indications of Fluctuation Pressure within Pump1987-10-16016 October 1987 PNO-III-87-134:on 871015,w/unit Cold Shutdown for Maint, Operators Tripped Operating Shutdown Coolant Pump in Response to Alarms & Indications of Fluctuation Pressure within Pump PNO-III-87-131, on 871007,util & Bechtel Power Corp Issued Joint Press Release Announcing Tentative Agreement to Form New Joint Venture Which Would Own & Operate Facility.Util Would Continue to Operate Facility Under Contract for 3 Yrs1987-10-0707 October 1987 PNO-III-87-131:on 871007,util & Bechtel Power Corp Issued Joint Press Release Announcing Tentative Agreement to Form New Joint Venture Which Would Own & Operate Facility.Util Would Continue to Operate Facility Under Contract for 3 Yrs PNO-III-87-097A, on 870714,preliminary Review of Incident Determined That Startup Transformer 1-2 Faulted.Cause of Initial Fault Still Under Investigation1987-07-15015 July 1987 PNO-III-87-097A:on 870714,preliminary Review of Incident Determined That Startup Transformer 1-2 Faulted.Cause of Initial Fault Still Under Investigation PNO-III-87-097, on 870714,plant Lost Offsite Power Causing Reactor Trip.Caused by Ground Fault in One of Three Startup Transformers.Main Generator Will Be Disconnected from Main Transformer Which Will Feed Power to Plant1987-07-14014 July 1987 PNO-III-87-097:on 870714,plant Lost Offsite Power Causing Reactor Trip.Caused by Ground Fault in One of Three Startup Transformers.Main Generator Will Be Disconnected from Main Transformer Which Will Feed Power to Plant PNO-III-87-095, on 870709,reduction in Power Occurred Due to Handswitch Failure on Cooling Tower Pump B Discharge Valve. on 870710,decreasing Oil Pressure in Primary Coolant Pump Noted.Possibly Caused by Pump Vibration Creating Oil Leak1987-07-10010 July 1987 PNO-III-87-095:on 870709,reduction in Power Occurred Due to Handswitch Failure on Cooling Tower Pump B Discharge Valve. on 870710,decreasing Oil Pressure in Primary Coolant Pump Noted.Possibly Caused by Pump Vibration Creating Oil Leak IR 05000255/19870161987-07-0808 July 1987 Insp Rept 50-255/87-16 on 870608-12.No Violations Noted. Major Areas Inspected:Confirmatory Measurements Program Including Comparison of Licensee Analyses W/Region III Mobile Lab,Radiological Environ Program & Open Item PNO-III-87-085, on 870620,while Reducing Power for Governor Valve Test on Main Turbine,Turbine Was Taken Off Line After Discovery of electro-hydraulic Control Fluid Leak on 4 Governor Valve1987-06-22022 June 1987 PNO-III-87-085:on 870620,while Reducing Power for Governor Valve Test on Main Turbine,Turbine Was Taken Off Line After Discovery of electro-hydraulic Control Fluid Leak on 4 Governor Valve 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 ML20214T9121987-06-0404 June 1987 Exam Rept 50-255/OL-87-01 on 870504-08.Exam Results:Both Senior Operator Candidates Passed.Exam & Answer Key Encl ML20214U3261987-06-0404 June 1987 Requalification Exam Rept 50-255/OL-87-02 of Exam Admininstered on 870505-08.Exam Results:Five Senior Operators & Four Operators Passed Exams IR 05000255/19860351987-05-28028 May 1987 Insp Rept 50-255/86-35 on 861216-870216.Violations Noted: Inadequate Review of Mod Package,Inadequate Procedures for Conduct of 10CFR50.59 Evaluations & Failure to Identify Modified Breakers as Class 1E IR 05000255/19870071987-04-20020 April 1987 Partially Withheld Insp Rept 50-255/87-07 on 870320-30 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected: Licensee Actions Re Opening of Physical Barrier,Security Plan & Implementing Procedures & IE Info Notice 86-083 PNO-III-87-053, on 870412,reactor Manually Tripped as Result of Leak in Electrohydraulic Control (EHC) Sys for Main Turbine.Caused by Fatigue Failure of Impeller of Pump in EHC Sys.Pump Repaired1987-04-13013 April 1987 PNO-III-87-053:on 870412,reactor Manually Tripped as Result of Leak in Electrohydraulic Control (EHC) Sys for Main Turbine.Caused by Fatigue Failure of Impeller of Pump in EHC Sys.Pump Repaired PNO-III-87-044C, on 870405,unit Completed Testing Activities at 30% Level & Increased Power at 45% for Further Testing & Review.Power Held at 45% for Repair of Valve in Cooling Tower Sys & Oil Flow in Main Feedwater Pump Bearing1987-04-10010 April 1987 PNO-III-87-044C:on 870405,unit Completed Testing Activities at 30% Level & Increased Power at 45% for Further Testing & Review.Power Held at 45% for Repair of Valve in Cooling Tower Sys & Oil Flow in Main Feedwater Pump Bearing PNO-III-87-044B, on 870403,unit Tied to Util Electrical Grid for First Time Since 860519 Reactor Trip.Licensee Began Plant Startup on 870327 But Returned to Cold Shutdown to Replace Failed Nuclear Instrument1987-04-0303 April 1987 PNO-III-87-044B:on 870403,unit Tied to Util Electrical Grid for First Time Since 860519 Reactor Trip.Licensee Began Plant Startup on 870327 But Returned to Cold Shutdown to Replace Failed Nuclear Instrument 1999-10-14
