ML19221A894
| ML19221A894 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1977 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.068.01, REGGD-1.068.01, NUDOCS 7907100261 | |
| Download: ML19221A894 (3) | |
Text
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Revision 1 U.S. NUCLEAR REGULATORY COMMISSION January 1977 REGLLATORY GEB JE OFFICE OF STANDARDG DEVELOPMENT REGULATORY GUIDE 1.68.1 PREOPERATIOrJAL AND INITIAL STARTUP TERTING OF FEEDWATER AND CONDENSATE SYSTEMS FOR SOILING WATER REACTOR POWER PLANTS A. INTRODUCTION suited concermng this guide and has concurred in the regulatory position.
General Design Criterion 1. " Quality Standards B. DISCUSSION and Records. of Appendix A. " General Design Criteria far Nuclear Power Plants." to 10 CFR Part in 1972 the AEC insestigated upht abnormal ec-50
' Lice n.in e of Production and Utiii/ation Facilities, requ' ires that nuclear power plant struc-currences at h,se different B% R power plants wmch tures. ss stems. and components important to safets inmked inadsertent release of significant amounts of be te te'd to quahty standards commensurate with th'e primary co lant into primary contamment through main steam line safety and reliel, sakes. ihe study importance of the safety functions to be performed.
resealed that the ability to automatically control Criterion NI. " Test Controlf of Appendix B.
reactor sessel water lesel within acceptable bounds
" Quality A ssu rance Criteria for Nuclear Pow er during anticipated transients was less than satisfac-Plants and Fuel Reprocessing Ph.
to 10 CFR tory.
Part 50 requires that a test progam oc established to There base also been abnormal occurrences as-ensure identification and rerformar.ce of au testine sociated with feedwater systems at operating nuclear required ti demone.. th'at siructures ss stems. and power plants that resuhed f rom emme sibration of components ui perform satisfactord in sersice.
sy st em components ani piping. These operating Regulatory Guide 1.M. " Initial Test Procrams for problems could hase been identified by thorough Water-Cooled Reactor Power Plants." identifies tests testing during the initial test program.
acceptable to the NRC e ff for pieoperational and A h.er considering the experience to date. the NRL.
startup testing of nuclear power plant structures.
staff has concluded that guidance should be prosided s3 stems, and components. Tests for boiling water rep tding the preoperational and imtial startup reactor (BWR) pow er cons ersion sy stems are described in Reculators Guide 1.6S to proside as-testing identified in Reguhaors Guide 1.M for the surance that the'se syste'ms will perforrn as designed BWR teedwater and condsnue sy stems.
ar.d to aid in minimi/mg the probability of system Ihis guide addresses both preoperational nd in-malfunctions during subsequent olant operations.
itial punt startup phases of the testing of BW.R This guide desc-ibes in more detail the type and power plant f.eedwater and condensate sy stems.
nature of BW.R feedu ater and condensate system
- ' tests that are acceptable to the staff. The Adsisory
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C. REGULATORY POSITION the os eral; response of the control system, including the fmal control element. Tests should aho serify that Compreherwve preoperational and initial startup the oserall response of the control sy stem to testing programs on the feedwater an.1 condensate simulated limiting malfunctions in the control sy stem ss stems of boihng w ater reactors should be per-(such as feedwater controller failure to maximum formed to proside anurance that these systems will now demand) and to simulated plant transients (such accomf sh the regt. ed functions under normal as main steam line isolation s ahe ciosure at full flow li operational and transient conditions as stated in the conditions and turbine trip without bypass at full safety analy sn report.
flow conditions) is m accordance with performance requirements for the control sistem. Such testine
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an[il Preoperational testing is conducteJ prior to fuel should be conducted in both sinele-element loadmg to determme component operability and per-three-element sy stem control modes.
formance and to s erify proper sy steni installation.
