ML20196D478
ML20196D478 | |
Person / Time | |
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Site: | North Carolina State University |
Issue date: | 11/30/1998 |
From: | North Carolina State University, RALEIGH, NC |
To: | |
Shared Package | |
ML20196D474 | List: |
References | |
NUDOCS 9812020252 | |
Download: ML20196D478 (2) | |
Text
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NCSU PULSTAR Technical Specifications i 1.24 Senior Reactor Ooerator: A senior reactor operator is an (SRO) individual who
- is certified to direct the activities of reactor operators. i
- 1.25 Shutdown Margin
- Shutdown margin means the minimum shutdown reactivity
- necessary to provide confidence that the reactor can be made subcritical by means i
of the control and safety systems starting from any permissible operating condition
- with the most reactive scrammable rod fully withdrawn, the non-scrammable rod ,
(Shim rod) fully withdrawn, and with experiments considered at their most ;
- reactive condition, and finally, that the reactor will remain subcritical without j
- further operator action. '
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- 1.26 Total Nuclear Peaking Factor
- The factor obtained by multliplying the ;
measured local radial and axial neutron fluence peaking factors.
l 1.27 True Value: The true value is the actual value of a parameter. !
i j 1.28 Unscheduled Shutdown: An unscheduled shutdown is defined as any unplanned l 1 shutdown of the reactor caused by actuation of the reactor safety system, operator I error, equipment malfunction, or a manual shutdown ir n;sponse to conditions l l which could adversely affect safe operations. This does not include shutdowns ;
j which occur during testing or check-out operations. :
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l 30 November 1998 9812O20252 981130 I 5 Amendment 13 PDR ADOCK 0500029T P PDR,
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j NCSU PULSTAR j Technical Specifications 3.0 LIMITINO CONDITIONS FOR OPERATION l
l 3.1 Reactor Core Configuration Aoplicability i This specification applies to the reactor core configuration during forced l convection or natural convection flow operation. ,
Obiective l The objective is to assure that the reactor will be operated within the bounds of established Safety Limits.
Specification l
The reactor shall not be operated unless the following conditions exist: l
- a. A maximum of twenty-five fuel assemblies.
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- b. A maximum of ten reflector assemblies of either graphite or beryllium or a
! combination of these located on the core periphery.
- c. Unoccupied grid plate penetrations plugged. I
- d. A minimum of four control rod guides are in place.
l e. The maximum worth of a single fuel assembly shall not exceed 1.59%Ak/k (1590 pcm).
- f. The nuclear total peaking factor in any fuel assembly shall not exceed 2.92 4
Bases Specifications 3.1(a) through 3.1(d) require that the core be configured such that ;
there is no bypass cooling flow around the fuel through the grid plate. i Specification 3.1(e) provides assurance that a fuel loading accident will not result j in a Safety Limit to be exceeded as discussed in SAR Section 13.2.2.1.
Specification 3.1(f) provides assurance that core hot channel power are bounded by the SAR assumptions in Appendix 3-B.
30 November 1998 12 Amendment 13