IR 05000219/1985098
| ML20207S775 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/12/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20207S761 | List: |
| References | |
| 50-219-85-98, NUDOCS 8703200261 | |
| Preceding documents: |
|
| Download: ML20207S775 (69) | |
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U.S. NUCLEAR REGULATORY COMMISSION l
REGION I
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE INSPECTION REPORT 50-219/85-98 GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION ASSESSMENT PERIOD: JULY 1, 1985 - OCTOBER 15, 1986
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BOARD MEETING DATE: NOVEMBER 25 and 26, 1986 l
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0703200261 070312 PDH ADOCK 05000J19 l a PDR
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. SUMMARY (7/1/85 - 10/15/86)
OYSTER CREEK LER Number Summary Description 85-12 Reactor Isolation Scram 85-13 Failure to Maintain Drywell to Torus Differential Pressure 85-14 Unit Substatation Transformers IA2 and 1B2 Low 011 85-15 Automatic Scram on Low Condenser Vacuum 85-16 Reactor Scram on APRM Downscale and IRM Hi Hi 85-17 Drywell Bulk Temperature 85-18 Emergency Service Water Pipe Coating Failure 85-19 Non-Conservative Error in Technical Specification Setpoint Calculation 85-20 Loss of Both Diesel Generators 85-21 APRM Setpoint Did Not Meet Acceptance Criteria 85-22 Reactor Scram Due to Main Generator Trip 85-23 Emergency Service Water System Seismic Concerns 85-24 Reactor Trip Due to High Neutron Flux 85-25 Main Steam Isolation Valve Closure Caused by Operator Error 85-26 Neutron Flux Setpoints Exceed Technical Specification Limits 86-01 Reactor Low Level Sensors Found out of Specification 86-02 Inoperative Containment Spray Snubber Caused by Personnel Error 86-03 Three Out of Eight Isolation Condenser Pipe Break Sensors Out of Specification
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T2-2 86-04 Reactor Scram on Anticipatory Turbine Trip Caused by Limit Switch Failure 86-05 Core Spray and Diesel Generator Initiation Caused by Procedural Deficiency 86-06 Isolation Condenser Actuation Pressure Sensors Exceeded Setpoint Limit 86-07 Reactor Shutdown Due to Reactor Low Water Level Scram Switch Repeatability Problems 86-08 Local. Leak Rate Testing Results (Voluntary Report)
86-09 Scram Signal Received Due to Neutron Instrumentation . Noise 86-10 Inoperable Isolation Cendenser Snubbers 86-11 Secondary Containment Isolation and Initiation of Standby Gas Treatment System 86-12 Containment Isolation and Standby Gas Initiation Caused by Electrical Storm 86-13 Secondary Containment Isolation and Initiation of Standby Gas Treatment System 86-14 Containment Spray System Seismic Concerns 86-15 Refueling Bridge Limit Switch Failure Due to Personnel Error 86-16 Fuel Clad Failures 86-17 Containment Isolations and Standby Gas Initiation Caused by Storms 86-18 Secondary Contaiment Leak Rate 86-19 Standby Gas Initiation Caused by Personnel Error 86-20 Broken Valve Disc in Control Rod Drive Hydraulic Unit 86-21 Plant Systems did not Meet Seismic Design Bases 86-22 Control Rod Drive Hydraulic Control Units not Installed Per Design
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TABLE 3 ENFORCEMENT SUMMARY 7/1/85 - 10/15/86 OYSTER CREEK NUCLEAR GENERATING STATION A. Number and Severity Level of Violations Severity Level I 0 Severity Level II O Severity. Level III 0 Severity Level IV 21 Severity Level V 2 Deviations 1 Total '. 24 B. Violation vs.' Functional Area Functional Area Severity Level I II III IV V Dev Plant Operations 3 1 Radiological Controls 6 Maintenance 2 Surveillance / Inservice Testing 0 Emergency Preparedness O Security and Safeguards 0 Outage Management / Refueling 0 Technical Support 7 1 1 Training and Qualification 0-Assurance of Quality 3 Licensing 0 Totals 21 2 1 Note: Enforcement action is pending on several EQ concerns identified during this evaluation perio _ _ . - . .
