W3F1-2003-0074, Request for Amendment, Increase Unit'S Rated Thermal Power Level from 3441 Megawatts Thermal (Mwt) to 3716 Mwt. Without Enclosures

Request for Amendment, Increase Unit'S Rated Thermal Power Level from 3441 Megawatts Thermal (Mwt) to 3716 Mwt. Without Enclosures

ML040260330
Person / Time
Site:	Waterford
Issue date:	11/13/2003
From:	Venable J Entergy Nuclear South, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NPF-38-249, TAC MB0789, W3F1-2003-0074
Download: ML040260330 (7)

Text

Entergy Nuclear South Entergy Operatons. Inc.

1725 MM Fver Ruud Entergy villona, LA 70066 Tel 504 739 6660 Fax 504 739 6678 jvenbloe rgy.com Joseph E. Venable Vice Presiden. Operatto Waterfad 3 W3FI-2003-0074 November 13, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. DC 20555

SUBJECT:

License Amendment Request NPF-38-249 Extended Power Uprate Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

NRC Letter, T. Alexion (NRC) to C.Anderson (Entergy), "Application for License Amendment to Increase Authorized Power Level (TAC No.

MB0789)," April 24, 2002

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment for Waterford Steam Electric Station, Unit 3 (Waterford 3). Revisions to the Facility Operating License and Technical Specifications are requested to increase the unit's rated thermal power level from 3441 megawatts thermal (MWt) to 3716 MWt. This represents an 8%

increase over the present licensed power level (i.e., Appendix K margin recovery power level) and a 9.6% increase over the original licensed power level and requires modification of the high-pressure turbine. Therefore, this power uprate is defined as an Extended Power Uprate (EPU).

Relevant information is provided in the Attachments described below.

Attachment I contains descriptions and technical justifications for the proposed Operating License and Technical Specifcation changes. The NRC approved similar Operating Ucense and Technical Specification changes for Arkansas Nuclear One, Unit 2 (ANO-2) as described in the Reference. contains Operating License and Technical Specification markups to facilitate identifying proposed changes.

Attachments 3 and 4 Identify associated changes to the Technical Specification Bases and Technical Requirements Manual. These changes are provided for information only.

W3FI-2003-0074 Page 2 of 4 Attachment 5 contains the Extended Power Uprate Report (PUR). The PUR includes evaluations that demonstrate acceptable system and component performance under EPU conditions and analysis results confirming that acceptance criteria for Loss of Coolant Accident (LOCA) and non-LOCA safety analyses are met for the requested Increase Incore power.

These analyses were performed consistent with the proposed Technical Specification changes.

Environmental effects of the proposed power uprate are also evaluated and shown to be acceptable. contains a proprietary version of PUR Appendix 1- Safety Evaluation Report Compliance. PUR Appendix I contains information proprietary to Westinghouse Electric Company (WEC), LLC. contains the non-proprietary (redacted) version of PUR Appendix 1 - Safety Evaluation Report Compliance and Attachment 9 contains WEC's application for withholding the proprietary information from public disclosure.

The proposed change includes commitments as summarized in Attachment 8.

Two additional Ilcense amendment requests are required in support of this EPU submittal. They will:

• Extend the Pressure Temperature (P-T) curves from 16 to 32 effective full power years (accounting for EPU conditions).

• Eliminate the Hydrogen Analyzer and Recombiner requirements from Technical Specifications consistent with the recent rule change to 10 CFR 50.44.

The Pressure Temperature Curve license amendment request was submitted on October 22, 2003 (W3Fl-2003-0075). The Hydrogen Analyzer and Recombiner license amendment request Is scheduled to be submitted by the end of 2003. The approval of the EPU submittal is contingent upon the approval of these additional submittals.

Control room dose for non-LOCA events is not addressed in this EPU submittal. In response to Generic Letter 2003-01. *ControlRoom Habitability. Entergy has committed to complete an evaluation of the control room envelope by the end of September 2004. Control room dose for non-LOCA events under EPU conditions will be addressed based on the results of the Generic Letter 2003-01 required evaluation. Additionally, LOCA and FHA control room doses provided in this submittal will be reevaluated, as necessary, based on the results of the Generic Letter 2003-01 required evaluation.

The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that this change Involves no significant hazards considerations. The bases for this determination are included in the attached submittal.

Entergy requests approval of the proposed amendment by January 2005. Once approved, the amendment will be implemented during restart from refueling outage 13 in the spring of 2005 and unit operation at the Increased power level wll occur In Cycle 14.

W3FI-2003-0074 Page 3 of 4 If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.

I declare under penalty of perjury that the foregoing is true and correct. Executed on November 13, 2003.

