IR 05000289/1989026
| ML20012B726 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/27/1990 |
| From: | Young F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20012B722 | List: |
| References | |
| 50-289-89-26, NUDOCS 9003160177 | |
| Download: ML20012B726 (78) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
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Report No.
50-289/89-26
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. Docket No.
50-289
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' License No.
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i Licensee:
GPU Nuclear Corporation
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P.O. Box 480
p Middletown, pennsylvania 17057
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Facility:
Three Mile Island Nuclear Station, Unit 1
i Location:
Middletown, Pennsylvania Dates:
December 19, 1969.- January 23, 1990
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Inspectors:
R. Brady, Resident Inspector 0. Johnson, Resident Inspector
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T. Moslak, Resident Inspector F. Young, Senior Resident Inspector l
YAmebkeune df Approved by:
F. Young, ing CA ef ate
Reactor P cts M tion No. 4B
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Division of Reactor Projects i
Inspection Summary:
Inspection Report No. 50-289/89-26 for December 19, 1989 -
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January 23, ib90.
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l Areas Reviewed:
The NRC staff conducted routine safety inspections of power
operation, reduced power operation and plant shutdown /cooldown activities.
The-inspectors reviewed plant operations and maintenance / surveillance activities as
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they related to plant safety. -Specific items reviewed included plant shutdown
.for the BR refueling outage, an anomalous dose equivalent iodine RCS sample, an t
inadvertent RPS/ESF actuation resulting from surveillance testing on contain-ment isolation valves and CA-V-2 local leak rate test. Other items addressed
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L included a meeting with.the licensee for the mid-cycle SALP assessr.ent, fitness
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for duty training, a meeting with the licensee to discuss the 8R outage, review of LER's'for 1989, and licensee action on previous inspection findings.
Results: 0perations continue to be conducted safely.
The plant power coast i
down evolution to the end of the operating cycle was completed in a safety
conscious fashion. The subsequent plant shutdown and cooldown for the BR outage was accomplished expeditiously.
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A violation was identified during conduct of a local leak rate test for containment isolation valves for the 4 psig reactor building RPS/ESF actuation signal instrumentation. This violation indicated that insufficient guidance is contained in many surveillance procedures for technicians with minimal system knowledge. Generally, the large number of surveillances completed during the shutdown /cooldown were accomplished safely including the complex power transfer test.
Fitness for duty training was considered adequate but a weakness was identified in one area concerning identification of the illegal use of controlled substances. The licensee /NRC staff meetings were productive.
Licensee presentations for the outage and mid-SALP assessment were thorough and compre-hensive.
LER quality was generally very good, and licensee action on previous inspection findings was adequate.
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l SUMMARY OF PLANT PERFORMANCE 1989 j
(0001, 1/1/90)
(52 WKS)
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102% CAPACITY FACTOR
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54 PERSON REM EXPOSURE
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Attachment 2 Nuclear s;28pB9-26
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_ CONTRIBUTORS 1MPROVED MATERIAL CONDITION
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0- PREVENTATIVE MAINTENANCE (PM)
PROGRAM i
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PM ASSESSMENT PROGRAM
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0 - SUCCESSFUL - 7R OUTAGE
SYSTEM OUTAGES s
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AROUND THE-CLOCK MAINTENANCE O'
p ENGINEERING SUPPORT TO PLANT
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ATTENTION TO DETAIL - ALERTNESS
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STRONG, EFFECTWE OPERATOR TRAINING
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PROGRAM
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0 SIMULATOR
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0- APPLICATION IN PLANT AGGRESSIVE APPROACH-TO PROBLEM SOLVING
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0 UTILIZE RESOURCES OF. ENTIRE ~ GPUN ORGANIZATION
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POSITIVE EMPLOYEE ArnTUDE
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MANAGEMENT LEADERSHIP - OWNERSHIP-
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TEAMWORK
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INITIATIVES UNDERWAY j
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. UPGRADING PROCEDURES - PROCEDURE COMPLIANCE
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. INCREASING INVOLVEMENT OF CRAFT PERSONNEL-
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IMPLEMENTING PROFESSIONALISM PROGRAM
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IMPROVING WORK PLANNING
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EMPHASIZING FIRST LINE SUPERVISOR DUTIES
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IMPLEMENTING QUALITY MAINTENANCE TRAINING
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CONTINUING RELIABILITY CENTERED MAINTUANCE
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IMPLEMENTING THE RECOMMENDATIONS
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MAJOR. UPGRADING OF SITE FACILITIES
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-NRC MAJOR INSPECTIONS
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EMERGENCY OPERNHNG PROCEDURES (EOP)
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8 ADEQUATE FOR ' CONTINUED OPERATION
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L8 WILL ADDRESS HUMAN FACTORS COMMENTS
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MAINTENANCE INSPECTION s
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Page 9 1989 ' OPERATOR CHALLENGES
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LARGEST SINGLE CAUSE INTEGRATED CONTROL SYSTEM (ICS)
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PROBLEMS 14 PROBLEMS WERE PICKED
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MOST SIGNIFICANT ITEMS
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O POTENTIOMETER, SWITCH AND CAPACITOR REPLACEMENT -
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ADVANCED CONTROL SYSTEM
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J B&W OWNERS GROUP TASK FORCE GOALS
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IMPROVE RELIABILITY, OPERABILITY AND
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MAINTAINABILITY OF THE INTEGRATED
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CONTROL AND NON NUCLEAR INSTRUMENTATION l
SYSTEM.
