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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20055J2001990-07-13013 July 1990 Notice of Violation from Insp on 900422-0609.Violations Noted:Work Order Which Provided Instructions for Replacement of Plant Turbine Driven Auxiliary Feedwater Pump Speed Governor Not Appropriate to Circumstances ML20234E8071987-12-21021 December 1987 Corrected Notice of Violation from Insp on 861215-19. Violation Noted:Qualification Documentation for Limitorque Motorized Valve Actuators Did Not Establish Similarity Between Installed Actuator & Actuator Tested ML20215G3021987-03-26026 March 1987 Notice of Violation from Insp on 870202-13.App B Re Areas Inspected & Results Encl ML20211M1701987-02-10010 February 1987 Notice of Violation from Insp on 870112-13 ML20211L2691986-12-0909 December 1986 Notice of Violation from Insp on 860928-1108.Violations Noted:Containment Personnel Airlock Door Interlock Mechanism Failed on 860830 & Allowed Both Containment Doors to Be Open at Same Time ML20198J1291986-05-12012 May 1986 Notice of Violation from Insp on 860407-11.Violations Noted: Failure to Collect Iodine & Particulate Samples Daily, Failure to Log Axial Flux Difference Hourly & Failure to Conduct Surveillances IR 05000725/20080311986-02-12012 February 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Noted:Unit in Mode 1,2 or 3 from 850725-0831 & 1007-1127 W/One Channel of Automatic Actuation Logic for MSIV Inoperable IR 05000818/20090281985-10-16016 October 1985 Notice of Violation from Insp on 850818-0928 IR 05000323/20040271985-05-17017 May 1985 Notice of Violation from Insp on 850323-0427 ML20054L7751982-06-14014 June 1982 Notice of Violation from Insp on 820329-0402 & 0510-14 1990-07-13
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000275/19990121999-09-13013 September 1999 Insp Repts 50-275/99-12 & 50-323/99-12 on 990711-0821. Noncited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000275/19990071999-07-27027 July 1999 Insp Repts 50-275/99-07 & 50-323/99-07 on 990503-0714. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations & Engineering IR 05000275/19980161998-11-16016 November 1998 Insp Repts 50-275/98-16 & 50-323/98-16 on 980913-1024.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000275/19980111998-07-22022 July 1998 Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.No Violations Noted.Major Areas Inspected:Circumstances, Potential Safety Consequences & Licensee Response & Actions Taken Re Authorization of Tagout W/O Written Procedure IR 05000275/19980081998-04-17017 April 1998 Insp Repts 50-275/98-08 & 50-323/98-05 on 980202-06,23-27 & 0302-18.No Violations Noted.Major Areas Inspected: Engineering IR 05000275/19980031998-01-23023 January 1998 Insp Repts 50-275/98-03 & 50-323/98-03 on 980105-09.No Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation IR 05000275/19940271994-12-21021 December 1994 Insp Repts 50-275/94-27 & 50-323/94-27 on 941016-1126. Violations Noted.Major Areas Inspected:Operational Safety Verification,Plant Maint,Surveillance Observation,Plant Support Activities & in-office Review of LERs PNO-V-93-013, on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant1993-08-0909 August 1993 PNO-V-93-013:on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant PNO-V-92-033, on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near Parkfield1992-10-20020 October 1992 PNO-V-92-033:on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near Parkfield PNO-V-91-003, on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core1991-03-0707 March 1991 PNO-V-91-003:on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core IR 05000275/19900171990-10-22022 October 1990 Partially Withheld Safeguards Insp Repts 50-275/90-17 & 50-323/90-17 on 900924-1008.Noncited Violations Noted.Major Areas Inspected:Physical Security Program PNO-V-90-033, on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring Plant1990-07-27027 July 1990 PNO-V-90-033:on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring Plant ML20055J2001990-07-13013 July 1990 Notice of Violation from Insp on 900422-0609.Violations Noted:Work Order Which Provided Instructions for Replacement of Plant Turbine Driven Auxiliary Feedwater Pump Speed Governor Not Appropriate to Circumstances ML20245E9661989-07-31031 July 1989 Partially Withheld Insp Repts 50-275/89-20 & 50-323/89-20 on 890710-18 (Ref 10CFR2.790(d) & 73.21).No Violations Noted.Noncited Violation Noted Re Compensatory Measures. Major Areas Inspected:Physical Security Program IR 05000275/19890121989-04-18018 April 1989 Insp Repts 50-275/89-12 & 50-323/89-12 on 890403-07.No Violations or Deficiencies Noted.Major Areas Inspected: Followup on Previous Insp Findings & Operational Status of Emergency Preparedness Program IR 05000275/19890031989-02-0808 February 1989 Insp Repts 50-275/89-03 & 50-323/89-03 on 890117-26.No