ML20009H133
| ML20009H133 | |
| Person / Time | |
|---|---|
| Issue date: | 07/14/1981 |
| From: | NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20009H132 | List: |
| References | |
| REF-10CFR9.7 SECY-81-020D, SECY-81-020D-ERR, SECY-81-20D, SECY-81-20D-ERR, NUDOCS 8108060092 | |
| Download: ML20009H133 (2) | |
Text
..
. (xt)
Provide an evaluation of depressurization methods, other than by full actuation of the automatic depressurization system, that would reduce the possibility of exceeding vessel integrity limits during rapid cooldown.
(Applicable to BWR's only)
(II.K.3.45)
(2) To satisfy the folloring requirements, the application shall provide sufficient information to demor. strate that the required actions will be satisfactorily completed by the operating license stage. This information is of the type customarily required to satisfy 10 CFR 50.35(a)(2) or to address unresolved generic safety issues.
(1)
Provide simulator capability that correctly models the control I
room and includes the capability to simulate small-break 1.0CA's.
(Applicable to construction permit applicants only)
(I.A.4.2.)
4 (ii)
Establish a program, to begin during construction and follow into operation, for integrating and expanding current efforts to improve plant procedures. The scope of the program shall include emergency procedures, reliability analyses, human factors engineering, crisis management, operator training, snd coordination with INP0 and other industry efforts.
(Applicable to construction permit applicants only)
(I.C.9)
(iii)
Provide, for Comission review, a control room design that reflects state-c.f-the-art human factor principles prior to committing to fabrication or revision of fabricated control room panels and layouts.
(I.D,1)
(iv)
Provide a plant safety parameter display console that will display to operators a minimum set of parameters defining the safety status of the plant, capable of displaying a full range 8108060092 010714 PDR 10CFR PT9.7 pgg
,l 6 (xxiii) Provide, as part of the reactor protection system, an anticipatory i
reactor trip that would be actuated on loss of main feedwater and on turbine trip.
(Applicable to B&W-designed plants only).
1
( I I.K.2.10)
(xxiv) Provide the capability to record reactor vessel water level in one location on recorders that meet normal post accident recording requirements.
(Applicable to BWR's only).
(II.K.3.23)
(xxv) Provide an onsite Technical Support Center, an onsite Operational Support Center, and, for construction permit applications only, a nearsite Emergency Operations Facility.
(III.A.1.2)
(xxvi) Provide for leakage control and detection in the design of systems outside containment that contain (or might contain) TID 14844 source term radioactive materials following an accident. Applicants shall submit a leakage control program, including an initial test program, a schedule for re-testing these systems, and the actions to be taken for minimizing leakage from such systems. The goal is to minimize potential exposures to workers and public, and to provide reasonable assurance that excessive leakage will not prevent the use of systems needed in an emergency.
( III.D.1.1 )
(xxvii) Provide for monitoring of inplant radiation and airborne radioactivity as appropriate for a broad range of routine and accident conditions.
(III.D.3.3)
(xxviii) Evaluate potential pathways for radioactivity and radiation that may lead to control room habitability problems under accident conditions resulting in a TID 14844 source term release, and make necessary design provisions to preclude such problems.
(III.D.3.4)
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