ML12181A373

Riverkeeper Pre-Filed Evidentiary Hearing Exhibit RIV000113, in the Matter of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Vermont Yankee Nuclear Power Station), Docket No. 50-271 - Lr, ASLBP No. 06-849-03-LR..

ML12181A373
Person / Time
Site:	Indian Point
Issue date:	05/12/2008
From:	Horowitz J Riverkeeper
To:	Atomic Safety and Licensing Board Panel
SECY RAS
Shared Package
ML12181A367	List: ML12181A368 ML12181A369 ML12181A370 ML12181A371 ML12181A372 ML12181A373 ML12181A374 ML12181A375
References
RAS 22866, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12181A373 (3)

Text

RIV000113 Submitted: June 29, 2012 EXCERPT

• UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board May 12,2008 In the Matter of )

)

Entergy Nuclear Vermont Yankee, LLC ) Docket No. 50-271-LR and Entergy Nuclear Operations, Inc. ) ASLBP No. 06-849-03-LR

)

(Vermont Y allkee Nuclear Power Station) )

TESTIMONY OF JEFFREYS. HOROWITZ AND JAMES C. FITZPATRICK ON NEC CONTENTION 4- FLOW-ACCELERATED CORROSION I. WITNESS BACKGROUND JeffreyS. Horowitz ("JSH")

Ql. Please state your full name.

Al. (JSH) My name is Jeffrey S. Horowitz.

Q2. By whom are you employed and what is your position?

A2. (JSH) I am an independent consultant.

Q3. Please summarize your educational and professional qualifications.

A3. (ISH) My professional and eciucational experience is de-scribed in the curriculum vitae attached to this testimony as Exhibit E4-02. Briefly summarized, I have more than 36 years of experience in the field of nuclear energy and related disciplines. For the last 22 years, I have specialized in flow-accelerated corrosion ("F AC") and nuclear safety analysis.

My main client during this time has been the Electric Power

• Exhibit E4-06, Section 5.0.

Q20. What inspections are performed under VY's PAC Program?

A20. (JCP) The VY PAC Program confonns to the inspection rec-ommendations contained in NSAC-202L. See Exhibits E4-06, Section 5.0, and E4-07. The PAC Program calls for piping and component inspections to be *conducted at each refueling outage, with the items to be inspected being selected based on:

• required re-inspections and recommendations from previous outages.

• CHECWORKS susceptibility rankings or to calibrate the CHECWORKS models.

• industry/ utility/ station experience including items identified through work orders and condition reports .

• the susceptible non-modeled large bore and small bore program piping.

• engineering judgment.

See Exhibit E4-06, Section 5.3.

Q21. Could you explain in more detail how CHECWORKS is used in the PAC Pro-gram?

A21. (JCP) The PAC Program at VY primarily uses CHECWORKS' PAC wear rate analysis. VY uses CHECWORKS as a tool in planning inspections, evaluating inspection data, and managing the ultrasonic thickness ("UT") data compiled over the past thirteen refueling outages at Vermont Yankee.

Q22. Are there features of the VY design that result in a reduction of the amount of pip-ing and components at a typical plant that are potentially susceptible to FAC?

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• A22. (JCF) Yes. Compared to the majority of nuclear power plants in operation, VY is a relatively small and simple plant. There are fewer F AC-susceptible systems and piping components

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than at a typical plant, and many of those were either originally constructed ofF AC-resistant materials or have been replaced with F AC-resistant materials since their initial installation.

VY has vane-type moisture separators with no reheat steam system. This eliminates a large amount ofF AC-susceptible piping and a number of components known to be susceptible to FAC found in a typical nuclear power plant.

• The extraction steam system piping, which contains a signifi-cant portion of the two-phase piping in a power plant, was originally constructed from FAC-resistant materials. A number of other components and associated piping subject to two-phase flow (wet steam) have been replaced with FAC-resistant materials.

The original plant design and the component replacements re-sult in a significantly smaller amount ofFAC-susceptible pip-ing at Vermont Yankee as compared to the typical nuclear power plant of similar size.

Q23. Please describe the use ofFAC-resistant material at VY.

A23. (JCF) The most effective action in a Boiling Water Reactor

("BWR") to minimize potential FAC effects is to use piping materials that are resistant to FAC. As previously stated, the original design of VY already incorporated F AC-resistant pip-ing for the entire extraction steam system. In addition, since the plant went into operation, carbon steel piping and equip-

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