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l TABLE 4 INSPECTION HOURS SUMMARY (7/1/85 - 10/15/86)
OYSTER CREEK NUCLEAR GENERATING STATION HOURS % OF TIME l
Plant Operations 1971 38 Radiological Controls 478 9 Maintenance 647 12 i Surveillance / Inservice Testing 417 8 Emergency Preparedness
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Security and Safeguards 140 3 Outage Management / Refueling 301 6 i
Technical Support 968 19 Training and Qualification 0 0 i Assurance of Quality 0 0
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Licensing Not Applicable l
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Total 5189 -100
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TABLE 5 INSPECTION REPORT ACTIVITIES OYSTER CREEK NUCLEAR GENERATING STATION Report N Inspections Dates Inspector Hours Area Inspected 85-20 N/A -
Management Meeting - Security 6/17/85 Issue 85-21 N/A -
Management Meeting - Enforcement 6/13/85 Conference 85-22 Specialist 22 Meeting and Examination of IEB 6/25/85 79-02 and 79-14 Documentation 85-23 Resident 215 Routine 7/1 - 8/18/85 85-24 Specialist 35 Security 7/22-26/85 85-25 Specialist 102 Transportation Activities 7/29 - 8/1/85 85-26 Resident 124 Routine 8/19 - 9/22/85 85-27 Specialist 39 Shock Suppressors 8/19-23/85 85-28 Specialist 66 Transformers Low 011 Level and 9/23-27/85 Fire Protection / Prevention Program 85-29 Resident 316 Routine 9/23 -10/20/85 85-30 Specialist 28 Material Control and Accounting 10/1-4/85 85-31 Specialist 27 Inservice Inspection Data 10/7-10/85 85-32 Specialist 103 QA Program, Document Control, 10/21-25/85 Onatte Review Committees, and Record Program
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T5-2 85-33 Specialist 46 Radiation Control Program 10/21-25/85 85-34 Cancelled 85-35 Resident 284 Routine 10/21 -12/1/85 85-36 Specialist 254 Overpressurization of Low 11/7-22/85 (Team) Pressure ECCS Systems 85-37 N/A Management Meeting - IEB 79-02 11/13/85 and 79-14 85-38 Resident 125 Routine 12/2/85 -
1/5/86 85-39 Resident / 36 Environmental Qualification of 12/6-9, 19/85 Specialist Main Steam Sensing Devices 85-40 Specialist 8 Iodine Uptakes by Workers 12/21/85 (Special)
85-99 SALP 86-01 Specialist 201 Implementation of 0737 Items 1/13-17/86 (Special)
86-02 Resident 215 Routine 1/6 - 2/2/86 86-03 Specialist 88 Non-licensed Operator Training 2/10-14/86 and Offsite Support 86-04 Resident 171 Routine 2/3 - 3/2/86 86-05 Specialist 56 Security 2/18-21/86 86-06 Resident 373 Routine 3/3 - 4/13/86 86-07 Specialist 58 Emergency Preparedness Exercise 4/9-10/86 (Team)
86-08 Specialist 280 Qualification of Electric 3/24-27/86 (Team) Equipment
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T5-3 86-09 Specialist 105 IEB 80-11 5/5-9/86 86-10 Specialist Requalification Examinations 5/9-15/86 86-11 Specialist 42 Fire Protection / Prevention 4/14-18/86 Program 86-12 Resident 393 Routine 4/14 - 6/1/86 86-13 Specialist 74 Refueling Radiological Controls 4/21-25/86 86-14 Specialist 80 Maintenance Program / Activities 4/28 - 5/2/86 86-15 Specialist 11 Independent Safety Reviews and 4/30 - 5/2/86 GORB 86-16 Specialist 55 Nonradiological Chemistry 6/3-6/86 Program 86-17 Resident 179 Routine 6/1 - 7/6/86 86-18 Specialist 33 Diesel Generator Modifications 6/24-27/86 86-19 Specialist 44 Welding and Inservice Inspection 7/7-11/66 86-20 Cancelled 86-21 Resident 252 Routine 7/7 - 8/17/86 86-22 Specialist Operator Licensing Examinations 8/11-15/86 and Requalification Training 86-23 Specialist 43 Ultrasonic Examination of Welds 8/11-15/86 86-24 Resident 356 Routine 8/18 - 10/5/86 86-25 Specialist 35 Refueling Activities 8/25-29/86
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Specialist 1 Review and Planning for L 8/26/86 Underwater Weld Repair 86-27 Specialist 4-6 Local Leak Rate Testing and
- 9/4-9/86 CILRT Procedure-i I_ 86-28 Specialist 42 Review of Administrative
! 8/18-20/86 Overexposure l 9/8-10/86 l
- 86-29 Specialist 32 Effluents and Open Items s 9/30 -
10/3/86
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86-30 Specialist 70 Maintenance, Calibration, and 9/30 - 10/9/86 Concrete Deficiencies
! 86-31 N/A 8 Management Meeting - Piping 9/16/86 Reverification Program
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Table 6 c--
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Enforcement Data
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OYSTER CREEK NUCLEAR GENERATING STATI'ON
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Inspection Inspection Severity Functional x .
