ML13130A056

E-mail from R.Guzman to P.Couture Request for Additional Information - Relief Request RR-P02 Dated February 1, 2013 - Bvy 13-008

ML13130A056
Person / Time
Site:	Vermont Yankee
Issue date:	05/09/2013
From:	Richard Guzman Plant Licensing Branch 1
To:	Couture P Entergy Nuclear Vermont Yankee
Guzman R
References
TAC MF0624
Download: ML13130A056 (1)

Text

From: Guzman, Richard Sent: Thursday, May 09, 2013 10:32 AM To: 'Couture III, Philip'

Subject:

Vermont Yankee Request for Additional Information - Relief Request RR-P02 dated February 1, 2013 dated February 1, 2013 - March 27, 2013 - BVY 13-008 (TAC No. MF0624)

Phil, By letter dated February 1, 2013 (Agencywide Document Access and Management System Accession No. ML13039A027), Entergy Nuclear Operations, Inc., submitted for Nuclear Regulatory Commission staff review and approval, Relief Request RR-PR-02, an alternative request for the High Pressure Coolant Injection (HPCI) main/booster pump combination, P44-1A/B, from the acceptance criteria specified in Table 5121-1 of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the fifth 10-year inservice test interval for Vermont Yankee Nuclear Power Station.

The NRC staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). To support the staffs timely review, we request that you provide a formal response by June 10, 2013. Please contact me if you have any questions.

REQUEST FOR ADDITIONAL INFORMATION (RAI)

ENTERY NUCLEAR OPERATIONS, INC.

VERMONT YAKEE NUCLEAR POWER STATION ALERNSIVE REQUEST RR-P02 DOCKET NUMBER 50-271 (TAC NO. MF0624)

RAI-1

In the licensees relief request dated February 1, 2013, the licensee submitted an alternative request for the High Pressure Coolant Injection (HPCI) main/booster pump combination, P44-1A/B, from the acceptance criteria specified in Table 5121-1 of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). Specifically, the licensee proposed to use higher acceptable and alert ranges than those specified in the OM Code for the vibration points I-3, O-3 and I-4. The licensee stated that of the ten vibrations measured during inservice testing, only three have not been reduced below the OM Code Alert Range limits. Please provide for NRC staff review, a detailed history of past test results taken from these vibration points: I-3, O-3, and I-4.

Rich Guzman Sr. Project Manager NRR/DORL/LPL1-1 US NRC 301-415-1030