W3F1-2009-0055, Revised Page for License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit

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Revised Page for License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
ML092800514
Person / Time
Site: Waterford Entergy icon.png
Issue date: 10/06/2009
From: Christian K
Entergy Nuclear South, Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2009-0055
Download: ML092800514 (5)


Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093

- Entergy Tel 504-739-6496 Fax 504-739-6698 kchrisl @entergy.com Kenny J. Christian Nuclear Safety Assurance Director Waterford 3 W3F1-2009-0055 October 6, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Revised page for License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

1. Waterford Steam Electric Station, Unit 3, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit, 6/3/09 (Agency-wide Documents Access and Management System (ADAMS) Accession No. ML091560027)
2. Teleconference with Mr. Kaly Kalyanam, October 5, 2009

Dear Sir or Madam:

This submittal is provided pursuant to Reference 2 and includes a replacement page for the Technical Specification mark-up from Reference 1.

The proposed change does not include any new commitments.

If you have any questions or require additional information, Please contact Robert J. Murillo at 504-739-6715.

I declare under penalty of perjury that the foregoing is true and correct. Executed on October 6, 2009.

Sil Aloof

W3F1-2009-0055 Page 2

Attachment:

1. Technical Specification Mark-up Replacement Page

W3F1-2009-0055 Page 3 cc: Mr. Elmo E. Collins, Jr.

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004

Attachment 1 W3F1 -2009-0055 Technical Specification Mark-up Replacement Page

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE DNBR 2.1.1.1 The DNBR of the reactor core shall be maintained greater than or equal to +26.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the DNBR of the reactor has decreased to less than 1-26-, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

PEAK FUEL CENTERLINE TEMPERATURE 2.1.1.2 The peak fuel centerline temperature shall be maintained less than 5080°F (decreasing by 58 0 F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A.)

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the peak fuel centerline temperature has equaled or exceeded 5080OF (decreasing by 58 0 F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A),

be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

MODES 3, 4, and 5 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, reduce the Reactor Coolant System pressure to within its limit within 5 minutes. /r WATERFORD - UNIT 3 2-1 AMENDMENT NO. 42,-8, +-88-