ML101470069

American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval

ML101470069
Person / Time
Site:	Browns Ferry
Issue date:	05/24/2010
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101470069 (10)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing May 24, 2010 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, System Pressure Test Program for the Fourth 10-Year Inspection Interval The Tennessee Valley Authority is submitting the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, System Pressure Test (SPT) Program for the Fourth 10-Year Inspection Interval for Unit 2 of the Browns Ferry Nuclear Plant (BFN). The Code of Record for the Fourth 10-Year Interval SPT Program is the 2004 Edition of the ASME Boiler and Pressure Vessel Code,Section XI. The Fourth 10-Year Interval for BFN, Unit 2, commences on May 25, 2011 and ends on May 24, 2021.

The applicable regulation, 10 CFR 50.55a(g), requires that SPT examinations of ASME components of a water-cooled nuclear power facility meet the requirements of the ASME Section Xl Code. Additionally, 10 CFR 50.55a(g)(4)(ii) requires that the SPT program be updated every 120 months to the latest NRC approved Edition and Addenda of the ASME Section XI Code, which is in effect 12 months prior to the start of the next 120-month Inspection Interval. The enclosed BFN, Unit 2, SPT program update satisfies that requirement.

AoD(4 7 printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 May 24, 2010 The enclosure to this letter contains the updated BFN, Unit 2, ASME Section Xl SPT Program for the Fourth 10-Year Inspection Interval, which conforms to the 2004 Edition of the ASME Section Xl Code. There are no requests for relief submitted as a part of this SPT program update.

There are no new regulatory commitments contained in this letter. If you have any questions, please contact Terry Cribbe at (423) 751-3850.

Respectfully, R. M. Krich

Enclosure:

American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval (See Attached)

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Browns Ferry Nuclear Plant Unit 2 ASME,Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval E-2

Inservice Pressure Test Pro-gram Owner Address of Corporate Office Name and Address of Nuclear Power Plant Applicable Nuclear Units Commercial Operation Date Tennessee Valley Authority Chattanooga Office Complex 1101 Market Street Chattanooga, Tennessee 37402-2801 Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35609-2000 Browns Ferry Nuclear Plant Unit 2 March 1, 1975 E-3

Table of Contents 1.0 Statement of Applicability 2.0 Purpose 3.0 Inspection Interval and Inspection Periods 4.0 Code of Record 5.0 Requests for Relief 6.0 Tentative System Pressure Test Schedule E-4

1.0 Statement of Applicability This program outlines the requirements for performing American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section Xl system pressure tests during the fourth inspection interval for Browns Ferry Nuclear Plant (BFN) Unit 2 systems which are classified ASME Code Class 1, 2 or 3 or equivalent, and contain water, steam or radioactive waste (other than radioactive waste management system).

Pressure tests will be performed in accordance with the ASME Section Xl editions, addenda, and code cases, NRC approved requests for relief and additional provisions specified below or provisions approved by the NRC at a later date. Details concerning performance of system pressure tests are not part of this program description, but are contained in plant surveillance instructions. Performance of pressure tests required because of Repair/Replacement activities will be prescribed and controlled by the work documents performing the Repair/Replacement work.

The requirements of this program are applicable during the fourth 10-year inspection interval which begins on May 25, 2011.

2.0 Purpose This program is designed to meet the requirements of Section XI of the ASME Boiler and Pressure Vessel Code which pertain to the inservice pressure testing of pressure retaining Code Class 1, 2 and 3 components, and pressure testing required following Repair/Replacement activities, at BFN Unit 2 during the fourth inspection interval. Compliance with Section Xl of the ASME Boiler and Pressure Vessel Code is required by Part 50 of Title 10 of the Code of Federal Regulations.

3.0 Inspection Interval and Inspection Periods The fourth 10-year inspection interval for BFN Unit 2 begins on May 25, 2011. The fourth 10-year inspection interval will be divided into three inspection periods as shown below and will end in May 2021. The dates of the three inspection periods are as follows:

First inspection period May 25, 2011 to May 24, 2014 Second inspection period -

May 25, 2014 to May 24, 2018 Third inspection period May 25, 2018 to May 24, 2021 E-5

4.0 Codes of Record 4.1 Primary Code Edition This inservice system pressure test program is prepared to meet the requirements of Section Xl of the ASME Boiler and Pressure Vessel Code, 2004 Edition.

4.2 Adopted Portions of Later Editions and Addenda None.

4.3 Adopted ASME Section XI Code Cases (as approved by NRC Regulatory Guide 1.147)

Code Case N-566 Corrective Actions for Leakage Identified at bolted Connections - for systems containing boron for the purpose of controlling reactivity Code Case N-686 -

Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 5.0 Requests for Relief None.

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6.0 Tentative System Pressure Test Schedule Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 2 System Code Unit 2 Fuel Cycle Description Class 17 18 19 20 21 22 Reactor Recirculation 1

L1 LE L

LL L,

(Primary System)

Small Bore 2

L L2 L

Primary System Piping I

Main Steam System 2

L L2 L

Fuel Pool Cooling 3

L L2 Standby Liquid Control 2

L L2 L

Core Spray 2

L L2 L

Residual Heat Removal-2 L

L2 L

Common Suction Residual Heat Removal -

2 L

L7 L

Injection Loops High Pressure 2

L L3 L

Coolant Injection Reactor Core 2

L L7 L

Isolation Cooling RHR Service Water 3

L L2 L

Emergency Equipment 3

L LT L

Cooling Water Legend:

L - System leakage test {ASME Section Xl, IWA-521 1 (a)}

Notes:

1 - At the end of the cycle refueling outage, prior to startup 2 - After 5/25/2014 3 - Before 5/24/2018 4 - All Class 1 pressure retaining components {ASME Section Xl, IWB-5222(b)}

5 - U2R22 refueling outage will fall within the following 10-year interval Note: ASME Section XI Code references in this section are from the 2004 Edition.

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Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 2 System Pressure Test Program Procedures and ASME Section XI Code Category and Item Number Procedure Number ASME Section Xl Code Category / Item Number 2-SI-3.3.1.A and 2-TI-358 Primary System Leakage Test B-P / B15.10 (including Scram Discharge Volume)

C-H / C7.10 2-SI-3.3.1.C C-H / C7.10 Main Steam 2-SI-3.3.1.D and 2-TI-358 C-H / C7.10 Primary System Small Bore 2-SI-3.3.3 D-B / D2.10 Fuel Pool Cooling 2-SI-3.3.4 C-H / C7.10 Standby Liquid Control 2-SI-3.3.6 C-H / C7.10 Core Spray 2-SI-3.3.8.A C-H / C7.10 RHR Loop I 2-SI-3.3.8.B C-H / C7.10 RHR Common Suction 2-SI-3.3.8.C C-H / C7.10 RHR Loop II 2-SI-3.3.9 C-H / C7.10 HPCI 2-SI-3.3.10 C-H / C7.10 RCIC 2-SI-3.3.13 D-B / D2.10 RHRSW 2-SI-3.3.13.C D-B / D2.10 RHRSW (pits) 2-SI-3.3.14.A D-B / D2.10 EECW North Header 2-SI-3.3.14.B D-B / D2.10 EECW South Header 2-SI-3.3.14.C D-B / D2.10 EECW (pits)

Note: ASME Section Xl Code references in this section are from the 2004 Edition, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1.

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