ML20236N240

Discusses 970731 Conference Call for Licensee to Seek Staff Interpretation of Definition of Core Alteration, Section 1.8 of TS

ML20236N240
Person / Time
Site:	Catawba
Issue date:	07/31/1997
From:	Tam P NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
Shared Package
ML20236J990	List: IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples IR 05000482/1991021 ML20236J987 ML20236K746 ML20236K751 ML20236K780 ML20236K784 ML20236K803 ML20236K816 ML20236K840 ML20236K853 ML20236K883 ML20236K902 ML20236K916 ML20236K936 ML20236K963 ML20236L549 ML20236L558 ML20236L563 ML20236L580 ML20236L584 ML20236L590 ML20236L597 ML20236L653 ML20236L921 ML20236L955 ML20236L971 ML20236M014 ML20236M020 ML20236M034 ML20236M057 ML20236M117 ML20236M138 ML20236M148 ML20236M911 ML20236M924 ML20236M966 ML20236M983 ML20236M996 ML20236N007 ML20236N047 ML20236N052 ML20236N066 ML20236N221 ML20236N240 ML20236N257 ML20236N271 ML20236N288 ML20236N323 ML20236N333 ... further results
References
FOIA-98-155 TAC-M72400, TAC-M72401, NUDOCS 9807150058
Download: ML20236N240 (1)

Text

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MEMORANDUM FOR: Docket File FROM: Peter S. Tam. Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/II

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Office of Nuclear Reactor Regulation

SUBJECT:

CATAWBA UNITS 1 AND 2 RECORD OF TELEPHONE CONVERSATION REGARDING CORE ALTERATION (TAC M72400 AND M72401)

On July 31. 1997. Margaret Chatterton of the Reactor Systems Branch and I held a conference call with Devereaux Tower of Catawba Nuclear Station. The call was previously requested by Mike Kitlan. Catawba site licensing manager.

The purpose of the call .was for the licensee to seek the staff's interpretation of the definition of " core alteration". Section 1.8 of the Technical Specifications (TS). It currently reads: ". . movement or manipulation of any component within the teactor pressure vessel with the vessel head removed and fuel in the vessel."

Section 3/4.9.4 specifies the containment configuration required before core alteration can take place.

Tha licensee's interest is that before fuel is moved during refueling. and presumably before the specified containment configuration is attained. equipment such as lights, cameras and tools can be moved into the reactor vessel. Such actions would cut a number of hours from the refueling time, and are not considered to have safety significance. Chatterton and I agreed that there is no safety concern: however, we informed the licensee that such actions would not literally comply with the current definition of core alteration. We did recogn12e that the core alteration definition in the proposed improved TS. currently under review, would permit such actions. That review is not scheduled to be completed before the next refueling. We stated that if the licensee is interested in using the definition in the proposed improved TS. the licensee may submit an amendment request to have the new definition in place before the next refueling outage.

T Docket Numbers 50 413 and 50 414 //7

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9807150058 980624 PDR FOIA

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