ML19221A895

Reg Guide 1.68.2,Revision 1, Initial Startup Test Program to Demonstrate Remote Shutdown Capablity for Water Cooled Nuclear Power Plants

ML19221A895
Person / Time
Issue date:	07/31/1978
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.068.02, REGGD-1.068.02, NUDOCS 7907100265
Download: ML19221A895 (3)

Text

Revision 1 July 1978

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U.S. NUCLEAR. REGULATORY COMMISSION O M*

OFFICE OF STANDARDS DEVELOPMENT MGL E'ORY G U OE

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REGULATORY GUIDE 1.68.2 INITIAL STARTUP TEST PROGRAM TO DEMONSTRATE REMOTE SHUTDOWN CAPABILITY FOR WAT5R-COOLED NUCLEAR POWER PLANTS A. INTRODUCTION nuclear power plant structures, systems, and General Design Criterion (GDC) 1,

' Quality Standards and Records, of Appendix A, " General This guide describes an initial startup test program Design Criteria for Nuclear Power Plants," to 10 CFR acceptable to the NRC for demonstrating hot Part 50,

' Domestic Licensing of Production and standby capability and ir,; potential for cold shut-L'tilization Facilities, requires that structures, sy s-down from outside the control room This guide is tems, and components important to safety be tested to applicable to water-cooled nuclear power plants. The quality standards commensurate with the importance Advisory Committee on Reactor Eafeguards has been of the tafety functions to be performed.

consulted concerning this guide and has concurred in the regulatory position.

C n.terion XI, " Test Control, of Appendix B,

" Quality Assurance Criteria for Nuclear Power B. DISCUSSION Plants. ' to 10 CFR Part 50 requires that a program be estabhshed to ensure that all testing necessary to Regulatory Guide 1.68 liso, as one of its initial demonstrate that structures, sy stems, and components startup tests the demonstration of " shutdown from will perform satisfactorily in service be identified and outside the control room, ' the capability for which is conducted. GDC 19, " Control Room, ' of Appendix required by GDC 19. Experience in the application of A to 10 CFR Part 50 requires that equipment at Regulatory Guide 1.68 has shown that amplification appropriate locations outside the control room be of guidance for initial test programs in this ara is provided (1) with a design capability for prompt hot desirable. For example, some applicants have not shutdown ' of the reactor, including necessary in-construed this provision of Regulatory Guide 1.68 to strumentation and contrcis to maintain the umt m a include demonstration of reactor trip capability from safe condition during hot shutdown, and (2) with a outside the control room, but oniv maintenance of the

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potential capability for subsequent cold autdown of hot standby condition. Further guidance has also been the reactor through the use of suitable procedures.

required to clarify the role of additional personnel Regulatory Guide 1.68, ' Initial Startup Test located in the control room dunng the demonstration, whose function would be to perform non-safety-Pro.erams for Water-Cooled Reactor Power Plants,"

describes a method acceptable to the NRC staff for related activities that v auld not be required during an complying with the Commission's regulations with actual emergency shutdown. Finally, no initial start-regard to preoperational and initial startup testing of up test programs reviewed to date have included pcovisions to fully demonstrate the requirements of end pan M paga@ m M GK W, nam @,

' The tern. " hot shutdown" used in GDc 19 corresponds to the term " hot standbs ' as defined in the Standard Technical the potential for cold shutdown from outside the Specificmont The terrn ' hot sta nd by ' will be used in this control room. This 1"st orovision is of considerable guide " Cold shutdown' is also defined in the StanJard importance since < nonstration of this capability Technical specifications lends the added as-ve that, in the event a fire or

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c. The authority and responsibility of the control unusante for an indeterminate lencth of time. no room vosers ers should be established and danpr to the health and safety of the public f rom potential low of controlled residual her :r m al Jocumented in the test procedme. Prosision should capability would result. Although it is cor hat be made for the following actions:

the likelihood of large-scale control rom.n d nage

'II ^"umphon of connol of the plant if an from any postulated esent is s ers sma;i the emergency or unsafe condition deselops dunng the defense-in-depth. concept practiced m the design, ny hat cannot N managd N the autdow n testing. and inspection of nuclear power plants bpe-I

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cificans, in the case of remote shutdow n capability.

set forth in GDC IH mandates tnat all practical (2) Per formance of non-saf ety -related ac-as sic ps be taken to ensure that the plant can be tisities that wouid not be required during an actual maintained in a safe condition at all times, even in remote shutdow n These could inc ude protection of the esent of highly unlikely, but foreseeable, non-safety-related equipment from mechanical dam-incidents.

age during the transient and the placement of equip-ment into standby status when no 1 nyer required

.The NRC statt has thus concluded that additional S.uch actisities should hase been prniously detmed guidance should be piosided regard;ne the scope of-and es aluated to ensure that,

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testine, documentation of procedures, and the reporti perfonned durine an actual remote shutdown safe me of te st result-ertainine to demonstration of Any shutdow n of. the plant could still be achiesed actisities m adJilion to these should be recorded and remote shutdow n iabilits. T he pu rpose of. the demonstration n thru.old: (1) to demonstrate that the dd um m & W m ww hir iny design of the plant is adequate to meet the rey'ure-on the validity of the total test performance.

