ML20211N761

Notification of 860616 Meeting W/Idcor & BWR Owners Group in Bethesda,Md to Discuss Idcor Methodology for Individual Plant Evaluations of Sys Reliability & Containment Performance During Severe Accident Conditions

ML20211N761
Person / Time
Issue date:	06/09/1986
From:	Bernero R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20209E138	List: ML20209E134 ML20209G637 ML20210B280 ML20210B759 ML20210B807 ML20210C592 ML20210G952 ML20210J028 ML20210L538 ML20210V255 ML20211A674 ML20211K137 ML20211K492 ML20211K505 ML20211K519 ML20211N756 ML20211N761 ML20212F264 ML20212N701
References
FOIA-87-10 NUDOCS 8607030237
Download: ML20211N761 (18)

Text

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UNITED STATES

[/'.t,"s-(( [g NUCLEAR REGULATORY COMMISSION s

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WASHINGTON, D C. 20555 ng;x.%, N;r

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June 9,1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Robert M. Bernero, Director Division of BWR Licensing

SUBJECT:

BWR MARK I, II AND III CONTAINMENT PERFORMANCE DURING l

SEVERE ACCIDENTS PURPOSE:

Discuss IDCOR methodology for Individual Plant Evaluations (IPE) of systems reliability and containment performance during severe accident conditions.

DATE/ TIME:

June 16, 1986 1:00 p.m. - 5:00 p.m.

Phillips Building LOCATION:

~

Bethesda, Maryland Room P-110 REQUESTED PARTICIPANTS:

NRC INDUSTRY R. M. Bernero IDCOR Group Representatives T. Speis BWR Owners' Group Representatives R. W. Houston G. Lainas J. Zwolinski E. Adensam D. Muller W. Butler m.

A Robert M. Bernero, Director Division of BWR Licensing m

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l6 PP

.1

- 91

^

1

-._.~., __

NRC SEVERE ACCIDENT POLICY e

FUTURE PLANTS STANDARD CONVENTIONAL REVIEW PRA 1

e EXISTING PLANTS THEY ARE SAFE EN0 UGH IDCbRPROCESS15'NEEDED INDIVIDUAL PLANT EVALUATIONS GENERIC TREA'TMENT FOR GENERIC MATTERS

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, - -. + ->. = - -.-> - - - - + - - - - ---ev-,-,-,--m--,n,,---e,

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2 e

TWO ACTIVITIES e

DEVELOPMENT-0F EMERGENCY OPERATING PROCEDURES SCOPE:

PREVENTION AND MITIGATION EPG

> PGP

> E0P NOW ON EPG REV. 4 e

IDCOR IPE SCOPE:

PREVENTION A11D MITIGATION METHODOLOGY

> IPE PROGRAM

>IPE METHODOLOGY BEF0,RE NRC e

COMMON FACTORS ARE IMPORTANT SCOPE PLANT / EVENT ANALYSIS 3

c L

3 CONCERNS e

E0P WHAT ARE THE E0P STRATEGIES?

WHAT ARE MINIRA TO TRANSFER FROM EPG

> PGP

> EOP?

ARE REQUIREMENTS CLEAR?

e IDCOR IPE IS IT AN ASSESSMENT OR AN EVALUATION?

SHAILEACHOWNERENTERTHEIPEWITHABLANKSLATE?

ARE THERE ANY GENERIC SOLUTIONS OR STRATEGIES EVIDENT?

PRIORITIES?

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e

I, 4

4

.6-RECALL WASH-1400 e

BWR VS PWR PROBABILITY OF CORE MELT BWR <

PWR CONSEQUENCES OF CORE MELT BWR ->

PWR e

BWR CHARACTERISTICS

-5 BWR-3 2 x 10 TC-y

',TW-7 6 x'10-6 BWR-2 TW-g' e

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3 A 5 ELEMENT POLICY 1.

HYDROGEN 2.

SPRAYS 3.

. PRESSURE 4.

CORE DEBRIS 5.

TRAINING AND PROCEDURES O

6 ELEMENT 1 - HYDR 0 GEN OBJECTIVE:

PREVENT HYDROGEN COMBUSTION CAUSED FAILURE REQUIREMENTS:

A.

0XYGEN CONTROL INERT TO START CONTROL INGRESS OF OXYGEN B.

HYDROGEN CONTROL CONTROLLED BURNING EQUIPMENT SURVIVABILITY 4

ISSUES:

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WHEN AND HOW LONG NOT INERTED i

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2.

INDEPENDENT POWER FOR IGNITERS l

3.

SURVEILLANCE FOR IGNITERS i

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7 ELEMENT 2 - SPRAYS OBJECTIVE: -SPRAY WATER T0:

1.

LOWER PRESSURE 2.

COOL VULNERABLE EQUIPMENT 3.

QUENCH DEBRIS 4.

SCRUB AEROSOLS REQUIREMENTS:

1.

SPRAY IN DRYWELL

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2.

• BACKUP WATER SOURCES AND PUMPS HOSE CONNECTIONS USE OF FIREMAINS ISSUES:

1,. - -. 3 r m,,

1.

RISK 0F IMPLOSION 2.

RISK 0F HYDROGEN COMBUSTION AFTER STEAM CONDENSATION 3.

MANUAL ACTIONS AND TIMING e

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8 ELEMENT 3 - PRESSURE OBJECTIVES: 1.

AVERT UNCONTROLLED OVERPRESSURE FAILURE 2.

CONTROL RELEASE PATH (SCRUBBING)

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Rt0VIREMENTS:

1.

SUBSTANTIAL CAPABILITY TO VENT WETWELL 2.

REMOTE / RELIABLE CONTROL OF VENT VALVE 3.

ABILITY TO RECLOSE VENT ISSUES:

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1.

DELIBERATE RELEASE OR RADI0 ACTIVITY 2.

WHAT IS REMOTE / RELIABLE CONTROL?

3 r IS DUCT BURST IN SECONDARY._

c. 2 CONTAINMENT-ACCEPTABLE?

4.

WHAT IS APPROPRIATE ACTION PRESSURE?

i

- 9 ELEMENT I4 - CORE DEBRIS OBJECTIVE:

REDUCE LIKELIHOOD OF FAILURE BY DIRECT ATTACK REQUIREMENTS:

1.

USE PRACTICAL DEBRIS RETARDING BARRIERS 2.

CONSERVE SUPPRESSION POOL WATER AS A QUENCHING POOL ISSUE:

WHAT IS PRACTICAL?

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10 ELEMENT 5 - TRAINING AND PROCEDURES OBJECTIVE:

ENSURE OPERATORS ARE READY TO USE PLANT FEATURES TO BEST ADVANTAGE IN SEVERE ACCID 5NTS REQUIREMENTS:

1.

CLEAR SYMPTOM BASED STRATEGIES (INTEGRATED) 2.

REMOVAL OF UNNECESSARY INHIBITIONS 3.

TRAINING / PROCEDURES ISSUES:

1.

COMPETING SAFETY REQUIREMENTS 2.

DEGREE OF TRAINING

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-11 AN INSTITUTIONAL APPROACH

- e GENERIC LETTER - ADVANCED NOTICE OF PROPOSED REQUIREMENTS - TO SOLICIT COMMENT e

COLLECTIVE PUBLIC REVIEW GENERIC LETTER OF REQUIREMENTS s

e IMPLEMENTATION WITH IPE AND EPG REV. 4 IMPLEMENTATION t a.

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