ML071500063

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License Amendment Request: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1 - Supplemental Information in Response to NRC Request for Additional Information
ML071500063
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/22/2007
From: Schimmel M
Constellation Energy Group
To:
Document Control Desk, NRC/NRR/ADRO
References
TAC MD4031
Download: ML071500063 (2)


Text

Constellation Energy P.O. Box 63 Lycoming, NY 13093 Nine Mile Point Nuclear Station May 22, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-4 10 License Amendment Request: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1 - Supplemental Information in Response to NRC Request for Additional Information (TAC No.

MD403 1)

REFERENCE:

(a) Letter from T. J. O'Connor (NMPNS) to Document Control Desk (NRC), dated January 4, 2007, License Amendment Request Pursuant to 10 CFR 50.90:

Revision of Service Water and Ultimate Heat Sink Temperature Requirements -

Technical Specification 3.7.1 Nine Mile Point Nuclear Station, LLC (NMPNS) hereby transmits supplemental information requested by the NRC in support of a previously submitted application for amendment to Nine Mile Point Unit 2 (NMP2) Renewed Operating License NPF-69. The initial application, dated January 4, 2007, (Reference a) proposed to revise NMP2 Technical Specification 3.7.1, "Service Water (SW) System and Ultimate Heat Sink (UHS)."

This supplemental information responds to a request for additional information that was provided in an email from the NRC to NMPNS on May 10, 2007 and was subsequently discussed in a telephone call between the NRC and NMPNS on May 11, 2007. Specifically, in Reference (a), Attachment (1), Section 4.3.2, the Main Steam Isolation Valve (MSIV) Closure Event is described as a main steam line isolation transient from 100 percent power with a loss of offsite power. This is a general description of the event but is not intended to describe the specific analysis inputs and assumptions. NMPNS confirms that the analysis for this event was actually performed at 102 percent of the licensed reactor core power level (i.e.,

1.02 x 3,467 = 3,536 megawatts thermal), as described in Section 6A.10.2.3.2 of the NMP2 Updated Safety Analysis Report.

This supplemental information does not affect the No Significant Hazards Determination analysis provided by NMPNS in Reference (a). Pursuant to 10 CFR 50.91(b)(1), NMPNS has provided a copy of this supplemental information to the appropriate state representative. This letter contains no new regulatory commitments.

Document Control Desk May 22, 2007 Page 2 Should you have any questions regarding the information in this submittal, please contact T. F. Syrell, Acting Licensing Director, at (315) 349-7198.

Very truly yours, Mark A. Schimmel Plant General Manager STATE OF NEW YORK TO WIT:

COUNTY OF OSWEGO I, Mark A. Schimmel, being duly sworn, state that I am Plant General Manager, and that I am duly authorized to execute and file this supplemental information on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

Subscribed and sworn before me, a Notary Public in and for the State of New York and County of Oswego, thi A'01 day of J 9 I1 ,2007.

1ý-4 WITNESS my Hand and Notarial Seal:

'--otary tPublic My Commission Expires: 1/I2 [iA(-1

/ Date TONYA L JONES Notary Public inthe State of New York Oswego CountyRig. No. 01  !

My Commission Expires J=161 4 I MAS/DEV cc: S. J. Collins, NRC M. J. David, NRC Resident Inspector, NRC J. P. Spath, NYSERDA