ML20034B018

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Proposed Tech Specs,Changing Definition for Core Alteration in Section 1.12 to Clarify Scope of Movement or Manipulation of Component During Core Alteration
ML20034B018
Person / Time
Site: Millstone 
Issue date: 04/10/1990
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20034B014 List:
References
NUDOCS 9004250219
Download: ML20034B018 (2)


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.c Docket No. 50-336~

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l h111 stone Nuclear Power. Station, Unit' No. 2 Proposed. Change to Technical -Specifications Core Alteration i

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1 DEFINITIONS CORE ALTERATION l.12 CORE ALTERATION shall be the movement or manipulation of fuel, CEAs, Neutron Sources, or Upper Guide Structure within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

Suspension of Core Alterations shall not preclude completion of movement of a component to a safe, conservative position.

SHUTDOWN MARGIN 1.13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be cuberitical from its present condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest j

reactivity worth which is assumed to be fully withdrawn.

l IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or l

b.

Leakage into the containment atmosphere from sources that are both l

specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSVRE BOUNDARY LEAKAGE.

UNIDENTIFJ.ED LEAKAGE 1.15 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

PRESSURE BOUNDARY LEAKAGE 1.16 PRESSVRE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolated fault in a Reactor Coolant System component body, pipe wall or vessel wall.

CONTROLLED LEAKAGE 1.17 CONTROLLED LEAKAGE shall be the water flow from the reactor coolant pump seals.

MILLSTONE - UNIT 2 1-3