Noncompliance Noted.Major Areas Inspected:Nonroutine Events, Followup of Open Items,Radwaste Sys & Radiological Environ Monitoring & Transportation Activities PNO-V-88-048, on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault1988-07-18018 July 1988 PNO-V-88-048:on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault ML20196D6151988-01-27027 January 1988 Exam Rept 50-275/OL-87-02 for Units 1 & 2 on 871208-17.Exam Results:Three Senior Reactor Candidates & Twelve Reactor Operator Candidates Passed Operating & Written Exams ML20234E8071987-12-21021 December 1987 Corrected Notice of Violation from Insp on 861215-19. Violation Noted:Qualification Documentation for Limitorque Motorized Valve Actuators Did Not Establish Similarity Between Installed Actuator & Actuator Tested PNO-V-87-083, on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart1987-12-14014 December 1987 PNO-V-87-083:on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart PNO-V-87-082, on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out1987-12-10010 December 1987 PNO-V-87-082:on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out IR 05000323/19870391987-11-17017 November 1987 Insp Rept 50-323/87-39 on 870805-1030.Violations Noted. Major Areas Inspected:Improperly Authorized Flame Heating of RHR Pipe on 870505 PNO-V-87-074, on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation1987-11-10010 November 1987 PNO-V-87-074:on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation PNO-V-87-073, on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of Parts1987-11-0909 November 1987 PNO-V-87-073:on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of Parts PNO-V-87-066, on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared1987-10-0606 October 1987 PNO-V-87-066:on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared IR 05000275/19870321987-09-0101 September 1987 Mgt Meeting Repts 50-275/87-32 & 50-323/87-32 on 870817. Major Areas Discussed:Recent Plant Events & Apparent Problem Areas That Have Developed Since Last Mgt Meeting on 870306 PNO-V-87-053, on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure1987-07-24024 July 1987 PNO-V-87-053:on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure PNO-V-87-051, on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation1987-07-14014 July 1987 PNO-V-87-051:on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation IR 05000275/19870221987-06-23023 June 1987 Insp Rept 50-275/87-22 on 870520-22.Major Areas Inspected: Followup on Allegation File Number RV-87-A-0094 & Followup on Regional Open Items List ML20215F9001987-06-17017 June 1987 PNS-V-87-005:on 870617,American Protective Svc Notified Util That Security Personnel on Strike Over Monetary Benefits. Licensee Capable to Meet Security Staffing Requirements Through Use of Proprietary Security Personnel PNO-V-87-041, on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair Weld1987-06-0303 June 1987 PNO-V-87-041:on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair Weld IR 05000275/19870181987-05-0808 May 1987 Insp Repts 50-275/87-18 & 50-323/87-17 on 870420-24.No Noncompliance or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training,Followup of Part 21 Repts,Various Vital Areas & Equipment ML20209D5131987-04-23023 April 1987 Updated PNO-V-87-030B:on 870421,onsite Phase of AIT Team Special Insp Into 870410 Loss of Suction to RHR Sys While in half-loop Concluded W/Meeting at Site PNO-V-87-030A, on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event Encl1987-04-20020 April 1987 PNO-V-87-030A:on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event Encl PNO-V-87-030, on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched1987-04-13013 April 1987 PNO-V-87-030:on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched PNO-V-87-028, on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing1987-04-0606 April 1987 PNO-V-87-028:on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing ML20215G3021987-03-26026 March 1987 Notice of Violation from Insp on 870202-13.App B Re Areas Inspected & Results Encl IR 05000275/19870011987-03-25025 March 1987 Insp Repts 50-275/87-01 & 50-323/87-01 on 870202-13. Violation Noted:Failure to Maintain Control Over Lubricants PNO-V-87-025, on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected1987-03-23023 March 1987 PNO-V-87-025:on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected IR 05000275/19860331987-03-17017 March 1987 Insp Repts 50-275/86-33 & 50-323/86-31 on 861215-19. Deficiencies Noted.Major Areas Inspected:Implementation Program for Establishing & Maintaining Environ Qualification of Electrical Equipment Important to Safety IR 05000275/19870091987-03-11011 March 1987 Insp Repts 50-275/87-09 & 50-323/87-08 on 870223-27.No Noncompliance Noted.Major Areas Inspected:Followup of IE Bulletins,Vital Areas & Equipment PNO-V-87-018, on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 8702171987-03-0202 March 1987 PNO-V-87-018:on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 870217 PNO-V-87-016, on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem1987-02-23023 February 1987 PNO-V-87-016:on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem IR 05000275/19870041987-02-20020 February 1987 Insp Repts 50-275/87-04 & 50-323/87-04 on 861228-870207.