ML19221A944

For Comment Issue of Reg Guide 1.133, Loose Part Detection Program for Primary Sys of Light Water Cooled Reactors

ML19221A944
Person / Time
Issue date:	09/30/1977
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.133, REGGD-1.133, NUDOCS 7907110168
Download: ML19221A944 (6)

Text

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U.S. NUCLEAR REGULATORY COMMISSION September 1977

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OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.133 LOOSE-PART DETECTION PROGRAM FOR THE PRIMARY SYSTEM OF LIGHT-WATER-COOLED REACTORS A. INTRODUCTION met. Paragraph (cx5). "Administratisc Controls,"

requires an appheant for a facility operating license Criterion 1. " Quality Standards and Records." of to proside proposed technical specifications relating Appendix A. " General Design Criteria for Nuclear to reporting necessary to ensure <4eration of the Power Plants / to 10 CFR Part 50, " Licensing of facihty in a safe manner.

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Production and Utilization FacihtiesJ' requires that structures, systems, and components important to Paragraph 20,1(c) of 10 Ch Park " Standards safety be designed, fabricated. erected, and tested to for Protection Against %t.k. " stat that, in ad-quahty standards commensurate with the importance dition to complyin pth ' thy ' ments set forth in of the safety functions to be performed and that a that part. hcens hgJd qke every reasonable ef-quality assurance program be established and fort to main n frure t5 radiation as far below implemented in order to preside adequate assurance the limits 1,fic at part as is reasonably that these structures systems, and components will achiev '. A satisfactorily perform their saf ety functions.

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f scribes a method acceptable to the Cntenon 13. "Instrumemanon and Contro!/ re-J' sta 3r implementmg the above regulatory re-quires m p trt. that mstrumentation be prosided t-

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nts with respect to detecting a potentially 1

monitor sanables and etems o.er their anticipate

/ y-elated loose part in light-w ater-cooled reac-ranges for normal operation. for a n t i

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to.' during normal operation This guide also out-operational o currences and for accident cc tio i

.nes a program that can help heensees to meet the to ensure adequate safety. mcludmg t able Part 20 cnterion that exposures of station personnel and systems that can affect the fissio ess,. y to radiation dunng routine operation of the station tegnty of the core. and the reactor k olant essure will be "as low as is reasonably achievable" boundary.

(ALARA)

Section 50.36. "TecFg al SpecificationsJ of 10 B. DISCUSSION CFR Part 50 requ applicant for a facihty pgeh @f'), proposed technical The presence of a loose (i.e., disengaged and drif-operating licrnse specificationsga

" Limiting Condi-ting) part in the primary coolant system can be in-tions for Omatio(grg@ifies a proposed technical

'm dicative of degraded reactor safety resulting from specific.p oQ~ relat g to the low est functional failure or weakening of a safety-related component.

capa [ N j M ts 1ance lesels of equipment re-A loose part, whether " 'e from a faded or w eakened quire 3

>a fe peranon of the facihty Paragraph component or from a.

em inadvertently left in the (cX3), hrseillance RequirementsJ identifies a primary system during construction. refueling, or proposedbechnical specifica tion relating to test.

maintenance procedures can contribute to compo-cahbration. or r

'mn to ensure that the necessary nent damage and material wear by frequent im-quahty of sye

' components is maintained, pacting with other parts m the system. A loose part that facihty oper

-dl be within the safety hmits, can pose a serious threat of partial flow blockage and that the hmit.

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3 (DNB) which m turn could result in failure of fuel inspections of the primary system. For this reason, cladiing. In addition a I;ose part increases the this guide emphasizes the need for providmg system potentiallor control-rod jamming and for accumula-features that will minimize false alert signals and for tion of increned levels of radioactive crud in the developing diagnostic procedures that can be quickly primary system.

implemented to supplement information from the loose-part detection system to determine the short-The primary purpose of the loose-part detection and long-term safety significance of a loose part. A program is the early detection ofloose metallic parts well-deseloped loose-part detection system should in the primary system Early detection can provide enable discrimination of the signal mduced by the im-the time required to aseid or mitigate safety-related pact of a loose part from those signals induced by damage is or malfunctions of primary system com.

normal hydraulic, mechanical, and electrical ponents.

background noise and large amplitude electrical tran-sients.

