ML20195F127
| ML20195F127 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/16/1998 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20138L702 | List: |
| References | |
| NUDOCS 9811190198 | |
| Download: ML20195F127 (8) | |
Text
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g77 Northern states Power Company 1717 Wakonade Dr. E.
Welch, MN 55089 Telephone 612-388-1121 October 16,1998 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 i
Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 The information in Attachment 1 is provided in response to an NRC staff request made in a teleconference on September 14,1998, for additional information related to our proposed revision to the Main Steam Line Break Methodology dated June 26,1997. provides a revision to the Main Steam Line Break Methodology which changes the acceptance criteria for reactor coolant system pressure to a value
]
consistent with the more restrictive acceptance criteria used in the Steam Generator Tube Rupture Analysis.
In this submittal we have made no new NRC commitments. If you have any questions related to this matter, please contact John Stanton at 651-388-1121.
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I Joel P. Sorensen 1I g
Plant Manager QO y' Prairie Island Nuclear Generating Plant e
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- USNRC NORTHERN STATES POWER COMPANY October 16,1998 Page 26f 2 Affidavit:
Request To Withhold Proprietary Information From Public Disclosure :
Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 :
Steam Line Break Methodology, Revision 1, NSPNAD-97002-P, October 1998, Proprietary Version :
Steam Line' Break Methodology, Revision 1, NSPNAD-97002, October 1998, Non-Proprietary Version c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC Kris Sanda, State of Minnesota w/o Attachment 2
. J E Silberg w/o Attachment 2
-4
UNITED STATES NUCLEAR REGULATORY COMMISSION l
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos.
50-282 50-306 i
REQUEST TO WITHHOLD PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE Northern States Power Company, a Minnesota corporation, hereby requests that to the letter entitled, " Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997", be withheld from public disclosure due to its proprietary nature.
The details of this request are provided in the following affidavit:
AFFIDAVIT I, Joel P. Sorensen, being duly sworn, depose and state as follows:
(1)
I am Plant Manager, Prairie Island Nuclear Generating Plant, Northern States Power Company ("NSP") and have been authorized to apply for withholdi-ihe information described in paragraph (2).
(2)
The information sougnt to be withheld is the Report entitled, " Steam Line Break Methodology, NSPNAD-97002, Rev.1, October 1998", Proprietary Version presented in Attachment 2 to the NSP letter to the NRC entitled, " Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997". Attachment 2, which contains 67 pages, has the words, "NSP Proprietary Information", on the bottom of each page.
(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).
AFFIDAVIT NORTHERN STATES POWER COMPANY Requist to Withhold Propri:tary Information Pag 3 2 of 2 To the best of my knowledge and belief; a.
This information is considered company confidential and has been held in confidence by NSP.
b.
This information is of the type customarily held in confidence by NSP and the rationale basis is that it would provide an unfair advantage to i
competitors ifit were disclosed.
c.
This information is transmitted in confidence to the NRC and the purpose of this request is to maintain its confidentiality.
d.
These analyses for the Prairie Island two-loop Westinghouse nuclear plant are not available from public sources.
i 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 these analyses; failure to withhold this information would allow others to benefit from it without commensurate expenditures.
This letter contains no restricted or other defense information.
NORTHERN STATE POWER COMPANY By s
Jp. Sorense'n' Plant Manager Prairie Island Nuclear Generating Plant l
On this day o b
before me a notary public in and for said' County, personalhfappeared, Joel P. Sorensen, Plant Manager of the Prairie Island Nuclear Generating Plant, and being first duly sworn acknowledged that he is authorized to execute this document on 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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MARCIA k. LaCORE NOTARY PUBUC-MINNESOTA HENNEPIN COUNTY h
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Attachment i NORTHERN STATES POWER COMPANY October 16,1998 Page 1 of 2 Response to September 14,1998, Request for Additional Information on l
Proposed Revision to Main Steam ulne Break Methodology dated June 26,1997 Question 1:
Provide the reactor coolant system hot leg temperature (steam generator inlet) versus time for a 1,4 ft' main steam line break from 102% full reactor power.
Response
2 The following plot was generated for a 1.4 ft main steam line break from 102% full reactor power using the methodology' described in NSPNAD-97002-P, June 1997.
l SG Inlet Temperature 102% Power,1.4 sqft Break 600 l I I I
! I I T 1
i 575
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7 E 550 N
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500 I
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10 20 30 40 50 60 Time (sec)
This is the same methodology described in NSPNAD-97002-P, October 1998.
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t NORTHERN STATES POWER COMPANY October 16,1998 Paga 2 of 2 j
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Question 2:
Describe the basis for the uncertainty that w?3 applied to the entrainment data.
Response
The basis for the uncertainty is explained in section 3.2.2 of WCAP-8822. This uncertainty adds additional conservatism to the calculated mass and energy releases and reduces the sensitivity l
of the results to possible inaccuracies in the modeling of the steam generator and steam l
separator in the TRANFLO analyses.
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October 16,1998 NORTHERN STATES POWER COMPANY l
Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 1
i Steam Line Break Methodology Revision 1 NSPNAD-97002-P l
October 1998 l
Proprietary Version l
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October 16,1998 NORTHERN STATES POWER COMPANY Response to September 14,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 l
Steam Line Break Methodology Revision 1 NSPNAD-97002 October 1998 Non-Proprietary Version d