ML20090L559

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Informs of Measures Util Intends to Pursue to Meet Provisions of Section V.B of App I to 10CFR50.Info Will Be Submitted by 760604.Meeting W/Nrc Requested During Wk of 760315
ML20090L559
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/09/1976
From: Mayer L
NORTHERN STATES POWER CO.
To: Ziemann D
Office of Nuclear Reactor Regulation
References
2460, NUDOCS 9102110425
Download: ML20090L559 (3)


Text

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e T e NS58 HORTHERN STATES POWER COMPANY MIN N E APOLI S. MIN N E SOTA 55409 9.

Ma rch 9, 1976

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Division of Operating Reactors U.S. Nuclear Regulatory Commission 7

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Washingtun, DC 20555

Dear Mr. Ziemann:

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MONTICELLO NUCLEAR GENERATING PIANT i

Docket No. 50-263 License No. DPR-22 Response to NRC Request for Filing of Appendix I Information This letter is to inform you of the measures Northern States Power Company (NSP) intends to pursue to meet the provisions of Section V.B of Appendix 1 to 10 CFR Part 50, for the Monticello Nuclear Generating Plant, he proposed action incorporates the guidance provided in your lette e of February 23, 1976, including Enclosures 1 and 2.

We will demonstrate, by conservative models and data derived from Rt.gulatory Guides 1.AA, 1.C0,1. DD and 1. EE, that the Monticello Plant can be op-erated to meet the Appendix I design objectives.

The following actions will be included:

1.

Plant releases of liquid and gaseous effluents will be calculated cccording to the models and equations set out in Regulator / Guide 1.CC.

2.

Using the release data from Item 1 above, and the dispersion models from Regulatory Guides 1.DD and 1.EE, off-site doses to man will be calculated according to Regulatory Guide 1. AA.

3.

Doses computed from Item 2 above will be analyzed with reference to the design objectives set forth in Section II, Para, A, B and C of Appendix 1.

4.

Appropriate effluent release data from previous reactor operation will be provided and will be evaluated against the so'2rce terms calculated under Item 1 above.

We will gather and develop the additional information outlined in Enclosure 2 to your February 23 letter. This information will facilitate calculation of off-site doses based on ef fluent release data collected during previous re-actor operation.

We scope will include the following categories:

9102110425 760309

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NORTHERN OTATED POWER COMPANY 1

Mr. D. L. Ziemann 2

March 9, 1976 1.

Plant design and operational data 4

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Dose pathway information 3.

Meteorological and topographical data The data to be furnished will be developed, as appropriate, considering the options available to u:: for some of the Enclosure 2 information (such as meteorological).

The information required pursuant to Section V.B of Appendix I will be sub-j_

mitted on or before June 4,1976 and we anticipate furnishing the Enclosure 2 information prior to that date.

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Since we have engaged consultants who have comenced preparing this infor-l mation, we wish to assure ourselves, as early as possible, of the suitability of our specific approach in meeting the requirements set out in your l

February 19 letter.

Therefore, we request a meeting with you as soon as possible af ter receipt of this letter and preferably during the week of March 15.

i As you recommended, we will hold in abeyance any development work on Technical Specifications related to Appendix I, pending receipt of appropriate regulatory guidance.

E Yours very truly, k

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L. O. Mayer, PE 1

Manager, Nuclear Support Services LGi/ECW/ deb l

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MPCA Attn:

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