Regulatory Guide 1.68
| ML13350A354 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1977 |
| From: | NRC/OSD |
| To: | |
| References | |
| RG-1.068.1, Rev. 1 | |
| Download: ML13350A354 (3) | |
7,, V
Revision, 1 US. sNUCLER REGULATORY COMMISSION. January, 1977
- REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 1.68.1 PREOPERATIONAL AND INITIAL STARTUP TESTING OF
FEEDWATER AND CONDENSATE:
SYSTEMS FOR BOILING WATER REACTOR POWER PLANTS
suited concerning this guide and has concurred in the
A. INTRODUCTION
r*gulatory position. I.
Generai Design Criterion I. "Quality Standards
B. DISCUSSION
anid.. R ords." of Appendix A. "Gern'eral Design
- Criteria for Nuclear. Power. Plants." to 10 CFR Part In 1972 the A,.EC investigated eight abnormal oc- M., "Licensing of Production andLUtilization currences at five different BR.. power plants which FacilitieusL requires that nuclear power plant struc- involved inadvertent release of significant a.iOunts of lures. sstlems. andconmponents important to salety primary coolant into primary containment through be tested .to quality standards conimensurate %ith the main steamn line .safety, and relief valves. The. study"'
I.niportance.of the safety runctions Io he".performed:
revealed that the.ability to autom atical.v -on.ntrol reactor vessmil water level within:acceptahle hounds
.. Cr~teron Xl. "Test Control." of Appendix B,
during anticipated transients was less ihan satiSfaic-
- Oualitv Assurance Criteria for Nuclear Power Plants and F'uel Re'processing Plants." to 10 CFR tory.
Part 50 requires-that a test program he established to There have also been abnormal occurrencls as*
ensure identification and performance of all testing sociated with feedwater systerms at operating nuclear required tO demonstrate that structures. systems, and power plants that resulted from e\cessive vibration of
0 components will perform satisfactorily in service.
Regulatory Guide 1.68, "Initial Test Programs for Water-Cooled Reactor Power Plants." identifies tests s.stem components and piping. These operating problems could have been identified by thorough testing during the initial test program.
acceptable to the NRC staff for preoperationai and After considering the experience to date. the NRC-
startup testing of nuclear power plant ,iructures. staff has concluded that guidance should be provided systems, and components.. Tests for boiling '%ater regarding the. preoperational and initial stairtup reactor (BWR) power conversion .. sstems are tesling identified in Regulatory.Guide 1.68 for the described in: Regulatory' Guide 1.68 to provide as- BE\R feeddwater and condensate systems.
surance. that these systems will perform as designed and to aid in minimizing the prdbabiiity of system This guide addresses both preoperational and iln- malfunclions during subsequent plant, operations. itial plant startup, phases of the testing of B\WR
This guide describes -in more detail the type and power plant feedwater and condensate systems.
nature of BWR feedwater and condensate system eate froin Operatingv l1itiiing
"E'valltillion ll' el" rinmtr,, .oo];lan [*lw tests that are acceptable to the staf
f. The Advisory
1N Committee on Reactor Safeguards has been con- W afer R ac:tisr," I
' .. ] 1.1260.; ..K: *ropi, rtt:,a I.h tttti d t'rtrn the N ittionaI .reuhnlical InfOrntitioh S:rv.:c, t.I S. patrtl.rll ,i1 Slaines indicltoc suhstanltivt clh*tnjgs Ifrtom previous issuc. Cttonwt'rce. Springfidd. VA 221I.
Comnments fhilutd he sent to the Secretary of the Comrnrris', nn S Nmitr,r, USNRC REGULATORY GUIDES
Regulaitorv Comnnission. Washington D.C 2%55. Atte*irris, Dio r.kotiij Anid AiRgulatoay Guides are issued to describe and make available to the pubic Serice Section.
.
methods a~cepfable to the:NRC staff of !mplementng specific parts of t.
Commllon's regulations. to delineate, eehniQues used by the it.l il evailu t issued u d0%jlvl%,1 nit loiowig tiili.n a tO to dtph t
tling specific probtlems or post ulited accidento.
I. Power Reactors 6 Prottucis cants- Regulatory Guides are trot substitutes for regulation
s. And compliance
2 Reetctandest Reactour 7 tansport,nrirnn with themi not reqUiled Methods and solulions differaent from those s
5. t out in
3 ufuels arid Materiats Fatciliies 8 OcctuzpallitirI Ffllitll the guides will be acceplable if they provide i b:Sis flot the fimdings ferlutte tif
4 Eivrnorrerta uit a irilnlj 9 Antitrust Re*I*w the issuance e of a permit or license by fhe Conrnlltsson
5 Marterrafs and Plant Prutetionn 10 Oerr.rt Commn nts and suggestions for improvemenis in these guides are encourgAid.
at Alt times. and guides will be fainsed, as appropriate. to Atccommrrlodate con, irritirairtit inh a, a Copra% of published guides may tie obttainied ly written, rnlrtlutirt ments and to reflect new inlormation Oe.mpritlence 1his gquide wa% lteCnrll C
staff diviions desired to lhe U S Nuclear Regulatory Comnr-l1llo. Wa/tf'lictlat'ItD
fesult of substantive cnmments received from the public and additional
205.Arir*ertioti Oi lect. Office of SI.aliniads. Denvlloprtelli t review
7 ý-v C, "RE.GULATORY POSITION the. overall response of the-control system. including r the final control element. Tests should also verify that i
C6mprehensive -preoperational and initial-siartuip the.' overall; response. of the. control . svstem to. ,
testing programs o"n the feedw'iter' and: co*densate simulated Ilimiting malfunctions in the control system
.systm o.f boiling .ilier reacto rs "..sh0ould b e .per- (such as feedwater controller failure to maximum.
