ML20202G367

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Forwards Proprietary & non-proprietary Version of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units. Proprietary Info Withheld,Per 10CFR2.790(b)(1)
ML20202G367
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/29/1999
From: Richard Anderson
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20136E570 List:
References
NUDOCS 9902050131
Download: ML20202G367 (9)


Text

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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East i

Welch, Minnesota 55089 l

2 Jar-

/ 9,1999 U S Nuclear Regulatory Commission l

Attn: Document Control Desk l

Washington, DC 20555 PRAIRIE ISLAND NUCLEAF. GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 NSPNAD-8102, Revision 7:

Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units In December of 1994, the Nuclear Regulatory Commission granted appreval of Revision 6 to NSPNAD-8102, " Prairie Island Nuclear Power Plant Safety Evaluation Methods for Application to Prairie Island Units" Since then, NSP has developed new methods for determining the minimum required shutdown margin for a dilution accident when the reactor is subcritical. Consistent with the USAR text describing the Chemical and Volume Control System Malfunction analysis, the acceptance criterion used in the attached methodology is selected to ensure that a complete loss of shutdown margin will not occur for at least twenty-four minutes from initiation of the dilution. This criterion 4

is applied for operating modes three through six. Since NSP wishes to obtain approval

/I7 of these new methods for subcritical shutdown margin calculations, Revision 7 of NSPNAD-8102 describing these new methods in Appendix G has been issued.

Attachments 3 and 4 to this letter are proprietary and non-proprietary versions of this revision. We are seeking NRC approval of this revision allowing us to implement this new methodology.

Since the issuance of Revision 6 of the subject document, sections of text have bee

  • found that either contained errors or needed enhancement. Correction of this tex' does not introduce riew information nor represent new methodology requiring approval for l

implementation. These corrections have been included in Revision 7 only to formally i

9902050131 990129 PDR ADOCK 0500o282:

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USNRC NORTHERN STATES POWER COMPANY January 29,1999 Page 2 capture them on the docket'. It is not anticipated that significant review wil! be required.

However, some document reformatting might mask these tui changes so they are catalogued in Attachment 2 to facilitate NRC review. A general description of these changes are provided, as well.

The Prairie Island Nuclear Power Plant Reload Safety Evaluations methodologies are considered company confidential and as such, NSP requests Attachment 3, the proprietary version of the document, to be withheld from public disclosure pursuant to 10 CFR 2.790(b)(1). An affidavit to support this request is provided as Attachment 1.

Any questions related to this letter should be directed to Jack Leveille at 612.388.1121, Ext. 4142.

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' Roger O Anderson

Director, Nuc! ear Energy Engineering c: Regionci Administrator - Region Ill, NRC Senior Resident inspector, NRC NRR Project Manager, NRC State of Minnesota V;hout Attachment 3)

Attn: Kris Sanda J E Silberg (without Attachment 3)

Attachments:

1. Affidavit Requesting Withholding of Proprietary Information from Public Disclosure.
2. Description of Corrections introduced in Revision 7 of NSPNAD-8102.
3. NSPNAD-8192-P, Revision 7: Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units; January,1999; Proprietary version.
4. NSPNAD-8192-NP, Revision 7: Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units; January,1999; Non-proprietary version.

' Some corrections to Section 3.14, Main Steam Line Break, were disregarded since NSP is anticipating approval of new methodology that would make the text in that section obsolete, anyway.

9

UNITED STATES NUCLEAR REGULATORY COMMISSION 4

NORTHERN STATES POWER COMPANY 1

PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos. 50-282 50-306 REQUEST TO WITHHOLD PROPRIETARY INFORMATION i

FROM PUBLIC DISCLOSURE Northern States Power Company, a Minnesota corporation, hereby requests that to the letter entitled, "NSPNAD-8102, Revision 7: Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units", be withheld l

from public disclosure due to its proprietary nature. The details of this request are provided in the following affidavit:

AFFIDAVIT l Roger O. Anderson, being duly sworn, depose and state as follows:

(1) I am Director, Nuclear Energy Engineering, Northern States Power Company

("NSP") and have been authorized to apply for withholding the information described in paragraph (2).

