ML20211N761
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: |
References | |
FOIA-87-10 NUDOCS 8607030237 | |
Download: ML20211N761 (18) | |
Text
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,f p ae rg I UNITED STATES
, [/'.t ,"s-(( [g s
./ :;
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555 ng;x.%, N;r / June 9,1986 o.,,,.
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.
LOCATION:
~
Phillips Building 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
- m. W. Butler A % _
Robert M. Bernero, Director
- Division of BWR Licensing m
(
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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r- yy,-,,m4,--y- , - - . + -> . = - - .-> - - - - + - - - - ---ev-,-,-,--m--,n,,---e, .-,- ,--- ---, -w-+,----.-
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? ,
m M
e
4 I, 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 BWR-2 6 x'10-6 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:
a_
.x
. . . - . . . . , . ,u.. . , ; .., .
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- 1. WHEN AND HOW LONG NOT INERTED i
- i. . -- 2. INDEPENDENT POWER FOR IGNITERS l 3. SURVEILLANCE FOR IGNITERS i
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s m -- --,-e ,,we-,..- ,,~,-s-.-,. - _ , _ - , _ , . , , , - ,_ , , , , - . , , , , , , , , - , , , - .- - -
,,n,.,, , - -_- .,,,..r,_,,,,-,.-.,-.-...,.n. _ - . - ..,., . , , . -,- ---- ,,
. 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
~'
- 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)
~
Rt0VIREMENTS:
- 1. SUBSTANTIAL CAPABILITY TO VENT WETWELL
- 2. REMOTE / RELIABLE CONTROL OF VENT VALVE
- 3. ABILITY TO RECLOSE VENT
~
ISSUES: ,
- 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?
- " ' ' * * *' t g e-D
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
~
=
D
..- -11 AN INSTITUTIONAL APPROACH
-e GENERIC LETTER - ADVANCED NOTICE OF PROPOSED REQUIREMENTS - TO SOLICIT COMMENT e COLLECTIVE PUBLIC REVIEW s GENERIC LETTER OF REQUIREMENTS e IMPLEMENTATION WITH IPE AND EPG REV. 4 IMPLEMENTATION
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l PWR subatmospheric containment configuration l '
1 HUREG-1037 2-20
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NUREG-1037 2-22
I Reactor t silding (secondary containment)
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pool Figure 4 BWR Mark I containment configuration NUREG-1037 2-24
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1 Figure 5. BWR Mark II containment configuration
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(Detail drawing not to scale)
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Figure 6. BWR Mark III containment configuration ..
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,j NUREG-1037 2-29 L