forLn ied to provide .assurance.h, th t he'se system Will .s flwdemand) nd'toinulated pattransients (ch.
iacconmplish 'the required functions tinder:.normal -asmain. steam line isolion valve.closure at full' f .ow operational a.nd.trns entcondctions atns safet, ana hlsisu report .
stated'in: the S..Preoperational testling: is conducted prior to fuel
-conditions and turbine. trip without by-pass at full flow conditioris) is in accordance with performance.
r ..equireIments .for the control system. Such -testing..
should be conducted in both single-elementand'
.I
Ioading to determine component operability and per- three-element system control modes.
formane. and to) verify proper -system installation.
.. hik as m uch of this typ of
\% e testing as.practicable g... Proper operation of instrumentation and alarms should be i*ccomp.1ished during this phase. the ability utilized to.monitor the performance of the systems.
to.conduct.soe* c system-level testing and component testine i's limlited b%the unavailability of reactor 2. Startup Testing power or.systemm flow paIths. or other factors. Thus.
these iests.should be completed as part of the. initial The startup phase ofthe initial test program should plarit startup test progranm. include at least tests and measurements to verify the fonlowing:
"- Tes~ts that. ...were, .sa.tisf~ictorily c. ompleted --dur~ing preoperational testing need:ruot be repeated. a. Operabililty:of the feedwater svstem.at low reac- tor power (<-1% reactor power).
1.I lre .perationalT esting b. Proper response of the feedwater control system The preoperational phase of the initial' test in.themanual mode:of control. Tusts should verify program should include at least tests and m'easu.re- that the system can be operated in the manual mode ments to verify the following: and that Itransfer to the.automatic mode can be ac- complished
- in accordance with design requirements a. Operability of pumps utilized .to.provide (-.I5%: reactor power).
feedwater flow (condensate. condensate booster. and
- feed 'Water pumps) . Tests should confirm that .the c. The stabilityand response characteristics of the pumps satisfy all, performain.ce requirements, in- automatic control system are in accordance with per- eluding required head. flow rate.-suction head. and formance requirements for normal plant operation
- overspeed characteristics. (15% to 100% reactor power).
b. Operability. and correct setpoints of permissive d. The stability and response characteristics of.the
- and prohibit interlocks in the starting and shutdown automatic controlsystem 'following plant transients controls for the pump drivers. are in accordance with system performance require-.
ments. Tests should verify that the acceptance criteria c. Proper .operation of controls used for manual for maximum and minimum water levelsin the reac- and
- automati=c starting and stopping of the -pump tot vessel arenot exceeded as a result of.plant tran- drivers. sients. such as turbine trip and main steam isolation valve closure, with the control system in the
.d. Operability of valves utilized for adjusting the automatic mode of control (15% to 100% reactor feedwater flow rate. Tests should verify proper power).
response of valves for the design. operaLing range and correct operation of protective features 'such as ther- mal overload devices and undervoltage sensing e. The response of the feedwater system is in ac-
- devices incorporated in the design of valve operators ccordance with performance requirements following and associated control circuitry; loss of a feedwater pump (100% reactor power).
e. Operability of sensors and associated' in- f. Vibration levels for system components and pip- strumentation that provide inputs to the feedwater ing are wiihin predetermined limits.
- control system. Tests should verify stable and' ac- curate outputs in response to test signals. g. Piping movements during.heatup. and steady- state and transient operation are within predeter- f. Operahility of the feedwater control system. *mined limits.
Tests should verify the proper response of individual components in the control system (including h. Adequate margins exist between system programmers, summers., and signal modifiers) and variables and' setpoints of instruments monitoring
1:68.1-2
these variables to prevent spurious actuation or loss tintoapifcants regarding the NRC stafrls planisfo of system:pumps and motr-operuted. valves. usingl, h regulaIo.tyg.uide.: "
I-Test -Reports This guide reflects current NRC staff pr:ci+.
.Thereofore.. except in those cases in which the .,npli- See Regulatory Position 9 in Regulatory Guide. cant proposes an:acceptable alternative method for
1.8. Initial Test Programs for Water-Cooled Reac, complying with specified portions of the Commis- tor Power Plants. -for. guidance regarding sion's regulations, the method described herein is be- preoperational and initial startup te+/-st reports. ing and will continue to beused in theý evaluation .of submittals.for.operating license or construction per-
0. IMPLEMENTATION mit applications until thisguide is revised as a result of suggestions from the public or additional staff The purpose of this section is to provide informa, review.
1.68.1-3