W3F1-2005-0013, . Modify Technical Specification (TS) 5.3.1, Fuel Assemblies and TS 6.9.1.11.1, Core Operating Limits
| ML050540401 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/21/2005 |
| From: | Harris A Entergy Nuclear South, Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2005-0013 | |
| Download: ML050540401 (5) | |
Text
- Entergy Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6475 Fax 504-739-6698 aharris@entergy.com W3Fl -2005-0013 Alan J. Harris Director. Nuclear Safety Assurance Waterford 3 February 21, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
REFERENCES:
Supplement to Amendment Request NPF-38-258, Modify Technical Specification (TS) 5.3.1, Fuel Assemblies and TS 6.9.1.11.1, Core Operating Limits Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
- 1.
Entergy letter to the NRC dated June 20, 2004, "License Amendment Request to Modify Technical Specification (TS) 5.3.1, Fuel Assemblies and TS 6.9.1.11.1, Core Operating Limits" (W3F1-2004-0036)
- 2.
Entergy letter to the NRC dated October 18, 2004, "Supplement to Amendment Request NPF-38-258, Modify Technical Specification (TS) 5.3.1, Fuel Assemblies and TS 6.9.1.11.1, Core Operating Limits" (W3F1 -2004-0099)
- 3.
Entergy letter to the NRC dated February 2, 2005, "Supplement to Amendment Request NPF-38-258, Modify Technical Specification (TS) 5.3.1, Fuel Assemblies and TS 6.9.1.11.1, Core Operating Limits" (W3F1 -2005-0003)
Dear Sir or Madam:
By letters (References 1, 2 and 3), Entergy Operations, Inc. (Entergy) proposed a change to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TSs) to support Cycle 14 core reload.
On February 16, 2005, Entergy and members of your staff held a conference call to discuss the need to include additional information in the proposed TS associated with the removal of a reference to a Combustion Engineering Topical Report number CENPD-107 from TS 6.9.1.11.1, item 6) "CESEC-Digital Simulation for a Combustion Engineering Nuclear Steam Supply System." As a result of the call, Entergy will add reference information, uCE letter LD-82-001 and NRC SE to CE dated April 3,1984," to the proposed TS change. Please see the attached markup of the affected TS page. No changes are proposed to any of the other marked up TS pages or to the inserts included in the original submittal dated June 20, 2004.
There are no technical changes proposed. The original no significant hazards consideration included in Reference 1 is not affected by any information contained in the supplemental letter. There are no new commitments contained in this letter.
W3F1 -2005-0013 Page 2 of 3 If you have any questions or require additional information, please contact Dana Millar at 601-368-5445.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 21, 2005.
Sincerely, AJH/DM Attachments:
- 1. Revised Markup of Technical Specification Pages
W3F1 -2005-0013 Page 3 of 3 cc:
Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Nageswaran Kalyanam MS O-7D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445
Attachment I To W3FI -2005-0013 Revised Markup of Technical Specification Pages
Attachment I to W3Fl-2005-0013 Page 1 of 1 ADMINISTRATIE QONTROLS CORE OPERATN IIS EpTCL (Continued)
- 6) "CESEC - Di talSi ation for a Combustion Engineering Nuclear Steam Supply System,"
Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating and group P CEA Insertion Limits, and 3.2.3 for Azimuthal Power Tilt).
- 7) "Qualification of Reactor Physics Methods for the Pressurized Water Reactors of the Entergy System," ENEAD-01-P. (Methoddogy for Soecifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and group P CEA Insertion limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW). and 3.9.1 Boron Concentration).
- 8) "Fuel Rod Maximum Allowable Gas Pressure, CEN-372-P-A. (Methodology for Specification 32.1, Linear Heat Rate).
Nv$5 T 6.9.1.112 The core operating limits shall be datelappicable limits (e.g., fuel thermal limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
6.9.1.11.3 The CORE OPERATING LIMITS REPORT, including any mid-cyde revisions or supplements thereto, shall be provided upon issuance, for each reload cyde, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted In accordance with 10 CFR 50.4 within the time period specified for each report.
6.10 Not Used AMENDMENT NO. 421446,15i82, WATERFORD - UNIT 3 6-20a
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