ML19309D566

Slide Presentation Entitled Fundamental Lesson

ML19309D566
Person / Time
Site:	Crane
Issue date:	10/25/1979
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19309D561	List: ML19309D559 ML19309D562 ML19309D563 ML19309D564 ML19309D565 ML19309D566 ML19309D567
References
ACRS-1684, NUDOCS 8004100527
Download: ML19309D566 (10)

Text

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O FUNDAMENTAL LESSON e

OPERATIONS SAFETY MERITS PARAMOUNT ATTENTION e

BUT OPERATIONS SAFETY NOT MORE IMPORTANT THAN SAFETY IN DESIGN e

INTEGRATING AND OPTIMIZING THE TWO AREAS SHOULD BE OUR OBJECTIVE a

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OPERATIONS SAFETY INCLUDES e

HUMAN FACTORS ENGINEERING e

PERSONNEL QUALIFICATIONS AND TRAINING e

QUALITY ASSURANCE OF OPERATIONS e

TECHNICAL AND MANAGEMENT SUPPORT OF OPERATIONS G0ALS OF OPERATIONS SAFETY ARE e

REDUCE CHALLENGES TO SAFETY

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e MITIGATE CHALLENGES TO SAFETY l

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OPERATIONS SAFETY IS UNIQUELY A NUCLEAR UTILITY'S RESPONSIBILITY NRC MUST SET CRITERIA AND VIG0ROUSLY ENFORCE THEM BUT HIGH RELIABILITY ONLY COMES FROM HANDS ON, DAY-TO-DAY ATTENTION TO DETAILS BY THE UTILITY l

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IMPROVEMENTS IN PLANT DESIGN e

BETTER IMPLEMENTATION OF PRESENT REQUIREMENTS e

USE OF PROBABILISTIC TECHNIQUES TO CROSS CHECK RESULTS OF DETERMINISTIC TECHNIQUES

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e INCLUSION OF DESIGN FEATURES FOR MITIGATION OF DEGRADED CORE AND CORE MELT ACCIDENTS f

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8 IMPROVEMENTS IN REACTOR REGULATION IMPROVED SAFETY POLICY BASIS -- SAFETY G0AL e

e BACKFIT POLICY REFORM OF LICENSING PROCESS TO IMPROVE QUA e

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. 'e ATTENTION TO UNRESOLVED SAFETY ISSUES 1

IMPLEMENTING LESSONS LEARNED FROM OPERATING e

EXPERIENCE n.

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n...... a TECHNICAL SUPPORT FOR EMERGENCY RESPONSE e

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1, r RSONNEL QUALIFICATIONS Ato IRAINING e

1.1 UTILITY MANAEENT ltNOLVEMENT 1.2 TRAINING PROGRA'4S 1.3 IN-PLANT DRILLS 1.4 OPERATOR LICENSING 1.5 tRC STAFF COORDINATION 1.6 LICENSED OPERATOR QUALIFICATIONS 1.7 LICENSEE TECHNICAL Are MANAGEtEtR SUPPORT i

1.8 LICENSING OF ADDITIONAL OPERATING PERSONfEL

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2. STAFFING OF CONTROL ROOM l

3. WORKING HOURS

4. SERGENCY PROCEDURES

5. VERIFICATION OF CORRECT PERFmtW EE & OPERATING j

ACTIVITIES

6. EVALUATIm & OPERATING EXPERIENCE 6.1 NATI0fMIm NETWORK 6.2 PROVIDING INF m m TION TO OPERATE S 7

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7. FW4 % CHINE INTERFACE 7.1 CG4TR3. fM) REVIEWS 7.2 PLANT SAFETY STATUS DISPL.AY 7.3 DISTURBANCE ANALYSIS SYSTEMS 7 A MANUAL VERSUS AuTa% TIC OPERATICt4S 7.5 STAR 0ARD CQ4TRa. Rm4 DESIGN

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8. RELIABIU TY ASSESSMEtTfS OF FINAL DESIGNS

9. REVIEW OF SAFETY CLASSIFICATIONS NO QUALIFICATICt4S

10. DESIGN FEATURES FOR CORE-MELT ACCIDENTS

11. DESIGN FEATURES FOR DEGRAI)ED CORE ACCIDENTS Y

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12. SA ET'l JAL Fm REACTm REGULATIM I

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13. STAFF REVIEW OBJECTIVES

14. tER EmasucY REsemsE TEAM 10 l