Sincerely, J. E. Venable Vice President, Operations Waterford Steam Electric Station, Unit 3 JEV/GDH/DBM/cbh Attachments:

1. Analysis of Proposed Technical Specification Changes

2. Proposed Operating License and Technical Specification Changes (mark-up)

3. Changes to Technical Specification Bases Pages - For Information Only

4. Changes to Technical Requirements Manual - For Information Only

5. Waterford 3 Extended Power Uprate Report

6. Waterford 3 Extended Power Uprate Report Appendix I - Safety Evaluation Report Compliance (Proprietary)

7. Waterford 3 Extended Power Uprate Report Appendix 1 - Safety Evaluation Report Compliance (Non-proprietary)

8. List of Regulatory Commitments

9. Westinghouse Electric Company Application for Withholding Proprietary Information from Public Disclosure

W3FI-2003-0074 Page 4 of 4 cc: Mr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford NPS 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 Radiological Emergency Plan and Response Surveillance Division P. 0. Box 4312 Baton Rouge, LA 708844312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29 th S. Main Street West Hartford, CT 06107-2445

Attachment I W3FI-2003-0074 Analysis of Proposed Technical Specification Changes to W3FI-2003-0074 Page 1 of 21

1.0 DESCRIPTION

This letter is a request to amend Operating License NPF-38 for Waterford Steam Electric Station, Unit 3 (Waterford 3).

The proposed change will revise the Operating License to permit Waterford 3 to operate at a maximum steady state reactor core thermal power of 3716 MWt. The requested Increase constitutes an Extended Power Uprate (EPU) and Is requested to provide greater unit electrical generating capacity. Entergy requests approval of the proposed amendment by January 2005.

Once approved, the amendment will be implemented during restart from refueling outage 13 in the spring of 2005 and operation at the increased power level will occur in Cycle 14.

2.0 PROPOSED CHANGE

The requested change involves one revision to the operating license and several changes to the Technical Specifications. Each change is described below and evaluated in Section 4.0 of this attachment.

Operating license change:

License condition 2.C.1, Maximum Power Level It is proposed to change the maximum core power level from 3441 MWt to 3716 MWt.

Technical Specification changes are identified below. Some changes are required for the EPU and others are requested improvements that are not required to support facility operation under EPU conditions. The required changes are identified as such in the description of the changes.

The Technical Specification table of contents has been revised to be consistent with the proposed Specification changes. Changes to the table of contents are strictly an editorial/administrative matter, and are not discussed further.

Dose Equivalent 1-131. Definition 1.10 The definition of DOSE EQUIVALENT I-131 is revised to be consistent with ICRP 30 dose conversion factors since ICRP conversion factors were used in dose consequence analyses. Reference to Table IlIl in TID 14844 is replaced with reference to ICRP 30, Supplement I to Part 1, pages 192 - 212, Tables titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity." This Is an EPU related change.

Rated Thermal Power. Definition 1.24 Rated thermal power is changed from 3441 MWt to 3716 MWt This is an EPU related change.

to W3FI-2003-0074 Page 2 of 21 Table 2.2-1, Reactor Protective Instrumentation Trip Setpoint Limits, Functional Unit #7 The Steam Generator Pressure - Low trip setpoint is reduced from Ž 764 psia to 21662 psia and the allowable value is reduced from 2 749.9 psia to 2 647.9 psia. This is an EPU related change.

Borated Water Sources- Shutdown, Specification 314.1.2.7 Boron concentrations, in weight percent, are deleted in Specification 3.1.2.7, leaving concentrations expressed only in ppm. The range of boron concentration is specified as being between 4900 and 6125 ppm. The 4900 ppm represents an increase from the current minimum value of 3950 ppm (2.25 weight percent). The maximum value of 6125 ppm (3.50 weight percent) is unchanged. The boron concentrations specified in 3.1.2.7 are identified as indicated values. The increase in minimum required boron concentration is an EPU related change.

In Surveillance Requirement 4.1.2.7, Reactor Auxiliary Building air temperature and boric acid make-up tank solution temperature are identified as indicated values.

Borated Water Sources - Operating, Specification 3/4.1.2.8 and associated Figure 3.1 -1 Figure 3.1-1 in 3.1.2.8a.2 is changed to new Figure 3.1-2. This is an EPU related change.

The value 475,500 gallons in 3.1.2.8b.1 is deleted, leaving the minimum required refueling water storage pool volume of 83% indicated level in the Specification. In 3.1.2.8b.2, the boron concentration values are identified as indicated values. In 3.1.2.8b.3, the boric acid solution temperatures in the refueling water storage pool are identified as indicated values.

In4.1.2.8a, The Reactor Auxiliary Building air temperature is identified as an indicated value. In 4.1.2.8b, the BAMT temperature and the Reactor Auxiliary Building air temperature are identified as indicated values.

The page number for 3/4.1.2.8 is changed from 3/4 1-14 to 3/4 1-13.

Figure 3.1-1 Is replaced with a new figure to reflect the revised minimum boric acid concentration of 4900 ppm and an increase in Boric Acid Makeup Tank (BAMT) minimum volume required when relying on one BAMT. New Figure 3.1-2 is added to reflect the revised BAMT boron concentration and volume requirements when relying on two BAMTs. This is an EPU related change.

The page number for Figure 3.1-1 is changed from 3/4 1-13 to 3/4 1-14.

Reactor Coolant Cold Leq Temperature, Specification 3.2.6 The cold leg temperature range is changed from 541OF - 5580 F to 5360 F - 5490F, and the temperatures are identified as indicated values. In addition, the temperature of