W3F1-2006-0037, Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006

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Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006
ML062020165
Person / Time
Site: Waterford Entergy icon.png
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)
v • d • e


Text

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

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