2CAN129804, Forwards Corrected TS Page to 980629 Application for Amend to License NPF-6.Amend Request Corrections Were Determined to Be Necessary,Per Subsequent Conversations with Staff & Listed

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Forwards Corrected TS Page to 980629 Application for Amend to License NPF-6.Amend Request Corrections Were Determined to Be Necessary,Per Subsequent Conversations with Staff & Listed
ML20198K119
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/17/1998
From: Vandergrift J
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198K123 List:
References
2CAN129804, NUDOCS 9812300340
Download: ML20198K119 (3)


Text

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g Enttrgy oper:tions,Inc.

r ld 1448 SR 333 RusschiAe, AR 72801

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D - =har17,1998 i

r 2CAN129804 U. S. Nuclear Regulatory Commission

, Document Control Desk Mail Station OP1-17' Washington, DC 20555 J

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Subject:

Arkansas Nuclear One -Unit 2

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Docket No. 50-368 License No. NPF-6

' Additional Information In Support Of h Main Steam Safety Valve Tolerance i Technical Specification Change Request (TAC # MA2222) j l

i Gentlemen:

By letter dated June 29,1998 (2CAN06aSO4), Entergy Operations requested changes to the Arkansas Nuclear One (ANO) Unit 2 Technical Specifications (TSs). The proposed changes

- increase the allowable as-found lift setting tolerance on the main steam safety valves and

! pressurizer safety valves. In subsequent conversations with the staff, corrections to this amendment request were determined to be necessary and are discussed below.

  • The proposed modifications to TS 3.4.2 inadvertently omitted a footnote from this speci6catioa. The footnote designated with a # symbol was left off the proposed and  !

marked up pages. TS page 3/4 4-3 has becen corrected and is attached.

  • The marked up page for TS 3.4.3 contained a footnote annotation inconsistency in the limiting condition for operation section of this proposed specification. W associated footnote was' designated with the # symbolinstead of the
  • symbol. TS page 3/4 4-4 has been corrected and is attached. The proposed TS page 3/4 4-4 was correct in the original submittal and is therefore not included herein.
  • The first sentence in the last paragraph of the Bases for TS 3/4.7.1.1 has been modified.

The information discussing the most reuricting design bads events has been removed from the proposed and marked up pages. The revised Bases page B 3/4 7-1 is attached.

The information contained in this letter does not affect the conclusions of the no significant hazards determination of the June 29,1998 submittal. I l

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U. S. NRC j December 17,1998 j 2CAN129804 Page 2 Very tmly yours,

. T y D. Vandergri

. - Director, Nuclear S ety

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JDV/rde

Attachments i

J cc: Mr. Ellis W. Merschoff )

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlingter., TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR?2847 Mr. Chris Nolan NRR Project Manager Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852

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  • PROPOSED TECHNICAL SPECIFICATION PAGES I

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