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1 NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CML PENALTIES - 1 Consumers Power Company Docket No. 50-255 Palisades Nuclear Generating Plant License No. DPR-20 EA 97-567 & EA 97-569 During an NRC inspection conducted from October 28 to November 19,1997, violations of NRC requirements were identified. . In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the NRC proposes to impose civil penalties 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 violations and associated civil penalties are set forth below:
Palisades Nuclear Power Plant Technical Specification 6.4.1.s (Amendment 174), " Procedures,"
requires, in part, that written procedures shall be implemented covering the applicable procedures recommended in Regulatory Guide (RG) 1.33, Revision 2, Appendix A, " Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors," February 1978.
RG 1.33, Revision 2, Appendix A, states, in part, that the following are typical safety-related activities that should be covered by written procedures: authonties and responsibilities for safe operation (Section 1.b); equipment control (Section 1.c); maintenance that can affect the performance of safety-related equipment (Section 9.a); and control of maintenance (Section 9.e).
- 1. Administrative Procedure 4.00 (Revision 20 - 7/18/97), " Operations Organization, Responsibilities and Conduct," a procedure required by Section 1.b of RG 1.33, at Step 4.2.3.b.6, required that the Control Room Supervisor shall keep the Shift Supervisor informed of plant and equipment status.
Contrary to the above, on October 17,1997, the Control Room Supervisor failed to property implement Administrative Procedure 4.00 in that the Shift Supervisor was not kept informed that power would be removed from all of the control rod drive motors in order to facilitate maintenance on control rod 38. (01013)
- 2. Administrative Procedure 4.10 (Revision 6 - 4/30/97), " Personnel Protective Tagging," a procedure required by Section 1.c of RG 1.33, at Step 7.2.2 required that the Shift Supervisor shall ensure that equipment may be removed from service by ensuring that the Technical Specification requirements, including the Limiting Conditions for Operations and Action Statements, are met.
Palisades Nuclear Power Plant Technical Specification 3.10.4.b, Amendment 169, states, in part, that a control rod is considered inoperable if it cannot be moved by its operator and if more than one control rod becomes inoperable then the reactor shall be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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i 9004070269 980402 PDR ADOCK 05000255 G. PDR
' Notice of Violation Contrary to the above, on October 17,1997, the Shift Supervisor (and the Control Room Supervisor, Shift Engineer (all licensed senior reactor operators)) failed to ensure that '
equipment could be removed from service by failing to ensure that Technical Specification requirements, including the Limiting Condition for Operation and Action Statements, were met prior to removing all the control rods from service. Specifically, power was removed from all the rods and the licensed operator failed to realize that removing power from more than one control rod required entry into a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> action to shut down the plant. (01023)
- 3. ~ Administrative Procedure 4.02 (Revision 15 - 6/27/97) " Control of Equipment," a -
procedure required by Section 1.c of RG 1.33, at the NOTE before step 1 of Attachment 8, " Safety Assessment for Removal of Plant Equipment (SSCs) From Service," required that Attachment 8, or an equivalent risk-based assessment, be completed for maintenance activities that met all of the following conditions:
a) entry into unplanned maintenance outages ,
b) involved high safety significant systems identified in Attachment 10 i c) would rorder the system incapable of performing its Maintenance Rule function l
d) did not occur with the equipment positioned in its designed safety position prior to removing its power source.
Contrary to the above, on October 17,1997, the licensee failed to complete Administrative Procedure 4.02, Attachment 8, or perform an equivalent risk-based assessment for the maintenance on control rod 38. Specifically, this maintenance activity: (1) was an unplanned maintenance outage isecause the corrective maintenance on control rod 38 was emergent work; (2) involved the control rod drive system which was a high safety significant system identified in Attachment 10; (3) rendered the control rod drive system incapable of performing its maintenance rule function of manual operation; and (4) did not occur with control rod 38 positioned in its designed safety position of fully inserted prior to removing its power source.