(2) The information sought to be withheld is the Report entitled, *NSPNAD-8102-P, Revision 7: Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units; January,1999", proprietary version presented in to NSP's letter to the NRC entitled, "NSPNAD-8102, Revision 7:

Prairie Island Nuclear Power Plant Reload Safety Evaluation Methoc's For Application to PI Units" Attachment 3, which contains 298 pages, has a "-P" following the document number indicating that it is the proprietary version.

(3) In making this application for withholding of proprietary information of which it is the owner, NSP relies upon the exemption from disclosure set forth in the NRC regulation 10 CFR 2.790(b)(1) for confidential commercial information.

(4) Justification for the request for withholding from public disclosure is provided by addressing the five considerations identified in 10 CFR 2.790(b)(4).

To the best of my knowledge and belicf:

a.

This information is considered company confidential and has been held in confidence by NSP.

b.

This information is of the type customarily held :n confidence by NSP and the rationale basis is that it would provide an unfair advantage to competitors i

if it were dicciosed.

i

January 29.1999

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c.

This information is transmitted in confidence to the NRC and the purpose of this request is to maintain its confidentiality.

d.

This methodology for the Prairie Island two-loop Westinghouse nuclear plant is not available from public sources.

e.

Public disclosure of the information sought to be withheld is likely to cause harm to NSP's competitive position; NSP expended substantial resources in developing this methodology; failure to withhold this information would allow others to benefit from it without commensurate expenditures.

This letter contains no restricted or other defense information.

NORTisERN STATES POWER COMPANY By Y tw (k A

<znv R6gef O. Anderson Director Nuclear Energy Engineering On this }

day of b b i u (t 14(

l999 before me a notary public in and for said County, personally appeared, Roger O. Anderson, Director, Nuclear Energy Engineering, and being first duly sworn acknowledged that he is authorized to execute this document of behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief, the statements made in it are true and that it is not interposed for delay.

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r Att:chment 2 (Page 1 of 5): Description of Corrections introduced in R; vision 7 ts NSPNAD 8102.

Rev. 6 Page Rev. 7 Page Number (s)

Number (s)

Description of Change 1

1*

Revision number and date of the report were changed. The '-A' was dropped from the report number (indicating this revision has not yet received NRC approval).

2, 3 2*,3*

Margins were adjusted to use full page.

4 4 - 7*

Added List of Tables, List of Figures, and Appendices G end H to Table of Contents Also added subheadings for Section 3 X analyses and the other appendices.

5 8*

Made titles for Tables 3.17-1, C-1, -2 and -3 consistent with text.

6 9*

Changed titles for Figures 3.1-6,3.2-8.

7 10*

Corrected title for Figure 3.7-1.

9 10*

Corrected titles for Figures 3.11-1 through -8.

11 11*,12*

Changed titles for Figures 3.17-X.

12 12*

Changa 'vs' to 'vs.' for title of Figure C-4.

13 13*

Fourth paragraph, first sentence, nineteenth word: 'is' was changed to 'are' for subject / verb agemment.

Fifth paragraph, third sentence: comma was eliminated following '(NSP)'.

Sixth paragraph: first comma changed to period to correct typographical error.

21 22*,23*

Page 22, last paragraph, ninth word: 'anyone* was changed to 'any one' to correct typographical error.

Page 23, paragraph under Section 3.1.1, sixth word from the end: spelling of ' excursions' was corrected.

22 23*

Second paragraph under Section 3.1.2, last sentence, ninth word: 'are' was changed to 'is' for subject / verb agreement.

23 24*

Third paragraph under Section 3.1.3, seventh word from end: ' compares' was changed to ' compare' for subject / verb agreement.

H:\\RTHD09\\ DATA \\N8102\\ attachment summary of changes to NAD8102. doc

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> (Pege 2 of 5): Description of C@rrections introduced in RQvision 7 to NSPNAD 8102.

