ML060190486

Implementation of Amendment Associated with New Reactor Building Emergency Sump Strainers, Tcs Number 2004-08

ML060190486
Person / Time
Site:	Oconee
Issue date:	01/05/2006
From:	Brandi Hamilton Duke Energy Corp, Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TSC-04-08
Download: ML060190486 (8)

Text

BRUCE H HAMILTON

_=_ k Vice President r frwero Oconee Nuclear Station Duke Power ONOJVP / 7800 Rocherster Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax January 5, 2006 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

Subject:

Oconee Nuclear Station Docket Numbers 50-269, 270 and 287 Implementation of Amendment Associated with New Reactor Building Emergency Sump (RBES) Strainers, TSC Number 2004-08 On November 1, 2005, the Nuclear Regulatory Commission (NRC) issued Amendment Nos. 348 and 350 to Renewed Facility Operating Licenses DPR-38 and DPR-47 for Oconee Nuclear Station (ONS), Units 1 and 2. The amendments consists of changes to Technical Specification (TS) in response to a Duke Energy Corporation (Duke) application dated August 18, 2005, as supplemented by letter dated September 15, 2006.

Duke's License Amendment Request (LAR) requested the change for Unit 3, however, supporting calculations for the Unit 3 modification had not been completed prior to the need date for Unit 2. As a result, NRC issued the amendment for Units 1 and 2 only.

During implementation of this change, in order to retain the existing requirements for Unit 3 and implement the new requirements for Units 1 and 2, Duke created separate TS pages applicable to Units 1 and 2 (Amendment Nos. 348 and 350) and to Unit 3 (retained existing Amendment No. for Unit 3). The NRC (Leonard Olshan) agreed that this method of implementation was appropriate and strictly administrative.

The NRC requested we submit the revised pages after implementation.

Attachment 1 provides the revised Technical Specification pages.

www. dukepower. corn

U. S. Nuclear Regulatory Commission January 5, 2006 Page 2 If there are any additional questions, please contact Boyd Shingleton at (864) 885-4716.

Very truly yours, Bruce H Hamilton, Vice President Oconee Nuclear Site

U. S. Nuclear Regulatory Commission January 5, 2006 Page 3 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 Dr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. C. Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201

January 5, 2006 ATTACHMENT 1 TECHNICAL SPECIFICATION Remove Page Insert Page 3.5.2-5 3.5.2-5a 3.5.2-5b 3.5.3-3 3.5.3-3a 3.5.3-3b

HPI 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each HPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing Program required developed head.

SR 3.5.2.4 Verify each HPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.5 Verify each HPI pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.5.2.6 Verify, by visual inspection, each HPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet strainers I show no evidence of structural distress or abnormal corrosion.

SR 3.5.2.7 Cycle each HPI discharge crossover valve and 18 months LPI-HPI flow path discharge valve.

OCONEE UNITS 1 & 2 3.5.2-5a Amendment Nos. 348 & 350 l

HPI 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each HPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing Program required developed head.

SR 3.5.2.4 Verify each HPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.5 Verify each HPI pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.5.2.6 Verify, by visual inspection, each HPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

SR 3.5.2.7 Cycle each HPI discharge crossover valve and 18 months LPI-HPI flow path discharge valve.

OCONEE UNIT 3 3.5.2-5b Amendment No. 314 l

LPI 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.2 ------------------------NOTE-------------------------

Not applicable to operating LPI pump(s).

Vent each LPI pump casing. 31 days SR 3.5.3.3 Verify each LPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing required developed head. Program SR 3.5.3.4 Verify each LPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.3.5 Verify each LPI pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.5.3.6 Verify, by visual inspection, each LPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet strainers I show no evidence of structural distress or abnormal corrosion.

OCONEE UNITS 1 & 2 3.5.3-3a Amendment Nos. 348 & 350 l

LPI 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.2 ------------------------ NOTE-------------------------

Not applicable to operating LPI pump(s).

Vent each LPI pump casing. 31 days SR 3.5.3.3 Verify each LPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing required developed head. Program SR 3.5.3.4 Verify each LPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.3.5 Verify each LPI pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.5.3.6 Verify, by visual inspection, each LPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

O C O NEE U NIT 3 3.5.3-3b Amendment No. 341 l