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities & Followup of Onsite Events,Open Items & LERs PNO-V-87-014, on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk1987-02-18018 February 1987 PNO-V-87-014:on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk IR 05000275/19870071987-02-12012 February 1987 Insp Repts 50-275/87-07 & 50-323/87-06 on 870202-06. No Items of Noncompliance or Deviations Identified.Major Areas Inspected:Design,Design Changes & Mods & Followup on IE Notices & Nonconformance Repts ML20211M1701987-02-10010 February 1987 Notice of Violation from Insp on 870112-13 IR 05000275/19870061987-02-0606 February 1987 Insp Rept 50-275/87-06 on 870112-13.Violation Noted: Notification of 870102 Emergency Plan Unusual Event Did Not Occur Until 95 Minutes After Declaration IR 05000275/19860321987-01-30030 January 1987 Insp Repts 50-275/86-32 & 50-323/86-30 on 861109-1227 & 870116.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities, Followup of Onsite Events & Allegations IR 05000275/19870031987-01-30030 January 1987 Insp Repts 50-275/87-03 & 50-323/87-03 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Items,Transportation,Solid Waste,Licensee Identified Violation & Facility Tours 1999-09-13
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APPENDIX A -
NOTICE OF VIOLATION .i Pacific Gas and Electric Company Docket Nos. 50-275, 50-323 Diablo Canyon Units 1 and 2 License Nos. DPR-80, DPR-82 As a result of the inspection conducted during the period of February 2 through February 13, 1987, a violation of NRC requirements was identified. In accordance with the General Statement of Policy and Procedure for NRC ,
Enforcement Actions, 10 CFR Part 2, Appendix C, the following violation was identified:
10 CFR 50, Appendix B, Criterion V, states in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures or drawings."
Plant administrative procedure, AP D-753, Revision 10, dated April 25, 1986, titled " Control of Plant Lubricants," establishes the requirements for the storage and use of lubricants for plant equipment. AP D-753 '
states in part:
"Small cans used to transfer lubricants from bulk storage shall be I uniformly identified and dedicated to a specific lubricant to preclude mixing of unlike lubricants." .
and "A log book shall be available at the bulk storage areas to keep a ',
record of all lubricants dispersed, including approximate quantity and where used. This log book will be reviewed by the foreman at the same frequency as the foreman's logs."
Contrary to the above, at the time of the inspection, a one gallon unlabeled container filled with oil was in the tool shed area of the intake structure, a one gallon unlabeled container filled with oil was in a storage cabinet in the new cold machine shop, and three unlabeled filled grease guns were in the hot machine shop tool room. In addition, l log books were not being maintained at the bulk storage areas or at any other of the dispensing areas.
This is a Severity Level IV Violation (Supplement 1) 8704130077 870326 PDR G
ADOCK 05000275 PDR W
4 Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in response to the above violation, including: (1) the corrective steps which have been taken and the results achieved, (2) corrective steps which will be taken to avoid further violations, (3) the date when full compliance will be achieved. Consideration may by given to extending your response time for good cause shown.
MAR 261987 S r b #~~T2 d Dated Stuart Richards, Chief Engineering Section -
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~4 APPENDIX B Areas Inspected and Results Postulated Significant Events Three postulated significant off-normal scenarios based on actual events at
other sites were developed to allow evaluation of plant procedures, hardware and operator training. The simulator Control Room was used to direct auxiliary operators (A0s) stationed in a " ready room" in the plant to go to specific locations in the power block and to simulate the operation of various manual backup valves and controls needed to control the events. The main
emphasis of the walkdown of these events was to assess the auxiliary operator ,
actions and equipment function ability during the use of manual backup methods.
The team found that the control and auxiliary operators were very knowledgeable about plant operation and the location and operation of the manual valves and electrical breakers that were needed to contain the casualties.
