L-MT-13-073, Extended Power Uprate: Status of Safety Communications Review - Response to Request for Additional Information

From kanterella
Jump to navigation Jump to search

Extended Power Uprate: Status of Safety Communications Review - Response to Request for Additional Information
ML13199A487
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 07/18/2013
From: Schimmel M
Northern States Power Co, Xcel Energy
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-MT-13-073, TAC MD990
Download: ML13199A487 (3)


Text

Xcel Energy Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 July 18, 2013 L-MT-13-073 10 CFR 50.90 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22 Monticello Extended Power Uprate: Status of Safety Communications Review -

Response to Request for Additional Information (TAC MD9990)

References:

1) Letter from T J O'Connor (NSPM) to Document Control Desk (NRC),

"License Amendment Request: Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5,2008. (ADAMS Accession No. ML083230111)

2) Email from T Beltz (NRC) to J Fields (NSPM), "Monticello Nuclear Generating Plant - Draft Requests for Additional Information (EVIB)

Supporting Review of the Extended Power Uprate License Amendment Request (TAC MD9990)," dated July 9,2013.

3) Letter from T J O'Connor (NSPM) to Document Control Desk (NRC),

"Monticello Extended Power Uprate: Updates to Docketed Information (TAC MD9990)," L-MT-10-072, dated December 21,2010. (ADAMS Accession No. ML103570026)

4) Letter from M A Schimmel (NSPM) to Document Control Desk (NRC),

"Monticello Extended Power Uprate: Supplement to Revise Technical Specification Setpoint for the Automatic Depressurization System Bypass Timer (TAC MD9990)," L-MT-12-091, dated October 30,2012.

(ADAMS Accession No. ML12307A036)

Pursuant to 10 CFR 50.90, the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, requested in Reference 1 an amendment to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specifications (TS) to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.

Document Control Desk Page 2 In Reference 2 the NRC provided NSPM a draft request for additional information (RAI).

The RAI concerns the status of NSPM's review of certain Safety Information Communications from General Electric-Hitachi. The response to the Reference 2 RAI is included in the enclosure to this letter.

The RAI response provided herein does not change the conclusions of the No Significant Hazards Consideration and the Environmental Consideration evaluations provided in Reference 1 as revised by References 3 and 4.

In accordance with 10 CFR 50.91 (b), a copy of this application supplement, without the enclosure is being provided to the designated Minnesota Official.

Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: July!!., 2013

~~~R Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure cc: Administrator, Region III, USNRC (w/o enclosure)

Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC (w/o enclosure)

Minnesota Department of Commerce (w/o enclosure)

L-MT-13-073 ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION This enclosure provides a response to the request for additional information (RAI) from the Nuclear Regulatory Commission (NRC) provided in an email dated July 9,2013.

The NRC RAI is presented below along with the response from the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy.

NRC RAI NSPM indicated in Item 25 of Enclosure 1 to L-MT-12-114 (Agencywide Documents Access and Management System Accession No. ML13039A200) that GE-Hitachi (GEH)

Safety Communication (SC) 09-03 was addressed for MNGP at EPU conditions.

The U.S. Nuclear Regulatory Commission staff is aware of other, more recent, GEH Safety Communications, including SC 09-03 (Rev. 1), SC 11-07, and SC 12-20, regarding various loadings on the reactor pressure vessel and internals.

Has NSPM evaluated these more recent GEH SCs for EPU conditions?

NSPM Response On June 10,2013 General Electric-Hitachi issued the following Safety Information Communications (SCs):

o SC 09-03, Rev. 1, "Shroud Screening Criteria Reports" o SC 11-07, Rev. 0, "Impact of Inertial Loading and Potential New Load Combination from Recirculation Suction Line Break Acoustic Loads" o SC 12-20, Rev. 0, "Error in Method of Characteristics Boundary Conditions Affecting Acoustic Loads Analyses" The SCs were entered into the Monticello Nuclear Generating Plant Operating Experience Program, and are currently being evaluated. A final determination has not yet been made regarding these SCs at EPU conditions.

Page 1 of 1