ML20244C841

Answers 840130 Questions Re Nuclear Plant Reliability Data Sys Data Collection for Reactor Protection Sys & ESF Actuation Sys Instrumentation

ML20244C841
Person / Time
Issue date:	02/13/1984
From:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Heltemes C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20236B036	List: ML20236B032 ML20236B122 ML20236B145 ML20236B169 ML20236B183 ML20236B317 ML20244C841
References
FOIA-87-465 NUDOCS 8402160637
Download: ML20244C841 (2)

Text

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[ NUCLEAR REGULATORY COMMI'.iSJON d-5 E WASHlHUToN, D, C. 20555 ,.I , )

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1 C. J. Heltemes, Jr.,! Director. 41

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MEMORANDUM FOR:

Office for Analysis and Evaluation of Operational Data FROM: Richard C. DeYoung, Director i i

Office of Inspection and.Enforc,ement.

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SUBJECT:

NPRD SYSTEM DATA COLLECTION FOR REACTORiPROTECTION SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION <

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In response to your memorandum dated January 30, MIN, on this subject',

we are providing the following answers to the qur.stipos that you posed

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.u I 1. Our need for engineering data records'(i.e. , NPRD-2 fccMs) pridh b componentfailureonReectorProtectionSystem(RPS)"andEnginkers)lc/ '!

I SafetyFeaturesActuationSy'. tem (ESFAS) instruments.ott;er,tha7 6 brs/ ,

! transmitters is limited to devices that have a relatb/c14 rMgn tailure  ;

rate. Thiscangenerallybetranslatedintopopulati.Up/aiaonswitches, i l sensors,-relays, breakers,letc.

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In view of the difficulty that you expressed involving defiping component ,f boundaries for signal processing cart's, we can accept the absence of ,

population data on such cards until failure occurs and a-failure, report is submitted.

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2. Our source of information on signal processing instruments is pridarily derived from the licensees on an'as-needed basis ffhe Office of  ;

Inspection and Enforcement (IE) has no enmprehensive de, tailed source of 1

information on the number,ttype, function, and design of signal processors J in use at each facility. When specific .information is required, the -

documents on hand, such as the FinaljSafety Analysis Report (FSAR) are  ;

consulted and then either the resichnt inspect 6for the licensee is I asked to furnish additional specific information, f/

3. The Office of Inspection and Enforcement.does' not/ require population,' 3 data on signal processing cards:at this time. However, if a- d particular type of card is identified with 'a tsarious generic or high j

l probability failure, population data on such cards would be useful.  ;

4. WehavenotusedNPRDsystem_ data:onRPS/ijfASinstrumentstodate. We-would expect to use the NPRD system more in the' future as the quality and completeness of the data improve. When .you tHnk the NPRD data . base has-sufficiently improved in quality and completeness, we would appreciate your arranging small, informal training.sessdons'for our Engineers'on the' accessibility and use of NPRO system datel..  ;

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5. We bavi, not constdudty' a fault tree analysis- of. RPS/ESFAS instruments <

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,,s Richard C. eoung,Dir(ector..,,

J' Office of pection and Enforcement cc:. .H. Denton, NRR R. Minogue,'RES "

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Regional Addijntstrators l

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UNITED STATES 1 1 , a l k NUCLEAR REGULATORY COMMISSIOrl- e c[' # ,iL

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WASHINGTON,0. C. 20555, 4

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MEMORANDUM FOR: C. J. Heltemes , Jr. , Director ., I i, Office. for Analysis and Evaluation' , t ht '

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of Operational' Data hU' i

FROM: Horold R. Denton, Director /) - O, l Office of Nuclear Reactor ~ RegulaHon .,-

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SUBJECT:

AE0D REQUEST-FOR COMMENTS ON LIST 40F KEY' ' ;' . 3 il COMPONENT APPLICATIONS CDR THE NPRDS i s k-l

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We have reviewed the list of key components sent to us. in your mmorandum' . =1 9 of December 2, 1983. We. agree that it is desirable to be able"to key upoh b,gch , .' i

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item on this list. >

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3 , J We note that the list of key components is preliminary andinet intended to 4  !

be all-inclusive. We also understand that this list may be expanded in the ,

future. Enclosed are our comments.on your Initial Component List, e?cng with a number of suggested components for possible inclusion in either '

thd presend list or a future, expanded list. >

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Harold R. Denton, Director-

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/0,ffic4,'df Nuclear Reactor Regulation 'l' [  !