The loose-part detection program also serses a se-cond purpose smce it can minimize radiation ex-The loose-part detection program out!med in this posure to station personnel by providmg for the early regulatory guide includes both automatic and manual detection and generallocation of abnormal structural modes of data acquisition. The automatic data ac-conditions. Information from the program can be quisition mode prosides for continuous monitoring used by station personnel to focus their efforts when of signals, but data are recorded only w hen the detec-taking a medial action to minimize the formation of tion system senses that a predesignated alert level has wear-generated radioactne crud and to minimize the been reached or exceeded. An alarm alerts control need for extensne structural repairs. The second pur-room personnel when the alert lesel is reached or ex-pose is consistent with the guidance contained in ceeded. The manual data acquisition mode provides Regulatory G uide 8 8, "Information Reies ant to En-periodic monitoring to determine system operability suring That Occupational Radiation Exposures at (mcluding calibration), establish the alert tesel, and Nu ' ear Power Stauons Will Be As Low As Is alert the licensee to data that require evaluation but Reasonably Achievable " which provides guidance to are ofinsufficient magnitude or inecrrect character to licensees for mamtaming occupational doses to in-otherwise imtiate alert procedures.

dn duals as far below the permissible limits specified n the NRC regulations as is reasonably achievable w hd e. at the same time, prosiding guicance on The loose-part detection program outlined herein methods to ensure that the sum of the doses received is not intended to be a research program Instrumen-by all esposed personnelis also at the lowest practical tation and procedures that will result in the need for a level disproportionate amount of attention by control room personnel are not encouraged. Instrumentation T he Adsisory Ccmmittee on Reactor Safeguards that can be used to approximate the site and location i ACRS) and the NRC staff hase. for the past several of a loose part but that does not interfere with the years, been encouragmg apphcants to employ online normal alert and false signal rejection function of the loosc-part detection sy stem s in an attempt to detection program w ould be useful in complementing sumulate technological.deselopment in that area other mstrumentation to determme the safety Th;s approach has resulted in a substantial increase significance of a detected loose part. Leose parts m mJcstry-wide experience and confidence m these traseling through the primary system will generally systems and has resulted in the commercial produc-accumulate, at least for a time,in such natural collec-tion of loose-part detection systems by several tion areas as the plenums m reactor sessels and steam engcermg and manuf acturmg organizanons. All generators. Therefore, this guide recommends that appheants for a construction permit or an operating sensors be located at these and other natural collec-iieense are required to describe the loose-part detec-tion areas. No benefit is seen in mstrumentmg tion program for the proposed reactor (Section 4.4.6, straight hnes of pipe or other areas through which a

" Instrumentation R eq uirem e n t s,"

of Regulatory loose part will quickly pass. Close scrutiny of a Guide 1.70, " Standard Format and Content of Safety relatisely small amount of clearly relesant data is Analysis Reports for Nuclear Power Plants").

considered a better detection program than cursory resiew of a large volume of less significant data.

An improperl) 4 cloped and poor!) implemented loose-put detcetan program mas require excessive attcnuon by plant operating personnel and can result A pyime consideration in developing the loose-part

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in increwed radiation ewosure due to more frequent detection prcgram is the avoidance of procedures re-quiring excess:ve attention by control room person-net and excessive reporting by the licensee. The e[na[I4. bgN.[$ r{k recommended program would require operator ac-em mme rea m e u,: m Lme -nm n e,,

ref e n %m tion or engineering review only w hen the alert levelis e aw are reached or exceeded er when co n fir m m g the 142 118 1.133 4

operab;lity of the instrumentation system Licensee system to permit channel operability (including reports to the Commission du ing operation are cahbration) tests. Regulatory Position 5 addresses necessary w hen defining the alert les el, w hen a loose operability tests as part of a suncillance requirement part is confirmed to be present. or when the as-for a proposed technical specification.

sociated techmeal spec 2fication is siolated Since an earthquakt is an esent that could induce a Although loose-part detection sy stems can, in a loose part in the pnmary system, it is desirable that lage number of cases. detect and indNate the ap-the loose-part detection system be designed to func-proumate lecation and we:ght of a loose pan, other tion following all seismic esents that do not require mformanon te g.. that obtamed from plant process plant shutdow n.

