ML20235E479
| ML20235E479 | |
| Person / Time | |
|---|---|
| Issue date: | 06/25/1987 |
| From: | Jordan E NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Haag F NEW YORK, STATE OF |
| Shared Package | |
| ML20235E440 | List: |
| References | |
| FOIA-87-371 NUDOCS 8707110077 | |
| Download: ML20235E479 (11) | |
Text
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Mr. Fred G. Haag State of New York Department m
Nuclear Power Generatio.c '. ;,.j" k7 Ai,.. --
1 of Public'Sarvice A p C h..,_
n Planner Systes Planning Sectica.
Power Division l
Three Empire State Plaza l
Albu:y. NY 12222 l
Dear Mr. Haag:
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l In response to your June 19 letter requesting a copy of the paper I presented at the June 22 AIF meeting in hfashington, 0.c., I as sending you a copy of the slides I used.
There waino prepared Wianuscript but the slides outline the material presented.
If you.hcve further questions about NRC use of perforniance indicators I will be glad te discuss then with you.
1 Sincerely,
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& W 4 5'e d! on E. C Sk Edward L, Jordan,, Director I
Office for Analysis and Evaluation of Operational Data l
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.r NRC PERFORMANCE INDICATOR PROGRAM-FOR OPERATING NUCLEAR POWER PLANTS 1
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NUCLEAR LEGAL AND LICENSING SYMPOSIUM JUNE 22, 1987
..a EDWARD L. JORDAN, DIRECTOR.
l OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA 6
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PROVIDE OBJECTIVE INPUT TO ASSIST NRC SENIOR MANAGEMENT IN PROMPT IDENTIFICATION OF P00R OR DECt.INING SAFETY PERFORMANCE AND AS AN INPUT TO ADJUST NRC PROGRAMS, 1
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BACKGROUND OF THE PROGRAM q
STAFF BRIEFED THE COMMISSION ON A PROPOSED PROGRAM (SECY 86-317)
-0N NOV. 7, 1986 THE COMMISSION APPROVED THE PROGRAM IN DEC.1986 WITH SOME i
CHANGES STAFF POLICY ON PPOPER USE OF PERFORMANCE INDICATORS DELETION OF ENFORCEMENT ACTION INDEX l
TAKE INTO ACCOUNT INP0 CONCERNS I
EXPLORE INDICATORS IN SEVERAL AREAS l
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STAFF BRIEFED THE COMMISSION ON PROPOSED NRC/INP0 COORDINATION PLAN (SEC 87-117) ON JUNE 9, 1987 l
FORMAll2E INTERFACE 1
PROVIDE FOR DATA SHARING CLARIFY RESPECTIVE NRC AND INP0 ROLES i
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COORDINATION WITH INDUSTRY ~
i CONTACTS WITH INDIVIDUAL LICENSEES ANS EXECUTIVE SEMINAR (SEPT 1986) l i
i REGIONAL WORKSHOPS FOR LICENSEES (JAN-MAR 1987)
J COORDINATION WITH INP0 ON ON-G0ING BASIS FOR DEVELOPMENT AND-IMPLEMENTATION COMMON DEFINITIONS OF CERTAIN Pls COORDINATION PLAN 4
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USE AMD LIMITATIONS OF Pls i
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-0NLY A TOOL FOR EARLY SCREENING OF PLANTS l
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i P!s NOT FOR RANKING PLANTS l
i NOT THE SOLE BASIS FOR MAKING DECISIONS ABOUT PERFORMANCE I
SENIOR NRC MANAGEMENT TO REVIEW PI DATA ALONG WITH SALP l
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l RESULTS OF INSPECTIONS 1
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l 0THER REGIONAL /HQ INPUTS REVIEW ON 6-MONTH INTERVALS DETAILED POLICY / PROCEDURES IN DEVELOPMENT 5
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STATUS OF THE PROGRAM SEVEN INDICATORS CURRENTLY IN THE PROGRAM TOTAL AUTOMATIC SCRANS (INP0)
SAFETY SYSTEM ACTUATIONS (INP0)
SIGNIFICANT EVENTS SAFEYY SYSTEM FAILURES
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FORCED OUTAGE RATE (INP0)
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EQUIPMENT FORCED OUTAGES PER 1000 CRITICAL HOURS COLLECTIVE RADIATION EXPOSURES (INP0)
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COLLECTIVE RADI ATION EXPOSURE RECENTLY ADDED TO THE PROGRAM j
i DATA CURRENTLY AVAILABl.E TO STAFF ON ANNUAL BASIS QUARTERLY DATA PLANNED TO BE OBTAINED FROM INP0 DATA FOR THE OTHER SIX IS AVAILABLE FROM NRC SOURCES OVARTERLY REPORTS PROVIDED TO THE SENIOR MI,NAGEMENT IN FEB '87 AND MAY '87
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SELECTION OF Pls f
J e D CRITERIA (IDEAL ATTRIBUTES OF Pls):
PIs RELATED TO NUCLEAR SAFETY / REGULATORY PERFORMANCE DATA AVAILABLE TO NRC READILY AND TIMELY DATA NOT SUSCEPTIBLE TO MANIPULATION DATA COMPARABLE BETWEEN UTILITIES
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Pls WORTHY GOAL FOR UTILITY Pls RELFECT A RANGE OF PERFORMANCE PIs INDEPENDENT OF EACH OTHER Pls LEADING OR PREDICTIVE OF FUTURE PERFORMANCE SET OF Pls BROAD EN0 UGH TO CORRELATE WITH SALP 7
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RELATIONSHIP 0F Pts TO LOGIC MODEL4yg@
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- FORCED OUTAGE
- EQUIP, FORCED SAFETY SYSTEM RATE OUTAGES ACTUATIONS
- SAFETY SYSTEM
- COLLECTIVE RAD SIGNIFICANT EVENTS FAILURES EXPOSURE 8
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PLANS FOR DEVELOPMENT REFINEMENT OF THE PROGRAM' DATA PRESENTATION / DISPLAY FACTORING IN PLANT TYPE, AGE RESOLUTION OF STATISTICAL ISSUES RISK-BASED Pts RISK-WEIGHTING'0F SOME EXISTING Pls UNAVAILABILITY (SYSTEM / TRAIN FROM LCOs).