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Enclosure:

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W ENCLOSURE

\. n NRR COMMENis ON INITIAL COMPONENT LIST' .

,- 1.- It is noted that acronyms are used to some extent.to identify both systems and components. It is recommended.that extensive use of acronyms would f greatly reduce the space required to-identify key component applications.

-\}- Attachment-1 provides some examples. Many of the current FSAR's' include: l lists which would be a convenient starting point to assembling a complete ", '

list. < Attachment 1 gives only a few examples and is not intended to be 7 completef B ..x a 2. In most of the proposed lists', it is noted that a system. identification is It is recommended that this'should be a requirement _in all cases "j used. l

,l where it may not be explicitly clear where the component may be used.- 3

3. With regard to system identification, it is noted that different tenns are used by different vendors to describe the same functional system.

Although we recognize that the list attempted:to incorporate a generic naming convention based on function, some improvements can still be made. One exam .

shuidown (SD) ple isorresidual cooling heat decay heat removal

~ (DH) (RHR) removal (DHR).which goes by_tenns

. Another example .is high pressure injection (HPI) pum'ps and high pressure safety injection (HPSI) pumps.

4. In many cases in the proposed list, the only difference is the system identification associated with a specific co'mponent. It would greatly ,

expand the identification system capability.to separate system -1 identification so that appropriate combinations could be used. j l 5. It would appear to be useful if.the terms were put on a computerized list so that terms could be listed alphabetically. Non-standard nomenclature items could.be included showing preferred usage.

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6. Because of ongoing work on severe accidents and containment. leakage, seals are becoming increasingly important. We suggest including in the keyword list:

equipment hatch seals personnel lock seals

' valve seals (e.g., for purge and isolation valves)

'( 7. As plants become older, degradation of some passive components is becoming an important safety issue. Inclusion of such components.in the S3 keyword list would be desirable. Examples are steam generator tube degradation and RWR pipe cracking.

8. Attachment 2 off.ers a list of additional components for possible inclusion-in either the Initial Components List or a future, more expanded list.

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. . . ATTACHMENT 1 EXAMPLES FOR' KEY _. COMPONENTS APPLICATIONS ,

SYSTEM IDENTIFICATION HPSI - high pressure safety injection LPSI - low pressure safety injection. ,,

RHR - residual' heat removal MFW - main feedwater - ,

AFW - auxiliary feedwater -

MS -- main steam .

CCW - component cooling water SW - service water COND - condensate VC -' voline control CI - containment isolation l 1

P - primiry I S - secondary EIE - electrical IE ENIE - electrical non IE SR - safety related (use only where needed)

NSR - non-safety related (use only where needed) 1 RTS - reactor trip system I

ESFAS - engineered safety feature actuation system

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. ..1 COMPONENT IDENTIFICATI0s '

.1. . : Valves. By. Ty,pe .

MOV - motor operated valves-A0V - air operated valves .

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HOV - hydraulic. operated valves MV - manual valve .

s CKY - check valve ,

A safety relief valve SRV -

PORY - power operated relief valve

2. Electrical Power Components

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M - motor -1 BKR - breaker F - fuse ,

C - cable CI - cable insulation TB - terminal block ... .

CP - containment penetration XFMR - transformer 3 .. Control Components Prefix ,

P - pressure' transmitter PD - . pressure differential transmitter p - flow

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'N . nuclear. ., ,

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C- - controller -

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T - transmitter. i S. - switch l

B - bistable j 1

.I - indication ,

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e.g: PC  : pressure controller, RI: Radiation indicator  ;

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P - pump l 1

F - fonn B ,, blower .

