W3F1-2006-0037, Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006
ML062020165 | |
Person / Time | |
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Site: | Waterford ![]() |
Issue date: | 07/18/2006 |
From: | Murillo R Entergy Nuclear South, Entergy Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
W3F1-2006-0037 | |
Download: ML062020165 (6) | |
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Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations W3F1-2009-0031, Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 20092009-07-0909 July 2009 Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 2009 W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 W3F1-2008-0073, Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 20082008-11-11011 November 2008 Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 2008 W3F1-2008-0052, Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration2008-09-17017 September 2008 Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration W3F1-2008-0016, Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 20082008-02-20020 February 2008 Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 2008 W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/20072007-06-13013 June 2007 Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 W3F1-2006-0037, Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 20062006-07-18018 July 2006 Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006 W3F1-2004-0090, Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/042004-10-0707 October 2004 Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/04 W3F1-2004-0016, Technical Specificaiton Bases Update to the NRC for Period July 24, 2003 Through February 25, 20042004-02-26026 February 2004 Technical Specificaiton Bases Update to the NRC for Period July 24, 2003 Through February 25, 2004 W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 20032003-07-24024 July 2003 TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003 W3F1-2003-0002, Technical Specification Bases Update to the NRC for the Period October 1, 2002 Through January 7, 20032003-01-15015 January 2003 Technical Specification Bases Update to the NRC for the Period October 1, 2002 Through January 7, 2003 W3F1-2002-0090, Technical Specification Bases Update to the NRC for the Period January 16, 2002 Through September 30, 20022002-10-14014 October 2002 Technical Specification Bases Update to the NRC for the Period January 16, 2002 Through September 30, 2002 W3F1-2002-0012, Revision to Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.22002-01-31031 January 2002 Revision to Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.2 W3F1-2002-0005, Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 20022002-01-16016 January 2002 Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 2002 ML18053A6971991-05-0808 May 1991 License Amendment Request Technical Specification Change Request NPF-38-114 2023-07-26 |
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Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6715
~Entergy Fax 504-739-6698 rmurill~entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3171-2006-0037 July 18, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Technical Specification Bases Update to the NRC for the Period November 1, 2005 through July 1,2006 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Pursuant to Waterford Steam Electric Station Unit 3 Technical Specification 6.16, Entergy Operations, Inc. (EQI) hereby submits an update of all changes made to Waterford 3 Technical Specification Bases since the last submittal per letter W3171 -2005-0062, dated December 1,2005. This TS Bases update satisfies the requirement listed in 10 CER 50.71 (e).
There are no commitments associated with this submittal. Should you have any questions or comments concerning this submittal, please contact Ron Williams at (504) 739-6255.
Very truly yours, RJ M/RLW/cbh Attachment Waterford 3 Technical Specification Bases Revised Pages AboDI
W3FI -2006-0037 Page 2 cc: (w/Attachments)
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 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. Mel B. Fields MS O-7E1 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 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers 95 Glastonbury Blvd - Suite 300 Glastonbury, CT 06033-4443
ATTACHMENT I To W3FI-2006-0037 Waterford 3 Technical Specification Bases Revised Pages to W3FI-2006-0037 Page 1 of 1 T.S. Bases Implementation Affected TS Bases Topic of Change Change No. Date Pages 45 3/1/2006 Page B 3/4 5-3 Change No. 45 to TS Bases section 3/4.5.4 Refueling Water Storage Pool (RWSP) was implemented by ER-W3-2006-0057-O00. TS Bases Section 3/4.5.4 was changed to more accurately state the RWSP 50OF minimum temperature limit is the limit assumed in the accident analyses with the TS operating limit conservatively specified at 550F indicated to
___________ ______________ I protect the 50OF analytical limit. -
TECHNICAL SPECIFICATION BASES CHANGE NO. 45 REPLACEMENT PAGE, (1 page)
Replace the following page of the Waterford 3 Technical Specification Bases with the attached page. The revised page is identified by Change Number 45 and contains the appropriate DRN number and a vertical line indicating the areas of change.
Remove Insert Page B 3/4 5-3 Page B 3/4 5-3
EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.4 REFUELING WATER STORAGE POOL (RWSP)
The OPERABILITY of the refueling water storage pool (RWSP) as part of the ECCS also ensures that a sufficient supply of borated water isavailable for injection by the ECCS in the event of a LOCA. The limits on RWSP minimum volume and boron concentration ensure that (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWSP and the RCS water volumes with all CEAs inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
4+(DRN 04-1243, Ch. 38)
The minimum contained borated water volume limit, 83% indicated, includes an allowance for water not usable because of pool discharge line location, other physical characteristics, and instrument uncertainty. The safety analysis assumes an available volume of 383,000 gallons which is bounded by the 83% level indicated.
4-(DRN 04-1243, Ch. 38)
The lower limit on contained water volume, the specific boron concentration and the physical size (approximately 600,000 gallons) of the RWSP also ensure a pH value of between 7.0 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
-b(ORN 06-1 88, Chi.45)
The maximum limit on the RWSP temperature ensures that the assumptions used in the containment pressure analysis under design base accident conditions remain valid and avoids the possibility of containment overpressure. A RWSP minimum temperature of 50OF is the analytical limit assumed in the accident analyses. The TS minimum temperature of 550F is specified to protect this analytical limit.
4-(DRN 06-1 88, Ch. 45)
WATERFORD - UNIT 3 B 3/4 5-3 AMENDMENT NO. 42-7--,4-30 CHANGE NO. 38, 45