ments of. Ot)L, lt (2) to demonstrate that the procedures be used in perf orming the shutdown

d. Preoperaticnal testing of plant instrumenta-trom outside the control room are sutticiently clear tion. controls, and sy stems to be used at remote and comprehensise and that the operating personnel shutdow n locations should hase been completed.

are familiar with their application; and (3) to demon-T his preoperational testing should hase included strate that the number of personnel as ailable to scritication that all sy stems to be used during shut-conduct the shutdow n operation is sufficient to per-down operation from outside the control room are form the many actions required by the procedure in a operable in the manner in which they would be used timely, coordinated manner.

during the operation ti e.

control from remote sta-tions, n'anual operation, use of as ailable po w er supplies, etc.) and that communication could be C. REGULATORY POSITION established and maintained among the personnel who win N performing the shutdown operation Addi-l Licensees of w ater-cooled nuclear power plants honahy..I appucaNe to the p! ant d'4pn. suWcanon should deselop and conduct a test procram to demon-strate remote shutdown capabilits hIr each unit of should hase been made that control of transferred their plants The test procram Ehould contain the conpcenh fmn the mMn contnd mun is nm e ahn mnnol M be mmponenh fmm the t

pov i following elements:

remote shatdown stations has been established Much

1. Objectises of this serification can be done in conjunction with other tests. such as indnidual sy stem or component Verification that the nuclear power plant can a

P"'opuanonal h stt if successfuh) completed. these be safely shut down from ou' side the control room.

verification tests need not be repeated

b. Verification that the nuclear power plant can

3. Ilot Standby Demonstrat. ion Procedure be maintamed in a hot standby condition f. rom outside the control room.

The test shoulJ be initiated f rom a location outside the control room with the reactor at a moderate power

c. \\,erification that the nucicar power plant has lesci (10-254 ) suf ficientis hich that plant sy stems the potential for being safels cooled f rom hot standhs y

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are in the normal configuration with the turbine-to cold shutdow n condition. from outside the control gennator in operation The test should be performed roo m.

with the minimum cf personnel required to be at the

2. Prerequisites reactor unit at any one time tminimum shift crew).

Data should be obtained at locations outside the Approved operatir.g procedures for perform-mnnol room to s erifs:

a.

ing a remote shutdown should be available, including approsed procedures for conducting the test.

a. That the plant has achiesed hot standby

b. Communications should e si st betw ee n the control room ebsersers and the remote shutdow n

b. 'Ihat the plant can be maintained at stable hot locationt standby conditions f or at least 30 minutes2

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During the demonstration, only that equipment for

c. A heat transfer path to the ultimate heat sink which credit woald be taken in peiforming an ac:ual can be established.

remote shutdown should be used.

d. Reactor coolant tempe ature can be reJuced

4. Cold Shutdown Demonstration Procedure approximately 5WF using th.s decay heat removal sutem at a rate that woulJ not exceed technical The demonstration of cold shutdown capabili'y hifiem on limits. This cooldown should show that need not necessarily be performed immediatel) fol~

the potential for achiesine cold shutdown from out-lowing the demonstration of achiesing and maintam-side the control room is available. ine safe hot standbv from outside the control room. During the demonstration, only that equipment for Rather, this cooldown portion of the test may be combined with another startup test requirine' the which credit would be taken to perform an -tual rt'nmte Mmtdown should be used. reactor to be cooled Jown, as long as the procedures and acceptance criteria for the combined test meet all

5. Reporting I the elements of each individual test.

See Regulatory Position 9 in Regulatory Guide The licensce should demonstrate a potential capa-1.68 for a listing of the information that should be bility for cold shutdown by partially cooling down included for this test in the startup report. the plant from the hot standby condition using controls and instrumentation located outside the con-trol room. This cooldown demonstration may be D. lMPLEMENTATIO N accomplished using additional personnel who could a t be made asailable to the unit prior to the time that . _he purpose of. h.is section is to provide informa-cooldown would have to be initiated. The number I*" I" ".pplicants regarding the NRC staff s plans for u ng is regulatog guk and level of such personnti should be (stablished by each applicant in the remote shutdown procedule. This guide reflects current NRC staff practice. The test should demonstrate that. Therefore, except in those cases in which the appli-

a. The reacto; soolant temperaore and pressure pmposes an ac'aptable alteraatise method tlor

a n t can be lowemd..ficiently to permit it.e operation of egnglying with specified portions of the Commij smn s regulations, the method described herem is the ec': decay heat removal sy stem that is to be being and will continue to be used in the evaluation @ uit:mately used to place the reactor in a re:ueling permit applications until th. """de is resised as a ' " * " II "P#""N"E "' C* m uctbn shutdown mode. is gui

b. Operation of this decay heat removal system result of suggestions from the public or additional can be initiated and controlled.

staff review. 125 353 g 1.68.2-3

UNITED STATES p q NUCLEAR RECULATORY COMMISSION .a W ASHINGTON. D. C. 20555 POST AGE AND FEES P AtD [ ?;T",t't."J,,:rllf: uma Orrici At eusi~Ess PENALTY FOR PRIVATE USE, $300 ( j O us 3s4 9}}