HX - heat exchanger -

D - Damper

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C - Chiller -

1 HVAC - heating, ventilation, air-ccaditioning

5. System Defined Components RCP - reactor coolant pump VCT -

Voline control tank P

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FormatForAEronyms' -

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- System Identification - Component - Subcomponent . , ..

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P - SRV (IncontrasttoS-SRV)- .. 1 HPSI - P - M .(Pump motor)

SR -- HVAC - Control Room-(use words where needed for clarification) q y

SW - NSR'- P (NSR use,d.for clarification)

ENIE - BKR - Switchyard j l

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ATTACHMENT 2' 4.

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LIST OF SUGGESTED ADDITIONS-TO AE00' COMPONENT LISTS i

PWR . I Inverters (General)' -

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1 Reactor Coolant Pump . .

' a '. - seals .

b. seal cooling . valves

c. seal: injection valves-l- PORY - Low Temperature Overpressure Control Pressurizer-

! Spray Valve and Operator

! Auxiliary Spray Valve and Operator l Auxiliary Feedwater Valves and Operators Turbine Driven Auxiliary Feedwater Valves and Operators Main Feedwater Pumps Condensate Booster Pumps L Main Feedwater Heaters <

1 l BWST, Heaters.and Mixers ,

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.ESAF Room Cool.ing System Components'

i Room Coolers'and Chillers' a.. auxiliary-feedwater pumps -

b. HPSI pumps

c. charging pumps 1

d. RHR pumps '

e. component cooling water pumps

f. . service water pumps- j

g. containment spray pumps  ;

PWR Emergency Baron Addition Valves and Operators BWR SRV Discharge Line to Drywell Vacuum Breaker Valves ,

HCU Accumulators CRD Pumps Scram Discharge Volume Control Dry Well Spray Va'ives and.0perators MSIV Leekage Control System

a. valves

b. valve operators C. pumps

'd. filters ADS Accumulators Steam Jet. Air Ejector.s

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Reactor Recirculation Pump

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a. seals. l

b. valves

c. operators ,,

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' Feedwater and Condensate

a. feedwater. pumps , , -

b. condensate booster. pumps

c. feedwater heaters SLCS Heaters and Mixers 1

ESAF Room Cooling System Components ,

BWR Isolation Condenser Valves and Operators BWR Recirculation Flow Controller 1

BOTH PWR AND BWR Fire Pump

a. electric

b. electric motor

c. diesel

d. diesel starting battery

e. diesel battery charter Fire and Smoke Detectors

a. heat ~

b. flame

c. smoke

d. actuation controls / logic Fire Spray / Sprinklers

a. actuation valves

b. actuation logic

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I Fire Suppression Systems Actuation Valves'and Logic' , ,

a. high pressure C02

b. . low pressure CO -

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c. halon ..

d. dry chemical Standpipe Hose Stations ll

a. valves b'. hose

c. nozzle  ;

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Yard Fire Hydrant .

a. valves '

b. hose I

c. adapter '

Ventilation System .]

a. fire dampers

b. fire doors

c. fire barriers .

- d. fire enclosures 1

e. penetration seals Fire Brigade Equipment ,

ll Portable ' Fire Extinguishers Emergency Lighting - for alternative and dedicated shutdown activites (ASB should identify these components).

Reactor Internals Control Room Ventilation System

a. fans

b. isolation dampers

c. fire dampers

d. ' radiation and chlorine monitors

e. chillers .]

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' . Y Switchgear and Battery Rooms Ventilation Systems .)

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a. fans. j

b. . isolation dampers l

c. fire dampers ",, .j l

Liquid Radioactive Waste Effluent Release Valves'and Operators Radioactive Waste Gas Storage System Release Valves and Operators Turbine. Bypass Valves and Operators i

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