ML20154G285

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Summary of 880407 Meeting W/Bwr Owners Group & GE Re Diversity Requirements for ATWS Rule (10CFR50.62) Implementation on Generic Basis.Viewgraphs & List of Meeting Attendees Encl
ML20154G285
Person / Time
Issue date: 04/19/1988
From: Huan Li
Office of Nuclear Reactor Regulation
To: Newberry S
Office of Nuclear Reactor Regulation
References
NUDOCS 8805240301
Download: ML20154G285 (13)


Text

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APR 191929 MEMORANDUM FOR: Scott Newberry, Acting Chief Instrumentation & Control Systems Branch Division of Enginearing & Systems Technology THRU: Jerry Mauck, Section Chief Instrumentation & Control Systems Branch i Division of Enginctring & Systems Technology FROM: Hulbert C. Li Instrumentation & Control Systems Branch Division of Engineering & Systems Technology

SUBJECT:

SUMMARY

OF MEETING WITH BWR OWNERS' GROUP TO DISCUSS I DIVERSITY REQUIREMENTS FOR ATWS RULE (10CFR50.62)

IMPLEMENTATION i On April 7, 1988 NRC staff members met with the BWR Owners Group and represent-atives from General Electric to discuss, on a generic basis, the diversity requirements for the ATWS Rule (10CFR50.62) implementation. This issue was raised during a plant-specific technical specification (TS) review on Brunswick l Unit 2 ATWS mitigation system TS changes. During this review, the staff concluded that Brunswick had installed the same type of analog transmitter and i

trip units (ATTU) for the ATWS/ARI system and the reactor trip system, which I does not appear to be in conformance with the ATWS Rule. The BWROG believes  ;

that this issue has generic implications and, during the meeting, presented i their basis for concluding that hardware diversity is not needed to satisfy the i diversity requirements of the ATWS Rule. This belief is cased on the extent of '

existing functional diversity within the General Electric reactor trip system  ;

and the fact that hardware diversity would add very little to safety. A limited )

PRA was provided by the BWR0G to support their view along with a rough estimate i (verbal) for the cost of implementing hardware diversity at a plant that has  !

installed this non-diverse ATWS instrumentation. The staff requested that the BWROG fomally submit the information provided during the meeting. We intend to review this information and provide our conclusions in a subsequent safety evaluation.

The copy of the slides from the BWROG presentation are attached in Enclosure 1.

A list of the meeting attendees is in Enclosure 2.

8805240301 880419 PDR TOPRP Et1VGENE Hulbert C. Li C PDR In trumentation & Control Systems Branch  !

Divuion of Engineering & Systems Technology

Enclosures:

As stated cc: See page 2 DISTRIBUTION:

Central Files (k

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Contact:

H. Li (S SD/ DEST), x20781 ICSB RF !j P .  !

NRC PDR SICB: DEST ST SIC EST L PDR t g HLi:bl 04//f/88

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/8[/88 SNe erry 04/f/88 S. Newberry J. Mauck / H. Li ,b k}'I ,

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1 Scott Newberry cc w/ enclosures:

J. Sniezek T. Martin L. Shao A. Thadani E. Adensam W. Hodges T. Collins R. Jones D. Lynch E. Sylvester SICB Members 1

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. ENCLOSURE I l l

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BWR OWNERS' GROUP /NRC MEETING ATWS ANALOG TRIP UNIT DIVERSITY l APRIL 7, 1988 ROCKVILLE, MD d

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MEETING CONTENT l

O REVIEW ATWS RULE REQUIREMENTS REGARDING MANUFACTURING. DIVERSITY OF ANALOG TRIP UNITS 0 PRESENT RESULTS FROM EVALUATION OF SYSTEM LEVEL SENSITIVITY TO DIVERSITY FROM RELIABILITY VIEWPOINT l