While as r-ch of thi " m cf mn; as practicable
- g. Proper operation ofinstrumentation and alarms should be accomphshed during this P ase, the ab;lity utilized to monitor the performance of the systems.
h to conduct some sy stem-lesel testing and component testing is hmited by the unasailability of reactor
- 2. Startup Testing pow er or sy stem flow paths or other factors. Thus, these test should be completed as part of the initial The startup phase of the initial test program should plant startup test program.
include at least tests and measurements to serifs the follow ing:
Fests that were satisfactorily completed during preopera: tonal testing need not be repeated.
- a. Operabililty of the feedw ater sy stem at low reae-tor power ( Gl57 reactor power).
- 1. Preoperational Testing
- b. Proper ruponse of the feedw ater control system The areoperation al phase of the initial test in tne manual mode of control. Tests should serify program should inclu ' at least tests and measure-that the system can be operated in the manual mode ments to serify the folMt mg:
and that transfer to the automatie mode can be ac-complished in accordance with design requirements
- a. Operability of pumps utih/ed to provide
(
153 reactor power).
feedwater flow (condensate. condensate booster, and feedu ater pumpst Tests should confirm that the
- c. The stability and response characteristics of the pumps satisfy all performance requirements. in-automatic control sy stem are in accordance with per-c!udmg required head, flow rate, suction head and formance requirements for normal plcnt operation oserspeed characteristics (157 to 100'i reactor power)
- b. Operabihty and correct setpoint:; of permissise
- d. The stabihty and response characteristics of the and prohibit interlocks in the starting and shutdow n automatic control sy stem following plant tran aents controh for the pump drisers.
are in accordance with sptem performance require-ments. Tests should serify that the acceptance criteria
- c. Proper operation of controls used for manual for maximum and minimum water lesels in the reac-and automatic starting and stonping of the pump tor sessel are not exceeded as a result of plant tran-sient'. such as turbine trip and ma:n steam isolation sal e closure, with the control ss stem in the
- d. Operabiht of. s ah es utih./ed f.or adjusting the automatic mode of courol (15" tiluul reactor f eeds.ater now rate. T ests si'ould s crity proper pow ert response of s ah es for the design o,erating range and correct operation of protectise femres such as ther-mal os erload des iees and
- u. der, waee sensine
- e. The response of the feedwater system is in ac-desices incorporated in the design of s ah'e operator's cordance with performance requirements f ollow ing and awociated control circuitrs.
k" of a feedwater pump (100'; reactor power).
- e. Operabilits of sensors and associated in-
- f. V brat;on les els for sy stem components and pip-strumentation that proside inputs to the feedwater n,g are within predetermined limits control sy stem. Tests should serify stable and ac-curate outputs in response to test sienals
- c. Piping mosement' during heatup and steady-state and transient operation are within nredeter-nuned limits
- f. Operability of the feedwater contrc! system.
n ests should serify the proper response of indnidual components in the control sy stem (including
- h. Adequate mareins cust b :t w een ss stem prog ra m m ers. summers. and signal modifiers) and s ariables and setpoin'ts of mstruments momtoring
'"2 125 348
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these s ariables to present spurious actuation or loss tion to applicants regarding the NRC staffs plans for of 9 stem pumps and motor-operated sabes.
using this reguhtory guide.
- 3. Test Report, This guide reDeets current NRC staff practice Therefore, euert in those cases in u hich the appli-See Regulatory Position 9 in Reculators Guide cant proposes an acceptable alternative method for 1.td. " Initial Test Procrams for Wate'r-Cooled Reae.
complying with specified portions of the Comn'; -
tor Po,, e r Plants' for cuidance recardine sion's regulations, the ti.thod described herein is preoperational and initial star' tup test repor'ts.
ing and will continue to be used in the esaluation. i submittah for operating license or construction per-D. IMPLEMENTATION mit applications until this guide is resised as a result of suggestions from the public or additional staff The purpose of this section a to proside infortna-res iew.
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