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L RESOLVE ICS / NNI COMPONENT OBSOLESCENCE
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ISSUE -
REPLACE THE ICS / NNI SYSTEM WITH A
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' STATE-OF THE-ART DIGITAL SYSTEM
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DIRECT INVOLVEMENT OF UTILITIES IN
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FAULT TOLERANT
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SINGLE HARDWARE FAILURE
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SELF DIAGNOSITCS
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= ADVANCED CONTROL-SYSTEM (CONT.)
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SCHEDULE
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VENDOR SELECTION MID 1990
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ALGORITHM DEVELOPED MID.1991
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PROTOTYPE DELIVERED MID 1991
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PROTOTYPE TESTED 3RD QUARTER '1992
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UTILITY INSTALLS IST ACS APPROX.1995
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ROCKVILLE OFFICE
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Attachment 1 50-289/89-26
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Page 12.
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1989 OPERATOR CHALLENGES
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O AVERTED OR MINIMlZED BY
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ON-LINE MONITORING
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RELIABLE BACKUP EQUIPMENT
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UNNECESSARY' TRIPS' DISABLED
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LOW OPERATOR / TECHNICIAN ERROR RATE
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PRE-PLANNING AND PRE-STAGING
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OPERATOR RESPONSE CORRECT AND TIMELY
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50-289/89-26
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EREVENTION AND ALERTNESS (AVOIDED INiSERVICE - FAILURES)
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0 PROGRAMS VIBRATION ~ ANALYSIS
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IN PLACE CORRECTION (SR P 1A,
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SR P-3A, NR P-1C)
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INCREASED MONITORING (DH-P-1A,
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OVERHAUL BEFORE FAILURE (N R-P-1B,
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SR P 3B, AH E-9A, VA-P 1C, HD P-1C)
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38 HOT SPOTS-WHICH REQUIRED -
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CORRECTIVE ACTION SEVERAL REQUIRED IMMEDIATE ACTION
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(SW-P-2A, MO P-1B, CRDM GP 5 PHASE AA, PRESSURIZER HEATERS (GP 8 & - 9)
O PEOPLE ' ALERTNESS EMPLOYEE IDENTIFIED DEFICIENCIES
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NS P 1 BEARING
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CO-P-1C SUCTION EXPANSION JOINT
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SMALL H2 VALVE LEAKS
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VA-P-2C AUXILIARY VACUUM PUMP SEAL
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VA P-1A MAIN VACUUM PUMP MOTOR
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BEARING 111-5
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PROCEDURES
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0- PROCEDURE SPECIALIST POSITION FILLED
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'O BIENNIAL - REVIEW PROCESS REVISED
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" MAINTENANCE PROCEDURE FORMATS CONSOLIDATED.;
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-O' ISSUED MAINTENANCE PROCEDURE WRITERS GUIDE
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QUALITY / USAGE
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CURRENT EMPHASIS ON MAINTENANCE PROCEDURES
PROCEDURE IMPROVEMENTS ON BIENNIAL REVIEW
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Page 16-
. OPERATIONS 0. STAFF SIZE AND EXPERIENCE 6-SHIFTS, 7 SHIFT SUPERVISORS, 2 CRO'S
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WITH SRO LICENSE, 54. TOTAL LICENSES AVERAGE-EXPERIENCE:
SS 18 YEARS;
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SF.12 YEARS; CRO 9 YEARS 19-LICENSED OPERATORS RECERTIFIED - BY
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LICENSED OPERATOR-TURNOVER (1989)i 2
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RESIGNATION i -TRANSFER-TO' NON-LICENSED TRAINING POSITION y
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OPERATIONS