Manual Valve Maintenance The walkdowns of various portions of safety and non-safety related piping systems indicated that the manually operated valves were generally not being greased or maintained by a preventative maintenance program.
A formal program to maintain the manual valves was being developed, but had not been finalized and implemented at the site.
Action Requests From the discussions with several operators with various levels of experience and qualifications, including licensed senior reactor operators, it was readily apparent that the operators lacked confidence in the " Action Request" -
(AR) program identified in procedure APC-1256, " Identification and Processing of Power Plant Action Requests and Quality Evaluations." The operators stated that they have requested work to be done by the maintenance department, but the work was not scheduled until a much later time than the operators considered reasonable.
Plant management was aware that a large backlog of ARs had been building and was attempting to resolve the priority of the ARs.
Emergency Training for Auxiliary Operators The training program for the auxiliary operators (AO) involves a lengthy "on the job" (0JT) type environment with some supplementary classroom training.
Actual formal emergency training has not been included in A0 training until the individuals enter control operator training.
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2 Although regulatory requirements do not specify that A0s receive formal emergency training, the licensee stated that the benefits of a formal emergency training program for the A0s will be evaluated.
Surveillance The surveillance test procedures examined and tests observed appeared to be comprehensive. No anomalies were identified.
Control of Lubricants The inspection of lubricant storage areas on site disclosed a lack of log books to record the type and quantity of lubricants dispensed, and the approximate location of use. The inspector also observed several instances of unlabeled lubricant containers. These observations appear to be a violation of requirements of the licensee's administrative procedure on the control of plant lubricants.
Lubrication records for the valve actuators of several motor operated valves for each unit in safety related systems were examined. The vendor manuals filed in the Record Management System related to preventive maintenance of valve actuators were reviewed. Several instances were identified where it was unclear whether the appropriate version of the vendor manuals were on file.
Equipment Condition / Housekeeping During walk-downs of both units, the following anomalies were observed: 1) on three of four RHR pumps inspected, motor housing oil was on the pump lagging;
- 2) cigarette butts were found inside the dedicated shutdown panels in the auxiliary building; 3) debris was found in several electrical control panels;
- 4) numerous boric acid crystals were in evidence in the plant and Action Request tags to correct the problem were not noted; 5) calibration tags were out of date on various permanent panel meters throughout both units. The above examples indicate an increased need for management to tour the plant and assure that their expectations are being implemented. '
The walk-down of the Compressed Air System control air supply lines and air operators for a number of safety related valves showed that the control air supply lines for several valves tended to slope toward the air operator. With the present configuration of the control air lines, water may accumulate at the valve operator if significant amounts of moisture were to enter the control air supply lines.
Maintenance The evaluation of the maintenance program included the interviewing of key staff members working in the maintenance area plus reviewing maintenance procedures and the administrative procedures which govern the maintenance program process. Also, action requests, work orders, and equipment history files for maintenance performed on components in the RHR system were examined.
Maintenance program planning was in a state of transition, but appeared to be basically sound. While no regulatory violations were identified, the following weaknesses were noted:
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- 1) There appeared to be a lack of formal operating procedures to govern some activities in the Work Planning Center.
- 2) The full history of maintenance work performed on plant components was difficult to retrieve. We understand that the licensee plans to consolidate past shop work folder equipment history into the current PIMS system.
- 3) It was not apparent that there was routine monitoring of priority corrective maintenance.
Strong Quality Control involvement in the review of ARs and Work Orders was viewed as a strength.
Quality Verification activities The team examined the QC organization structure, QC procedures, personnel qualifications, the QC program for control of in process work, trending, corrective actions, and interviewed QC personnel. The team concluded that the y program was generally effective in identifying problems; however, the corrective action program needed to be strengthened and receive additional management attention as evidenced by the repeated failures of the containment air lock doors.
IE Information Notice and Industry Experience Report Followup The program for followup of IE Information Notices and Industry Experience Reports was examined and appears to have been effectively implemented.
Internal Events The licensee was found to have implemented the stated corrective action for the six internal events that were examined.
Procurement An assessment was made of the program and its implementation for the procurement, control and dedication of commercial grade components for safety-related systems. While it appears that components were being properly controlled on-site, it was not apparent that Corporate Engineering was maintaining records of the analysis used for the basis for certification of these components.
The licensee agreed to examine this apparent deficiency and effect appropriate
- orrective action.
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