Rev. 6 Page Rev. 7 Page Number (s)

Number (s)

Description of Change i

24 25*

Paragraph e under Section 3.1.4, second and third sentences: these sentences were combined to improve i

clanty and grammar. No change to substance was made.

Paragraph e under Section 3.1.4, last sentence: 'is' was changed to 'are' for subject / verb agreement.

33 35' Paragraph d, second word: spelling of 'ENTHALPY' was corrected.

l 1

l 44 46*

Second paragraph under 3.3.4, third woni spelling of 'enthalpy' was corrected.

47 49 Text was changed to indicate that we use VIPRE instead of COBRA since receiving the SER allowing us to

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do that in Revision 3.

50 52 Typographical error in the equation for Moderator Temperature Coefficient was corrected. The application of the constant for bias in the NSP methodology had never changed. However, the information presented in the topical was not consistent with NSP documents. (Note: this merely corrected a typographical error in an equation by changing the subtraction of a constant to addition. The sign of the constant could have been just as easily been changed to make the old equation correct. This was just to establish consistency with existing documentation.)

The inequality for the excore tilt was changed from *2' to 's'. The correct inequality in Revision 5 ('s') was

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inadvertently changed in Revision 6 ('2'). This had not been identified as a change in that revision nor had it been intended to be one. This restores the correct inequality.

66 69*

Paragraph 3.5.1, next to last sentence: correct symbol for delta was used.

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67 70*

First paragraph under Section 3.5.3, last sentence: correct symbol for detta was used.

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Paragraph 3.5.4, first sentence: spelling of 'e.g.' was corrected.

j 74 78*

Paragraph 3.6.4, first sentence: spelling of 'e g.' was corrected.

83 87*

Paragraph 3.7.4, first sentence: spelling of 'e g.' was corrected.

L Paragraph 3.7.4, last sentence: period was added after 'etc'.

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Att chment 2 (Page 3 of 5): Description of Corrections Introduced in R; vision 7 to NSPNAD 8102.

I Rev. 6 Page Rev. 7 Page l

Number (s)

Number (s)

Desenption of Change l

84 88 A potential sensitivity to a most negative value was added to the application of the Doppler Reactivity Coefficient. This only adds information to the topical. No methodology desenbed in Revision 6 was eliminated. This is consistent with existing NSP methodology. This was merely an enhancement to l

information already existing in the topical.

96 100*

Paragraph 3.8.4, first sentence: spelling of 'e.g.' was corrected.

97 101 A potential sensitivity to a most negative value was added to the application of the Doppler Reactivity Coefficient. This only adds information to the topical. No methodology desenbed in Revision 6 was eliminated. This is consistent with existing NSP methodology. This was merely an enhancement to information already existing in the topical.

99 103*

Paragraph 3.9.4, first sentence: spelling of 'e.g.' was corrected.

131 136 Fourth paragraph in Section 3.11.3: descriptions for Figures 3.11-1 and -5 identify the incorrect number of pumps tripped for each analysis (the cases are swapped). This error was corrected.

132 137*

Paragraph 3.11.4, first sentence: spelling of 'e g.' was corrected.

132 138 Paragraph 3.11.4: An item, Shutdown Margin (Paragraph e), was added under Cycle Specific Physics Calculations with a sentence desenbing it. It had always been a part of the NSP methodology but just had not been identified here, previously. This was merely an enhancement of information already existing in the topical.

133 138 A potential sensitivity to a least negative value was added to the application of the Doppler Reactivity Coefficient. This accounts for circumstances where the Moderator Temperature Coefficient may be positive This merely adds additionalinformation to the topical. It maintains the concept that a bounding value for Doppler will be assigned based on the circumstances. This is consistent with existing NSP methodology.

This was merely an enhancement to information already existing in the topical.

A sensitivity to shutdown margin has been added. This had always been a part of the NSP methodology but just had not been identified here, previously. This was merely an enhancement of information already existing in the topical.