l Report N Date Level Area Violation
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85-23 7/1 - 8/18/85 IV Plant Failure to adhere to a Operations , station procedure IV Plant Failure to adhere to a Operations ' station procedure
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85-25 7/29 - 8/1/85 IV Radiological ' Quality Co61.ro11of '
Controls * waste shilments i l 85-33 10/21-25/85 IV Radiological :Transporiatidrb '
Controls fregulations, 85-35 10/21 - 12/1/85 IV Assurance of $21dingProhram
) Quality l IV Technical Failure to provide weld -
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IV Maintenance Modification :v inadequacies
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_ IV Assurance of QC Inspecticas f Quality *
l IV Radiological Failure to survey Controls carry-along items i
- 85-39 EQ enforcement pending .
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1/6 - 2/2/86
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86-02 IV Plant Snubb'er made~ inoperable -
Operations 3/3 - 4/13/86 Failure to maintain
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86-06 IV Technical Support station procedure IV Technical Failure to adhere to Support proaect reviews procedtres 86-08 EQ enforcement pending
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- 86-09 5/5-9/86 V Technical Evaluation of Support Support IV Technical ' Maintenance of records Support Deviation Technical Inadequate Support documentation to support mortar qualification 86-11 4/14-18/86 V Plant Failure to correct Operations a non-conformance 86-12 4/14 - 6/1/86 IV Maintenance Inadequate work control procedure IV Technical Inadequate design Support information IV Technical Weld control precedures Support
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IV Assurance of Inadequate QA/QC Quality (Issued subsequent to SALP period following yrp ,
enforcement conference)
86-17 6/1 - 7/6/86 IV Radiological Failure to lock Controls entrance to high rad area 86-21 7/7 - 8/17/86 IV Radiological Inadequate survey Controls 86-24 8/18 - 10/5/86 IV Technical Lack of safety Support evaluation for a procedure change that
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required one 86-28 8/18-20/86 IV Radiological Inadequate surveys 3. . 9/8-10/86 Controls
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4 j TABLE 7 i l'
7 UNFLANNED TRIPS AND SHUTDOWNS
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Date Descriotion
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Cause 7/1/85 Plant Operating at full power-i 7/8/85 Reactor Scram Lov. condenser vacuum due to cracked y , steam jet air ejector drain pump
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housing - equipment failure
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':- 7/9/85 Startup 7/22/85 Shutdow High Containment Spray heat exchanger i differential pressure caused by
' , delamination inside of emergency of coalservice tar lining on water piping - equipment failure-
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8/3/85 Startup
!. 8/9/85 Reactor Scram During shutdown all IRMs were
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inadvertently inserted while APRM's were downscale - operator error
'8/10/85 Startup
.10/18/85 Shutdown Month long outage for environmental qualification modifications 11/16/85 Startup 11/20/85- Reactor Scram Reactor trip due to generator trip resulting from a current transformer failure - equipment failure
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11/23/8 Startu '
12/15/85 Reactor Scram Electric pressure regulator failed due to a loose wire connection -
personnel error
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12/16/85 Startup 3/6/86- Reactor Scram Turbine trip resulting from limit switch failure - equipment failure
3/7/86 Startup 3/27/86 Shutdown Reactor low level switches declared inoperable - equipment failure 3/30/86 Startup 4/12/86 Shutdown 11R Refueling / Maintenance Modification outage
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TABLE 8 SALP HISTORY 8/1/79 - 10/15/87 g OYSTER CREEK NUCLEAR GENERATING STATION Assessment Report Period OPS RADCON MAIN SURV EP FP SEC OUTC QP LIC TS TRG 10/80 8/1/79 - 2 3 2 3 2 2 2 2 3 N N N 7/31/80 3/81 8/1/80 - 2 2 2 2 2 2 3 2 2 N N N 1/31/81 6/82 11/1/80 - 2 2 3 3 2 2 2 2 N 2 N N 10/31/81 7/83 2/1/82 - 2 2 2 2 2 2 1 2 N 2 N N 1/31/83 10/84 2/1/83 - 1 1 2 1 2 2 2 2 N 2 N N-4/31/84 3/86 5/1/84 - 2 1 3 2 1 2 2 2 N 2 2 N 6/30/8 /1/85 - 2 2 2 1 1 N 1 2 2 2 2 1 10/15/86 N = Not Evaluated During Assessment Period