0 REVIEW HISTORY AND PHILOSOPHY OF DIVERSITY IN ATWS DESIGN 0 DESCRIBE EXISTING DIVERSITY PROVISIONS 1

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MEETING OBJECTIVE 0 PROVIDE BASIS FOR CONCLUDING THAT MANUFACTURING DIVERSITY IS NOT NEEDED FOR ANALOG TRIP UNITS TO SATISFY THE DIVERSITY REQUIREMENTS T THE ATWS RULE l I

0 CLOSE OUT MNUFACTURING DIVERSITY ISSUE l

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ARI CONCEPT l

0 PROVIDE DIVERSE R0D INSERTION 0 RECOGNIZE EXISTING DIVERSITY WITHIN RPS DIVERSE SENSORS FOR ALL ANTICIPATED TRANSIENTS ANALOG TRIP UNIT DIVERSITY 0 PROVIDE DIVERSITY FROM RPS WHERE MOST BENEFICIAL l

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l ARI PROVIDES DIVERSE l R0D INSERTION i

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. s IEEE Btd

$821978 OENERAL PRINC!1 LES OF RELIABILITY ANALYala OF Table A7 Minimum Number of Like Functional Bloc's Required to l Suffer Common Mode Failure to Prevent Autor satic Reactor Trip l

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- _ __ _ _ __ _ l Number Numt te Transient Component Trata Affected Aethi Mode Overpressun Trip breaker, A and 3 2 2 Do not open circuit l DC nlays A and 3 2 4 Do not open etreult AC relays A and 8 4 6 Do not open circuit Analog ehennels A and a 2 3 Do not nmove power to relay coil NOTE: A similar tabulation can be made for combinations of unlike co iponents.

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A3.8.1 Failure Com6(nattons. As with any Table A8 system failure, common mode failures arise Commor . Mode Failure Preventative Measures only when certain associated functions are - --

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i not performed. If, for this example, one as- N"" C ** E 'Y P " #' N"" d" M'"""

sumes that the typical trip function shown in External n nmal

, Fig. l is the entire system, and that no others enwront ent runctional diversity act, a table can be made to summarize the sit. aute Du),gn op 'dmj do, u t,. T,troh eontrots untion (Table A7). sat. tailun mod.

A3.3.2 Causative Factors. Identification of g dar on the important causative factors to be consid- Equipment diversity ered is the next step in the analysis. Five ren- D ign de aciency Functions! diversity eral categories of causes are identified in con. Physical wperation )

i Design administratne controls  ;

nect. ion with common mode failure. operations) administrative controts (1) External NormalEnvironment: safe calluso mode.

(a) Dust dirt Majnten nee Functional diversity .

(b) Temperature errors operational administrative controts (c) Humidity moisture Equipment dinrsity (d) Vibration Extuna cstast ophe Functional diversity (e) Electricalinterference r3y,;e,i .epar. tion (2) Design Dc/iciency Dairn administritive controts (a) Unrecognized interdependence be- pq','y,uQ , l tween "independent" subsystems, compo-Functi cal y pents defie eney Functional diversity l (b) Unrecognized electrical or mechanical Design administrerive controls 2 dependence on common element O P'" 'I "'I '.d *l"'i' ti" " 18 a Equipnent diversity j (c) Dependence on equipment or para. - - = - =_--s=-_- - - ---- =_- -=-_=_ --- _

meters whose failure or abnormality causes l j need for protection (3) Operation and Maintenance Errors (a) Miscalibration (5' Functionaldeficiency

, (b) Inadequate or improper testing a) Misunderstanding of process variable I (c) Outdated instructions or prints beh; vlor l' (d) Carelessness in maintenance .b) Inadequacy of designed protective ac-(e) Other human factors tior (4) Erternal catastrophe (c) Inappropriate instrumentation (a) Tornado / 3.3.3 Preventative Measures. Redun-(b) Fire dai cy forms the principal Insurance against (c) Flood rar dom failures in that the probability of sev-(d) Earthquake ers i redundant components all failIng togeth-l l 64