H:\\RTHD09\\ DATA \\N8102\\ attachment s'ammary of changes to NAD8102. doc i

i (Page 4 of 5): Description of Correcilon2 Introduced in R1 vision 7 to NSPNAD 8102.

Rev. 6 Page Rev. 7 Page Number (s)

Number (s)

Description of Change 143 148*

Third paragraph under Section 3.12.3, first sentence: a space replaced a comma to separate the words

'respectively' and 'for'.

144 149*

Paragraph 3.12.4, first sentence: spelling of 'e g ' was corrected.

145 150 Paragraph 3.12.4: An item, Shutdown Margin (Paragraph f), was added under Cycle Specific Physics Calculations with a sentence desenbing it. It had always been a part of the NSP methodology but just had not been identified here, previously. This was merely an enhancement of information already existing in the topical.

A potential sensitivity to a least negative value was added to the application of the Doppler Reactivity Coefficient. This accounts for circumstances where the Moderator Temperature Coefficient may be positive.

This merely adds additional information to the topical. It maintains the concept that a bounding value for Doppler will be assigned based on the circumstances. This is consistent with existing NSP methodology.

This was merely an enhancement to information already existing in the topical.

A sensitivity to shutdown margin has been added. It had always been a part of the NSP methodology but just had not been identified here, previously. This was merely an enhancement of irdormation already existing in the topical.

155 160 Correct typo on pressure at which steamline break occurs.

157 163 Pressure under (e) is corrected.

186 192*

Paragraph 3.15.4, first sentence: spelling of 'e.g.' was corrected.

188 194 A typographical error in the equation for N was corrected. Specifically, we subtract the constant for reliability factor rather than add it. The application of this constant in the NSP methodology has not changed.

However, the information presented in the topical was not correctly reflecting the NSP methods. These text changes make the tcpical consistent with NSP's methodology.

A typographical error in the equation for Apexcrwas corrected. Specifically, an extraneous asterisk was eliminated.

199 205*

Paragraph 3.16.4. first sentence: speMy of 'e.g.' was corrected.

H:\\RTHD09\\ DATA \\N8102\\ attachment summary of changes to NAD8102. doc

Attrchment 2 (Paga 5 of 5): Description of Corrections introduced in Rsvizion 7 to NSPNAD 8102.

.e Rev. 6 Page Rev. 7 Page Eumber(s)

Number (s)

Description of Change 200 206 A typographical error on this page for the equation for Boron Reactivity Coefficient was corrected. In Revision 6, the structure of the equation for a. on this page conflicted with the description of its application in Section 3.0. Since the information in Section 3.0 was correct (hence, the information on this page wrong), it was necessary to correct this page to make it consistent. It was not done to reflect any change in the NSP methodology for the application of the constant for bias or reliability factor.

231 238*

Paragraph beginning with "The core-wide...", second and third sentences: spelling of "modeled' was corrected.

Next paragraph: spelling of 'modeling' was corrected.

First paragraph under section entitled Radial Power Distribution, last sentence: spelling of 'modeling' was corrected.

236 243*

Last paragraph, next to last sentence: added a space to separate words, 'would,' and 'however'.

257 264*

Under heat sinks: corrected the spelling of ' containment' for Vessel Shell Cylinder and Vessel Shell Dome in the first two rows.

Corrected the units for Conductivity and Capacity.

262 270*

First paragraph in Section F.2.4, last sentence: deleted redundant ' axial' in parentheses.

263 270*

Second paragraph in Section F.2.4, last sentence: changed 'Overtemperature A Trip' and 'f(a)' to

'Overtemperature AT Trip' and 'f(al)'

Next paragraph: changed 'f(a)' to 'f(AI)'

265 273*

First paragraph under Turbulent Mixing, last sentence: spelling of "modeled' was corrected.

NA 298 Added Appendix H to give a brief description of these changes made to Revision 7 of this report No revision bars are provided in the document for spelling and grammar corrections or text format changes.

H:\\RTHD09\\ DATA \\N8102\\ attachment summary of changes to NAD8102. doc

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