ML020720533

Annual Report of Safety Relief Valve Failures and Challenges January 1 Through December 31, 2001

ML020720533
Person / Time
Site:	Monticello
Issue date:	02/27/2002
From:	Forbes J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML020720533 (2)

Text

M2002015 Monticello Nuclear Generating Plant NM C Committed to Nuclear Excellence 2807 West County Road 75 Monticello, MN 55362-9637 Operated by Nuclear Management Company LLC February 27, 2002 Tech Spec Section 6.7.A.6 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Annual Report of Safety Relief Valve Failures and Challenges January 1 through December 31, 2001 In accordance with Monticello Technical Specification Section 6.7.A.6, and NUREG 0737 item I1.K.3.3, the Annual Report of Safety Relief Valve Failures and Challenges is provided in attachment A.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

Please contact Paul Hartmann at (763) 271-5172 if you require additional information concerning this report.

Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Attachment c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Sr. Resident Inspector, NRC Minnesota Department of Commerce CA 2122102 N C:\Documents and Settings\hrtpO4\Desktop\Safety Relief Valve Challenges Annual Report 2002.doe

Attachment A Annual Report of Safety Relief Valve Failures and Challenges January 1 through December 31, 2001 In accordance with Monticello Technical Specification section 6.7.A.6, and NUREG 0737 item II.K.3.3, the following Annual Report of Safety Relief Valve Failures and Challenges is provided:

Failures:

None.

Challenges:

10/23/01 SRV no. RV-2-71 H was cycled opened six times automatically by the plant's Low-Low Set System at a reactor pressure of 1052 psig following plant scram no. 112.

12/13/01 SRV no. RV-2-71A was manually opened at reactor pressure of approximately 150 psig in accordance with a surveillance test performed during plant startup.

12/14/01 SRV no.s RV-2-71B through RV-2-71H were manually opened at reactor pressure of approximately 150 psig in accordance with a surveillance test performed during plant startup.