ML20236F570
| ML20236F570 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/29/1998 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | Richard Anderson NORTHERN STATES POWER CO. |
| References | |
| TAC-M99108, TAC-M99109, NUDOCS 9807020224 | |
| Download: ML20236F570 (5) | |
Text
_
June 29, 1998 Mr. Roger O. Anderson, Director Nuclear Energy Engineering.
Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING PRAIRIE ISLAND PROPOSED REVISION TO MAIN STEAMLINE BREAK METHODOLOGY (TAC NOS. M99108 AND M99109)
Dear Mr. Anderson:
By letter dated June 26,1997, Northern States Power Company (NSP) submitted for staff review a plant-specific topical report of the revised main steam line break containment pressure response. As part of our continued review efforts of your request, the staff requires some additional information. Our request for additional information is enclosed.
Please provide your response within 30 days of the date of this letter to support our review of this report. If you have any questions regarding the content of the RAI, please contact me at (301) 415-1355.
Sincerely, Original signed by-T.J. Kim for:
Beth A. Wetzel, Senior Project Manager Project Directorate ill-l Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282,50-306
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
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JDonoghue KCampe DOCUMENT NAME: G:\\WPDOCS\\PRA!RIE\\Pl99108a.RAI To receive a copy of this document. indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy OFFICE
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June 29, 1998
'.e Mr. Roger O. Anderson, Director Nuclear Energy Engineering Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING PRAIRIE ISLAND PROPOSED REVISION TO MAIN STEAMLINE BREAK METHODOLOGY (TAC NOS. M99108 AND M99109)
Dear Mr. Anderson:
By letter dated June 26,1997, Northern States Power Company (NSP) submitted for staff review a plant-specific topical report of the revised main steam line break containment pressure response. As part of our continued review efforts of your request, the staff requires some additional information. Our request for additionalinformation is enclosed.
l.
Please provide your response within 30 days of the date of this letter to support our review of this report. If you have any questions regarding the content of the RAI, please contact me at (301) 415-1355.
l Sincerely, Original signed by T.J. Kim for:
Beth A. Wetzel, Senior Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation i
Docket Nos. 50-282,50-306
Enclosure:
As stated cc w/ encl: See next page l
DISTRIBUTION:
I Docket File PUBLIC PD# 3-1 Reading EAdensam (EGA1)
DOCUMENT NAME: G:\\WPDOCS\\ PRAIRIE \\Pl99108a.RAI l'
To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy i
OFFICE
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kWetzel CJamerson kCACarpenteb NAME h/1Q/98 b / d /9[/
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- l June 29, 1998 Mr. Roger O. Anderson, Director Nuclear Energy Engineering Northem States Power Company 414 Nicollet Mall l
Minneapolis, Minnesota 55401 i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING PRAIRIE ISLAND PROPOSED REVISION TO MAIN STEAMLINE BREAK METHODOLOGY (TAC NOS. M99108 AND M99109)
Dear Mr. Anderson:
By letter dated June 26,1997, Northern States Power Company (NSP) submitted for staff review a plant-specific topical report of the revised main steam line break containment pressure response. As part of our continued review efforts of your request, the staff requires some additional information. Our request for additional information is enclosed.
Please provide your response within 30 days of the date of this letter to support our review of this report.. If you have any questions regarding the content of the RAI, please contact me at (301) 415-1355.
Sincerely,
/
h- -
Beth A. Wetzel, Senior Project Manager Project Directorate 111-1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282,50-306
Enclosure:
As stated cc w/ encl: See next page l
I l
l
E Mr. Roger O. Anderson, Director Prairie Island Nuclear Generating Northem States Power Company Plant cc:
J. E. Silberg, Esquire Site Licensing Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W.
Plant l
Washington DC 20037 Northern States Power Company j
1717 Wakonade Drive East Plant Manager Welch, Minnesota 55089 Prairie Island Nuclear Generating Plant Tribal Council Northem States Power Company Prairie Island Indian Community 1717 Wakonade Drive East ATTN: Environmental Department Welch, Minnesota 55089 5636 Sturgeon Lake Road l
Welch, Minnesota 55089 Adonis A. Nebiett Assistant Attomey General Office of the Attomey General l
455 Minnesota Street Suite 900 St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Commission Resident inspector's Office
' 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region lll U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Stephen Bloom, Administrator Goodhue County Courthouse Box 408 -
Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 l
June 1998
!~,
4 REQUEST FOR ADDITIONAL INFORMATION
- 1. The revised methodology described in NSPNAD-97002-P (" Northern States Power Company Steam Line Break Methodology") includes taking credit for operation of the steam r
line non-return check valve to isolate the non-affected steam generator after the rupture.
Explein the basis for the assumptions made for check valve operation in this case.
Specifically address the fol lowing:
- a. The basis for assuming that the check valve will withstand the loads generated during a main steam line break.
l
- b. The basis for the assumed closing time of the check valve for the flow rates generated l-over the range of main steam line break sizes con'sidered. The response should focus on whether predicted reverse steam flow is sufficient in all cases to close the check i
valve in the time assumed for the analysis.
- 2. NSPNAD-97002-P explains that the modeling includes liquid entrainment in the steam
. blowdown from the steam line break. Reference is made to WCAP-8822 (Reference 10 in NSPNAD-97002-P), and the NSP report says that the WCAP entrainment data was used in the Prairie Island analysis. Appendix A to WCAP-8822 contains blowdown data for 3-and 4-loop Westinghouse plants. Explain the basis and methods for applying the 3-and 4-loop blowdown data to the 2-loop design at Prairie Island.
l-
_ 3. NSPNAD-97002-P references NSP VIPRE Version 95325, Revision 0, March 1996 as the
_ documentation for the VIPRE code. Available documentation indicates that the most recent NRC review of the code for Prairie Island was associated with the approval for NSPNAD i
8102-P, the reload safety evaluation methods report (NRC Safety Evaluation dated May 30, 1986). Discuss changes to VIPRE, relevant to the analysis of main steam line breaks, since l
the most recent NRC-approved revision as applied to the Prairie Island units.
- 4. NSPNAD-97002-P references NSP DYNODE-P Version 94305, Revision 0, January 1995 l
as the documentation for the DYNODE-P code. Available documentation indicates that the most recent NRC review of the code for Prairie Island was documented in the NRC Technical Evaluation Report, dated February 17,1983. Discuss changes to DYNODE-P since the most recent NRC-approved revision as applied to the Prairie Island units.
ENCLOSURE