ML062750181

Technical Specifications, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet

ML062750181
Person / Time
Site:	Seabrook
Issue date:	09/29/2006
From:	Geoffrey Miller NRC/NRR/ADRO/DORL/LPLI-2
To:
Miller G, NRR/DLPM, 415-2481
Shared Package
ML062630457	List: ML062750181
References
TAC MC8554
Download: ML062750181 (5)

Text

(4) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor Instrumentation and radiation monitoring equipment calibration, and as fission detectoirs In amounts as required; (5) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use Inamounts as required any-byproduct, source, or special nuclear matedal without restriction to chemical or physical form, for sample analysis or Instrument calibration or associated with radioactive apparatus or components; (6) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein; and (7) DELETED C. This license shall be deemed to contain and Issubject to the conditions specified Inthe Commission's regulations set forth in 10 CFR Chapter I and Is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter In effect; and Is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FPL Energy Seabrook, LLC, is authorized to operate the facility at reactor core power levels not In excess of 3648 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendix A,as revised through Amendment Noli-, and the Environmental Protection Plan contained InAppendix B are Incorpo'ated Into Facility License No. NPF-86.

FPL Energy Seabrook, LLC shall operate the facility Inaccordance with the Technical Specifications and the Environmental Protection Plan.

(3) License Transfer to FPL Ene .mySeabrook, LLC

a. On the closing date(s) of the transfer of any ownership Interests in Seabrook Station covered by the Order approving the transfer,

• FPL Energy Seabrook, LLC, shall obtain from each respective transfening owner all of the accumulated decommissioning trust funds for the facility, and ensure the deposit of such funds and additional funds, If necessary, into a decommissioning trust or trusts for Seabrook Station established by FPL Energy Seabrook, LLC, such that the amount of such funds deposited meets or exceeds the amount required under 10 CFR 50.75.with'respect to the Interest in Seabrook Station FPL Energy Seabrook, LLC, acquires on such dates(s).

• Implemented AMENDMENT NO. 1 1 .2 .

J. Additional Conditions The Additional Conditions contained inAppendix C, as revised through Amendment Nol.12, are hereby incorporated into this license. FPL Energy Seabrook, LLC, shall operate the facility in accordance with the Additional Conditions.

K. Inadvertent Actuation of the Emergency Core Coolinq System (ECCS)

Prior to startup from refueling outage 11, FPL Energy Seabrook commits to either upgrade the controls for the pressurizer power operated relief valves (PORV) to safety-grade status and confirm the safety-grade status and water-qualified capability of the PORVs, PORV block valves and associated piping or to provide a reanalysis of the inadvertent safety injection event, using NRC approved methodologies, that concludes that the pressurizer does not become water solid within the minimum allowable time for operators to terminate the event.

.3. This .license is effective as of the date, of issuance and shall expire at midnight on March 15, 2030. .

FOR THE NUCLEAR REGULATORY COMMISSION (Original signed by:

Thomas E. Murdey)

Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments/Appendices:

1. Appendix A - Technical Specifications (NUREG-1386)

2. Appendix B : Environmental Protection Plan

3. Appendix C - Additional Conditions Date of Issuance: March 15, 1990 AMENDMENT NO. 6,94-.-4., 4Q&- 112

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIREMENTS 4.4.5.4 Acceptance Criteria

a. As used in this specification:

1) Imperfection means an exception to the dimensions, finish, or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections;

2) Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either the inside or outside of a tube;

3) Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation;

4)  % Degradation means the percentage of the tube wall thickness affected or removed by degradation;

5) Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective;

6) Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness. During refueling outage 11 and the subsequent operating cycles until the next scheduled inspection, this criterion does not apply to degradation identified in the portion of the tube below 17 inches from the top of the hot leg tubesheet. Degradation found in the portion of the tube below 17 inches from the top of the hot leg tube sheet does not require plugging. During refueling outage 11 and the subsequent operating cycles until the next scheduled inspection, all tubes with degradation identified in the portion of the tube within the region from the top of the hot leg tubesheet to 17 inches below the top of the tubesheet shall be removed from service;

7) Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, .a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.4.5.3c., above; SEABROOK - UNIT 1 3/4 4-16 Amendment No. 112

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIRMENTS 4.4.5.4 (Continued)

8) Tube Inspection means an inspection of the steam generator tube from the point of entry (hot-leg side) completely around the U-bend to the top support of the cold leg. During refueling outage 11 and the subsequent operating cycles until the next scheduled inspection, the portion of the tube below 17 inches from the top of the hot leg tubesheet is excluded; and

9) Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy-current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

SEABROOK - UNIT 1 3/4 4-16a Amendment No.1 42

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-86 FPL Energy Seabrook, LLC, shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number Date 50 NAESCO is authorized to relocate certain technical The amendment specification requirements to licensee-controlled shall be documents. Implementation of this amendment implemented shall include the relocation of these technical within 60 days specification requirements to the appropriate from March 12, documents, as described in the licensee's 1997 application dated October 17, 1996, and evaluated in the staffs Safety Evaluation attached to this amendment 94 FPLE Seabrook, LLC must maintain a program in This amendment effect to control the administration of potassium shall be iodide (KI) to control room personnel during core implemented alterations when the Primary Comtainment within 60 days Equipment Hatch is open. This program will remain from October 3, in effect until the current licensing basis for 2003 unfiltered inleakage is revised.

FPLE Seabrook, LLC shall maintain the operational This amendment limit of primary-to-secondary leakage at 150 gallons shall be per day per Steam Generator and if this limit is implemented exceeded, FPLE Seabrook, LLC will take the within 90 days appropriate actions 11 in accordance with TS 3.4.6.2, from September 29, "Reactor Coolant System Leakage." Spebr2 1 AMENDMENT NO. 66, 94, 112