TRANSIENT FREQUENCY INTEGRATED WITH UNAVAILABILITY PROGRAMMATIC Pls MAINTENANCE (ITEMS OUT OF SERVICE, LCOs, SAFETY SYSTEM REWORK)
TRAINING (OPERATOR LICENSING EXAM RESULTS) l CAUSE 0F EVENTS (PERSONNEL ERROR, MAINT., EQUIP, l
FAILURE, DESIGN / FABRICATION / CONSTRUCTION ERROR) l STAFFING (VACANCIES, OVERTIME, TURNOVER RATE, CONTRACTOR, SUPPORT)
MANAGEMENT (GENERIC ISSUES BACKLOG, EFFECTIVENESS) 1 9
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DEFINITIONS OF PIs IN THE CURRENT PROGRAM 1.
AUTOMATIC SCRANS WHILE CRITICAL:
THIS IS IDENTICAL TO THE INDICATOR, UNPLANNED AUTOMATIC SCRAMS WHILE CRITICAL, USED BY INPO. IN ADDITION, THE NUMBER OF AUTOMATIC SCRAMS FROM ABOVE 155 POWER PER 1000 CP.ITICAL HOURS AND THE NLNBER OF AUTOMATIC SCRAMS WHILE CRITICAL BELOW 155 POWER WILL BE MONITORED.
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SAFETY SYSTEM ACTUATIONS:
THIS IS IDENTICAL TO THE INDICATOR, UNPLANNED SAFETY SYSTEM ACTUATIONS, USED BY INPO AND INCLUDES ACTUATIONS OF ECCS (ACTUAL AND INADVERTENT) AND EMERGENCY AC POWER SYSTEM (ACTUAL).
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SIGNIFICANT EVENTS:
THESE EVENTS ARE IDENTIFIED BY THE DETAILED SCREENING OF OPERATING EXPERIENCE BY NRR AND AE00, AND INCLUDE DEGRADATION OF IMPORTANT SAFETY I
EQUIPMENT, UNEXPECTED PLANT RESPONSE TO A TRANSIENT OR A MAJOR TRANSIENT, DISCOVERY OF A MAJOR CONDITION NOT CONSIDERED IN THE PLANT SAFETY ANALYSIS, OR DEGRADATION OF FUEL INTEGRITY, PRIMARY COOLANT PRESSURE BOUNDARY, OR IMPORTANT ASSOCIATED STRUCTURES.
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SAFETY SYSTEM FAILURES:
THIS INCLUDES ANY EVENT OR CONDITION THAT_ALONE COULD PREVENT THE FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES OR SYSTEMS.
TWENTY-FOUR SYSTEMS OR SUBSYSTEMS WILL BE MONITORED FOR THIS INDICATOR.
5.
FORCED OUTAGE RATE:
THIS INDICATOR'S DEFINITION IS IDENTICAL TO THE ONE USED BY INPO AND THE NRC GREY BOOK (NUREG-0020), AND IS THE NUMBER OF FORCED OUTAGE HOURS DIVIDED BY THE SUM OF FORCED OUTAGE HOUP.S AND SERVICE HOURS.
6.
EQUIPMLNT FORCED OUTAGES PER 1000 CRITICAL HOUR $:
THIS IS THE INVERSE OF THE MEAN TIME BETWEEN FORCED OUTAGES CAUSED BY EQUIPMENT FAILURES. THE MEAN TIME IS EQUAL TO THE NUMBER OF HOURS THE REACTOR IS CRITICAL IN A PERIOD DIVIDED BY THE NUMBER OF FORCED OUTAGES CAUSED BY EQUIPMENT FAILURES IN THAT PERIOD.
7.
COLLECTIVE RADIATION EXPOSURE:
THIS IS IDENTICAL TO THE ONE USED BY INPO.
IT IS THE TOTAL DOSE AT THE STATION. THE STATION TOTAL IS DIVIDED BY THE NUMBER OF UNITS AT THE SITE CONTRIBUTING TO EXPOSURE TO OBTAIN UNIT VALUES.
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