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DIVERSITY BETWEEN RPS LOGIC AND ATWS LOGIC TYPE RPS LOGIC ATWS. LOGIC LOCATION OF L%IC RPS CABINETS ECCS CABINETS POWER SOURCE 115 VOLT AC 125 VOLT DC LOGIC CONTACTS DURING OPERATION CLOSED OPEN OUTPUT STATUS ENERGIZED DE-ENERGIZED e

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ANALOG TRIP UNIT MANUFACTURING DIVERSITY 0 MANUFACTURING DIVERSITY DOES NOT PROVIDE SIGNIFICANT IMPROVEMENT

- TRIP UNITS AVAILABLE FROM DIFFERENT  ;

MANUFACTURERS ARE SIMILAR IN DESIGN l o- PROCESS TRANSMITTER INPUT l o- MA OR V0LTS TRIP SETTING o- POWER SUPPLY I

- MAJOR COMMON CAUSE FAILURE (MIS-CALIBRATION)

NOT SIGNIFICANTLY REDUCED o- CALIBRATION PROCEDURES NOT SIGNIFICANTLY DIVERSE

- ADDITIONAL COMPLEXITY IN PLANT PROCEDURES (TWO CALIBRATION PROCEDURES) i MANUFACTURING DIVERSITY NOT JUSTIFIED 1 i

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FIGURE 4 RPS FAULT TREE WITH ARI, COMMON CAUSE FAILURE

& MANUAL SCR4M C: (((CE

  • tii) + CM i FAILLRE TO INSERT SUFFICIDfT l RODS (C)

((CE

  • AR!)+ CC)* E l l RPS ELECTRICAL \ RPS PCCHANICAL AND AR1 FAILS FAILURE AND ( CM )

OR gg g C(# TON CAUSE FAILURE RSS ELECT Ato ARI j (CE

  • ARl)+ CC RPS ELECTRICAL AND ARI FAILS OR CCttON CAUSE FAILURE RPS ELECT Ato ARI fC AM g gg 3 )

b CCet04 CAUSE FAILURE RPS ELECT AFO AR!

( CC )

CE

  • ARI CE : 2.0 E-5 l AR) FAILS ASSUtf ARI : 2.0 E-3

$ : 5.0 E-2 CM : 1.0 E-5 - l BETA : 2.0 E 1 CC : 0.4 E-5

, RPS ELICTRICAL ARI IAIN FAILS

- ( CE ) ( AR) )

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A BRUNSWICK PRA RESULTS BASE CASE f%NUAL SCRAM = .05 NO ARI SYSTEM CDF = 2,496 E-05 COMMON ARl/,7.?S ANALOG TRIP UNITS MANUAL SCRAM = .05 BETA = 0.2 (FROM NEDC - 30844)

CDF = 2.388 E - 05 DIVERSE KANUFACTURER FOR ANALOG TRIP UNITS MANUAL SCRAM = .05 l BETA = 0,0 CDF = 2.367 E - 05 f CONC LUSIONS MANUFACTURIflG DIVERSITY lilPROVES CDF BY AT BEST ONLY 0.021 E - 05 l

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I C CNCLUSIONS I

ARI DIVERSITY TO THE RPS IS IN THE ATWS RULE AND IS ACHIEVED BY THE CURRENT DESIGNS r

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ENCLOSURE 2 4

1 MEETING ATTENDEES ,

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NRC BWR Owners' Group General Electric E. Adensam Terry Pickens (NSP) Larry Gifford S. Newberry SteveFloyd(CP&L) Bill Sullivan i W. Hodges L. G. Byrves (GPC) George Samstad J. Mauck Jeff Esterman V. Thomas (Sargent & Lundy)

E. Sylvester Jack Fulton R. Stevens (Boston Edison)

H. Li Sofia Toth (NYPA)

Pat Simpson (SERI)

E.Fotoponlos(Bechtel)

Richard January (Yankee Atomic)

LinTurner(TVA) j l

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