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Table 9 LICENSING ACTIVITIES NRR/ Licensee ~ Meetings (at NRC or Licensee HQ)
Cycle 11 Refueling outage 07/02/85 August 1985 Progress Review Meeting 09/18/85 Expanded Safety System Facility Status 09/20/85 Detailed Control Room Design Review 10/09/85 September 1985 Progress Review Meeting 10/24/85 at State of New Jersey, BRP Deferments from Cycle 11R outage 11/20/85 Deferment of Feedwater Nozzle Inspection 12/13/85 from Cycle 11R outage December 1985 Progress Review Meeting 01/22/86 Discuss the channel checks for RWL 01/23/86 instrumentation Discuss special circumstances for 02/11/86 licensee's exemptions to Appendix R Integrated living schedule program for 02/12/86 Oyster Creek February 1986 Progress Review Meeting 03/26/86 NUREG-0737 Items II.F.1.1 and II.F. /02/86 Containment purge / vent isolation valves 04/03/86 Upgrade containment nitrogen purge / vent 04/10/86 system March 1986 Progress Review Meeting and 04/23/86 Director's annual visit to licensee HQ Seismic design considerations 04/24/86 Generic Issue 77, Flooding of Safety 04/30/86 Related Equipment Erratic behavior of dp Static-0-Ring switches 06/12/86 Isolation condenser piping penetrations 08/22/86 Integrated leak rate testing 09/10/86 August and September 1986 Progress Review 10/31/86 Meeting NRR Site Visits and Meetings June 1985 Progress Review Meeting 07/31 to 08/01/86 October / November 1985 Progress Review Meeting 12/11/85 January 1986 Progress Review Meeting 02/20-21/86 Director of DBL visited site 03/24/86 March 1986 Progress Review Meeting and 04/22/86 Director's annual visit to site April and May 1986 Progress Review Meeting 06/16-17/86 Exemptions to Appendix R 06/23/86
_ Plant orientation visit 08/25-29/86 June and July 1986 Progress Review Meeting 08/27-28/86
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o T9-2 Commission Meetings None Reliefs Granted Deferment of modifications from Cycle 11R 10/06/86 Cancel replacement of containment purge / vent 10/10/86 isolation valves Cancel modifications of torus for thermal 10/01/86 mixing and local quencher temperature monitoring Cancel modification to SGTS duct 04/18/86 Defer inspection of feedwater nozzles from 02/24/86 Cycle 11R outage Revise requirements on recirculation loop 07/15/86 interlock ,
5. Schedular Extensions Granted SPDS implementation 10/06/86 Control room habitability 07/15/86 Mark I containment modification 10/06/86 6. Exemptions Granted Exemption to Appendix R 03/24/86 7. Licensee Amendments Issued Amendment Title Date 87 Drywell-Suppression Chamber 07/01/85 Differential Pressure 88 Relief Valve Position Indication 07/01/85 89 Audits of the Fire Protection 07/02/85 Program and Quality Assurance Program 90 Inservice Inspection and Testing 10/18/85 91 Low-Low Reactor Water Level 11/19/85 Instrumentation Modification 92 Limit Overtime 11/19/85 i
93 Water Purity of Reactor Coolant 11/21/85 94 NUREG-0737 Technical Specifica- 11/22/85 tions (GL 83-36)
95 Reactor Water Level Instrumenta- 11/30/85 tion Channel Check
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i^ .o T9-3 License Amendments Issue, Continued Amendment- -Title Date 96 Valve Position Indicator Accident 12/09/85 Monitoring Instrumentation 97 Reactor Coolant Pressure Boundary 01/06/86 Leakage 98 Post Accident Sampling Program 01/14/86 99 Standby Diesel Generator Fuel 02/04/86 Tank 100 Mechanical and Hydraulic Snubbers 03/31/86 101 Diesel Generator Pump Battery 03/31/86 System 102 Licensed Control Room Operators 05/12/86 Onsite 103 Standby Gas Treatment System 05/28/86 104 Excess Flow Check Valves 07/09/86 105 Control Room Habitability 07/15/86 106 Recirculation Pump Interlock 07/15/86 Scope Change
, 107 Appendix B Technical Specifications 07/17/86
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Retyped Appendix A Technical 10/01/86 Specifications Emergency License Amendments Amendment Title Date 88' Relief Valve Position 07/01/85 Indication 91 Low-Low Reactor Water Level 11/19/85 Instrumentation Modification 95 Reactor Water Level Instrumentation 11/30/85 Channel Check
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c:,c FIGURE 1 NUMBER OF DAYS SHUTDOWN ( ) PER MONTH 1985 JUL 2 Shutdowns _ (10 days)
AUG I 35 (4 days)
SEP OCT 1 Shutdown (13 days)
NOV 1 Shutdown (20 days)
1986 JAN FEB MAR 2 Shutdowns (5 days)
APR 1 SD Refuel / Mod /Maint Outage (18 days)
MAY JUN JUL AUG SEP OCT End of SALP Period NOV 5 10 15 20 25 30
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