Recording equipment how es er, signals, from an mspection of the facihty, or from need not be designed to function without prior operatmg histors) w d! he necessary in most in.

maintenance followmg such seismic events provided stances to determine the safety implication of the the system retams audio or sisual alarm capability.

loose part Therefore, no action with respect to reac-tor operanon n recommended based on the informa-C. REGULATORY POSITION tion obtained from the loose-part detection system Mone. An aiert resulting from the loose-part detec-An insenice loose-part detectioa program should t on sy stem n cormdered a w arnog. and it is impor-be implemented for the pnmary system of light-tant that follow up steps (e g, acqunition of ad-water-cooled reattors durmg preoperational testing ditional diagnmtic mformanoni be td en to deter-and the startup and power operation modes in accor-rmne the s:gmticante of the alert signal. If a loose dance with the following guidelines:

part n show n ta he present. its short and long-term safety imphcatmns need to be determmed.

I. System Characteristics The potern d for damage imnated by a loose part T he following 'emures should be mcorporated into is not nemsuds propornenal to the impact energy each loose-pet detecuon system of the too tre l'or es imp'e, a sma!! piece of tlit a Sen w In ation Sensors capable of detecting metal plate t vy impri ! ' tic impact energy but could restnct loc.d tiow ta the reactm cc re How es er, there acousuc dnturhances should be strategically located 9

are technhal df uh:es m in t a to Atinguish s ery.

on the cuenor surface of the reactor coolant pressure low-entm unr ict gnah fro ' th< normal reactor boundary A rmmmum of tw o sensors, suitably acoustic none F sperance th lee-part dettetmn located to proside broad coserage. should be located sy stems for oper tmp preuunted and hoihng w ater at each natural collecnon region (e.g reactor sessel sn f or estab! shmg an impact upper and lower plenums and each PWR steam ceactors pros. des tht nergy of 0 5 f'-lh to n mulest c g the kinetic generator reactor coolant inlet plenum).

energy of a D ' !b tn 2T k g) part tra chng at x h 'sec

( 2 44 m. sec). as tht recommended o stem sensitnits

h. St ucm Senutoni I he onhne sensitivity of the m Regulatory Poutmn i.h bper ence shows that sy stem should he such that, as a mmimum, the system ugnals resulung f rem met dia ebject impacts of that can detect a metalla loose part that weighs from 0.25 magmtude arc d nt mg u n hahic f rom the normal M ll4 k ) to 30 !b (131 kg) and impacts with a F

background none.

kmetic energy of 0.5 ft-lb t0A75 joules) on the inside s u r fa c e of the reactor coolant pressure boundary In order to ensure that as a m:nimum, each loose-w it h m feet (I meter > of a sensor. An acceptable p art detect >. sy stem has A ahhty to detect w nat method for senfymg thn onhne sensitnity is to the staff considen to be the mow son heant range of demonstrate i l) the haue system sensitisity during luese-part u eighh. the stah rea. ' men L W egu!atory phnt shutdow n and (2) that the background noise Position I b) that ca h loose-put detecuon system he measured durmg plant optration is no greater than c a pa ble, m conrancnon with the 02 ft-lb energy 20 percent of 'he signal associated with the specified criterion, of detecung loose parts that weigh between detectable loose-part impact 0 25 (0114 kg) and 10 ih (13 0 kg). The specified weight rar;ge is con ude:ed to he representatn e of the c Channel Separanon The instrumentation chan-most conunon and s4gnincaat Jass of loose parts.

nels (e g., cahimp, amphhers) associated with the two sensors recommended at each natural collection The high rad:atmn and therrn ! cychng ensiron-region should he p hy sically separated from each ment to wNb most of the pnman system is sub-other startmg at the sensor locations to a pomt m the lected could in ume aher operatmg charactenstics of plant that is alway s accessible fo maintenance dunng the !*se-part detecuon 3 ntem so that sun edlance full-power operatioi.