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i 0 OUTAGE PLANT STATUS CONTROL
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i INTEGRATED SCHEDULE /GMS II t
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OUTAGE ORGANIZATION (SHIFT
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WORK BOUNDARIES CONTROLLED BY
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0 INITIATIVES THIRD SRO ON SHIFT
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EQUIPMENT PAINTING
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Page 18 CHEMISTRY CONTINUED MORPHOLINE TREATMENT OF CONDENSATE /
FEEDWATER SYSTEMS
-REDUCED CORROSION AND ' CORROSION PRODUCT TRANSPORT 0 -
MINIMlZED AP BUILDUP IN OTSG'S UPGRADED ANALYSIS CAPABILITIES 0-DEVELOPED CORPORATE WIDE LABORATORY QC - PROGRAM TO BETTER DEFINE LLD'S AND EVALUATE BLIND SAMPLE 'RESULTS
FLUORIDE LOWERED LLD FROM 20 PPB TO -
10 PPB (PRIMARY SIDE) AND
<1 PPB-(SECONDARY SIDE)
O CHLORIDE LOWERED LLD FROM 1 PPB - TO 0.5 PPB (SECONDARY SIDE)
O SECONDARY PLANT ON LINE CHEMISTRY MONITORING IMPLEMENTED ON-LINE - ANALYSES
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FOR CHLORIDE, ACETATE, FORMATE AND FLUORIDE IMPLEMENTING ADDITIONAL DISSOLVED
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OXYGEN MONITORING, ON LINE MORPHOLINE AND-AMMONIA ANALYSES AND COMPUTERIZING COLLECTION OF ON-LINE DATA TO IMPROVE TRENDING
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OTHER CHEMISTRY INITIATIVES ESTABLISH -RADIOCHEMIST POSITION TO SUPPORT RAD CON AND CHEMISTRY BACKUP COUNTING LABORATORY IN TURBINE BUILDUP EXPANSION SECONDARY LABORATORY EXPANSION DOUBLING BENCH AND FUME HOOD SPACE ACTIVELY PURSUING REPLACEMENT-OF GASEOUS CHLORINE AS A RESULT OF:
'O PERSONNEL SAFETY CONCERNS
ENVIRONMENTAL RELEASE CONCERNS
CONTROL ROOM HABITABILITY CONCERNS
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MAINTENANCE
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AND 7 FOREMEN
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--62 DAYLIGHT CRAFFS WITH 15 FOREMEN AND 4 LEAD FOREMEN AVERAGE EXPERIENCE:
14 YEARS
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INPO ACCREDirATION FOR MECHANICAL &
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ELECTRICAL IN 1989, I&C IN 1990
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0 ONGOING PROGRAMS PREVENTIVE AND PREDICTIVE MAINTENANCE
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RELIABILITY CENTERED MAINTENANCE
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MAINTENANCE
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0 JOB PLANNING PLANNING ORGANIZATION FULLY MANNED
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GMS II (WORK MANAGEMENT SYSTEM)
IN
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PLACE PLANNING BACKLOG REDUCED
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PLANNERS WILL REMAIN INVOLVED AS WORK
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SCOPE CHANGES l
0 INITIATIVES GMS II AND INTEGRATED SCHEDULE
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IMPROVED TRACKING / MONITORING SYSTEMS FOR MAINTENANCE PROCESS
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Page 24 tr
- RADIOLOGICAL CONTROLS
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TOTAL PERSON REM
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INITIATIVES-1 i
SOURCE TERM REDUCTION - EMPHASIS
'O COLLECTIVE DOSE OVERVIEW-GROUP (SENIOR MANAGEMENT)
0 AD HOC SOURCE TERM REDUCTION GROUP
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0- EVALUATING; H 022 ADDITION, COORDINATED PH/LI
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0 - FURTHER COBALT REDUCTION
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. RADIOLOGICAL.. ASPECTS-OF 8R OUTAGE PLANNING l
0 : ADDITIONAL RAD CON SUPERVISOR / TECHNICIAN MANPOWER
0 EXPANDED PLANT-DECONTAMINATION EFFORT
USE. OF': LASER VIDEODISC SYSTEM FOR JOB - PLANNING 0 ADVANCED RADIATION WORKER TRAINING IN GET 0 - CONTROL POINT FACILITY MODIFICATIONS 0 RADIO SYSTEM FOR IMPROVED COMMUNICATIONS l
0: IMPROVED AIRBORNE IODINE CONTROLS IN CONTAINMENT
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RADIOLOGICAL CONTAINMENT REDUCTION PROGRAM O COORDINATED BY MAINTENANCE DEPARTMENT III.C-2
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.50-289/89-26.,
SALP REPORT ISSUES.
. Page' 26,.
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ITEM STATUS UNNECESSARY RADIATION-EXPOSURE FOR BDENTIFIED BY GPUN EARLY IN 7R.
7R OUTAGE SCAFFOLD ERECTION - GOOD MAGNITUDE - FEW REM.
SCAFFOLD MANAGEMENT RESPONSE NOTED IN ;SALP
' COORDINATOR ESTABLISHED FOR 8R.'
PERMANENT SCAFFOLD INSTALLATION PLANNED FOR BR C
NEW RADRATION SURVEYS OCCASIONALLY EMPHASIS BY RADCON AND QA I
NOT POSTED FOR EXPIRED SURVEYS HAS EFFECTIVELY ELIMINATED THIS
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