ML20199D961

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Submits Revised Pages to Be Added to Original TS Change Request NPF-38-204.Change Adds Requirements That CR Intake Monitors Operable & Surveillance Requirements Be Applicable During Movement of Irradiated Fuel
ML20199D961
Person / Time
Site: Waterford Entergy icon.png
Issue date: 01/12/1999
From: Ewing E
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20199D966 List:
References
W3F1-99-0004, W3F1-99-4, NUDOCS 9901200272
Download: ML20199D961 (2)


Text

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EntIrgy Oper tion 2. Inc.

-m Killona, LA 70066 Tel 504 739 6242 Early C. Ewing. til v

afety & Regulatory Affars W3F1-99-0004 A4.05 PR Januay 12,1999 U.S. Nuclear Regulatory Commission

- Attn: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Technical Specification Change Request NPF-38-204, Revision 1 s

Actions That Suspend Positive Reactivity Changes Gentlemen-Entergy, on behalf of Waterford 3, originally provided Technical Specification Change Request (TSCR) NPF-38-204 by Letter W3F1-98-0044 on June 29,1998. The proposed changes modified Technical Specification (TS) 3.7.6.1 (Control Room Emergency Air Filtration System - Modes 1-4), TS 3.7.6.2 (Controi Poc m Emergency Air Filtration System - Modes 5 and 6), TS 3.7.6.3 (Control Room Air Temperature -

Modes 1-4), TS 3.7.6.4 (Control Room Air Temperature - Modes 5 & 6), and TS 3.7.6.5 (Control Room Isolation and Pressurization), and the associated Bases.

On January 6,1999, Entergy discussed this change with Mr. Chandu Patel of the Staff. Based on this conversation, Entergy is submitting the attached revised pages to be added to the original TSCR. The additional proposed changes modify TS k )

Tables 3.3-6 and 4.3-3 for the Control Room Intake Monitors. This change adds the requirement that the Control Room Intake Monitors be OPERABLE and the l.

Surveillance Requirements be applicable during movement of irradiated fuel. This change is necessary since these radiation monitors are required for isolation of the control room. Entergy has concluded that this change is bounded by the original No ht 0

Significant Hazards Evaluation. Therefore, the original No Significant Hazards Evaluation continues to be applicable.

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- Technical Specification Change Request NPF-38-204, Revision 1 W3F1-99-0004 Page 2 January 12,1999 i

Should you have any questions or comments concerning this request, please contact Early Ewing at (504) 739-6242.

Verh truly yours, ji

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E.C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/ CWT /rtk Attachments:

Attachment A-Existing Specification Attachment B - Proposed Specification i

cc:

E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR l

1. Ahmed, NRC-NRR J. Smith N.S. Reynolds NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)

American Nuclear Insurers I

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