mng ncessne alert

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becomes meffectual e& - K <

ugnals or by decreasing sens;tnity to lome parts.

d. Data A yuntrum Si nem The system should in-Therefore. in Repu!at 'n Founen 1.f the staf f recom-clude both automatu and manual st irtup of data ac-mends thst prosnmns he m;mmated mte the quis: tion equipment nee Regulatory Position 3). In

' 133 1

the event the alert lesel is reached or exceedcJ. the need not function without maintenance followmg the data acquisition system should automatically ac-speciGed,eismic esent provided the audio or usual tivate, and an audible or usual alarm shoald alert the alarm capability remains functional. The system control room personnel of that condition. The data should also be qualified according to the recommen-acquisition sy stem should proside for the dations of Regulatory Guide 1.89, " Qualification of simultaneous recording of all ensor signals and be Class IE Equipment for Nuclear Power Plants " but capabic of immechate visual and audio monitoring of the quali6 cation program need not include the en-these signals. (An acceptable alternctive to the sironment existing during or after accident condi-simultaneous recording of all sensor signals in the tions (eg..

loss-of-coola n t accident, steam line automatic mode a the recording oi cant-related break).

parameters that characterue the ',ose part condi-

h. Gualitr of S stem Components Components tion, e g., sensor-signal arrival time sequer.ces, rate of 3

occurrence of impacts, number of "ringdow n" oscil-should be of a quality that is consistent with lationt) minimum maintenance requirements and low-failure rates. Components should be compatible with the 40-

e. Alert Level Provision should be made for incor-year design hfe of the reactor system. Prosision potating into the system a reference signallevel(alert should be made for replacing parts that are an-level)that is indicative of the presence of a loose part ticipated to hase limited sersice hfe.

consistent with Regulatory Position 1.b. Depending on the alert logic (i e., internal prouing of system

i. Srstem Repair. The system should be designed signals), raw or processed signals should be to facihtate the recogmtion, location, replacement, automatically and continuously compared to the repair, and adjustment of malfunctioning compo-alert level. Points to be considered in establishing the nents. Equipment, procedures, and layout should alert lesel are noted in ReguLtory Position 2.

facilitate maintenance to minimi/c personnel time in high radiation areas and minimve occupational

f. Capabihtyfor Senwr Channel Operabdity Tests.

radiation exposure.

Provision should be made for periodic online channel check and channel functional tests and for offline channel calibration during periods of cold shutdown

2. Establishing the Alert leet i

or refueling (see Regulatory Position 3 a(3)).

In all cases, the alert lesel should be consistent with

g. Operability for Seismic and Ensironme rtal Con-Regulatory Positions 1.b and 1.e and should include ditions. The loose-part detection system should be the effects of background noise.

capable of performmg its function following all seismic events that do not require plant shutdown, The following points should be considered when i e., up to and including the Operating Basis Earth-establishing the alert lesels:

quake (OBE) The system should be show n to be ade-quate for the OBE by analysis or test, guidance for

a. The alert logic should incorporate suitable in-which may be obtamed from Regulatory Guide ternal criteria to distinguish the transient signal due 1.100, "Scismic Qualification of Electric Equipment to the impact of a loose part from the signals as-for Nuc! car Power Plants.' Recording equipment sociated with normal hydraulic, mechanical, and electric noise and large-amplitude electrical tran-

'The standard tethnical specifications derme cha,,el cAcct.

sients. For example, it may be desirable to include aaneel fuwnana! resi. and aner! ca!>rcru as fab 5 logic that requires the comparison of two or more A au,et ara a the queatne aucwnent of channel Nhavior sensor signals with the alert level.

daneg operation by chters ation. includirg, w Fere penible, corn.