(01033)
- 4. Maintenance Procedure CRD-E-32 (Revision 7 - 2/21/95), "CRDM [ Control Rod Drive Motor]
Control Relays Cleaning and Inspection," a procedure required by Section 9.a of RG 1.33, at Step 3.4.2.e, required during plant operation with rods withdrawn and the clutch power supply energized that only one relay set and its related fuses be removed from service at a time.
Contrary to the above, on October 17,1997, during implementation of work order 24714120, maintenance on control rod 38, licensee personnel failed to properly implement Maintenance Procedure CRD-E-32 in that more than one control rod relay set and its related fuses were simultaneously removed from service and inspected. (01043)
I Notice of Violation 5. Administrative Procedure 5.01 (Revision 21 - 5/12/97), " Processing Work Requests / Work 1 Orders," a procedure required by Section 9.e of RG 1.33, Attachment 2, " Work Order
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Scheduling, Performance, and Completion," at Step 2.3.c, required the Assigned Supervisor to review scheduled work orders to determine the work could be performed as scheduled, and if not notify the Shift Supervisor (" scheduled" includes both the time of occurrence and manner of conduct). Step 6.1 of Attachment 2, required the work order to be replanned, per the requirements of this procedure, if the Assigned Supervisor determined that the work required to correct the problem was not adequately described in the work orderjob plan.
Step 5.11.b required the repairperson to document the "as found" conditions and the repairs / adjustments made.
Contrary to the above, on October 17,1997, during implementation of work order 24714120,
. maintenance on control rod 38, licensee personnel failed to properiy implement Administrative Procedure 5.01 in that three additional control rod drive relay contactors for control rods 3,40, and an unidentified Group Ill control rod were removed, inspected, and reinstalled. This represented a condition not allowed by the work procedure and was an unplanned and undocumented expansion of the approved work scope without the required notification to the Shift Supervisor. (01053)
- 6. Administrative Procedure 5.19 (Revision 6 - 4/15/97), " Post Maintenance Testing," a procedure required by Section 9.e of RG 1.33, at Step 5.2.e, required the Operations Manager to ensure that Post Maintenance Testing was property performed prior to declaring the equipment operable. Step 5.4.c required the Maintenance Supervisor to ensure that the specified post maintenance testing was revised, as necessary, if the scope of maintenance performed was changed after initial planning.
Administrative Procedure 4.02 (Revision 15 - 6/27/97), " Control of Equipment," a procedure required by Section 1.c of RG 1.33, at Step 9.3.b, required operability testing to be performed on safety-related equipment following any maintenance activity which had the potential to affect the equipment's operability.
Contrary to the above, following implementation of work order 24714120, maintenance on control rod 38, on October 17,1997, licensee personnel failed to properly implement Administrative Procedures 5.19 and 4.02. Specifically, more than one control rod relay set and its related fuses were removed from service and inspected which represented a change )
in the scope of maintenance after initial planning. However, the specified post maintenance l testing was not revised as necessary. Consequently, appropriate Post Maintenance Testing was not identified or performed. (01063)
These violations represent a Severity Level lll problem (Supplement 1). Civil Penalty $55,000.
Pursuant to the provisions of 10 CFR 2.201, Consumers Power Company (Licensee) is hereby i 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 i
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Notice of Violation -4 l
Imposition of Civil Penalties (Notice). This reply should 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 q 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 i adequate reply is not received within the time specified in this Notice, an order or a Demand for j information may be issued as why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Consideratum may be given to extending the response time for good cause shown. Under the authority of Sechon 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 Ucensee may pay the civil penalties 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 cumulative amount of the civil penalties or may protest imposition of the civil penalties in whole or in part, by a written answer addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission. Should the Ucensee fail to answer within the time specified, an order imposing the civil penalties will be issued. Should the Ucensee elect to file an answer in accordance with 10 CFR 2.205 protesting the civil penalties, in whole or in part, such answer should be cleariy marked as an " Answer to a Notice of Violation" and may:
(1) deny the violations 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 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 penalties.
in requesting mitigation of the proposed penalties, 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 Ucensee is directed to the other provisions of 10 CFR 2.205, regarding the procedure for imposing civil penalties. i Upon failure to pay any civil penalties due which subsequently has been determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attomey General, and the penalties, 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 penalties, and Answer to e Notice of Violation) should be addressed to: Director, Office of Enforcement, U.S.
Nuclear Fsegulatory 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 lll and a copy to the NRC Resident inspector at the Palisades Plant.
Because your response will be placed in the NRC Public Document Room, to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it l
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Notice of Violation can be placed in the Public Document Room 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 my11 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. Lisle, Illinois this 2nd day of April 1998 l
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