ML20212R562: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
| project =  
| project = TAC:65078, TAC:65079
| stage = Request
| stage = Request
}}
}}

Latest revision as of 02:22, 5 May 2021

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Raising Peaking Factors to Reduce Magnitude of Predicted Worst Case Derate.Fee Paid
ML20212R562
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 04/13/1987
From: Musolf D
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20212R565 List:
References
TAC-65078, TAC-65079, NUDOCS 8704270242
Download: ML20212R562 (2)


Text

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Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 Telephone (612) 330-5500 April 13, 1987 10 CFR Part 50 Section 50.90 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated April 13, 1987 Peaking Factor Changes Attached is a request for a change in the Technical Specifications, Appendix A of the Operating License, for the Prairie Island Nuclear Generating Plant. This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90. A check is attached in the amount of $150.00 in accordance with the requirements of 10 CFR Part 170 for the amendment application fee.

Due to recent changes in the Unit 1 Cycle 12 peaking factor predictions, application of the current Technical Specifications will result in a significant derate for Unit 1 Cycle 12 (See Figure 1, Exhibit A). Higher peaking factors are being proposed by this license amendment request to reduce the magnitude of the predicted worst case derate to essentially zero (See Figure 2, Exhibit A).

Exhibit A describes the proposed changes, provides the reasons for the changes and provides the supporting safety evaluation /significant hazards determination. Exhibit B contains the proposed changes marked up on the l

, existing Technical Specification pages. Exhibit C contains the revised j Technical Specification pages. Exhibits D, E and F contain supporting  ;

. documentation. '

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8704270242 870413 0 0\h g6)

PDR P

ADOCK 05000282 PDR \ g

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Dir, NRR 1 13, M87 Northem States Power Company fP Unit 1 Cycle 12 is scheduled to begin early next month. We realize that review and approval of this request cannot be completed prior to Unit 1 Cycle 12 startup, however, we do request expedited processing of this request to reduce the magnitude of predicted derates. We apologize for the late date of this submittal. If there is anything we can do aid the timely review of this amendment please contact us.

M kw David Musolf Manager - Nuclear Support Services DMM/TMP/tp c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn: J W Ferman C Charnoff Attachments:

iffidavit and Check for $150.00 to the US Nuclear Regulatory Commission Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit B - Proposed Changes Marked.Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages Exhibit D - Safety Evaluation of Increased FQ and FdH, NSPNAD - 8705 Exhibit E - Demonstration of the Conformance of the Prairie Island Units to Appendix K and 10 CFR 50.46 for Larga Break LOCAs (Fq - 2.36 and F-DELTA-H - 1.63)

Exhibit F - Demonstration of the Conformance Lf he Prairie. Island Units to Appendix K and 10 CFR 50.46 C6r ..ai y Break LOCAs (Fq - 2.32 and F-DELTA-H to fa 1

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