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
| ML20198K119 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| 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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_. _ _ ~ _, _. - _ _ _ _ _ _ _.. _. _ _ _. _. _ _ _.. _.,
p-g Enttrgy oper:tions,Inc.
ld 1448 SR 333 RusschiAe, AR 72801 r
Td 501858400U i
D - =har17,1998 i
r 2CAN129804 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OP1-17' Washington, DC 20555 J
i
Subject:
Arkansas Nuclear One -Unit 2
{
Docket No. 50-368 License No. NPF-6
' Additional Information In Support Of h Main Steam Safety Valve Tolerance i
l Technical Specification Change Request (TAC # MA2222) j 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.
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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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