panion of the channel indication er status Ch o'her indications

b. False alert signals resulting from deliberate or statas derned frorn independent instrurnent channels measunng plar.t maneuvers (e g., Control-rod stepping) and the same parameter other sources that cannot be avoided by the A channel tecno,a/ test for analog channes is the ir"ect'on of a procedures associated v.ith Regulatory Positicn 2.a simu'ated signal into the chanc.cl as close.o the pnmary sensor as may be avoided by automatic procedures that practicable to venfy operabihty. indud:ng alarm and top func-trans. rer histab'e channe's it n the meetu, of a s:muisted sanai momentarily disable the alert-level alaim.

into the channel serier to senfy operah Ety, inJad rg alarrn and tnp functiens

c. The alert logic may proside for the alert lese to A areer'c!>< anon is the aduatment. ai necenan. er the channcf be a function of the normal steady-state operating output so that it respends u d the rece'sary rarge'and a; curacy to Condition.

knv*n values of the parameter that the channel momtors The channel cahbrahon er;ompasses the ennte thannel. induding the

d. As appropriate, it may be desirable for the alert sensor and alarrn and trip functions. and indades the thannel func.

lOgic to provide for the alert lesel to vary from sensor tional test The channel c : Prat.on mas be perf, ncJ by any series to sensor to compensate for the inherent level of of sequential, oscrlappirg. er tatal chnre! steps sa that the entire channel is cahbrated background noise at a specific transducer location.

142 120 1.133-4

if the alert lesel n eseceded or if the quarterly

3. I' sing the Data Acquisition Wdes measurements mdicate the presena or possihihty of a The loos 'part detecuan program should melude loos: part, m onulou s behas ior. or a signilicant data data upusmon in automatic and manual modes trend that may he safety related, diagnostic steps 1 he autom.dic mode n for onhne detection of loose should be taken withm ~': hours to confirm the p.n ts. Fhe m mual made n for determinmg system presence of a loose p irt and determine its safety operaNhty tmcludmg cahhrationt estahinhing the imphcanon or to determme the nature of the alert Ic. c l. ind deteam; upmficant safety-related anomalous data or data trend trends in the senser ugnals a tfe al m./c ~1 h:s mode of data acquisition should be used at 'he fonowing times f or the in-

4. Content of Safety Analysis Reports dicated purpme A desenptmn of the loose-part detection program (1) Preoperational testmg: Estabhsh alert lesel should he submitted to the Commission in response for this test ph ne to the NRC staff request fc infermation on loose-part detecuon sy stems m Secuan 4.4.6, "Instrumer.-

(3 Martup and powcr operation.

tauen Requirements ' of Regulatory Guide 1.70, t al 1:suhhsh alert l e'. els for st.u t u p and

" Standard Format c,d Content of Safety Analysis power opeut eu. I he a:ert icsel f or power operation Reports for Nuclear Power Plantsf should ne sui nutted to <iie Coinnuen (m the start-up upoi' w hen one is pro,ided) w n!nn 90 das s to).

The pregum description should include those lew mg compleuen of the star tup test procram il the items covered in Regulatory Positions I, 2, and 3.

alert lesel n f or power ope.auon follow mg initial Special attention should be gnen to the following items.

startup or there n a enange to the precusting alert lesel tor pow er operanon.

a Sensor ty pes, mounting locations, and thi At least once p:r 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Perform chan-mounting procedures, meiuding cntena for choice of nel check sensor and mounting locations.

(ci At least once per 31 days-Perform channel

h. Data acquncion. recordmg, and calibration 9

f unct:onal tes's.

equipment (di At least once per T days Venfy that alert

c. Anacipated major sources of external and inter-les el s are s nsiaent uith the norned background na! extraneous noise.

nw rd that the data do not indicate the presence or pos abihn o! a h c,e part, anomalous behavior, or d Precautmns taken to ensure acquisition of a ugm ficar' trend that may be safets related. The quahty data alert lesel and alert hwie may ht reused to proiide for the Packground noie of these later measure-

e. Desenption of the nanner in which the alert ments T he deuds of such a re.auon should be sub-level will be determmed and also the alert logic (if nuned unhm N) days to the Commasion as an any) employed by the s> stem hardw are and software amerJn nt to the program desenpuon.

in generatmg an a ert signal Thu should include a desenptian of the program capahihty for dis-loose part and normal

<1 CelJ shuidow n or refuehng. At least once tinguniong b etw een a per lx nnu.ths, senf'. channel cahbration usmg a con-background none.

imcal input te g. weight falhng through a f: u n h me;. Channels shou!J. as recessary, be f Refer ace to the techmcal specification (see r aahbrate_ at thn umm if recabbranon n : ete3sary Regulatory Poition 5)

%Jcutm shouh! Fe pnen to replacement of un-u sum sq sem g Surmary of supplemental data and diagnostic prmeJares mat are as ailab'e and that can he used as s/c T h; ai.tomauc mode should pan of.; thagnosuc program to confirm the presence b

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be i'a m a x <aun; f v the predeugnated of a loose part T he summary should address the use ah, ac! n cu 0 ;u Acc.as should comprne an of infor matmn hem plant process signals, radiation ul a!irm to the s.mtrol room operator leakage naanm, creatmg hntory, exercising of vi' a

s anJ smulur cous in.uan 'n of J. u re :ordmg equip-controi ruds, <> t ang or pnmary coolant pumps, and men: ILt. <hoa:J bu m.qwred f or a su:fiuent penod inspecuon of th; pnnury coolant system.

of u,. to p,operly char,iaen/c the signals from all

sensor,

!ah alert should bc d: amented w:th

h. Pie A o tar perf inmne channel check, chan-regard ic tma and plant wndman fu tuona: te9 and shannel cahbration u

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i ' rocedures for mimmi/mg radiation esposure guidehnes f or reportable occurrences that call for to ation personnel during maintenance, cahbration,

" prompt notification with w ritten tollow up" as sum-and diagnostic procedures. (Reference m Chapter 12.

marized in Regulatory Guide 1.16. " Reporting of

" Radiation Protection.' of the Safen Analysis Operatmg I nformation-A ppenda A Techmeal Report.)

Specifications?

j. Traming program lor plant personnel that ad-I he follow up report to be subnutted to the Com-dresses operation of the system hardw are and the imssion within 2 weeks of the imtial notification of purpose and implementation of the loose-part detee-the presence of a loose part should melude t 1) a sum-tion program. (Reference in Chapter 13. " Conduct of mary of data obtained in the manual and auton?atic Operations ' of the Safety Analysis Report )

data acquisition modes: (21 a summary of the analy sis, inspections, and correlations with operating

5. Technical Specification for the Imose-Part I)etec-data that were performed to esaluate data from the tien System I iose-part detection program; and (3) a summary 01 conclusions and a description of modifications or A techmcal speciheation Ier the toose-part detec-other actions planned or already performed to tion sy stem should he prosided. Ihe techn: cal esaluate the safety implication of the loose part or to specihcanon should melude.

tnsure that sptem and component safety funcuons a.

T he location of the sensors.

h. A knuting condition for operation requiring the loose-part detection sptem to be operable durmg startup and power operation and. if one or more re-D. IMPLEMENTATION quired loose-part detection system chann4

.s m-operable for rnore than 30 days. ' ecial report to be lhe purpose of this section is to proside informa-c prepared and submiued to the Commission withm tion to appheants regardmg the NRC staffs plans for the next 10 days outlining the cause of the malfunc-using this regulatory guide.

oon and the plans for restoring the channeks) to an operable status b eept m those cases in w hich the applicant proposes an alternatise method f or complying with

e. A surseillance requirement that each channel of specified portions of the Commission's regulations, the loose-part detection sy stem be demonstrated the method described herein will be : sed in the operable by a channel check performed at least once esaluation of submittals for operatmg heense or con-per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. a channel funchonal test performed at struction permit appheations docketed after June 1, least once per 31 day s, and a cahbration tot per-1971 formed at least once per lM months.

If an applicant wishes to use this regulatory guide

6. Notification of a Imse Part in deseloping submittals for appheations docketed on or before June 1.197X. the pertinent portmns of the if the presence of a loose part is conbrmed, the application will be esaluated on the basis of this Commission should be natified according to the guide.

O 142 122 1.133-6

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